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BU-7 SHIPPING PACKAGE CONSOLIDATED APPLICATION i
CERTIFICATE OF COMPLIANCE O
osx/sois/ar i
General Electric Company Nuclear Fuel & Components Manufacturing Wilmington, North Carolina K$hhhh$3, PDR LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1
- i-
 
TABLE OF CONTENTS Page
 
==1.0 INTRODUCTION==
1 2.0 PACKAGE DESCRIPTION 2
2.1 General 2
2.2 Gross Weight 2
2.3 Uranium Oxide Powder & Pellet Container 2
2.4 BU-7 Inner Containment 2
2.5 BU-7 Outer Container 3
2.6 Insulating Material 3
2.7 Package Description - Contents 3
3.0 PACKAGE EVALUATION 6
3.1 General.
6 3.2 Single Package - Normal Transport Conditions 6
3.3 Single Package - Accident Evaluation 7
3.4 Acceptance Criteria 8
4.0 CRITICALITY SAFETY EVALUATION 14 4.1 Uranium Oxides in Powder Form - H/U Ratio < 0.45 14 4.2 Uranium Oxides in Powder Form - H/U Ratio I 1.6
& C/U Ratio < 1.27 14 4.3 Uranium Oxides In Pellet Form 14 5.0 TESTING, OPERATING & MAINTENANCE 15 O
5.1 Testing 15 5.2 Operating 15 5.3 Maintenance 16 6.0 BU-7 TRANSPORT PACKAGE SPECIFICATIONS 17 APPENDICES A-Drawing 112D1592, " Shipping Container - Model BU-7" B- " Test Report for Model BU-7 Bulk Uranium Shipping Container" C
" Criticality Safety Analysis of BU-7 Shipping Container for l
UO Powder" 2
l D
" Criticality Safety Analysis - BU-7, Theoretical Density" i
E
" Safe Batch Limits for UO and H 0", NRC License SNM-1097, Condition 9, Part I,Tabfe4.4 2
LICENSE SNM-1097 DATE 12/22/86 PAGE 1
DOCKET 71-9019 REVISION 1
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==1.0 INTRODUCTION==
,.L]
The BU-7 package is currently authorized by NRC Certificate of Compliance USA /9019/AF as a Fissile Class I. container for the transport of fissile radioactive material in the form of uranium dioxide powder and pellets.
A complete series of tests have been conducted on the BU-7 package to verify conformance with the requirements of 10 CFR 71.
This application amendment contains a consolidation of all applications and package test results previously submitted in Docket 70-754 (for NRC License SNM-960),
Docket 70-1007 (for NRC License SNM-54), and Docket 71-9019 for license and certificate amendments pursuant to 10 CFR 71 related to the General Electric BU-7 (m) package.
It is requested that the BU-7 package be certified as complying with the revised regulatory requirements of 10 CFR Part 71 published in the Federal Register, Volume 48, No. 152, on August 5, 1983, with an effective date of September 6, 1983.
The purpose of the revision was to make NRC transportation regulations compatible with those in " Safety Series No.
6, IAEA Safety Standards, Regulations for the Safe Transport of Radioactive Materials, 1973 Revised Edition (As Amended)".
LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1
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2.0 PACKAGE DESCRIPTION 2.1 GENERAL Inner containment is a nominal 16-gallon drum closed by a gasketed, bolted lid, centered and supported within an outer 55-gallon drum by solid insulating media, and containing two or more steel pails which contain uranium oxide powder and pellets.
(See Drawing 112D1592.in Appendix A.)
2.2 GROSS WEIGHT 370 pounds, maximum 2.3 URANIUM OXIDE POWDER & PELLET CONTAINER 1
One or more closed containers, 11.25" inside diameter
(
fabricated of minimum 24-gauge steel, vertically stacked in each BU-7 unit.
2.4 BU-7 INNER CONTAINMENT A nominal 16-gallon drum constructed of 18 gauge steel, modified by the welded attachment of a closure flange to accept a 3/16" thick steel lid which is gasketed for resistance to high temperature as shown in Drawing.
112D1592 and attached by twelve 5/16" minimum steel The minimum inside dimensions of'the inner bolts.
containment drum are 13 3/4" diameter by 26 3/4" high.
I LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1
_2_
l
 
2.5 BU-7 OUTER CONTAINER O
A nominal 55-gallon DOT Specification 17H steel drum (with three rolling hoops) or Uniform Freight j
Classification Rule 40 steel drum (with two rolling hoops).
Drum is' 18-gauge steel with a nominal outer dimension height without the cover of 35" and a nominal inner diameter dimension of 22 1/2".
2.6 INSULATING MATERIAL The inner containment drum is centrally held within the outer container by, and the space between the inner and the outer containers is completely filled with, solid insulating media composed of fire-retardant phenolic foam as specified in Drawing 112D1592.
Four 1/4" diameter vent holes equally spa'ced near the top of the outer container, covered with waterproof tape, would
()
permit steam to escape in the event free moisture in the insulating material were exposed to the heat from an accidental fire during transport.
2.7 PACKAGE DESCRIPTION - CONTENTS 2.7.1 Type & Form of Material (1)
Uranium oxide powder enriched to not more than 4.0 235 isotope.
The maximum H/U atomic W/O in the U ratio shall not exceed 0.45.
The mass of moderating materials within the inner container when added to the total mass of moderator within the fuel shall not exceed 525 grams.
(See Appendix D.)
LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1 _
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l (2)
Uranium oxide powder with a maximum bulk density
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not greater than 4.5 grams /cc.
Uranium may be enriched to not more than 4.0 W/O in the U 235 isotope.
The maximum H/U atomic ratio shall not exceed 1.6.
The mass of moderating materials within the inner container when added to the total mass of moderator within the fuel shall not exceed 1750 grams.
(See Appendix C.)
v.
(3)
Uranium oxide as pellets enriched to not more than 4.0 W/O in the U235 isotope.
The. maximum H/U atomic ratio shall not exceed 0.45.
The mass of moderating materials within the inner container when added to the total mass of moderator within the fuel shall not exceed 1.5% of the UO mass 2
limit..
(See Appendix D.)
}
2.7.2 Maximum' Quantity of Material per Package (1)
For contents described in 2.7.1(1) and (2), the maximum contents of uranium oxide powder per package and pail shall be limited to 70 kgs and 35 kgs, respectively.
(2)
For contents described in 2.7.1(3), the maximum contents per package and pail shall be limited in j
accordance with the following table:
l LICENSE SNM-1097 D. ATE 12/22/86 PAGE
()
DOCKET 71-9019 REVISION 1 !
 
Maximum O'
U 235 Enrichment, Maximum UO,, kgs W/O Per Pail Per Package 3.0 35.0 70.0 3.2 34.1 68.2 3.4 31.0 62.0 3.6' 28.'S 57.0 3.8 26.4 52.8 4.0 24.7 49.4 2.7.3 Mixtures of Uranium oxide Powder &' Pellets The maximum contents per package and pail for mixtures of uranium oxide powder and pellets shall be limited to the amounts shown in the table in Section 2.7.2(2).
2.7.4 Mixtures of Uranium-Oxide Powder with Additives For contents as described in 2.7.1(2), ammonium oxalate
()
and/or ammonium bicarbonate additives are permitted in the UO Powder to the extent that the C/D ratio does not 2
exceed 1.27.
(See Appendix C.)
l I
LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1._. _ _ _ _ _ - - _.., _ _ -. - _ _. ~ -
 
3.0 PACKAGE EVALUATION 3.1 GENERAL There are no components of the packaging or its contents which are subject to chemical or galvanic reaction during normal transportation.
The package cannot be opened inadvertently, uses no coolant and has no lifting or tiedown attachments.
3.2 SINGLE PACKAGE - NORMAL TRANSPORT CONDITIONS Between March 20 and April 2, 1980, a series of tests were performed on the BU-7 transport package.
These tests are described in a report dated April 25, 1980, which is included in Appendix B to this application.
()
Included in these tests were some simulated normal transport conditions.
Not all such conditions were tested because the package requirements for some of these conditions could be demonstrated to be satisfactory by other means.
Two BU-7 packages were loaded with two 5-gallon steel p wder pails, each pail being filled with 45 kgs of UO 2 containing natural uranium, for a total of 90 kgs of UO 2 powder per package.
These packages were used for the tests' simulating hypothetical accident conditions, as described in the test report.
One BU-7 package was loaded with two 5-gallon steel pails containing a total of 93 kgs of lead shet.
This LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1
package was subjected to tests simulating normal f ')
transport conditions.
~-
A summary of this information is given in Table 3-1.
The tests and assessments set forth in Table 3-1 provide assurance that the powder or pellet contents are contained in the pails during normal transport and there is no reduction in effectiveness of the package system.
It has been demonstrated, moreover, that there would be no water inleakage to the product during 'cormal transport conditions.
3.3 SINGLE PACKAGE - ACCIDENT EVALUATION On February 6, 1978, through February 10, 1978, a series of immersion / pressure tests were conducted on a BU-7
(]')
shipping package.
These tests are described in a report dated February 10, 1978, which is included in Appendix B.
The results of these tests are summarized in Item (5) of Table 3-2.
Between March 20 and April 2, 1980, a series of tests were performed on the BU-7 transport package.
These I
tests are described in a report dated April 25, 1980, which is included in Appendix B to this application.
Included in these tests were some done sequentially simulating hypothetical accident conditions during transport.
A summary of these tests is given in Table 3-2.
LICENSE SNM-1097 DATE 12/22/86 PAGE t' }
DOCKET 71-9019 REVISION 1
Upon completion of the four hypothetical accident (v) condition tests,, conducted in thd sequence prescribed in 10 CFR 71, the package subjected to all these tests, was opened and inspected.
There was no damage to the inner containment sealing features; the original computer weigh cards were with the 5-gallon pails; they were not wet and there was no moisture in the inner container.
The top insulation disc was badly charred and the outside of the bolted cover had some blistered paint, but there was no structural damage, breach of containment, or loss of shielding.
3.4 ACCEPTANCE CRITERIA Acceptance criteria for meeting the requirements of 10 CFR 71 are as follows:
o No water intrusion to the contents.
(j No. rupture of the product containers or inner o
container.
No damage to the inner containment sealing features o
that would yield them ineffective.
No significant defo.rmation to the outer container o
that would affect criticality safety considerations.
We have concluded, as a result of these tests described above, that all tests required by 10 CFR 71, have been conducted, witnessed by Quality Control Engineering, and have passed the acceptance criteria.
Test completion check sheets and compliance certificates are included in l
Appendix B to this application.
LICENSE SNM-1097 DATE 12/22/86 PAGE
/ )'s i
DOCKET 71-9019 REVISION 1
TABLE 3-1 SINGLE BU-7 TRANSPORT PACKAGE - NORMAL TRANSPORT CONDITIONS
.(d
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10 CFR 71.71 Requirements Tests Conducted Results (1) Heat. An ambient No tests required.
Temperature of 100* F is within temperature of 38' C (100*
normal operating range for materials of construction.
F) in still air, and insolation according to the following table:
INSOLATION DATA Total Insolation for a 12-Form & Location hr Period 2
of Surface (g cal /cm )
Flat surfaces transported horizontally
- Base None
- Other Surfaces 800 Flat surfaces not transported horizontally 200 Curved surfaces 400
/]
(2) Cold. An ambient No tests required.
Temperature of -40' F is within
()
temperature of 40*C (-40*F) normal operating range for in still air and shade.
materials of construction.
(3) Reduced external oressure.
Package was submerged in water o No water leakage into inner An external pressure of 24.5 to a pressure of 1.50 kg/cm2 (50 containers after 8 hours of kilopascal (3.5 psi feet of water), then pressurized submergence.
absolute).
and checked for leakage in four increments:
o No leakage of air from inner (4) Increased external pressure.
containers when pressurized 2 for 3 hours and held at each pressure An external pressure of 140 o 0.75 kg/cm 2 for 3 hours increment for 3 hours.
kilopascal (20 psi) o 1.0 kg/cm 2 for 3 hours absolute.
o 1.25 kg/cm o 1.5 kg/cm2 for 3 hours (5) Vibration. Vibration No tests required.
Packages of this type have normally incident to withstood sevecal years of transport.
transport with ru occurrences of significant damage due to normal l
vibration.
(6) hter array. A water spray Package was exposed to a water There were no signs of water that simulates expceure to sprey sufficiently heavy to keep damage to the package.
rainfall of approximately all exposed surface except the five em (2") per hour for at bottom wet for a period of 30 least one hour.
minutes.
I
^
LICENSE SNM-1097 DATE 12/22/86 PAGE l
DOCKET 71-9019 REVISION 1
TABLE 3-1
' Continued b
v 10 CFR 71.71 Requirements Tests' Conducted Results (7) Free drop. Between 1-1/2 The package, loaded with 93 kgs There was a slight deformation and 2-1/2 hours after the of test weight, was dropped 4 of the outer container closure conclusion of the water feet with the closure ring ring that did not inpair its spray test, a free drop impacting onto a flat reinforced function. There was no damage through the distance concrete pad. The test was to the inner container seal of
.specified below onto a flat, conducted 2 hours after the the 5-gallon pails, and there essentially unyielding, water spray test, was no separation of the closure horizontal surface, striking ring from the lid of the outer the surface in a position cont ainer.
for which maximum damage is expected. For Fissile Class 11 packages, this free drop must be preceded by a free drop from a height of 0.3 m (1 ft) on each corner or, in the case of a cylindrical Fissile Clase !! package, onto each c' e quarters of each rim.
CRITERIA FOR FREE DROP TEST (WEIGHT / DISTANCE)
Free Drop Package Weight Distance Kilograms Pounds Meters Feet 5,000 or (11,000) 1.2 (4) less 5,000 to (11,000-10,000 22,000) 0.9 (3) 10,000 to (22,000-0.6 (2) 15,000 33,000)
More than More 0.3 (1) 15,000 than 33,000 (8) Corner Drop. This test No teste were required.
The package gross weight exceeds applies only to packages 110 pounds.
which are constructed primarily of wood of fiberboard, and do not exceed 110 pounds gross weight.
(9) Compres-lon. For packages Weight equal to more than 5 No damage to the package due to weighing up to 5000 kg, the times the weight of the package compressive loading was found.
package must be subjected, was applied to the top of the for a period of 24 hours, to package for a period of 24 (cont'd)
(cont'd)
LICENSE SNM-1097 DATE 12/22/86 PAGE 1
DOCKET 71-9019 REVISION 1 __.
 
TABLE 3-1 Continued 10 CFR 71.71 Requiremente Teste Conducted Results a compressive load applied hours. The test weight used wie uniformly to the top and 2,440 pounde.
bottom of the package in the position in which the package would normally be transported. The compressive load must be the greater of the followings (1) The equivalent of five times the weight of the packages or (ii) The equivalent of 12.75 2
kilopescal (1.85 lb/in )
multiplied by the vertically projected area of the package.
(10) Penetration. Irupact of the The package wee penetration There wee a eli@t indentation hemispherical end of a tested by impacting the where the 13 pound bar struck vertical steel cylinder of
. hemispherical end of a vertical the container. It did not-3.2 cm (1-1/4") diameter steel cylinder 1-1/4" in penetrate the package.
and six kg (13 lb) mass, diameter and weighing 13 pounds, dropped from a height of and dropped from a height of 40" one n (40") onto the into the top of the container exposed surface of the where it is most susceptible to packege which is expected a' projectile penetration.
to be most vulnerable to puncture. The long axis of the cylinder must be perpendicular to the packege surface.
l
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LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1
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.-,_------.--.--.,a-
 
TABLE 3-2 SINGLE BU-7 TRANSPORT PACKAGE - ACCIDENT CONDITIONS
*O G
10 CFR 71.73 Requirements Tests Conducted Results (1) Free Drop. A free drop of Each of the two packages was Both packeges inpacted at the specimen through a raised by a crane to a 30 ft pre-determinod angles. Areas at distance of nine m (30 ft) height at approximately a 45' points of impact of both units onto a flat, essentially angle. The height was were without fracture. Beyond unyielding, horizontal determined by a measured, this, the only significant surface, striking the weighed cord hanging from the dmage was a slight opening of surface in a position for containers. A quick release the cover where the closure ring which maximum dmage is mechanism was used to drop the of one package was deformed.
expected.
packages, which fell at The bottom corner free-fall test approximately a 45' angle, of the outer package caused landing on the corners of the somewhat more crushing of the package.
container than was experienced in the too drop. There was no evidence of fractures or separation of the package side from the bottom; therefore, the package with the slight opening
{
due to the top drop was deemed
~
to have suffered the maximun d mage.
Post-test inspection showed N0 damages to the sealing features of the inner containers or to the 5-gallon pails.
(2) Puncture. A free drop of Both packages were free-dropped Both packages were slightly the specimen through a through a distance of 40",
indented (about 1/4"). There distance of one m (40") in a striking the top end of a was no puncture of either position for which maximum vertical steel bar mounted on a
: package, damage is expected, onto the reinforced concrete pad. The upper end of a solid, bar was fabricated per the vertical, cylindrical, alld requirements of 10 CFR 71, steel bar mounted on an Appendix B.
essentially unyielding, horizontal surface. The bar A vertical drop with the must be 15 cm (6") in container impacting on the 18 dimeter, with the top gauge cover near the outer edge horizontal and its edge was considered the most rounded to a radius of not vulnerable orientation to more than six mm (1/4") and puncture.
of a length as to cause maximum damage to the package, but not less than l
20 cm (8") long. The long exis of the Der must be i
vertical.
(3) Thermal. Expcaure of the A thermal test of one of the Inspection of the inner whole specimen for not less packages (the one that sustained container after all the tests than 30 minutes to a heat the most damage from the showed no damage to the inner flux not less than that of a free-drop through 30 feet) container, its sealing features (cont'd)
(cont'd)
(cont'd)
LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1
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TABLE 3-2 Continued
,b 10 CFR 71.73 Requirements Tests Conducted Results radiation environment of followed the 30 foot free-drop or to the 5-gallon pails that 800* C (1475* F) with an and puncture tests. The thermal would yield either of them emissivity coefficient of at test conducted required exposure ineffective. The paint was least 0.9.
For purposes of to an environment of 1475*
slightly blistered in a small calculation, the surface minimtn for a period of 30 area at the top end of the inner absorptivity nust be either minutes. Since an actual container, but no indication of I
that value which the package gasoline fire with open flames this on either of the 5-gallon
'P "d'''
may be expected to possess provides the most realistic pails containing UO2 if exposed to a fire or 0.8, means of satisfying the whichever is greater. In requirements of 10 CFR 70 addition, when significant, thermal test, this method was convective heat input must chosen for the BU-7 test.
be included on the basis of still, anblent air at 800* C (1475* F).
Artificial cooling must not be applied after cessation of external heat input and any combustion of materials of construction must be allowed to proceed until it terminates naturally. The effects of solar radiation may be neglected prior to, during, and following the test.
e]
,V (4) Immersion-fissile material.
After the fire test, the package Following immersion as For fissile material, in was allowed to cool down for the described, the package was those cases where water prescribed period of time, and opened and inspected. The inner inleakage has not been then placed in the water container was dry, the silicone assumed for criticality immersion tank under 3-1/2 feet rthber gasket was not damaged, analysis, the specimen must of water. One hundred-twenty and analysis of the UO P "d''
2 be immersed under a head of pounds of weights were attached showed there was no significant water of at least 0.9 m to the unit to insure that it increase in the moisture (3 ft) for a period ot' not would sink, it remained
: content, less than eight hours and in submerged for 10 hours.
the attitude for which maximta leakage is expected.
(5) Immersion-all packages. A The BU-7 package was submerged There was. no water leakage in separate, undamaged specimen to a depth of 50 feet above the the inner container after eight rust be subjected to water container for a period of eight hours o' submergence in 50 feet pressare equivalent to hours.
of water.
immersion under a head of water of at least 15 m (50 ft) for a perloc of nat less than e @ t hours. For test purposes, u external pressure cf water of 147 kilopascal (21 psi) gauge is considered to meet these conditions.
m LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1
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4.0 CRITICALITY SAFETY EVALUATION
/,
y, 4.1 URANIUM OXIDES IN POWDER FORM - H/U RATIO 10.45 For the contents described in Section.s 2.7.1(1-) and 2.7.2(1) (uranium oxide powder with H/U ratio 1 0.45),
the criticality safety of the BU-7 package is described in Appendices C and D.
These analysis results demonstrate that for these contents, the BU-7 package can be transported as Fissile Class I, pursuant to the applicable sections of 10 CFR 71.
4.2 URANIUM OXIDES IN POWDER FORM - H/U RATIO 11.6
& C/U Ratio 11.27 For the contents described in Sections 2.7.1(2) and 2.7.2(1) (uranium oxide powder with H/U ratio f 1.6 and C/U ratio 1 1.27), the criticality safety of the BU-7
(~)
package is described in Appendix C to this application.
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These analyses results demonstrate that the BU-7 package can be transported as Fissile Class I, pursuant to the applicable sections of 10 CFR 71, for these contents.
4.3 URANIUM OXIDES IN PELLET FORM For the contents described in Sections 2.7.1(3) and 2.7.2(2) (uranium oxide pellets), the criticality safety of the BU-7 package is described in Appendices D and E.
These analysis results demonstrate that for these contents, the BU-7 package can be transported as Fissile Class I, pursuant to the applicable sections of 10 CPR 71.
LICENSE GNM-1097 DATE 12/22/86 PAGE lll DOCKET 71-9019 REVISION 1
t 5.0 TESTING, OPERATING, AND MAINTENANCE 5.1
. TESTING Inner containers are verified for leak tightness by a submerged bubble pressure test at 15.0 psig, minimum.
The test is conducted using a silicone rubber gasket as the only sealing agent between 'the flange and cover.
5.2 OPERATING 5.2.1 Inspection Prior to First Use The BU-7 package is inspected prior to first use to assure that the requirements of 10 CFR 71.85 are met, and to assure that it has been constructed in accordance with the package design as approved by the NRC.
()
5.2.2.
Inspections Prior to. Subsequent Use 1
Prior to subsequent use, each BU-7 package is inspected to assure that the requirements of 10 CFR 71.87 are met, and to assure that the effectiveness of the package has not been degraded.
5.2.3 Quality Assurance Program Constructior. and use of the BU-7 packages will be accomplished in conformance with 10 CFR 71.101 and the l
General Electric Quality Assurance Program as described in the submittal to the U.S. Nuclear Regulatory Commission made on December 27, 1978 and as currently approved on October 9, 1984.
LICENSE SNM-1097 DATE 12/22/86 PAGE 15 -
DOCKET 71-9019 REVISION 1
 
5.3 MAINTENANCE
_LO All BU-7 packages foured to be unacceptable as a result of inspections conducted either prior to first use or Prior to subsequent use will be identified for the necessary repair or maintenance.
Inspection of the repair or maintenance will be conducted prior to use.
O LICENSE SNM-1097 DATE 12/22/86 PAGE
()
DOCKET 71-9019 REVISION 1
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'6.0 BU-7 TRANSPORT PACKAGE SPECIFICATIONS O
Specifications for the BU-7 transport package are shown on General Electric Drawing 112D1592 in Appendix A.
O l
LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1
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APPENDIX A DRAWING 112D1592
" SHIPPING CONTAINER - MODEL BU-7" O
LICENSE SNM-1097 DATE 12/22/86 PAGE g
DOCKET 71-9019 REVISION 1
A
 
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THREADED FOR 5/8" DIA. BOLT GASKEI 1/8" THICK $1LICONE 1 INNER LID 45 TO 75 MRWiER (SEE DETAIL ZONE D-2)
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FOUR EOUALLY SP CED 1/4" DIA. VENT HOLES.'
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7/16* DIA THRU 12 HOLES
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GPCSS WEIGHT) 370 LBS. MAX. LOADED, O
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: 1. LEAK TIGHTNESS IS VERIFIED BY A SUBPIRGED BUBBLE PRESSURE TEST lANDNUT.(SEENOTE7)
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AT 15.0 PSIG, MI'llMUM. TEST IS CONDUCTED USING THE SILICONE IU3EER RUBEER CONTAINER GASKET AS THE ONLY SEALING AGENT. EETWEEN
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FLANGE AND COVER.
: 2. C0fwEXITY OF BOTTOM HEAD: 3/8* MIN TO 3/4" MAX,
: 3. MINIP2 CAVITY DEPTH REQUIRED TO ACCOMODATE PRODUCT CONTAINERS.
g 4.
ALL FAERICATION AND MACHINING DIMENSIONS ARE NOMINAL UNLESS
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IFTER FIDL ACCEPTANCE INSPECTION, PARK CONT 1.lNER WITH NE H-9) 1/2* (MIN!P.'M) CHARACTERS. USING WHITE PAINT:
J i * <'IE ET*3 (7-9 LBS ER CU.FT.)
GENERAL ELECTRIC COMPANY
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EDDEL EU-7 TYPE A r :: accmomct tim g: wtatat.s knia SP4 on as poeirica av oesp USA / 9019 / AF GROSS CMT V/P-6575.
7.
tFFIX TAMPER SAFE SEAL 10 3/8" DIA. E0LT PER REQUIREPENTS OF 10CFR11.43 (6),
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O APPENDIX B f
" TEST REPORT FOR MODEL BU-7 BULK URANIUM SHIPPING CONTAINER" O
John A.
Zidak 4/25/80 i
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LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1
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TEST REPORT FOR MODEL BU '7 BULK URANIUM SHIPPING CONTAINER In accordance with criteria for compliance with CFR49 -
paragraph 173.398 and 10CFR, paragraphs 71.31, 71.32 71.35 and 71.36 BY John A. Zidak Manager Packaging Engineering General Electric Co.
Nuclear Energy Traffic Operation San Jose, California DATE ISSUED April 25, 1980 e
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TEST REPORT FOR
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MODEL BU-7 BULK URANIUM SHIPPING CONTAINER b' f(
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==1.0 INTRODUCTION==
1.1 TEST DESCRIPTION Normal and Hypothetical accident condition tests were conducted on General Electric Model BU-7, Bulk Uranium Shipping Containers in accordance with 10CFR71, " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Cor.ditions." The tests were conducted at the Wilmington Manufacturing Department facility on March 20th and 21st 1980, and April 1st and 2nd 1980.
h The BU-7 Container is intended to be a fissile class I shipping container for shipment of enriched uranium powder.
1.2 PACV. AGING DESCRIPTION J
k Inner containment is a nominal 16-gallon drum closed by a gasketed-bolted lid, centered and supported within an outer 55-gallon drum (3
by a solid insulating media,.and containing two steel pails which
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contain UO2 (See Drawing 112D5231A and Figure 1.)
: 1. 2.1.
Outer Container A nominal 55-gallon, Uniform Freight Classification Rule 40,18 gauge steel drum with nominal outside dimensions of 22.82" diameter by 36.5" high. Fourl/4" holes near the top of the container are provided for venting and are covered with waterproof tape. The cover is flat 18 gauge steel. The closure ring is 12 gauge steel with 5/8" bolt meeting D0T Specification 17H.
1.2.2.
Inner Container A nominal 16-gallon drum constructed of 18 gauge steel, modified by welding a closure flange to accept a 3/16"'
thick steel lid. The lid is gasketed for resistance to high temperature and attached with twelve 5/16" steel bolts. The inside dimensions are 13.75" diameter by 27" high.
1.2.3.
Insulation The 16-gallon inner containment drum is centrally held hsr within the outer container by, and the space between the
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two drums is completely filled with, solid fire-retardant phenolic foam per USAEC Specification SP-9.
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Product Container
{g Two closed 5-gallon containers fabricated of 24 gauge steel, vertically stacked in each BU-7 container.
1.2.5.
Test Weight Each 5-gallon pail contained 45 kgs (99 pounds) of j
natural UO2 powder. Total test weight including weight of the 5-gallon pails is 209 pounds. Gross weight of the BU-7 is between 365 and 375 pounds, depending on variations in weights of BU-7 container populations.
Actual gross weight of the two 5-gallon pails as recorded on the computer weigh sheets was 94.81 kgs (209 pounds) for container S/N K0174, and 95.29 kgs (210 pounds) for container S/N k1878).
2.0 TESTING 2.1 TEST
 
==SUMMARY==
The test program consisted of a combination of normal and hypothetical accident condition tests as described in 10CFR71 Appendix A and B.
Three BU-7 containers were utilized in the tests. They were taken from the G.E. inventory of containers at Wilmington and are built to same specifications as all model BU-7 Containers. Serial numbers and tests they were subjected to is as follows:
('
' CONTAINER SERIAL TEST CONDITION WUMBER TESTED WATER SPRAY TEST K0319 DROP TEST 4 FT.
K0319 Normal.Cond.
-i tests PENETRATION TEST K0319 COMPRESSION TEST K0319 30 FEET FREE DROP K0174 K1878 Hypothetical Accident PUNCTURE TEST K0174 K1878 Con tion THERMAL TEST K1878 WATER IMMERSION TEST Kl878 Container No. K0319 was used only for the normal test conditions.
K0174 was drop tested 30 feet impacting on the bottom seam, then puncture tested. Container S/N Kl878 was drop tested 30 feet impacting on the closure ring, then subjected to all remaining hypothetical accident conditions, that were applied sequentially in the order indicated in 10CFR71 Appendix B, to determine their cumulative effect on the package. All tests were monitored by General Electric Fuel Quality Control Engineering, and certified O(-
there completten per test check sheets in the Appendix.
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LOADING p
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2.2.1 Hypothetical Accident Loading
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Containers K0174 and K1878 were loaded with approximately 45 kilogram:s (99 pounds) of natural U02 powder, in the Fusi Mancfacturing Operation (FMO) powder pack facility, using a corrputer controlled loading and accountability system, see figures ( 2 and 3) the computer punch cards remained with the 5 gallon pails of powder during the tests. (Loading Record Sheets and Request Sheet are in the Appendix).
2.2.2 Normal Condition Loading Container Serial No. K0319 was loaded with lead snot weighing 93 Kg's (205 pounds) gross weight.
2.2.3 Moisture Content Moisture content analysis of the natural uranium powder was made before and after the Hypothetical accident tests.
., 2.3 NORMAL CONDITION TESTS NOT CONDUCTED OI The following normal. conditions tests were not. conducted becau.se their requirements have been satisfied for the following reason:
(
* Heat:
Temperature of 130*F is within normal operating range for materials of construction.
* Cold:
Temperature of -40 F is within normal operating range for materials of construction.
* Reduced Pressure:
Successfully passed this requirement in prior tests. (See GE Packaging Engineering test report dated 2/10/78 included as Appendix 3.)
* Vibration:
Centainers of this type have withstood years of transport with no occurences of significant damage due to normal vibration.
* Corner Drop:
Not required since package weight exceeds 110 pounds.
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I 3.0 TEST RESULTS 3.1 Normal Condition Tests. (container S/N 0319) f 3.1.1 Water Spray Test
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Container was exposed to a water spray sufficiently heavy to keep all exposed surface except the. bottom wet for a period of 30 minutes. (See Fig. 4).
RESULT There were no signs of water damage to the package.
3.1. 2 Four Foot Drop' Test The container, loaded with 205 pounds of test weight was dropped four feet with the closure ri.ng impacting onto a flat reinforced concrete pad. Test was conducted 2 hours after water spray test.
(See Fig. 5).
4 4
RESULT There was a slight deformation of the outer container closure ring that did not impair its function. No damage to the inner container seal or the 5 gallon pails.
3.1.3 Penetration Test O
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Container was penetration tested by impacting the f
hemispherical end of a vertical steel cylinder 1-1/4 inches in diameter and weighing 13 pounds and dropped from a height of 40 inches into the top of the container where it is most susceptible to a projectile penetration.
(See Fig. 6).
RESULT There was a slight indentation where the 13 pound bar struck the container. It did not penetrate the package.
3.1.4 Compression Test Weight equal to more than 5 times the weight of the package be applied to top of the containers for a period of 24 hours. (Minimum weight for BU-7 is 5 times 375 pounds, or 1,875 pounds). Test weight used was 2,440 pounds (.See Fig. 6).
RESULT No damage due to compression loading.
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3.2 Hypothetical Accident Condition Tests Ta araath tic i accideat coadit$aa * =*=
r coaduct d O(4 in the sequence specified in Appandix B to 10CFR71, to
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evaluate the ability of the package to with:;tand cumulative damage of the four tests. To establish the drop orientation that covers the most severe damage, two containers (S/N K1878 and K0i74 were selected at random,.then one (k1878 was dropped on its top closure ring and'the other (Serial No. K0174), impacted on the bottom seam as these are the ones most likely to create a breach; impact angle of both tests was approximately 45*.
After completion of the drop test, both containers were puncture tested, then container S/N Kl878 was subjected to the thennal and water immersion tests.
3.2.1 Free Drop The pacirages were raised by.a crane to a 30 foot height at approximately a 45' angle as shown in figure.
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The height was determined by a measured, weighted cord hanging from the containers. A quick release mechanism was used to drop the packages, which fell of the containers (See Fig. 8 and 9)g on the corners at approximately a 45' angle, landin i
RESULT Both containers impacted at the pre-determined angles.
(.I Areas at points of impact of both units were without
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N fracture. Beyond this, the only significant damage was a slight opening of the cover where the closure ring of container No. K-1878 was deformed, as shown in Figures 10 thru 14. The bottom corner free fall test of container K0174 caused somewhat more crushing of the container than was experienced in the top drop. There was no evidence of fractures or separation of the containers side from the bottom (See Fig.15 and 16) therefore the container with the slight opening due to the top drop was deemed to have suffered the maxhnum damage.
Past test inspection showed N0 damage to the sealing features of the inner container or to the 5 gallon pail s.
3.3.2 PUNCTURE TEST Containers K-1878 and K-0174 were free dropped through a distance of 40 inches, striking the top end of a vertical steel bar mounted on a reinforced concrete pad. The bar was fabricated per the requirements of 10CFR71, Appendix B (See Fig.17).
A vertical drop with the container impacting on the 18 OL gauge cover near the outer edge was considered the most vulnerable orientation to puncture.
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3.3.2 PUNCTURE TEST (cont.)
m RESULT
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Both packages were slightly' indented about 1/4 inch, there was no puncture of either container.
(See Figures 18 and 19).
=
3.2.3 THERMAL TEST A Thermal Test of container No. K-1878 followed the 30 foo.t free drop and puncture tests. The thermal test conducted required exposure to an environment of 1475* minimum for a period of 30 minetes. Since an actual gasoline fire with open flames proddes the most realistic means of satisfying the requirements of 10CFR70 thennal test, this method was chosen for the BU-7 test.
Test set up as shown in Fig. 20 was used. The gasoline and' water supplies were. located 100 feet from the fire pan.
A thermocouple mounted on the closure ring adjacent to the slight opening of the container lid was monitored using a Honeywell Model R7353A Dial-0-Troll, Serial No. 7812-3849, which was calibrated using a West millivolt pot that has traceability to the National Bureau of Standards.
l The eight foot square fire kit with container mounted 3 feet O<-
hove the surrace iiowea~ror paroximateir 2 reet or rie=es A.
around all sides of the container.,By using the open gasoline L
fire', the emissivity and absorbtion coefficients were in accordance with those specified in 10CFR71. Appendix B.
3.2.3.1 Test Procedure Approximately 200 gallons of water were fed into the pit resulting in a water level of 5 inches.
Approximately 50 gallons of gasoline were then fed into the steel fire pit to form a layer of fuel about one inch deep on top of the water surface.
I After ignition, (See Fig. 21) the fuel and water supplies were turned on and manually controlled to one gallon per minute of water and 5.8 GPM of fuel to maintain a fire that completely enveloped the BU-7 Container. Figures 22 thru 31 are random photographs taken during the test. The temperature measured on the surface of the test container increased rapidly to 1475* F. (See Figs. 32 and 33]
and exceeded that throughout the test with a maximum temperature of 2000* F. being reached. The full pd fire test continued for 42 minutes burning 300
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l gallons of fuel during that period.
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3.2.3.1 Test Procedure (cont.)
RESULTS n{
Inspection of the inner container after V
all the tests showed no damage to the
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inner container, its sealing features or to the 5 gallon pails that would yield either of them ineffective. The paint was slightly blistered in a small area at the
' top and of the inner container, but no indication of this~ on either of the 5 gallon pails containing UO2 Powder.
3.2.4 Water Imersion Test After the fire test, container No. K-1878 was allowed to cool down for the prescribed period of time, and then placed in the water immersion tank (See Fig. 34) under 31/2 feet of water. One hundred and twenty pounds of weights were attached to the unit to insure that it would sink; it remained submerged j
for 10 hours.
RESULTS Following immersion as described, container No. K-1878 was opened and inspected. The inner contafner was dry, the silicone rubber gasket was not damaged, and analysis of the
(
UO2 powder showed there was no significant increase in the
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i moisture content.
N 3.2.5 Post Test Inspection l
Upon completion of the four hypothetical accident condition tests, conducted the sequence prescribed in 10CFR71 container Serial No. Kl878_ was opened and inspected. As prevIously mentioned, there was no damage to the inner containment l
sealing features; the computer weight cards were with the 5 gallon pails; they were not wet and there was no moisture in t
the inner container.
(See Figures 35 thru 38). The top insulation disc was badly charred (See Fig. 39) ind the out-
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side of the bolted cover had some blistered paint, but there was no structural damage, breach of containment or loss of shielding. Post Test condition of all three containers tested is shown on Figure 40.
I 3.3 Acceptance Criteria Acceptance Criteria for meeting the requirements of 10CFR71( paragraphs 71.35 and 71.36 was as follows No water intrusion to the contents.
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No rupture of the product containers or inner container.
No damage to the inner containment sealing features that would yield them ineffective.
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3.3 Acceptance Criteria (cont.)
No significant deformation to the outer container that would
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affect criticality safety consideraticas.
3.4 Conclusion All tests required by 10CFR71, have been conducted, witnessed by Quality Control Engineering and have passed the acceptance criteria.
Test completion check sheets and compliance certificates are included in the Appendix.
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LIST OF FIGURES 1
1.
BU-7 CONTAINER 2.
WEIGHTING UO2 POWDER 3.
LOADING 5 GAL. PAILS INTO BU-7 4.
NORMAL CONDITION WATER SPRAY TEST 5.
NORMAL CONDITION 4 FOOT DROP TEST 6.
NORMAL CONDITION PENETRATION AND COMPRESSION TESTS 7.
30 FOOT DROP TEST 8.
CONTAINER NO. K0174 IMPACTING ON THE BOTTOM CORNER 9.
CONTAINER NO. K1878 IMPACTING ON THE CLOSURE RING 10.
SERIAL NO. K-1878 AFTER IMPACT 11.
SERIAL NO. K-1878 AFTER IMPACT 12.
SERIAL NO. K-1878 AFTER IMPACT 13.
SERIAL NO. K-1878 AFTER IMPACT 14.
SERIAL NO. K-1878 AFTER IMPACT 15.
CONTAINER NO. K0174 AFTER 30 FOOT DROP 16.
CONTAINER NO. K0174 AFTER 30 FOOT DROP 17.
CONTAINERS K-1878 AND K-0174 DURING PUNCTURE TEST 18.
CONTAINER NO. K-0174 AFTER PUNCTURE TEST 19.
CONTAINERS NO. K-1878 AFTER PUNCTURE TEST 20.
THERMAL TEST SETUP
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IGNITION OF FIRE TEST 22.
THERMAL TEST 23.
THERMAL TEST 24.
THERMAL TEST 25.
THERMA'. TEST
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THERMAL TEST 27.
THERMAL TEST 28.
THERMAL TEST 29.
THERMAL TEST 30.
THERMAL TEST 31.
THERMAL TEST 32.
HONEYWELL DIAL-0 TROLL SHOWING TEMPERATURE READING DURING THERMAL 33.
HONEYWELL DIAL-0 TROLL SHOWING TEMPERATURE READING DURING THERMAL 34.
WATER IMMERSION TEST 35.
POST TEST INSPECTION 36.
POST TEST INSPECTION O(-
37.
POST TEST INSPECTION 38.
POST TEST INSPECTION h
39.
CHARRED INSULATION DISC 40.
CONTAINEFS AFTER COMPLETION C
 
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par,E 1 of 3 Oc AeeenDix 1 COMPLIANCE The test referenced in Paragraph 5 have been conducted and satisfactorily meet the acceptance criteria of the test plan.
Container Drawing No. 128ns231 Container Serial No.
K1878 Date Tested 3/20/80. 3/21/80, 4/1/80 and 4/2/80 Oc M,
Y-2-70 Packaging Engineer v
@/F4#
Fuel Quality Control Engineering f
V[2t[8-Licensing & Compliance Audits i
f /,/pd Traffic & Material Distribution W
i I
 
PAGE 2 of 3
{
APPENDIX 1 COMPLIANCE l
The test referenced in Paragraph 5 have been conducted and satisfactorily meet the acceptance criteria of the test plan.
Container Drawing No. 128D5231 Container Serial No.
K 0174 Date Tested 3/20/80 and 3/21/80 Packaging Engineer 8
K 2.-Pa a
Fuel Quality Control Engineering M M-/DIO Licensing & Compliance Audits t/,1/
Traffic & Material Distribution f/
d
/
r OL i
 
par-E 3 of 3 Oc APeENotx 1 COMPLIANCE The test referenced in Paragraph 5 have been conducted and satisfactorily meet the acceptance criteria of the test plan.
Container Drawing No.
128D5231 Container Serial No.
K 0319 Date Tested April 1, 1980 O(
Y-2.40 Packaging Engineer a
//-/(/-70 Fuel Quality Control Engineering e
Y
/
Licensing & Compliance Audits
/
'777 M
,t//fo Traffic & Material Distribution
/
t Ot
=
 
PAGE 1 of 3 APPENDIX 2 j
(
TEST CHECK SHEETS Container Drawing No.
/ N 8 8 f23/
Container Serial No.
K /T 78 s
Date Pre Test Visual Inspection
[/
J/.ro/po l
per Paragraph 5.1 fosporoor#
Loading faK W*Rggg6Po0G' Ob20lN Water Spray Test O(
Drop Test Penetration Test Compression Test 30 Feet Free Drop i
g/w %/M
////.Id/M Puncture Test l
Thennal Test
/A (8
Water Immersion Test A
Yfd l
l Fuel Quality Control Engineering
/
I L_.
 
PAGE 2 of 3 rxQ{
APPENDIX 2 TEST CHECK SHEETS Container Drawing No. /jE O 5'23/
Container Serial No. KO/7Y Date Pre 'est Visual Inspection per Paragraph 5.1 M G[ta/ro fs2.R8P oot #
Gdto/ro Loading pppopoetr Water Spray Test
~
O(
oroP Test
~
o Penetration Test T
Compression Test 30 Feet Free Drop i
A //,,7/w/9
/$29.?pff Puneture Test
~
Thermal Test Water Innersion Test Fuel Quality Control Engineering 7
: OL
 
PAGE 3 of 3 i
Oc Aeeenoix 2 TEST CHECK SHEETS Container Drawing No. /#38f2 J/
Container Serial No. kO319 Date Pre Test Visual Inspection per Paragraph 5.1 (aoS#Geod
/A% f[1s/Sa Loading Ah 3/18/fo Water Spray Test Je f[i/fa
)% 'ffffD Drop Test Penetration Test dr77 Y//fD
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Compression Test
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Request N).
[O-79 NSR Area No.
(~'s PROCESS AND EQUIPMENT / FACILITIES CHANGE REQUEST U
questor Initiating Component _ M S Installation Responsibility
. Equipment Location C M MO POWDER PACK AREA AND TEST PAD WEST Or FMUA.
Purpose of Change T1.5T LOADED BU-/ AND BU-b COHTAINt.R5 YOR Mt,LIC1.Nbt.
BY G NRC.
NATURAL..
Description of Change STAHDARD PACK b b-tuALLUN l' AIL 5 WIT 11 4D KUb UU
'V' 9
EUA]
LOAD AND SEAL IN { BU-7 AND 1 BU-5 CONTAINERS.
TEST CONTAINERS TO NRC TEST STANDARDS ATTACHED (30-FOOT DROP, 40-INCH, FIRE, ETC.)
Scheduled Project Completion Preliminary NSE Review N dB
.glu/8 Final NSE Review Needed By 3/18/80 Requestor's Signature /Date h 7
4/ly/8 kQ
** ' L(AIM Nuclear Safety Engineering 3f/
6 1.
Type Analysis Required: *Cri ticality O
*R diological O
None 2.
New/ Updated NSE Method Sheet Required: Crit.
d Radio. /\\/O None 3.
Anticipated Availability of NSE h q Shee gLf Required
.3
/ o it 4.
Signatures:lCrit a ityhSafe I
1
/J M c io logical Safet
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Remarks:
i-W o r-110 0 <.hJ Llra- -
A 5.
t
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Fuel Quality Control Engineering Np C
1.
Is New/ Changed Quality Instruction Required? Yes No If Yes, Antic'ipated Availability of Instruction 2.
Responsible Fuel Quality Control Engineer 3.
Approval:
Mgr., Fuel Quality Control Engineering Fuei Process Technology //p s.
1.
Is New/ Changed Instruction Required? Yes No If Yes, Anticipated Availab'lity of Instruction I
2.
Responsible FPT Engineer t
3.
Approval: Responsible FPT, Unit flanager SHOP hv rs 4
~-
Subsection Manager Approval b^
'N l
Area Manager 1.
Priority Assignment.For Nuclear Safety Review 2.
Area Manager Approval b' e:c,p Nuclear Safety Engineering Date Approved Request Receihd Date Completed N
Ot. Meneser Accentence of Completed ero3ect Dete
* Documented information from requestor required per P/P 40-5 Appx. A APPEN9fX 4 NF-1-014 (11pf)
URANIUM POWDER LOA. DING REQUEST
- l' a.
* 2 APPENDIX 3 Page 1
$0VlAh GENERALQ ELECTRIC
-pC'k RELATIONS AND IfrILITIES OPERATION San Jose, California February 10, 1978 TEST REPORT BU-5 AND BU-7 CONTAINER PRESSURE TEST A.
OBJECTn'E The objective of this test was to verify the integrity of the BU-5''
and BU-7 containers for the New Japanese Container Regulations, f]{
The procedures were presented to the Japanese and approved by them.
B.
SibNARY i
The following tests were performed on one BU-5 and one BU-7 con-tainer on Febniary 6,1978 thru February 10, 1978.
2 1.
Both containers were tested under water to 1.50 Kg per 01 i
for eight hours. This was done by submerging them in the test l
tank in Building G, to a depth of 50 feet above the containers.
l 2.
The containers were then pressurized internally and checked for l
1eakage at four increments:
?
a.)
.75 Kg/G1' for tlirea hours b.)
1.0 Kg/01 f r three hours 2
t 2
l c.)
1.25 Kg/01 for three hours l
l d.)
1.5 Kg/Or for three hours i
I x) --
1-
 
GENER AL $ ELECTRIC
*(d (
TEST REPORT 2-10-78 Page 2 C.
TEST EQUIPMENT The following equipment was used in the test:
1.
60 feet deep test tank 2.
BU-5 container S/N B-7522 3.
BU-7 container S/N K-0397 4.
Permagage # 175 0 to 60 psi pressure gage, regulator and valves as shown in Figure 1.
D.
CALIBRATION The pressure gage was calibrated prior to testing. Calibration record and curve (Figure 2) are included in this report. Calibra-(a (
)
tion was made with equipment traceable to the National Bureau of Standards conformance.
E.
TEST RESULTS 1.
Water Imersion Test There was no water leakage in the inner containers after eight hours of submergence in 50 feet of water.
2.
Air Pressurization Tests There was no leakage of air from the inner containers when pressurized as shown in Figure 1 and held at pressure incre-ments of.75,1.0,1.25 and 1.50 Kg per square centimeter for periods of three hours for each pressure increment.
CCNCLUSION The BU-5 and BU-7 containers passed all the pressure test require-ments for the New Japanese Container Regulations.
In fact, the tests exceeded their requirements. The water submergence test was for eight hours rather than three, and the BU-7 container was tested at Ot t
O
 
GENERAL $ ELECTRIC Oc rest ne a r 2-10-78 r
Page 3 2
1.25 gm/cm for 14 hours. There was no leakage in either case.
1 i
/,
Certified By:
Ge7
/
J. A. Zidak W. S. Cdwan, Manager Packaging Engineer Packaging Engineering M/C 512 M/C 512 JA2/da e
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Mall!TEl'Al'CE RECORD TECHNOLOGY & DEVELOPMENT METROLOGY & CALIBRATION LABOR ATORIES
: 3. REVIEWED BY DATE
: 4. F AMILY CODE
: 5. MF R CODE
: 6. MODE UDWG NO.
: 18. RACK /SYS IC NO.
bESSA$LE k
hCMA6AG6 bd b
: 7. IC NO.
: 8. ST ATUS
: 9. PREVIOUS CYCLE N/A La usE 9/A
: 10. MOS E )PSE D % e. C,aG, 11.
: 19. OPE R ATION NA
: 12. D ATE SE RVICE D
: 13. D ATE OUE
: 14. CAL HRS 15.MAINT HRS 16.OTHER HRS 17,
: 20. LOCATION b 'YR)h FW bb 'YRUD 1.O 0.0 0.0 Tmtet 9 FW
: 21. M ANUF ACTU RE R
: 22. INSTRUMENT NAME
: 23. SE RI A L NO.
MA ssi4A.tLTok.N T'fE46u 9 e GrAuGE 84 f EE
: 24. SPE CIF IC AT SONS
: 25. PROCEDURE USED I. L d M - 1 ?_ - 00 5' W MFG
: 26. D AT A ISSUE D F O OTHER (DESCR18El-O YES
: 27. REPORT NO.
SJ O
: 28. TYPE OF SERVICE
: 29. R E C EIV E D 30.LAST SERVICEO
: 33. LABOR ATORY ENVIRONMENT
!YR FW D !YR
[CALIB R ATION CE RTIFICATION FW TEMPE R ATURE
'C
: 31. ASSIGNED RECAL L INTERV AL O PREVENTIVE MAINTENANCE hi RELATIVE HUMIDITY
'~
: 32. SPE CIF ICATIONSF
: 34. OPE R ATION ALP M
O OuT MES O NO O(r l
CALIBR ATION INSTRUMENTATION USED MFR MODEL DR AWING NEXT OUE MFA MODEL DR AWING NEXTDUE I
O.
IC NO.
CODE NUMBER FOR CAL CODE NUMBER FOR CAL ME eMM-83 24 60063 5 -s-76 s
1 i
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=
 
Call 8 RATION DATA P.
1 MENT NAME ICfdO.
MFR Mats 9 ALLToted MODEL ORAWING NO.
SE R4 AL NO.
Il4MAdA&E 176 Oh! E6 l
i FUNCTION AND/OR Call 0R ATION NOMINAL RANGE TESTED TOLERANCES VALUE 1NITI AL RUN T L(/
FINAERUN 6-60 PSIGr SrAudAno cAuce TE6T o
e o
s
: 4. 5 6
l0 9.35 lo ts 14.0 5' 15 20 19.0 5 Do
~25 D V. 90 D5 30 99,25 So 4o S9. c o 4o
.k SD
'l9.60 50 60
: 59. G0 Go Oc t
 
O G
APPENDIX C
" CRITICALITY SAFETY ANALYSIS OF POWDER" BU-7 SHIPPING CONTAINER FOR 00 2 O
W. C. Peters 3/6/80 LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1
i
 
Prepared:
3/6/80 CRITICALITY $AFETY ANALYSIS OF gC g
Sh#
BU-7 SHIPPING CONTAINER FOR UO POWDER 2
 
==1.0 INTRODUCTION==
Model BU-7 shipping containers are used by the General Electric Company for the transportation of low-enriched unirradiated uranium oxide powder.
The BU-7 container is a fissile Class I package which is currently licensed for a maximum U-235 enrichment of 4.0% with no more than two five -
gallon containers, each limited to no more than one safe batch of UO, powder.
In addition, it is required that the H/U ratio in the fuel in each five-gallon container must be no more than 0.45.
The purpose of the present analysis is to extend the Fissile Class I certification for the BU-7 to include the following:
1.1 Increased water moderation by increasing the fuel H/U limit from 0.45 to 1.577.
1.2 Replacement of the safe batch limit with a limit of 35 Kg 00 per five-gallon container.
The total BU-7 9
O3 container mass limit is still 89 Kg.
k[/ k 1
1.3 Reduced levels of insulating media (phenolic resin) composition and densities requiring that at least 60%
by weight of each of the constituents of the full density phenolic resin must be present.
1.4 The presence of carbon in the UO fuel provided that the 2
C/U ratio in the UO fuel mixture does not exceed 1.262.
2 All other limits and requirements for the BU-7 container are unchanged.
2.0 ANALYSIS SCOPE The present analysis has been undertaken to demonstrate that the GE Model BU-7 shipping container meets the applicable criticality safety standards for Fissile Class I shipping packages as required by Part 71, Title 10, of the Code of Federal Regulations.
2.1 BU-7 Container Specifications This analysis is valid for the following BU-7 container
(
specifications.
p N
\\
m
 
('
-v i.
2.1.1 Outer Container g)mp' 18-gauge, 55 gallon steel drum, or similar drums larger in dimensions or with thicker steel walls (reference Drawing 128D5231).
Drums with smaller dimensions or with steel walls which are ' thinner than 18 gauge are'not covered by this analysis.
2.1.2 Insulation Phenolic resin containing the amounts of hydrogen, boron, carbon, nitrogen and chlorine and minimum
~
resin density as shown in - Table 4.1.
2.1.3 Inner Container 16-gallon, 18-gauge steel drum with an inner diameter of 13.75
* 0.25 inches and an inner height of 27.75
* 0.25-inches.
This container must have a leak-proof seal and cover as described in Drawing 128D5231.
2.1.4 Contents
()r)
Two five-gallon steel containers or three Ae three-gallon steel containers with an inner g)./
diameter no greater than 11.25 inches and with a total stacked height of no more than'27.64 inches.
The steel containers must be at.least 0.0206 inches thick.
Plastic bags wrapped around the five-gallon container or used as a liner inside of the container are permitted.
2.1.5 Fuel Up to 70 Kg of UO powder per BU-7 container at 3
a U-235 enrichment of no more than 4.0%.
Each five-gallon product container may hold no more The UO powder may be mixed than 35 Kg of UO7
-with water or hydrogen-car $on additions subject to the requirements that the fuel-additive mixture may not exceed:
.1 an H/U ratio of 1.577 l
l
.2 a C/U ratio of 1.262
( )['
In addition, the bulk density of the U0, powder may not exceed 4.5 gm/cc.
,M.
y-r
-,-.---.,,--,r
,--,-%-..,,--------v-.e-+-..-.v,.---.%..
- -.... - - - -,. ~. - -.
-m
,w.
 
2.2 Fissile Class I Criteria f~s t
/gs I
To demonstrate that the BU-7 shipping container as
~%sd (
described in Section 2.1 meets the criticality safety standards for Fissile Class I packages as defined in Part 71, Title 10, of the' Code of Federal Regulations, j
the following calculations have been performed.
2.2.1 Normal Case The'K.
of an infinite array of BU-7 containers has been calculated for three cases:- full density phenolic resin, 80% of full density phenolic resin and 60% of full density phenolic resin.
2.2.2 Accident Case The K gg of a 256 unit array has been calculated e
for the conditions of optimum interspersed modera-tion.and full reflection of the array.
This analysis was performed for BU-7 containers limited to 2 x 35 = 70 Kg of UO2 as well as for the case of the two product (five gallon) containers filled with powder at a U02 density of 4.5 gm/cc (202 Kg UO2 total).
p 2.2.3 Evaluation of Carbon
()
The most reactive cases in 2.2.1 and 2.2.2 (with 35 Kg UO /five-gall n container limit) were 2
reanalyzed for UO -H O mixtures to which an addi-2 2
tional amount of carbon was added.
The atom density of the carbon was taken to be 80%'of the atom density of hydrogen in the mixture to simulate mixtures of U0,10,000 ppm by weight of 2
water and 40,000 ppm by weight of H-C additives.
l 2.2.4 Accidents Involving a Single BU-7 Container To demonstrate the safety of a single BU-7 con-L tainer under extraordinary upset conditions, two five-gallon product containers have been analyzed
~
for optimum moderation and full reflection by water.
2.2.5 Concrete Reflection The impact of concrete reflection of the most reactive 256 unit array as described in Section 2.2.2 has been analyzed.
l b
3-
~
1 i
.m.,_,__,
 
.l
?
'~
2.2.6 Code validation
%m#
fTo demonstrate the validity of the computational codes used in this analysis, validation calcula-i tions have been made for the following cases:
.1 Comparison between codes for: -
e Normal case (K. ) BU-7 container e
256 unit array of BU-7 containers with optimum interspersed moderation'and full reflection by water e
A single BU-7 container with 0.075 gm/cc of interspersed water i
e Two five-gallon containers in a vertical j
column with optimally moderated UO and 2
with full reflection by water
.2 Calculation of the K ggs of the low enriched e
U038 low moderated benchark critical experi-ments described in Reference 7.
l-2.3 Analytical Methods (I
i.
The criticality analysis of the BU-7 container has been performed with the General Electric' Company MERIT and I'
GEMER codes and with the KENO IV Monte Carlo Code.. MERIT and GEMER are Monte Carlo neutron transport codes which employ 190 broad group cross section sets generated from ENDF/B-IV and which treat resonance absorption by explicit-ly modelling the resonance parameters on a discrete energy basis.
The difference between MERIT and GEMER is that the
'former has a geomet'ry package especially designed to model HBWR lattices while the latter has an enhanced version of the regular and generalized geometry packages in the KE'NO IV code.
l The KENO.IV Monte Carlo' Code was used in this analysis with 16 group modified Hansen and Roach cross section sets (Reference 5).
4 i
3.0
 
==SUMMARY==
AND CONCLUSIONS l
The results of this analysis have demonstrated that the GE Model BU-7 shipping container meets the criticality safety requirements i
of 10 CFR 71 for a Fissile Class I package for the transporta-l tion subject to the conditions specified in Section 2.1 of this
{]}.
analysis.
'In summary, these results are:
V' -
 
4-3.1 Normal Case
[
The K=
calculated with KENO IV for the normal case BU-7 container is 0.903 + 0.003.
3.2 Accident Case The K,ff calculated with KENO IV for the 256 unit array of BU-7 containers with the most reactive degree of interspersed moderation and with full reflection by water is 0.955 1 0.005 for 202 Kg UO per BU-7 container 2
and 0.750 1 0.005 for 70 Kg UO2 per BU-7 container 3.3 Presence of Carbon The presence of carbon in amounts which, result in a C/U ratio in the fuel of no more than 1.262 increases the K gfeggiy, of the 30-7 container by less than 1.25%.
e Applying this to the values in 3.2 and 3.1 above for BU-7 containers limited to not more than 70 Kg U0 per 7
i; container does not result in critically unsafe reactivities for these cases.
%/(
3.4 Two Five-Gallon- (Product) Containers calculated with KENO IV of two closely packed TheK,gflonproductcontainerswithoptimummoderation five-ga and full reflection by water is K,ff = 0.968 1 0.006 if the U0 contents of.the 2
containers are not restricted (approximately 65 Kg U02 per container) i 1
K,ff = 0.909 1 0.005 if the UO contents of each of the containers are restricted to 35 Kg.
t 3.5 Concrete Reflection Concrete reflection on all six sides of the 256 unit accident array of BU-7 containers (limited to 70 Kg UO 2 per container) results in a K f 0.789 1 0.004, an increase of 5.2% overthewakfer reflected system.
e k_
sd,
N
~
 
3.6 Code Validation
/"Tk l(.
The validation calculations performed in this analysis
,b,p have demonstrated that 3.6.1 For infinite or finite arrays of BU-7 containers, MERIT'and GEMER predict neutron multiplication factors from 2 to 5% lower than the values calcu-lated by KENO IV.
MERIT and GEMER results are in excellent agreement.
The discrepancy with KENO is due in part to the cross-section sets used in the KENO calculations.
The cross-section sets were determine based only upon the moderation in the fuel mixture.
3.6.2 For a single BU-7 container, MERIT, GEMER and KENO IV all agree with 0.4%.
3.6.3 Likewise, MERIT, GEMER and KENO IV are in excellent agreement for the case of two closely-packed opti-mally moderat2d fully reflected five-gallon con-tainers (with U0 contents of 65.8 Kg or more per 2
container).
3.6.4 For the Rocky Flats low enriched U 0 low moderated 3g benchuarks, the KENO IV calculated Kefg averaged
( )g over the 10 cases is 0.997 + 0.002 and the GEMER
\\
value is 1.003 + 0.003.(for 7 cases)
M
~
4.0 PACKAGE DESCRIPTION BU-7 shipping conta'iners are 55-gallon drums ionstructed of 18 gauge steel which contain an inner 16-gallon, 18 gauge steel drum enclosed in and supported by a phenolic resin liner.
Specifications of the BU-7 shipping container are given in Figure 4.1, Drawing 128D5231, Figure 4. 2 (ANSI MN 2.2-1974, UFC-Rule 40 55-gallon drum) and Figure 4.3 (. NSI MH 2. 5-1974, DOT specification 17H 55 gallon A
drum), and include:
55 gallon drum dimensions:
Diameter 22 inches Height 33 5/8 inches Thickness 0.0428 inches Material Carbon steel 16 gallon drun. inner dimensions:
Diameter 13 15/16 inches Height 27 inches Thickness 0.0428 inches Material Carbon Steel 5 and 3 gallon product container:
Diameter 11 1/4 inches
( )(.
Inner Dimensions Height 13.5 inches (5 gallon) 7.5 inches (3 gallon)
Thickness 0.0208 inches Material Carbon Steel M
M h%
 
FIGURE 4-BU.; gnIPPING CONTAINER
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ANSI MH2.2-1974 FIGURE 4.2 - UFC-RULE 40 55-GALLON DRUM O(
23U
=
16 7
7 I.
H 7..
g 2317 32 23h-
- - -Q. A...-
,,v..
s s
- g-I l
.E Il 8 f
l 1
'(
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l_
O(
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34 4
.i 351 Il 16
(
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l
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_ gg 5
i 2
3-MIN (SEE NOTE 2)
- M AX j
4
{
l I. _. _.._
lI
.....t.
t..
.I.
b 4
NOTLS:
h].
: 41) All dimeniions ase in in.hn.
\\JN i2) Minunus.:coniesity us liust.im head is 31s in.h
-B-
 
.~
ANSI MH2.51974 FIGURE 4.3 - DOT SPECIFICATION 17H 55-GALLON DRUM
(\\
h 23 IG 7
(~ 8 9
P m
.i 2
2 23
=
2 23h
=
^^ '^
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3 3-MIN 8
(SEE NOTE 21 3 max ra c
n 9
i La4 NOTLS:
OL ill lhese dinienseuns are ai pis.bte to tuth the sap anJ bottom he4Js. Minimum constut) of ea li tic 4J si 1 a in t11 Alldienentions are la in.fici.
V
- 8A -
_ j
 
The 16 gallon. drum has been modified by the welded attach-('T -
ment of a closure flange to accept a 3/16 inch thick steel cover whida s / (['
is gasketed for resistance to high temperature and is attached
\\sE by twelve 5/16-inch steel bolts.
This gasket has been demon-strated to survive the drop, flame, flood and impact tests required by 10 CFR 71 and insures that the five gallon product pails con-tained within the 16 gallon drum do not come into contact with additional moderating materials (for example, water) as a result of the postulated accident conditions.
Due to the 11.25 inch inner diameter and maximum height of 13.5 inches, a single standard product pail has a volume of no more than 22.5 libes.
This is less than the 29.0 liter. safe volume limit for containers of optimally moderated UO2 powder at en-richments not exceeding 4.0% U-235.
As described in Figure 4.1, the space between the concentric inner 16 gallon and outer 55 gallon drums is completely filled with a solid phenolic resin insulating material.
The chemi-3 cal composition of full density ( 8 + 1 lbs/ft ) phenolic resin is shown in Table 4.1.
Oc s
)
C )( %/
l
 
D (VV(
TABLE 4.1 CHEMICAL COMPOSITION OF FULL DENSITY PHENOLIC RESIN INSULATION ELENENIAL WEIGIT PEI'. CDC OBCANIC CO! POUNDS-WEIGIT PER CDE Element Full Density Weight Weight Element Per Cent Material Per Cent Hydrogen 4.S Union Carbide Phenolic 65.8 Besin BRL 2760 Boron 3.2 Silicone Surfactant LS30 2.0 Carbon 41.0 Boric Anhydride B-203 8.2 Nitrogen (approx) 0.0 Anhydride Oxalic Acide 8.2 Oxygen 48.6 Freon 113 6.6 luorine (approx) 0.0 Fiberglass Ibving 9.6 g
V Silicone 2.2 011orine 0.5
' Ictal 100.0 100.4 3
Density = 8 + 1 lb/ft Minimm Permissible Density 4.8 lb/ft OL a.
E
 
. l
({}.0 TECHNICAL CONSIDERATION
\\sI 5.1 Mixtures Densities The mixture atom densities used in this criticality safdty analysis are tabulated in Appendix A.
The 16 group modified Hansen and Roach U-235 and U-238 cross section-sets used in the KENO IV Monte Carlo calcula-tions were taken to be the sets corresponding to min min cr and cr U-235 U-238 with min dF o
g p
as described in Table 5.1 and with no other a satisfying ia*"
a i
e-Thea's are the potential scattering cross section values
/(
(in b arns) corresponding to U-235 and U-238 cross-section g/
sets (Reference 4).
11
 
EII 5.1 KENO IV RESWANCE ABSORPTICN CROSS SECTICN CAIfUIATICNS v
i a,
{
N 'i g
No where Ng = atom density of isotope i in mixture "i = potential scattering cross section for material i as tabulated below
% = atom density of isotope whose effective resonance absorption cross section is being computed Material / Isotope "i (barns)
Hydrogen 20.0 Carbon 4.7 Oxygen 3.8
. v(
U-235 15.0
:j U-238 10.7 Water 43.8 i
S D-v 12 -
i
 
5.1.1 Moderation of Fuel Mixture n
Jk As noted in Section 4.0, in leakage of water into
\\*/
the 16 gallon inner drum (and consequently into the five or three gallon product containers) does not occur under the postulated accident conditions (drop, flame, flood or imp.act).
The level of modera-tion in the five or three gallon product containers will therefore not change when the BU-7 containers are subject to the postulated accident conditions.
The maximum ncrmal levels of water'or hydrogeneous moderation in the UO2 p wder are:
.1 from 0.3 to 1.0% by. weight of moisture (H O) 2
.2 for certain blends of UO powder up to 4.0%
3 by weight of hydrogen-carbon materials for which e
the hydrogen content is less than the equivalent.of 4.0 weight per cent of water e
the ratio of atoms of hydrogen to atoms of carbon in the additive is no less than one.
(}{
5.1.2 Fuel Mixture Atom densities of the fuel mixture's for 4.0% en-l riched 002 powder and water used in the present analysis are tabulated in Appendix A.
These mixture densities were computed in one of two ways:
.1 Mixtures with 50,000 ppm of water or its equivalent For systems of UO2 powder and water in which the water content is restricted to low volumes, fuel-water mixtures may be determined by taking the maximum 00 density and water density 2
possible.
F,or UO powder, the maximum density 3
possible is less than 4.5 gm/cc unless mechanical presses (etc.) have been used to compress the powder.
Mixtures of UO and 50,000 ppm H O are 2
2 then specified by fUO2 = 4.5 0
fHO=
2
*0.05 = 0.23684 gm/cc 2
. 9 5)
{
carbon = 0.80
* gg (atom densities)
N I
s_e 1 !
- ~
 
This last condition simulates a mixture of 10,000 r-ppm H 0 and 40,000 ppm of hydrogen-carbon additive
's)3 ([
in whkch the weight fraction of hydrogen is the same
%it as that in water (11.19%) and for which the ratio of hydrogen atoms to carbon atoms (in the additive) is' no less than one.
.2 UO
- H O Mixtures Occupying Minimum Theoretical Volumes 2 Given a weight fraction of water in the mixture, the densities of UO and water are specified by 2
/
3 (UO l
2 HO 2
[1-WFHOb 2
l+
WF r
k 10.96
)
HO 2
and U0
( )(
fHO=1-2 2
h/
10.96 l
As in 5.3.1, maximum permissible carbon content is determined by NC = 0.80
* NH O
i I
i l
' v 4
14 -
=
 
l
, {}
5.2 BU-7 Geometry model
%=/
The geometry model used in this analysis is illustrated in Figure 5.1 and the KENO IV and GEMER geometry input is tabulated in Tables 5.2 thru 5.4.
For the normal case, the Figure 5.1 model was spacially reflected on all six sides (J = 0) to simulate an infinite array.
Calculations were then performed for the phenolic resin insulation mixtures in Regions 6 and 8 or for varying amounts of interspersed water in Regions 6, 7, 8, 10 and 12.
Calculations were also performed with interspersed water in Region 4 as well in order to evaluate the impact of close-packed moderation about the five or three gallon product pails.
The three-
-gallon product pails were not explicitly modeled since it is readily evident that they are less reactive than the five-gallon containers (less U02, m re carbon steel and smaller volumes).
4 For the accident analysis, a 256 unit array was defined with the same Table 5.2 - 5.4 geometry but with eight containers in the X and Y directions and four contaiaers in the Z direction.
The 8 x 8 x 4 configuration gives the array d
with the minimum geometrical buckling and is therefore the most reactive case from an array geometry standpoint.
()(
h/
i a
4 4
1 C:)t
-s
 
FIGURE.5.1: KENO /GEMER GEOMETRY MODEL FOR BU-7. CONTAINER Z
C,) (
h N
y,q w
!.3eg P4-l.
se.,
I" belf rsed M r
. tat -
,3753 U'dfI"N<SpalW. der
.s.i.
es c s is c,
Ca<ba Shel
?.oS
* ll.%
P z
l P
i h
t A
c
+
Ns0 v,
I,.
9 5
1 A
5 V
i.
p e
e D.C S o
(
,y e
i e
3 I
i c
1 e
0s.
=
1
- e t
u o
*'.05 [
I y
l w
a t
et t
i UO t
t Nuo
.545
$. i o es
\\
5,"1067 II Il l
ll 11 il 11 2.9291N ll 2.uw/--
ii is i
i g
-----__gi_
__ii--_i
*N l
ll Il I
I, OL n
v i
o,oo l'f.asa s is.39 11.7o
: 17. Set 23.475 25575 2 3. c.t y i.
L hil 0.~,_..
 
l TABLE 5.2: BU-7 CONTAINER INFINITE ARRAY GEOMETRY MODEL (KENO /GEMER INPUT)
Radius
+ Height
~
or or Region Geometry Type Material
+X
+Y
+Z 1
Cylinder Carbon Steel 14.2875
+
0.05 2
Cylinder UO -H O Fuel Mixture 14.2875
+ 35.05 2
2 3
Cylinder Carbon Steel 14.34
+ 35.1 4
Cylinder Void 17.70
+ 35.1 5
Cylinder Carbon Steel 17.808 35.5763
- 35.2087' 6
Cylinder Phenolic Resin or 23.495 35.5763
- 42.8287 Interspersed Water 7
Cylinder Void or 23.495 36.688
- 42.8287 Interspersed Water 8
Cylinder Phenolic Resin or 28.575 44.308
- 42.8287' Interspersed Water 9
Cylinder Carbon Steel 28.575 44.4167
- 42.9374 10 Cylinder Void or 28.575 4523692
- 44.8424
(-)
Interspersed Water
;l
.1 Cylinder Carbon Steel 28.684 45.3692
- 44.8424 12 Cuboid Void or
+28.684
+ 28.684 45.3692 Interspersed Water
- 44.8424 13 Core void
+28.684
+ 28.684 45.3692
- 44.8424 14 Cuboid Void
+28,684
+ 28.684 45.3692
- 44.8424 l
* Dimensions in cm
()b ui
[
 
TABLE 5.3:
GEOMETRY MODEL' MODIFICATIONS FOR 35 KG s
(
UO CALCULATIONS (KENO /GEMER INPUT) 2
' + '
Region Geometry Type Material Radius +
I-Height 1*
Cylinder Carbon Steel 14.2875
+ 0.05 1A Cylinder Void 14.2875 0.05 A
2 Cylinder UO
-HO 14.2875 B
-35.05 2
2 Fuel Mixture 2A Cylinder Void 14.2C75 35.05
-35.05 3
Cylinder Carbon Steel 14.34
+ 35.1 Fuel Mixture Height of+
No.
Fuel in Container A,
B,
(
1 12.128
- 2;.922 12.178 gj 2
20.0
- 15.05 20.05 0.05 35.05 3
35.0 Unchanged
+ Dimensions in cm l
i f
Ot v
 
TABLE 5.4:
GEOMETRY MODEL MODIFICATIONS FOR 8 x 8 x 4 FINITE ARRAY (KENO /GEMER INPUT)
+
~ ++
+
+
Region Geometry Type Material
-X
-Y
-Z 12*
Cuboid Carbon steel
+
28.684
+ 28.684 45.3692
~
13 Core Void
+ 229.472
+229.472
+180.4232 14 Cuboid Full Density
+ 260.0
+260.0
+212.0 Water (or concrete)
O(
s
*Unchanged
* Dimensions in cm h.
s.
 
s(
FIGURE 5.2 - FIVE-GALLON PRODUCT CONTAINER GEOMETRY MODEL A.
SINGLE CONTAINER (FGC)
ID = 28.575 cm UO IH = 35.0 cm 2
+
OD = 28.680 cm HO OH = 35.1 cm 2
Walls - carbon steel s
B.
TWO FIVE-GALLON CONTAINERS Side-by-side Stacked s{
l' H O reflector l'(min)H O reflector 2
2 top Vi*"
l FGC FGC l
FGC l
/
void side i
view FGC I
O] c FGC FGC FGC I
l' H O reflector l' H O reflecton 2
2 l
l lon-
 
FIGURE 6.1 - K, for U (4.05) 02 - Carb:n Syctcm g -
: n..,..
i i
a.
.i.
.....i...
i
.i l
j 2,.
)
.!. I65..i
..i..i N s' i
i
= _.
.........a.
s.
l 8
.;e
:. a..
l...a a.
i.
e f.
l 1
i.
1..
3 j
.i..
s g
i 1
j l..
g t
.I i
t.
i
..s
,4 I
O l
H g
x p
I in 3
i D
g,,
.g.
7 i
~
.I.
,1 e
2
.;. 1 4,,l 9.!
g 3
. l 1 1 g
,--.r.-
. _3...,
_A g.
[
i I
l
........ }....
..?.
I.7 3
i
..1...
.o, I
y g
--J l.
j.
....i l
l 3
...... ~.
4 I
IA l
l 4
l l
I i
t
.i l
. a i
- e
...s...
3..
..4..
4 t
N l
t t
+.
l i
e s*
l f
..a t
e
* i i
n l
1 x
bs.
l
)
i I
t 8
I I
l.
\\
I i
.I I
...y.
g.
..g.._
: o....
m......
- 2 g
e g
.4 4
x 4
4
-19B-
=
 
Tight reflection of the 256 unit array was modeled by 12-inch t
thick slabs of full density water on all six sides of the array.
For the case of concrete reflection, the 12-inch thick slabs were replaced with 16-inch thick concrete slabs (KENO IV material number 300).
One aspect of the Figure 5.1 geometry model that should be noted is that the dimensions used are conservative as compared to the actual BU-7 container described in Figures 4.1 and 4.2.
This especially applies to the use of the 22.5 inch inner diameter for the maximum size of the 55 gallon drum rather than taking credit for the 23h inch diameter of the drum provided by the two or three corrugations along the length of the container.
This constitutes a reduction by at least 4 % in the diameter and 9% in the volume of the drum and is a significant factor of conservatism in the analysis of the 256 unit accident array.
This reduction of 9% in the volume conservatively simulates the collapsing of the rolling heaps on the lateral surface of the drums under the postulated accident conditions (drop, flame, flooding).
It is advised that the geometry model used in this analysis for the BU-7 container is different from that used in the Reference 3 analysis.
The Figure 5.1 model is more con-
. {
servative than the one previously used.
5.3 Five Gallon Product Container Geometry Model The five gallon product containers have been modeled in this analysis as shown in Figures 5.2.
The ID = 28.575 cm, IH = 35.0 cm dimensions slightly overestimate the true size of a five gallon product container (the value is 22.44 liters as compared.to the true value of less than 22.0 liters), and the model is therefore conservative, especially since the carbon steel walls are modeled as being less than 0.0207 inches thick.
k- -
i
 
6.0 RESULTS j
6.1 BU-7 Container Analysis Tables 6.1 through 6.5 show the results of the MERIT /
GEMER/ KENO IV calculations for the BU-7 container.
6.1.1 Normal Case TABLE 6.1 NORMAL CASE Kos for BU-7 CONTAINER PERCENT OF FULL DENSITY i #
OF PHENOLIC RESIN GEMER MERIT KENO IV 100 0.758 + 0.004 0.753 1 0.004 0.790 1 0.004 80 0.799 1 0.004 0.804 1 0.003 0.843 1 0.004 60 0.853 1 0.004 0.850 1 0.003 0.903 1 0.003 "with 202 Kgs UO2 per BU-7 container These results show tha't the normal case infinite array of BU-7 containers is critically safe and that the phenolic resin serves as an "overmoderating" influence in that die more resin present the lower than K..
Comparison of MERIT, GEMER and KENO show that MERIT and GEMER are in good agreement but that KENO overpredicts the K s relative to them by from five to six per cent.
l l
l l
l s
e l 1
l l
 
6.1.2 Accident Case - Optimum Interspersed Water
.1 Infinite Arrays
[
These calculations were performed in order to compare MERIT /GEMER and KENO.
(The MERIT geometry package is unable to model the 256 unit finite array.)
t TABLE 6.2 - K.
FOR BU-7 CONTAINER WITH OPTIMUM INTERSPERSED WATER
* K.
+o INTERSPERSED WATER (gm/cc)
GEMER MERIT KENO IV 0.000 1.111 + 0.003 1.106 + 0.003 1.163 + 0.003 0.025 1.147 + 0.003 1.147 + 0.003 1.182 + 0.004 0.050 1.117 + 0.003 1.116 + 0.003 1.153 + 0.004 Q)s 1.099 + 0.004 0.075 1.067 + 0.003
~
0.100 1.021 + 0.003 1.046 + 0.003 0.200 0.829 + 0.003 0.848 + 0.004 0.500 0.634 + 0.004 0.-6 4 2 + 0. 00 4 1.000 0.610 + 0.004 0.617 + 0.004 i With 202 Kg UO2 per BU-7 container
* Interspersed water in Regions 6, 7, 8, 10 and 12 (Table 5.2)
 
')f TABLE 6.3 - K.
FOR BU-7 CONTAINER WITH CLOSE t
~
A PACKED OPTIMUM INTERSPERSED WATER KENO IV Interspersed Water (gm/cc) 1
=
0.000 1.163 1 0.004 0.025 1.185 1 0.003 0,050 1.144 1 0.004 0.075 1.065 1 0.004 0.100 1.008 1 0.004 0.200 0.792 1 0.004 0.500 0.641 1 0.005 1.000 0.657 1 0.004 t
(){
With 202 Kg UO2 per BU-7 container
* Interspersed water in Region 4 as well as in Regions 6, 7,
8, 10 and 12 (Table 5.2)
Table 6.2 indicates the same trends as shown in Table 6.1.
GEMER and MERIT are in good agreement but KENO IV overpredicts the K.s relative to them by three to five per cent in the region around optimum interspersed moderation.
Table 6.3 indicates that, as is to be expected, a slight shift may exist in 'the density of interspersed water corresponding to optimum moderation, but the impact on the K s is smaller than the Monte Carlo statistical uncertainties.
This is evi-dence that the addition of hydrogen anywhere outside of the UO fuel has been implicitly considered by analyzing the BU-7 3
container arrays for optimum interspersed moderation between containers (and within the 55 gallon drums)..
e
.~
.7 7 -
 
2 Single container 9-(
To provide a further comparison between MERIT, GEMER and KENO IV, the Keff of a single BU-7 container was cal'culated.
The conditions for this calculation were 202 Kg 00 in the container and 0.075 gm/cc 3
of water in Regions 6, 7, 8, 10 and 12 (see Table 5.2).
The results were:
Code K,ff i
o
.GEMER 0.355 1
0.004 MERIT 0.356 1
0.003 4
KENO IV 0.356 1
0.004 3
Accident Case - 8 x 8 x 4 Arrays of BU-7 Containers The GEMER and KENO IV results for the analysis of the 8 x 8 x 4 arrays of BU-7 containers with optimum interspersed water are given in Tables 6.4 and 6.5.
Table 6.4 is for the case O(
in which the BU-7 containers each hold'202 Kg
*/
UO (full five-gallon product pails at 4.5gm UO /cc) while Table 6.5 contains the results fo the containers limited to 70 Kg UO each 9
(35 Kg U0 Per five-gallon product paiI).
2
. OL
_s
--w--
w
%*.y
,.gm-,--9.-
y
,w--,---.-w---
----e-,
-,--v..
 
.l
{
I TABLE 6.4 - K s for 8 x 8 x 4 ARRAY eff OF BU-7 CONTAINERS (202 Kg UO PER CONTAINER) 2 Interspersed eff 1
Water (gm/cc)
GEMER KENO IV 0.000 0.853 1 0.004 0.025 0.884 1 0.004 0.906 1 0.004 0.050 0.921 1 0.004 0.955 1 0.005
~
0.075 0.928 1 0.005 0.944 1 0.004 0.100 0.929 1 0.005 0.200 0.802 1 0.003 0.500 0.637 + 0.004
;) \\
1.000 0.617 1 0.005 7 The array is tightly reflected on all six sides by 12 inches of water.
No interspersed water is placed in Region 4 (see Table 5.2)
('~)) \\
/
\\_
 
+
t TABLE 6.5 - K,ggs for 8 x 8 x 4 Array
(~}
of BU-7 Containers (70 Kg
\\#
UO Per Container) 2 KENO IV K,ff ia Height in Height in Height in Interspersed Can of Can of Can of
~
' Water (gm/cc) 12.128 cm 20.0 cm 35.0 cm(Full) 0.000 0.534 + 0.004 0.530 + 0.003 0.532 1 0.003 0.025 0.609 1 0.004 0.624 + 0.005 0.655 1 0.005 0.050 0.637 + 0.004 0.679'+ 0.004 0.731 + 0.004 0.075 0.656 + 0.004 0.693 + 0.004 0.750 + 0.005 0.100 0.641 1 0.004 0.681 + 0.005 0.743 + 0.004 0.200 0.537 + 0.004 0.573 + 0.004 0.623 + 0.004 0.500 0.419 1 0.004 0.410 + 0.004 0.427 + 0.004 1.000 0.417 + 0.004 n/ r 0.406 + 0.004 0.401 + 0.005 L
\\.075 0.149 + 0.002 0.231 + 0.002 0.351 + 0.003 Single BU Cbntainer l
The array is tightly reflected on all sides by 12 inches of water.
I No interspersed water is placed'in Region 4 (see Table 5.2).
l Oi-t/ l I--
 
It is concluded from those two tables that the BU-7 container
(
array is critically safe under the postulated optimum inter-spersed moderation, full reflection accident condition even if the individual BU-7 container mass limit of 70 Kg 00 is 2
exceeded.
This assumes that the H/U = 1.577 and C/U =
1.262 limits are still met.
As in the previous cases, the KENO IV results around the optimum interspersed water level are one to three per cent higher than the corresponding GEMER values.
(The 8 x 8 x 4 array cannot be modeled in MERIT due to geometry limitations.)
The Keff for the 8 x 8 x 4 array with optimum interspersed water and full reflection and with the 70 Kg U0 limit per 2
container is 0.750 + 0.005 (at 0.075 gm H 0/cc interspersed water.)
For comparison, this case was andlyzed replacing the tight water reflector by a tight 16-inch thick concrete reflector (on all six sides).
The KENO IV Keff for this case was 0.789 + 0.004, an increase of 5.2%.
6.2 EVALUATION OF CARBON ADDITIVES From Reference 8, the relative moderating factor for a mixture of water and carbon can be determined to be:
(~b(
ggj Moderating factor = 20 NH + 0.76 Nc + 0.50 No 1
where N, Nc, and No are the corresponding atom densities for g
hydrogeM, carbon, and oxygen in the moderator.
It follows from this relationship that the worth of carbon as a moderator is 0.76
* 20 = 0.038 times the worth of hydrogen. Applying this value to the mixture of UO water and hydrogen-carbon additives which is approved fob,the BU-7 container, (an H/U atomic ratio of 1.577 and a C/u atomic ratio of 1.262) then results in an equivalent UO2 - H O mixture with 51438 ppm H 0 as opposed 3
2 to the 50,000 ppm H O limit for the H/U rati5 of 1.577.
2 l
The effect of the additional 1438 ppm H O equivalence can be l
estimated from existing tabulated data 2(Reference 6) to be less than 1.0% in K.
However, as part of the present analysis of the BU-7 container, additional calculations have been made using the KENO IV Monte Carlo code to evaluate the effect of carbon on 4.0% enriched UO systems.
The results of these 2
are given in Tables 6.6 through 6.10.
/D (
k;I'.
YO
 
,\\
q t
C/ (
TABLE 6.6 K, s of U(4.05) 0
- Carbon Systems 2
s Weight Fraction of Carbon in C/U-235 KENO IV' Mixture Atcmic Ratio K,
+
o 0.00 0.0 0.806 + 0.002 0.10 61.6 0.814 7 0.002 0.20 138.7 0.803 7 0.002 0.30 237.8 0.778 T 0.002 0.40 369.9 0.775 7 0.002 0.50 554.9 0.788 7 0.002 0.60 832.4 0.809 I 0.003 0.70 1294.8 0.867 I 0.003 0.80 2219.6 0.936 7 0.003 0.85 3144.4 1.056 7 0.003 0.875 3884.3 1.122 7.0.003 0.90 4994.1 1.196 7 0.003 0.925 6843.7 1.303 7 0.003 0.95 10543.
1.359 I 0.003
] (A
./
l 0.975 21641.
1.438 { 0.003 0.982 30273.
1.448 + 0.003 g
0.990.
54935.
1.377 + 0.003 i
l
# 'Ihe theoretical density of carbon was taken to be 2.25 gms/cc l
O\\
s l I"
 
I O ( JsLE 6.7 g
MINDLE CRITICAL MASSES OF U(4.05)02 - g 0 CARBON SYSTEMS
\\
KENO IV calc.
Weight Fraction Weight Fractigh C/U-235 Min. Crit.tcal of H O of Carbon Atmic Ratio Mass of UO (K9) 2 2
0.0 0.975 21641 140.9 0.982 30273 128.1 0.990 54935 147.4 0.0 0.00 2208 i
0.05 22.84 1954.5 30.0 1658.0 200.0 861.3 1000.0 419.8 0.0 0.00 337.5 0.10 22.84 277.6 200 262.3 1000 164.0 0.0 0.00 101.0
_C).d(
'O.20 22.84 104.9 200 108.9 1000 93.7 0.0 0.00 74.4 0.30 22.84 70.9 200 76.7 1000 101.8 0.0 0.00 65.9 0.40 22.84 66.2 200 73.2 1000 331.6' 0.00 68.6 0.0 0.50 22.84 73.5 200 96.9 W
P
= 2.25 gn/cc c
t Water reflected s
m
 
)
%d TABLE 6.8 MINI 1U1 CRITICAL MASSES OF U(4.05) 0 - H O SYSTEMS 2
2 l
KENO IV ralt'1 ated 1
Weight Fraction H/0 Mimnun Critical of H 0 Atcznic Ratio Mass of UO2 (Kg) 3 0.05 1.577 2208.
0.10 3.330 337.5 0.20 7.492 101.0 0.30 12.84 74.4 0.40 19.98 65.9 4
O(
v 0.50 29.97 68.6 0.60 44.95 113.7 i
0.70 69.92 1770.
i l
l l
.O t v,
-4%---,
-.9,.
,m,
 
I LO LO LO c
m
~
TABLE 6.9:
MERIT VERIFICA".' ION OF KENO IV U0 MINIMUM. CRITICAL MASSES 2
C/U-235 Weight Fraction Critical U02 Critical MERIT Atomic Ratio of Water Radius Mass (Kg)
Keff 1 0
0.30 20.98 74.4 1.0031 1 0.0042 0
0.40 22.84 65.9 1.0041 1 0.0039 0
0.50 26.14 68.6 0.9941 1 0.0033 22.84 0.30 21.12 70.9 0.9895 1 0.0048 22.84 0.40 23.34 66.2 1.0019 1 0.0043 22.84 0.50.
27.23 73.5 1.0016 + 0.0034 1
1000 0.10 36.24 164.0 0.9926 + 0.0048 8
1000 33.01 93.7 0.9963 1 0.0042 1000 37.16 101.8 0.9819 1 0.0039
.L I See Table 6.7 1
I i
1 h
i
 
TABLE 6.10 - BU-7 CONTAINER ANALYSIS WITH CARBON 0(
s A.
Normal case K,with 60% of full density phenolic resin (202 Kg U02 per BU-7 container)
KENO IV K,without carbon 0.903 1 0.003 KENO IV K,with carbon 0.913 1 0.005 B.
Accident case:
8 x 8 x 4 water reflected array with 70 Kg UO Per BU-7 2
Density of Interspersed H O KENO IV K KENO IV K gg) 2 eff e
(gm/cc)
(without carbon (with carbon i
0.025 0.655 + 0.005 0.663 + 0.004 Or
~
~
,j ).
0.050 0.731 1 0.004 0.731 1 0.004 0.075.
'O.750 1 0.005 0.757 1 0.005 0.100 0.743 1 0.004 0.745 1 0.004 C/U = 1.262 e
Height of fuel in five gallon product pails is 35.0 cm
(
_s 32 -
m T---'
s-n amy-a w-de-w--
--r----
-e w,
_--,e,,-_._
,._--e,-m
,___w-
.-m,-,,_,__,,
 
. = -
=.
~
. The K. results in Table 6.6 can be compared with the tabulated
. (K=
ralues in Reference 6 for U(4.0) 02 - H2O in which the maximum is no greater than 1.40.
Figure 6.1 is a plot of the Table 6.6 results.
In addition, if all the moderator in the UO 9
moderator mixture in the.BU-7 containers were carbon, TabIe 6.6 indicates.that the K. of the fuel would be less than 0.8.
(An.
H/U ratio of 1.577 and C/u ratio of 1.262 imply an effective "C/U" ratio of 42.737 when using the 0.038 equivalence factor between carbon and hydrogen).
The K. o f a U ( 4. 0 ) 02-HO 2
mixture with 40000 ppm H O (a H/U ratio of 1.577) is greater 2
than 1.0.
Tables 6.7 and 6.8 show minimum critical masses calculated with KENO IV for 'U(4.05) 02 - H 0-C and U(4.05) 0 H 0 systems.
2 2
9 These two tables indicate that the minimum criti5a1 mass occurs for pure UO -H O mixtures and that the presence of carbon there-2 2
fore results in dilution of the fuel mixture.. Table 6.7 clearly establishes however that carbon moderation can be appreciable for under moderated systems such as the BU-7 container.
In this regard, the entries in Table 6.7 for 0.05 weight fraction of water indicate.the impact of the C/U = 1.262 BU-7 container limit.
With no carbon, the minimum critical mass at the H/U ratio With of 1.577 (i.e., 0.05 weight fraction water) is 22C8 Kg U02 a mixture containing carbon with a C/U-235 ratio of 30, (an H/U of about 1.2), the critical mass decreases to 1657.7 Kg UO2' "
(])
33% effect.
Table 6.9 presents a verification of the KENO IV UO minimum criticalmasseswhichwasperformedwiththeMERITkonteCarlo code.
The MERIT code was used to calculate the Keff of the UO2 spheres determined to be critical with KENO IV (via the i
search option).
The results show excellent agreement between MERIT and KENO IV for these UO
- H 0-carbon systems.
2 2
Finally,. Table 6.10 summarizes the results of KENO IV calcula-tions for the BU-7 container normal case and accident case analyses described in Section 6.1 with the addition of carbon in the fuel mixtures..The C/U ratio for these calculations is 1.262.
As can be seen, the addition of the carbon increases the K. and Kefg values by no more than 1.25%.
In both cases, the,BU-7 container system is still subcritical.
Ot
\\/
y y
p---,-,-.-
---,,1g.
,---,ecm.-
, mm n r
 
6.3 Analysis of five Gallon Product Pails I(
The safety of individual BU-7 containers has been analyzed by calculating the effective neutron multiplication factors of two five gallon product pails under conditions of optimum moderation and full reflection.
The results of these calcula-tions are shown in Tables 6.11 and 6.12.
Table 6.11 gives the results of KENO IV calculations for two five gallon containers placed side by side (and touching) with tight water reflection in all areas except immediately between the two containers.
j The maximum K,ff, for this case are-0.968 + 0.006 for 65.8 Kg UO2 per container and Per container 0.909 j; 0.006 for 35.0 Kg U02 Table 6.12 gives the results of calculations for the two five gallon containers stacked in a vertical column.
Again, the containers are touching and the assembly is tightly reflected by at least 12 inches of water.
The maximum K f r the effs vertical arrangement are:
(
0.964 + 0.005 for 65.8 Kg UO2 per container and 0.904 f; 0.004 for 35.0 Kg UO2 per container Since the BU-7 shipping container is limited to 35.0 Kg per five gallon product pail, the criticality safety of an indivi-
. dual container is established for the case of optimum moderation and full reflection.
l l sj
-m-es+--mne,
 
9 rs TABLE 6.11 - ANALYSIS OF TWO FIVE GALLON CONTAINERS SIDE BY SIDE A.
Full Containers with Maximum UO Masses 2
KENO IV Weight Fraction Mass of UO 2 of H O in Fuel in Single Keff +
2 Container (Kg) 0.05 156.0 0.805 +
0.004 0.10 110.9 0.890 T 0.005 0.20 65.8 0.968 7 0.006 0.30 43.2 0.947 7 0.006 0.40 29.6 0.909 7 0.005 0.50 20.6 0.841 +
0.003 B.
Containers.with 35 Kg UO Mass Limits 2
s Intermediate Weight Fraction KENO IV K
ff of H O in fuel Minimum He,lgnt Height Full cans 2
in cans in cans 35.0 cm V
0.05 0.581 + 0.004 0.538 + 0.004 0.534 + 0.004
~
(127128 cm)
(20.0 m) 0.10 0.639 + 0.005 0.579 + 0.004 0.537 + 0.004 (12128 an)
(20.0 cm) 0.20 0.801 + 0.005 0.746 + 0.004 0.688 + 0.004
~
(187624 cm)
(25.0 cn) 0.30 0.885 + 0.005 0.851 + 0.004 (287370 cm) 0.40 0.909 + 0.005 (3570 ch) 0.50 0.841 + 0.003 (3570 cm)
Qt 1 v l l l
 
TABLE 6.12 - ANALYSIS OF TWO FIVE GALLON CONTAINERS STACKED VERTICALLY A.
Full Containers with Maximum UO Masses 2
T Weight Fraction Mass of UO2 in of H O in Fuel Single container bff I i
ff -
2 0.05 156.0 0.804_M.004 0.10 110.9 0.902_+0.006 0.20 65.8 0.964_+0.005 0.955_+0.004 0.953_+0.006 0.30 43.2 0.954_+0.005 0.40 29.6 0.904_+0.004 0.50 20.6 0.850_+0.005 B.
Containers with 35 Kg U0 Mass Limits 2
KENO IV Keffs Weight Fraction Minimum Height Intennediate Full Cans of H O in Fuel in Cans Height in Cans (Height =35.0cm) 2 0.05 0.586+0.005 0.550 + 0.004 0.519 + 0.004 (12.T28 m)
(20.6 cm) k.) (
0.10 0.633+0.004 0.578 + 0,005 0.536 + 0.005 V
(12.T28 m)
(20.0 t,
0.20 0.793 + 0.005 0.736 + 0.005 0.678 + 0.005 (18.674 cm)
(25.6 m) 0.30 0.881 + 0.005 0.851 + 0.005 (28.370 cm) l 0.40 0.904 + 0.004 (34.0 cn) 0.50 0.850 + 0.005 (35.0 cm) l h/k l
-35A-1
 
4 The Kegg = 0.909 + 0.005 and 0.904 + 0.004 results listed above constitute upper limits for extreme accident conditions since G (.
the moderation limit in the containers is limited by BU-7 specifi-
\\w/
cations to 50,000 ppm H2O or less.
(50,000 ppm is the same as a weight fraction of 0.05.)
In Table 6.12 Keff results have also been presented for MERIT and GEMER calculations of the vertically stacked assembly with 65.8 Kg 002 (weight fraction of water = 0.20).
The MERIT and GEMER results for this case are in excellent agreement and are about 1% lower than the KENO IV result.
Finally, it is noted that the presence of carbon in these containers has been found in Section 6.2 to increase the Keffs by no more tuan 1.25% provided that the H/U = 1.577 and C/U = 1.262 limits are met.
The conditions analyzed in Tables 6.11 and 6.12 would in such accident conditions still correspond to a C/U = 1.262 case but the H/U ratio would exceed 7.5 (see Table 6.8).
In this case the pre-sence of the low level of carbon would have an even smaller effect on the system Keffs.
Nevertheless, if tne system Keffs were to increase by-1.25%, the two 5 gallon containers with 35 Kg UO2 in either geometry arrangement would still be critically safe since effs would be no higher than 0.920.
most K b/v iL/s
/.
 
o i
6.4 Evaluation of Rocky Flats Low Enriched Low Moderation U 0 38
(''
Benchmark Critical Experiments 5(
Reference 7 describes a set of benchmark critical experiments that were. performed by Rockwell International (Rocky Flats Plant) to provide data for low enriched Uranium Oxide systems with low levels of moderation.
The Rocky Flats experiments consisted of a 5X5X5 array of Aluminum tins which contained 4.46% enriched U 03 8 powder and for which the average hydrogen content in the entire assembly resulted in an H/U ratio of 0.77.
Ten different cases were run for the critical experiments corresponding to the type of fully enriched Uranium Drive- (metal, low Uranium content solution or high Uranium content solution) and to the type of reflector (con-crete, metal or plastic).
Measured amounts of water were added to the U308 in the Aluminum tins through drilled holes (56 per tin).
The measured critical parameter in the experiments was the separation distance between halves of the 125 unit array.
Both KENO IV and GEMER calculations have been performed for the Rocky Flats experiments with very detailed modeling of the assem-blies in regular and enhanced KENO IV geometries.
The major area in which the geometry models differed in the true configuration was in the smearing of the holes in the Aluminum tins which were used to add the measured amounts of water.
The impact of this
-smearing has been evaluated however by analyzing the K, of a single Aluminum tin with and without the Aluminum holes.
From
(-) {
KENO IV with enhanced geometry these results are J
K, = 1.0838 1 0.0040 For single oxide can.
without holes
(" smeared")
For single oxide can K,=
1.0830 1 0.0053 with holes ("unsmeared")
Any difference is completely masked by the 0.3 to 0.5% statistics.
Table 6.13 shows the results of the KENO IV and GEMER calculations for the Rocky Flats experiments.
Cases 1-3 were not performed with GEMER because of geometry modeling difficulties.
(These cases re-quire the use of'the enhanced geometry option not currently available in GEMER.)
The results of the benchmark calculations are that KENO IV predicts an average K ff = 0.997 1 0.002 and GEMER predicts an average K *g,'
1.003 _+ 0.00 Oc ss.
7 w--
---:---,--,-rw--t
---e n --
e-w
-=--m-r-----r--w-----
*we,
 
I LO LO 10:
TABLE 6.13 - KENO IV AND GEMER CALOULA O NS FOR ROCKY FLATS LOW ENRICHED U g O
~'
)
3
{
LOW MODERATION BENCHMARK CRITICAL EXPERIMENTS j
EXPERIMENT eff i NO.
DRIVER REFLECTOR-KENO CRMER-1 Metal Concrete 1.0060+0.0057 2
Metal Plastic 0.9931+0.0064 i
a j
3 Metal Steel.
1.0075+0.0067 4
High Uranium Concrete 0.9948+0.0052 0.9961+0.0060 Content Solution
~
5 High Uranium Plastic 0.99841,0.0052 1.0115+0.0059 i
' Content Solution
}
d, 6
High Uranium Steel 0.9819+0.0055 0.9816+0.0082 i
m Content Solution 7
Low Uranium Concrete 0.9950+0.0048 1.0219+0.0087 Content Solution i
8 Low Uranium Plastic (Spacing 1) 0.9981+0.0045' 1
Content Solution l.0045+0.0064
+
9 Low Uranium Plastic (Spacing 2) 0.9970+0.0050 1.013810.0079 Content Solution i
10 Low Uranium Steel 0.9979+0.0051 0.9898+0.0080 l
Content Solution i
Average values 0.997+ 0.002 l'.003 + 0.003 I
e
 
e s I
REFERENCES
,l g_
Q l.
Y-DR-51, " Criticality Analysis of Bulk Uranium oxide Shipping Container," J. T. Thomas 2.
GE-BU-4-1, Rev. 1, " Criticality-Safety Analysis of General Electric's BU-4 Shipping Container for the Transportation of Dry Unirradiated Uranium Dioxide," R. Artigas, 1971 3.
NEDO-11277, "The General Electric Model BU-7 Uranium Shipping Container - Criticality Safety Analysis," R. Artigas, 1974 4.
ORNL-4938, " KENO IV, An Improved Monte Carlo Criticality Program," L. M. Petrie & N. F. Cross, 1975 5.
LAMS-2543, "Six and Sixteen Group Cross Sections for Fast and Intermediate Critical Assemblies," G. E.
Hansen & W. H.
Roach 6.
ARH-600, " Criticality Handbook - Volume II," Atlantic Richfield Hanford Company 7.
NUREG/CR-0674, " Benchmark Critical Experiments on Low-Enriched Uranium Oxide Systems with H/U = 0.77," Systems Group, August 1979 8.
Glasstone, S and Edlund, M.C.,
"The Elements.of Nuclear Reactor
(
Theory," Von Nostrom, 1952, pp. 145-146 l
O i
e v v i
~39-
 
--. =..
i i.
(
Appendix A.
Mixture Densities i '.
A.1 Fuel Mixtures t-A.2 Phenolic Resin and Carbon Steel A.3 Interspersed Water 4
f i
4 6
4 b
+
l
. O(
v i
1
(
e 1
6 4
I
)
l I
i
: Ot u
1
~
(
; -.,..,+,-.
--.,r-,
,..--,,,,,.,,~n,--
_,n,,-,
..-- --.- ~,-,
 
UO -H 0-C MIXTURE DENSITIES
- ~} TABLE.A.1 2
2 V (.
A.
4.5 gm UO2/cc + 0.23684 gm H2 /cc Mixtures 0
Material MERIT /GEMER KENO IV HANSEN-ROACH Atom Density Atom / Material 16 Group (atoms / barn-cm)
Density (atoms /
Material-ID barn-cm)
U-235 4.0657 E-04 4.0657 E-04 92508 i
U-238 9.6344 E-03 9.6344 E-03 92810 Oxygen 2.8001 E-02 2.00828 E-02 8100 Hydrogen 1.58365 E-02 Water 0.237269*
502 1.26692 E-02 6100 Carbon (Optional)
(
Use:
101 Kg UO2 in'5 gallon container occupying entire volume of can (height = 35 cm) or 35 Kg 002 in 5 gallon container occupying minimum volume of can (height = 12.128 cm) l i
~
= 0.23684/0.9982, which is the KENO input density (gm/cc j
in this case - not atoms / barn-cm).
i i
O (''
s/
41-
,y
,,,.----_-..w.
,,,..--.ywr&_.,m,.
y,m---,ww<,--y-----%*y et,.w-.--=
~esww -+e=
---ew
'm*
 
4 I
.l kr V N'.
2.7288 gm UO2/cc + 0.14362 gm H 0/cc 2
MATERIAL MERIT /GEMER KENO IV HANSEN-ROACH Atoia Density Atom / Material 16 Group (atoms / barn-cm)
Density (atoms /
Material ID barn-cm)
U-235 2.46546 E-04 2.46546 E-04 92508 U-238 5.84235 E-03 5.84235 E-03 92810 Oxygen 1.69800 E-02 1.21783 E-02 8100 Hydrogen 9.60334 E-03 t
O.143881 502 Water
(~'h Use:
35 Kg UO2 in 5 gallon container occupying partial volume of can (height = 20.0 cm)
= KENO input density (gm/cc in this case - not atoms / barn-cm).
 
.,. 4
,7s-
\\_
\\m/
.. 1.5593 gm UO /cc + 0.08207 gm H2 /cc 2
0 l
MATERIAL MERIT /GEMER KENO IV HANSEN-ROACH Atom Density Atom / Material
: 16. Group (atoms / barn-cm)
Density (atoms /
Material ID barn-cm)
U-235 1.40883 E-04 1.40883 E-04 92508 f
U-238 3.33849 E-03 3.33849 E-03 92810 Oxygen 9.70284 E-03 6.95903 E-03 8100 Hydrogen 5.48763 E-03 Water 0.0822179*
502 Carbon 4.39009 E-03 6100 Use:
35 Kg 002 in 5 gallon container occupying entire volume of can (height = 35 cm) t 4
t KENO input density (gm/cc in this case - not atoms / barn-cm).
?
l I
O(..
v.
e---,-e-.+p-
, r g
--e~
---a
,--e-w,-ee
..e-,,w,.-~~
~.-,, -,
,-,._,,,en
,-n.-,--e-,-
----- -- a
 
es s UO -H O MIXTURES
~
r FULL THEORETICAL DENSITY 2
2 1.
KENO Mixtures Atom / Material Density (Atoms / barn-cm)
WF H2O U-235 U-238 Oxygen Water (Material)
(Material)
(Material 8100)
(Material 502) 0.10 4.46'492 E-04 1.058505 E-02 2.20548 E-02 0.550088 (92509)
(92818) 0.20 2.64765 E-04 6.27409 E-03 1.30783 E-02 0.733941 (92510)
(92825) 0.30 1.73810 E-04 4.11875 E-03 8.58547 E-03 0.824960 (92511)
(92831)
.h 9 0 1.19208 E-04 2.82485 E-03 5.88836 E-03 0.881201
'(92512)
(92835) 0.54 8.27944 E-05 1.9619 E-03 4.08969 E-03 0.918040 (92512)
(92840) c' m Oxygen - Material
(
Water
- Material WF H O = 0.20 2.
MERIT /GEMER Mixture:
2 Material Atom Density (atoms / barn-cm)
U-235 2.64765 E-04 U-238 6.27409 E-03 Oxygen 3.75717 E-02 Hydrogen 4.89868 E-02 tPartial density atom densities are determined by the ratio of the height of the fuel in the container to the height of theoretical density mixture in container divided into the l
densities in Table D.1
(.
KENO input density (gm/cc in this case - not atoms / barn-cm).
M
 
i...
BLE A2 PHENOLIC RESIN AND CARBON STEEL A.
Phenolic Resin Material Full Density 80% Density 60% Density (atoms / barn-cm)
Hydrogen 3.0140 E-03 2.4112 E-03 1.8084 E-03 B-10 4.2688 E-05 3.4151 E-05 2.5613 E-05 B-ll 1.6726 E-04 1.2581 E-04 9.4356 E-05 Carbon 2.3050 E-03 1.8440 E-03 1.3830 E-03 Nitrogen 5.2890 E-05 4.2312 E-05 3.1734 E-05 Oxygen 2.0510 E-03 1.6408 E-03 1.2306 E-03 t
1.997 E-04 1.5976 E-04 1.1982 E-04 Boron x, B.
Carbon Steel Material Densi'ty (atoms / barn-cm)
Carbon 3.921 E-03 Iron 8.3491 E-02 Material 100 1.0000 (Hansen-Roach)
KENO IV Material b.
M
 
1
(
~
i,LE A.3 INTERSPERSED WATER DENSITIES q
KENO Material MERIT /GEMER Densities Density (atoms / barn-cm)
Hydrogen Oxygen 0.010 6.6866 E-04 3.3433 E-04
-0.025 1.67173 E-03 8.35816 E-04 0.050 3.3433 E-03
- 1.6716 E-03 0.075 5.01489 E-03 2.50745 E-03 0.100 6.6866 E-03 3.3433 E-03 0.200 1.3373 E-02 6.6866 E-03 0.500 3.3433 E-02 1.6715 E-02 1.000 6.6866 E-02 3.3433 E-02
.I i
Material 502 I.
,wy
--------,,,,w.
,y
,--,w-.
-,--ey.--,
 
r O APPENDIX D
" CRITICALITY SAFETY ANALYSIS - BU-7, THEORETICAL DENSITY" O
J. T. Taylor January 1986 LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1
D
 
Page 1 of 2
( )-
Criticality Safety of BU-7 Container The BU-7 container has been licensed as a Fissile Class I shipping container.
For a Fissile Class I container it is necessary-to demonstrate that:
1) an infinite array of normal containers is critically safe with optimum interspersed moderation, and 2) an array of at least 250 containers subjected to the hypothetical shipping accident is critically safe with optimum interspersed water and full water reflection, and 3) a single container with optimum moderated contents and full water reflection is critically safe.
These criticality safety demonstrations are provided for the BU-7 container by three sources.
I)
" Criticality Safety Analysis of BU-7 Shipping Container for Powder", 3/6/80, WC Peters 00 UO2 II)
" Criticality Safety Analysis - BU-7, Theoretical Density",
(}
1/24/86, JT Taylor.CO m
III)
License SNM-1097, Rev(3)6, Table 4.4,
" Safe Batch Limits for
& H 0", 10/23/84.
UO2 2
There are three container contents in the shipping certificate:
A)
Uranium oxide powder with nominal enrichment not greater than 4.0 w/o and H/U atomic ratio not greater than 0.45.
B)
Uranium oxide powder with nominal enrichment not greater than 4.0 w/o, bulk density not greater than 4.5 gm/cc, and H/U atomic ratio not greater than 1.6.
C)
Uranium oxide pellets with nominal enrichment not greater i
than 4.0 w/o and H/U atomic ratio not greater than 0.45.
Content type A is limited to 35 kg/can and 70 kg/BU-7.
Content type B is limited to 35 kg/can and 70 kg/BU-7.
Content type C is limited to the lesser of one safe batch /can and two safe batches /BU-7 or 35 kg/can and 70 kg/BU-7.
flhppendix C of Consolidated Application
(
(2hppendix D of Consolidated Application (3hppendix E of Consolidated Application
 
Page 2 of 2 Criticality Safety of BU-7 Container O:
(continued)
The following table correlates the required demonstrations, container contents, and analyses.
Contents A
B C
Demonstratio Powder, H/U 10.45 Powder, H/d 11.6 Pellets, H/U10.45
: 1. Normal Array II I
II
: 2. Accident II I
II Array
: 3. Single I
I III Container O
I O
 
3 January 24, 1986
\\_-)
CRITICALITY ANALYSIS OF BU-7 CONTAINER FOR THEORETICAL DENSITY PELLETS i
I. SCOPE This analysis is performed to demonstrate criticality safety for the BU-7 shipping con tciner at 4.025% U235 enrichment with theoretical densi ty, heterogeneous UO2 and an H-to-U ratio not greater than 0.45.
The container was previously shown safe for-these contents but only up to a bulk UO2 density of 4.2 gm/ce.
II. GENERAL DISCUSSION The BU-7 shipping container consists of a phenolic resin insulation sandwiched between a 30 gallon inner drum and a 55 gallon outer drum.
The inner drum can hold up to two 5 gallon cans or three 2-1/2 or 3 gallon cans. The container is shown in Figure 1. The BU-7 container has been licensed as a Fissile Class I container based on the testing performed in Reference 1.
The original analysis of the BU-7 container by R Artigas is documented in Reference 2. Safety was demonstrated under both normal and accident shipping conditions with filled five gallon containers of U(4.00)O2 at a maximum density mixture with an H-to-U ratio notof 4.2 gm/cc and water as a homogeneous greater than 0.45 (ie:
~1.5 weight (ek /''y percent). The most, reactive Hansen-Roach U238 cross-sections (ID# 92801) were used. Because of this, shipments of dry (H-to-U < 0.45) UO2 pellets were covered provided that the bulk density was less than 4.2 gm/cc.
The theoretical packing factor for uniform right cylinders is 0.907 as shown in Attachment 1. The theoretical density of UO2 is 10.96 gm/cc.
Therefore, the theoretical bulk density for pellets (assuming no internal voids) is 9.94 gm/cc which is considerably larger than the maximum density used in the original analysis.
The BU-7 container is limited to twe safe batches of pellets per BU-7. However the original analysis assumed that each five gallon container was full. This assumption avoidt-d the necessity of considering intermediate densities, five versus three gallon containers, spacial distribution of fuel, and intermediate U235 enrichments. Under this assumption, each five gallon container has about 85 kg of UO2. The safe batch limit, however, would result in not more than 24.7 kg of pellets per five gallon container at 4.00% U235 enrichment.
In the current analysis, a maximum UO2 densi ty of 9.39 gm/cc has been used. (This results from a theoretical mixture of UO2 and 0.015 weight fraction water which is slightly conserv ative relative to an H/U ratio of 0.45.) Each five gallon container has 102 kg of UO2, which is greater than was used in the original analysi s. The 102 kg does no t c'omol e t ely fill a five gallon container at UO2 bulk densi ties greater than 4.5 gm/cc but is more than four times the 24.7 kg mass of 4.00%
U235 enriched UO2 pellets allowed by procedural controls.
The current analysis also supports a uniform BU-7 mass limit of 70
( )
km, consistent with Reference 4. The safetv factor between a 70 kg mass limit and the safety demonstration is a factor of about three.
s
 
January 24, 1986 page 2
CRITICALITY ANALYSIS OF BU-7 CONTAINER FOR THEORETICAL DENSITY PELLETS III. CRITICALITY SAFETY CONTROLS The following controls are necessary to meet thi s analysi s :
Control #1 Moderation - Contents must have an H-to-U ratio not greater than 0.45.
Geometry - Fuel may only be packaged in standard metal containers having radii not greater than 14.37 cm.
Control #2 Mass - Each BU-7 container is limited to not more than two safe batches of UO2 pellets as a function of enrichment and is limited to not more than 89 kg of total contents.
The following assumptions are made for this analysis:
Worst Credible Contents Form: heterogeneous UO2.
Density: 10.96 gm/cc (theoretical)
U235 Enrichment: 4.025%
Mass: 204 kg UO2/BU-7 Boundary Conditions Top: water re'flected array Bottom: water reflected array Sides: water reflected array Interunit Water - optimum Structure BU-7: carbon steel Fuel containers carbon steel Array Size Normal Condition: infinite Accident Condition: 8X8X4 IV. MODEL The current model is based on a 1980 reanalysis of the BU-7 container to demonstrate safety for UO2 powder with up to 50,000 ppm equivalent water moderation (Reference 4).
Two types of configurations are used in this analvsis, consistent with Reference 2. The normal model consists of an infinite close-oacked array of BU-7 containers with the insulation modeled as in Reference 4.
The accident model consists of an 8 by 8 by 4 high close-packed array of 4
vertical BU-7 containers with no insulation but with varying densities of water in the insulation regions.
The fuel mixture was obtained based on a theoretical mixture of U(4.025)02 olus 0.015 weight fraction water. Number densities are shown in the following table.
c.
,_/
 
January 24, 1986 page 3
CRITICALITY ANALYSIS OF BU-7 CONTAINER FOR THEORETICAL DENSITY PELLETS MATERIAL HANSEN-ROACH NUMBER DENSITY ID #
(ATOMS /BN CM)
U235 92507 8.53896E-04 U238 92801 2.01037E-02 OXYGEN 8100 4.19152E-02 WATER 502 1.43289E-01*
* MASS DENSITY The most reactive Hansen-Roach U238 cross-sections (ID# 92801) were used as in Reference 1. This enables the homogeneous fuel region to conservatively represent heterogeneous mixtures.
The calculational model contains 102.175 kg of UO2 in each of two five gallon containers. This corresponds to a full container of UO2 at a bulk density of 4.5 gm/cc. The following table shows the fuel height as a function of UO2 density.
RHO-UO2 FUEL HEIGHT (gm/cc)
(cm) 9.39 16.78 6.30 25.00 4.50 35.00 Since bulk censities greater than 4.5 gm/cc result in void regions within the inner container, spatial distribution of the fuel must be considered. Therefore, two models are used to represent the extremes of spatial distribution. The three spatial distributions considered are shown in Figure 2. Use of these three spatial distributions covers the use of five, three, or two and one-half gallon containers since the two five gallon containers have more volume and less metal than three of the smaller containers.
Figure 3 shows an X-Z geometry plot of a single BU-7 container from the model. Figure 4 sh<ss an X-Y plot of the accident array. Figure 5 shows an X-Z plot of the accident array. Sample listings of the GEKENO input are provided in Attachment 2. The model used for this analysis is significantly more reactive than the model used in the original analysis.
V.
CALCULATIONAL RESULTS Table 1 shows the results of calculations performed with the models in Section IV. Figure 6 shows the effect of the fuel density on k-eff for contiguous fuel when each five gallon container is limited to 102.2 kg UO2. Increasing the fuel density reduces the reactivity of the system.
Figure 7 shows the effect of separating the fuel regions within the inner container. The reactivity increases when the regions are seoarated (since a larger effective cross-sectional fuel area results) but is less i
than the smeared condition reactivity. These data show that the smeared
,(,
condition is the most reactive for the svstem being analy:ed.
The maximum k-effective + 3* sigma values are summarized below.
 
January 24, 1986 page 4
(O CRITICALITY ANALYSIS OF BU-7 CONTAINER FOR THEORETICAL DENSITY PELLETS CALCULATION CONDITION K-EFFECTIVE + 3* SIGMA LIMIT
____1____
BU7N. NORM NORMAL 0.7805 0.900 BU7N-35-125 ACCIDENT 0.9052 0.970 VI. CONCLUSION This analysis has demonstrated criticality safety of the BU-7 shipping container under the postulated shipping accident for not greater than 4.025% U235 enriched UO2 pellets up to and including theoretical density providing the H-to-U ratio within the inner container -does no t exceed 0.45 and the UO2 mass does not exceed 204 kg.
REFERENCES 1.
" Test Report for Model BU-7 Bulk Uranium Shipping Container",
04/25/80, JA Zidak.
: 2. "The General Electric Model BO-7 Uranium Shipping Container -
Criticality Safety Analysis", 02/74, R Artigas.
3.
" Criticality Safety Evaluation of a Shipping Container for Moderated Low-enriched Uranium Compounds", NUCLEAR TECHNOLOGY, VOLUME 19 07/73, R Artigas.
4.
" Criticality Safety Analysis of BU-7 Shipping Container for UO2 Powder", 03/06/80, WC Peters.
-#^N
% _,)
 
January 24, 1986 page 5
CRITICALITY ANALYSIS OF BU-7 CONTAINER FOR THEORETICAL DENSITY TELLETS LIST OF TABLES 1.
BU-7 CONTAINER, ARRAY CALCULATIONS, 0.45 H/U LIST OF FIGURES 1.
BU-7 CONTAINER GEOMETRY 2.
SPATIAL DISTRIBUTIONS CONSIDERED
: 3. X-Z GEOMETRY PLOT OF THE BU-7 CONTAINER
: 4. X-Y GEOMETRY PLOT OF THE BU-7 ACCIDENT ARRAY
: 5. X-Z GEOMETRY PLOT OF THE BU-7 ACCIDENT ARRAY 6.
EFFECT OF FUEL DENSITY ON K-EFF (CONTIGUOUS FUEL) 7.
EFFECT OF FUEL SEPARATION WITHIN BU-7 CONTAINER LIST OF ATTACHMENTS h
: 1. THEORETICAL PACKING FACTL OR ROD'S
: 2. SAMPLE LISTINGS OF GEKENO BU-7 MODEL INPUT i
 
January 27, 1986 TABLE 1 - BU-7 CONTAINER RESULTS ACCIDENT CAS(: 8X8X4 ARRAY (204 KG-UO2 PER BU-7, NO' INSULATION)
Fuel Fuel Fuel Interunit k-eff Sigma Histories Height Density Geometry Water (cm)
(gm/cc)
(sm/cc) 35.00 4.50 smeared 0.025 0.7654 0.0031 48500 0.050 0.8337 0.0029 45000 0.125 0.8959 0.0031 48500 0.250 0.8033 0.0032 48500 25.00 6.30 contiguous 0.025 0.7460 0.0035 26500 0.050 0.7942 0.0030 46500 0.125 0.8337 0.0031 34000 0.250 0.7435 0.0033 46500 16.78 9.39 contiguous 0.025 0.7301 0.0033 31500 0.050 0.7626 0.0026 45000 0.125 0.7753 0.0036 44500 0.250 0.7074 0.0028 48500 16.78 9.39 separated 0.025 0.7335 0.0029 44500 0.050 0.7842 0.0036 29000 0.125 0.8110 0.0026 48500 0.250 0.7148 0.0032 47000 NORMAL CASE: INFINITE ARRAY (204 KG-UO2 PER BU-7, W/ INSULATION)
Fuel Fuel Fuel k-eff Sigma Histories Height Density Geometry (em)
(sm/cc) 35.00 4.50 smeared 0.7742 0.0021 45500 g
l
 
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4 FIGURE 2 - SPATIAL DISTRIBUTIONS CONSIDERED SMEARED CONTIGUOUS FUEL SEPARATED FUEL VOID VOID VOID l
I h\\/
* v.
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3 93 0.0 00 e
6 0
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0.990
(
LEGEND HET. U(4)00 +.015 H00 o 204 KG-000- @ = 9.39
:< 204 6:G -i) 0 0 s @ = 6.30 0.960
+ 004 KG-UO2s C = 4.50 a
4 4
t 0.930 a
b 0.900 7~#
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. ti TE * ' '4 I T..,:i T."-
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FIGURE 7 - EFFECT OF FUEL EE?ARATION WITHI:1 SU-7 C001TAIi.E.9 0.220 LEGE!!D HET. U(4)C2
.015 H2O e 204 KG C 071 T I C U Q U O F '!! L
:=' 004 KG OEP6 RATED FUEL 0.960
+ 204 KG O t1E A R E D FUEL 1
1 0.930 4
4 0.900 j
,e<
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,4'
=
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* 6
 
e October 30, 1985 ATTACHMENT 1 - THEORETICAL PACKING FACTOR FOR RODS The theoretical packing factor for rods is determined as follows based on Figure A1. The triangle represents a unit cell which can be reflected on all three sides to obtain an infinite array of uniform cylinders with a triangular pitch.
Total Area = 0.5
* base
* height
= 0.5
* 2R
* 2R*COS(30)
Fuel Area
= 3
* 60/360
* Pi*R*R
= 0.5
* Pi*R*R Fuel Area Packing Factor
= ----------
Total Area Pi
= ___________
4
* COS(30) h
= 0.907 O
 
FIGURE A1 - THEORETICAL PACKING FACTOR FOR RODS 9
^^h
,s^'~...
/
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Januarv 17, 1996
\\
ATTACHMENT 2 - GEKENO INPUT LISTING FOR BU7N-35-125 85.227,8U7
,Hnnn, 4.025,WTFRO.015,0,884, 12.W.MB 999.0 100 500 3
16 6
9 5
12 15 1 2R8 4 9 2Z 10.0 1 11 1
-92507 4.09382E-04 1
92801 0.96383E-02 1
8100 2.00953E-02 1
502 0.68697E-01 2
6100 1.3830E-03 2
1102 1.8084E-03 2
5100 1.1982E-04 2
14100 3.1734E-05 2
8100 1.2306E-03 3
100 1.
4 502 0.125 5
502 1.
CYLINDER 3 14.37 0.05 -0.05 16*0.5 CYLINDER 1 14.37 35.05 -35.05 16*0.5 CYLINDER 0 14.37 35.05 -35.05 16*0.5 CYLINDER 3 14.42 25.1 -35.1 1G*0.5 CYLINDER 0 17.70 35.1 -25.1 16*0.5 CYLINDER 3 17.308 35.5763 -35.2087 16*0.5 CYLINDER 4 23.495 35.5763 -42.8287 16*0.5 llg CYLINDER 4 23.495 36.688
-42.8287 16*0.5 CYLINDER 4 28.575 44.308
-42.8287 16*0.5 g
CYLINDER 3 28.575 44.4167 -42.9374 16*0.5 CYLINDER 0 28.575 45.3692 -44.8424 16*0.5 CYLINDER 3 29.634 45.3692 -44.3424 16*0.5 CUBOID 0 28.684 -28.694 28,684 -23.684 45.3692 -44.9424 16+0.5 CORE BDY 0 229.472 -229.472 229.472 -229.472 180.4232 -190.4232 16Z CUBOID 5 260.
-260.
260.
-260.
212.
-212.
16Z
 
Januarv 22. 1986 ATTACHMENT 2 - GEKENO INPUT LISTING FOR BU7N-16.78S-050 85.227,8U7
,Hnnn, 4.025.NTFRO.015.0.SS4 5.W.MB 999.0 100 500 3
16 6
9 5
12 15 1 2RS 4 9 22 10 0 1 11Z 1
-92507 S.53896E-04 1
92801 2.01037E-02 1
8100 4.19152E-02 1
502 1.43289E-01 2
6100 1.3830E-03 2
1102 1.8084E-03 2
5100 1.1982E-04 2
14100 3.1734E-05 2
8100 1.2306E-03 3
100 1.
4 502 0.050 5
502 1.
CYLINDER 3 14.37 0.05 -0.05 16*0.5 CYLINDER 0 14.37 18.22 -18.22 16*0.5 CYLINDER 1 14.37 35.05 -35.05 16*0.5 CYLINDER 3 14.42 35.1 -35.1 16*0.5 CYLINDER 0 17.70 35.1 -35.1 16*0.5 CYLINDER 3 17.808 35.5763 -35.2087 16*0.5 CYLINDER 4 23.495 35.5763 -42.8287 16*0.5
~s CYLINDER 4 23.495 36.688
-42.8287 16*0.5 CYLINDER 4 28.575 44.308
-42.8287 16*0.5
('
CYLINDER 3 28.575 44.4167 -42.9374 16*0.5 CYLINDER 0 28.575 45.3692 -44.8424 16*0.5 CYLINDER 3 23.684 45.3692 -44.8424 16*0.5 CUBOID 0 28.684 -28.684 28.684 -28.634 45.3692 -44.8424 16*0.5 CORE BDY 0 229.472 -229.472 229.472 -229.472 130.4232 -180.a232 16Z CUBOID 5 260.
-260.
260.
-260.
212.
-212.
16Z m
\\
 
January 22. 1996 ATTACHMENT 2 - GEtENO INPUT LISTING FOR BU7N. NORM 85.227,8U7
,Hnnn. 4.025,WTFRO.015,0,000, 0.I.MB.
999.0 100 500 3
16 6
9 5
12 13 1 1 1 1 9 1 0 10 0 1 11Z
-1.0 -1.0 -1.0 -1.0 -1.0 -1.0 1
-92507 4.09332E-04 1
92801 0.96393E-02 1
8100 2.00953E-02 1
502 0.68697E-01 2
6100
: 1..?S30 E-0 3 2
1102 1.3084E-03 2
5100 1.1992E-04 2
14100 3.1734E-05 2
8100 1.2306E-03 3
100 1.
4 502 0.125 5
502 1.
CYLINDER 3 14.37 0.05 -0.05 16*0.5 CYL I NDER-1 14.37 35.05 -35.05 16*0.5 CYLINDER 0 14.37 35.05 -35.05 16*0.5 CYLINDER 3 14.42 35.1 -25.1 16*0.5 CYLINDER 0 17.70 35.1 -35.1 16*0.5 CYLINDER 3 17.808 35.5763 -35.2087 16*0.5 CYLINDER 2 23.495 35.5763 -42.8237 16*0.5
_ _s
(
i CYLINDER 2 23.495 36.688
-42.8297 16*0.5 y;
CYLINDER 2 23.575 44.303
-42.8287 16*0.5 CYLINDER 3 29.575 44.1167 -42.9374 16*0.5 CYLINCER 0 28.575 45.3692 -44.8424 16*0.5 CYLINDER 3 28.684 45.3692 -44.8424 16*0.5 CUSOID 0 28.384 -23.634 28.G34 -28.634 45.3692 -44.8424 1G+0.5
/
 
m 0
APPENDIX E TABLE 4.4
" SAFE BATCH LIMITS FOR 00 AND H 0" 2
2 NRC LICENSE SNM-1097 CONDITION 9, PART I
,j LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1
 
I TABLE 4.4 4
7.((
SAFE BATCH LIMITS FOR UO, & H,0 (Kgs UO2)
)
l Nominal
)
U23s U23s Enrich-Enrich-j ment 00 UO ment UO UO 2
2 2
2 w/o Powderl Pellets 2 w/o Powder l Pellets 2 1.1 2629 510 3.4 34.6 31.0 j
1.2 1391 341 3.6 31.1 28.5
}
1.3 833 246 3.8 28.3 26.4 1.4 583 193 4.0 25.7 24.7 1.5 404 158 4.2 23.7 22.9
)
1.6 293.3 135 4.4 21.9 21.4 1.7 225.0 116 4.6 20.2 20.0 1.8 183.0 102 4.8 19.1 18.8 1.9 150.6 90.5 5.0 18.1 18.1 2.0 127.5 81.6 5.5 15.4 15.4 j
2.1 109.2 73.1 6.0 13.8 13.8 l
2.2 96.8 66.4 7.0 8.3 8.3 j
2.3 84.3 61.0 8.0 6.9 6.9 i
i 2.4 74.7 56.1 9.0 5.9 5.9 2.5 68.9 52.1 10 5.1 5.1 2.6 60.5 48.8 11 4.4 4.4 2.7 56.6 45.4 12 3.9 3.9 j
2.8 52.2 42.9 13 3.5 3.5 j
2.9 47.6 40.1 14 3.3 3.3 3.0 44.5 38.1 15 3.0 3.0 3.2 38.9 34.1 NOTE:
For enrichments not specified above, smooth curve interpolation of safe batch values may be used.
l ilomogeneous mixtures j
Hetergeneous mixtures 2
}
LICENSE SNM-1097 DATE 10/23/84 PAGE DOCKET 70-1113 RCVISION 6
I_4,9
)
i
- -}}

Latest revision as of 16:59, 23 May 2025

Rev 1 to Consolidated Application for Certificate of Compliance 9019 for Model BU-7
ML20207P092
Person / Time
Site: 07109019
Issue date: 12/22/1986
From:
GENERAL ELECTRIC CO.
To:
Shared Package
ML20207P087 List:
References
NUDOCS 8701150039
Download: ML20207P092 (163)
v • d • e


Text

~h (V

BU-7 SHIPPING PACKAGE CONSOLIDATED APPLICATION i

CERTIFICATE OF COMPLIANCE O

osx/sois/ar i

General Electric Company Nuclear Fuel & Components Manufacturing Wilmington, North Carolina K$hhhh$3, PDR LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1

- i-

TABLE OF CONTENTS Page

1.0 INTRODUCTION

1 2.0 PACKAGE DESCRIPTION 2

2.1 General 2

2.2 Gross Weight 2

2.3 Uranium Oxide Powder & Pellet Container 2

2.4 BU-7 Inner Containment 2

2.5 BU-7 Outer Container 3

2.6 Insulating Material 3

2.7 Package Description - Contents 3

3.0 PACKAGE EVALUATION 6

3.1 General.

6 3.2 Single Package - Normal Transport Conditions 6

3.3 Single Package - Accident Evaluation 7

3.4 Acceptance Criteria 8

4.0 CRITICALITY SAFETY EVALUATION 14 4.1 Uranium Oxides in Powder Form - H/U Ratio < 0.45 14 4.2 Uranium Oxides in Powder Form - H/U Ratio I 1.6

& C/U Ratio < 1.27 14 4.3 Uranium Oxides In Pellet Form 14 5.0 TESTING, OPERATING & MAINTENANCE 15 O

5.1 Testing 15 5.2 Operating 15 5.3 Maintenance 16 6.0 BU-7 TRANSPORT PACKAGE SPECIFICATIONS 17 APPENDICES A-Drawing 112D1592, " Shipping Container - Model BU-7" B- " Test Report for Model BU-7 Bulk Uranium Shipping Container" C

" Criticality Safety Analysis of BU-7 Shipping Container for l

UO Powder" 2

l D

" Criticality Safety Analysis - BU-7, Theoretical Density" i

E

" Safe Batch Limits for UO and H 0", NRC License SNM-1097, Condition 9, Part I,Tabfe4.4 2

LICENSE SNM-1097 DATE 12/22/86 PAGE 1

DOCKET 71-9019 REVISION 1

ii -

1.0 INTRODUCTION

,.L]

The BU-7 package is currently authorized by NRC Certificate of Compliance USA /9019/AF as a Fissile Class I. container for the transport of fissile radioactive material in the form of uranium dioxide powder and pellets.

A complete series of tests have been conducted on the BU-7 package to verify conformance with the requirements of 10 CFR 71.

This application amendment contains a consolidation of all applications and package test results previously submitted in Docket 70-754 (for NRC License SNM-960),

Docket 70-1007 (for NRC License SNM-54), and Docket 71-9019 for license and certificate amendments pursuant to 10 CFR 71 related to the General Electric BU-7 (m) package.

It is requested that the BU-7 package be certified as complying with the revised regulatory requirements of 10 CFR Part 71 published in the Federal Register, Volume 48, No. 152, on August 5, 1983, with an effective date of September 6, 1983.

The purpose of the revision was to make NRC transportation regulations compatible with those in " Safety Series No.

6, IAEA Safety Standards, Regulations for the Safe Transport of Radioactive Materials, 1973 Revised Edition (As Amended)".

LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1

_ 1 -

2.0 PACKAGE DESCRIPTION 2.1 GENERAL Inner containment is a nominal 16-gallon drum closed by a gasketed, bolted lid, centered and supported within an outer 55-gallon drum by solid insulating media, and containing two or more steel pails which contain uranium oxide powder and pellets.

(See Drawing 112D1592.in Appendix A.)

2.2 GROSS WEIGHT 370 pounds, maximum 2.3 URANIUM OXIDE POWDER & PELLET CONTAINER 1

One or more closed containers, 11.25" inside diameter

(

fabricated of minimum 24-gauge steel, vertically stacked in each BU-7 unit.

2.4 BU-7 INNER CONTAINMENT A nominal 16-gallon drum constructed of 18 gauge steel, modified by the welded attachment of a closure flange to accept a 3/16" thick steel lid which is gasketed for resistance to high temperature as shown in Drawing.

112D1592 and attached by twelve 5/16" minimum steel The minimum inside dimensions of'the inner bolts.

containment drum are 13 3/4" diameter by 26 3/4" high.

I LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1

_2_

l

2.5 BU-7 OUTER CONTAINER O

A nominal 55-gallon DOT Specification 17H steel drum (with three rolling hoops) or Uniform Freight j

Classification Rule 40 steel drum (with two rolling hoops).

Drum is' 18-gauge steel with a nominal outer dimension height without the cover of 35" and a nominal inner diameter dimension of 22 1/2".

2.6 INSULATING MATERIAL The inner containment drum is centrally held within the outer container by, and the space between the inner and the outer containers is completely filled with, solid insulating media composed of fire-retardant phenolic foam as specified in Drawing 112D1592.

Four 1/4" diameter vent holes equally spa'ced near the top of the outer container, covered with waterproof tape, would

()

permit steam to escape in the event free moisture in the insulating material were exposed to the heat from an accidental fire during transport.

2.7 PACKAGE DESCRIPTION - CONTENTS 2.7.1 Type & Form of Material (1)

Uranium oxide powder enriched to not more than 4.0 235 isotope.

The maximum H/U atomic W/O in the U ratio shall not exceed 0.45.

The mass of moderating materials within the inner container when added to the total mass of moderator within the fuel shall not exceed 525 grams.

(See Appendix D.)

LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1 _

,-ww y-

..c-,

,y

,.-y_

y

.m,i->--

l (2)

Uranium oxide powder with a maximum bulk density

()

not greater than 4.5 grams /cc.

Uranium may be enriched to not more than 4.0 W/O in the U 235 isotope.

The maximum H/U atomic ratio shall not exceed 1.6.

The mass of moderating materials within the inner container when added to the total mass of moderator within the fuel shall not exceed 1750 grams.

(See Appendix C.)

v.

(3)

Uranium oxide as pellets enriched to not more than 4.0 W/O in the U235 isotope.

The. maximum H/U atomic ratio shall not exceed 0.45.

The mass of moderating materials within the inner container when added to the total mass of moderator within the fuel shall not exceed 1.5% of the UO mass 2

limit..

(See Appendix D.)

}

2.7.2 Maximum' Quantity of Material per Package (1)

For contents described in 2.7.1(1) and (2), the maximum contents of uranium oxide powder per package and pail shall be limited to 70 kgs and 35 kgs, respectively.

(2)

For contents described in 2.7.1(3), the maximum contents per package and pail shall be limited in j

accordance with the following table:

l LICENSE SNM-1097 D. ATE 12/22/86 PAGE

()

DOCKET 71-9019 REVISION 1 !

Maximum O'

U 235 Enrichment, Maximum UO,, kgs W/O Per Pail Per Package 3.0 35.0 70.0 3.2 34.1 68.2 3.4 31.0 62.0 3.6' 28.'S 57.0 3.8 26.4 52.8 4.0 24.7 49.4 2.7.3 Mixtures of Uranium oxide Powder &' Pellets The maximum contents per package and pail for mixtures of uranium oxide powder and pellets shall be limited to the amounts shown in the table in Section 2.7.2(2).

2.7.4 Mixtures of Uranium-Oxide Powder with Additives For contents as described in 2.7.1(2), ammonium oxalate

()

and/or ammonium bicarbonate additives are permitted in the UO Powder to the extent that the C/D ratio does not 2

exceed 1.27.

(See Appendix C.)

l I

LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1._. _ _ _ _ _ - - _.., _ _ -. - _ _. ~ -

3.0 PACKAGE EVALUATION 3.1 GENERAL There are no components of the packaging or its contents which are subject to chemical or galvanic reaction during normal transportation.

The package cannot be opened inadvertently, uses no coolant and has no lifting or tiedown attachments.

3.2 SINGLE PACKAGE - NORMAL TRANSPORT CONDITIONS Between March 20 and April 2, 1980, a series of tests were performed on the BU-7 transport package.

These tests are described in a report dated April 25, 1980, which is included in Appendix B to this application.

()

Included in these tests were some simulated normal transport conditions.

Not all such conditions were tested because the package requirements for some of these conditions could be demonstrated to be satisfactory by other means.

Two BU-7 packages were loaded with two 5-gallon steel p wder pails, each pail being filled with 45 kgs of UO 2 containing natural uranium, for a total of 90 kgs of UO 2 powder per package.

These packages were used for the tests' simulating hypothetical accident conditions, as described in the test report.

One BU-7 package was loaded with two 5-gallon steel pails containing a total of 93 kgs of lead shet.

This LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1

package was subjected to tests simulating normal f ')

transport conditions.

~-

A summary of this information is given in Table 3-1.

The tests and assessments set forth in Table 3-1 provide assurance that the powder or pellet contents are contained in the pails during normal transport and there is no reduction in effectiveness of the package system.

It has been demonstrated, moreover, that there would be no water inleakage to the product during 'cormal transport conditions.

3.3 SINGLE PACKAGE - ACCIDENT EVALUATION On February 6, 1978, through February 10, 1978, a series of immersion / pressure tests were conducted on a BU-7

(]')

shipping package.

These tests are described in a report dated February 10, 1978, which is included in Appendix B.

The results of these tests are summarized in Item (5) of Table 3-2.

Between March 20 and April 2, 1980, a series of tests were performed on the BU-7 transport package.

These I

tests are described in a report dated April 25, 1980, which is included in Appendix B to this application.

Included in these tests were some done sequentially simulating hypothetical accident conditions during transport.

A summary of these tests is given in Table 3-2.

LICENSE SNM-1097 DATE 12/22/86 PAGE t' }

DOCKET 71-9019 REVISION 1

Upon completion of the four hypothetical accident (v) condition tests,, conducted in thd sequence prescribed in 10 CFR 71, the package subjected to all these tests, was opened and inspected.

There was no damage to the inner containment sealing features; the original computer weigh cards were with the 5-gallon pails; they were not wet and there was no moisture in the inner container.

The top insulation disc was badly charred and the outside of the bolted cover had some blistered paint, but there was no structural damage, breach of containment, or loss of shielding.

3.4 ACCEPTANCE CRITERIA Acceptance criteria for meeting the requirements of 10 CFR 71 are as follows:

o No water intrusion to the contents.

(j No. rupture of the product containers or inner o

container.

No damage to the inner containment sealing features o

that would yield them ineffective.

No significant defo.rmation to the outer container o

that would affect criticality safety considerations.

We have concluded, as a result of these tests described above, that all tests required by 10 CFR 71, have been conducted, witnessed by Quality Control Engineering, and have passed the acceptance criteria.

Test completion check sheets and compliance certificates are included in l

Appendix B to this application.

LICENSE SNM-1097 DATE 12/22/86 PAGE

/ )'s i

DOCKET 71-9019 REVISION 1

TABLE 3-1 SINGLE BU-7 TRANSPORT PACKAGE - NORMAL TRANSPORT CONDITIONS

.(d

\\

10 CFR 71.71 Requirements Tests Conducted Results (1) Heat. An ambient No tests required.

Temperature of 100* F is within temperature of 38' C (100*

normal operating range for materials of construction.

F) in still air, and insolation according to the following table:

INSOLATION DATA Total Insolation for a 12-Form & Location hr Period 2

of Surface (g cal /cm )

Flat surfaces transported horizontally

- Base None

- Other Surfaces 800 Flat surfaces not transported horizontally 200 Curved surfaces 400

/]

(2) Cold. An ambient No tests required.

Temperature of -40' F is within

()

temperature of 40*C (-40*F) normal operating range for in still air and shade.

materials of construction.

(3) Reduced external oressure.

Package was submerged in water o No water leakage into inner An external pressure of 24.5 to a pressure of 1.50 kg/cm2 (50 containers after 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of kilopascal (3.5 psi feet of water), then pressurized submergence.

absolute).

and checked for leakage in four increments:

o No leakage of air from inner (4) Increased external pressure.

containers when pressurized 2 for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and held at each pressure An external pressure of 140 o 0.75 kg/cm 2 for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> increment for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

kilopascal (20 psi) o 1.0 kg/cm 2 for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> absolute.

o 1.25 kg/cm o 1.5 kg/cm2 for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (5) Vibration. Vibration No tests required.

Packages of this type have normally incident to withstood sevecal years of transport.

transport with ru occurrences of significant damage due to normal l

vibration.

(6) hter array. A water spray Package was exposed to a water There were no signs of water that simulates expceure to sprey sufficiently heavy to keep damage to the package.

rainfall of approximately all exposed surface except the five em (2") per hour for at bottom wet for a period of 30 least one hour.

minutes.

I

^

LICENSE SNM-1097 DATE 12/22/86 PAGE l

DOCKET 71-9019 REVISION 1

TABLE 3-1

' Continued b

v 10 CFR 71.71 Requirements Tests' Conducted Results (7) Free drop. Between 1-1/2 The package, loaded with 93 kgs There was a slight deformation and 2-1/2 hours after the of test weight, was dropped 4 of the outer container closure conclusion of the water feet with the closure ring ring that did not inpair its spray test, a free drop impacting onto a flat reinforced function. There was no damage through the distance concrete pad. The test was to the inner container seal of

.specified below onto a flat, conducted 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the the 5-gallon pails, and there essentially unyielding, water spray test, was no separation of the closure horizontal surface, striking ring from the lid of the outer the surface in a position cont ainer.

for which maximum damage is expected. For Fissile Class 11 packages, this free drop must be preceded by a free drop from a height of 0.3 m (1 ft) on each corner or, in the case of a cylindrical Fissile Clase !! package, onto each c' e quarters of each rim.

CRITERIA FOR FREE DROP TEST (WEIGHT / DISTANCE)

Free Drop Package Weight Distance Kilograms Pounds Meters Feet 5,000 or (11,000) 1.2 (4) less 5,000 to (11,000-10,000 22,000) 0.9 (3) 10,000 to (22,000-0.6 (2) 15,000 33,000)

More than More 0.3 (1) 15,000 than 33,000 (8) Corner Drop. This test No teste were required.

The package gross weight exceeds applies only to packages 110 pounds.

which are constructed primarily of wood of fiberboard, and do not exceed 110 pounds gross weight.

(9) Compres-lon. For packages Weight equal to more than 5 No damage to the package due to weighing up to 5000 kg, the times the weight of the package compressive loading was found.

package must be subjected, was applied to the top of the for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, to package for a period of 24 (cont'd)

(cont'd)

LICENSE SNM-1097 DATE 12/22/86 PAGE 1

DOCKET 71-9019 REVISION 1 __.

TABLE 3-1 Continued 10 CFR 71.71 Requiremente Teste Conducted Results a compressive load applied hours. The test weight used wie uniformly to the top and 2,440 pounde.

bottom of the package in the position in which the package would normally be transported. The compressive load must be the greater of the followings (1) The equivalent of five times the weight of the packages or (ii) The equivalent of 12.75 2

kilopescal (1.85 lb/in )

multiplied by the vertically projected area of the package.

(10) Penetration. Irupact of the The package wee penetration There wee a eli@t indentation hemispherical end of a tested by impacting the where the 13 pound bar struck vertical steel cylinder of

. hemispherical end of a vertical the container. It did not-3.2 cm (1-1/4") diameter steel cylinder 1-1/4" in penetrate the package.

and six kg (13 lb) mass, diameter and weighing 13 pounds, dropped from a height of and dropped from a height of 40" one n (40") onto the into the top of the container exposed surface of the where it is most susceptible to packege which is expected a' projectile penetration.

to be most vulnerable to puncture. The long axis of the cylinder must be perpendicular to the packege surface.

l

(

LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1

- 11 l

i

~,.n...._,

.-,_------.--.--.,a-

TABLE 3-2 SINGLE BU-7 TRANSPORT PACKAGE - ACCIDENT CONDITIONS

  • O G

10 CFR 71.73 Requirements Tests Conducted Results (1) Free Drop. A free drop of Each of the two packages was Both packeges inpacted at the specimen through a raised by a crane to a 30 ft pre-determinod angles. Areas at distance of nine m (30 ft) height at approximately a 45' points of impact of both units onto a flat, essentially angle. The height was were without fracture. Beyond unyielding, horizontal determined by a measured, this, the only significant surface, striking the weighed cord hanging from the dmage was a slight opening of surface in a position for containers. A quick release the cover where the closure ring which maximum dmage is mechanism was used to drop the of one package was deformed.

expected.

packages, which fell at The bottom corner free-fall test approximately a 45' angle, of the outer package caused landing on the corners of the somewhat more crushing of the package.

container than was experienced in the too drop. There was no evidence of fractures or separation of the package side from the bottom; therefore, the package with the slight opening

{

due to the top drop was deemed

~

to have suffered the maximun d mage.

Post-test inspection showed N0 damages to the sealing features of the inner containers or to the 5-gallon pails.

(2) Puncture. A free drop of Both packages were free-dropped Both packages were slightly the specimen through a through a distance of 40",

indented (about 1/4"). There distance of one m (40") in a striking the top end of a was no puncture of either position for which maximum vertical steel bar mounted on a

package, damage is expected, onto the reinforced concrete pad. The upper end of a solid, bar was fabricated per the vertical, cylindrical, alld requirements of 10 CFR 71, steel bar mounted on an Appendix B.

essentially unyielding, horizontal surface. The bar A vertical drop with the must be 15 cm (6") in container impacting on the 18 dimeter, with the top gauge cover near the outer edge horizontal and its edge was considered the most rounded to a radius of not vulnerable orientation to more than six mm (1/4") and puncture.

of a length as to cause maximum damage to the package, but not less than l

20 cm (8") long. The long exis of the Der must be i

vertical.

(3) Thermal. Expcaure of the A thermal test of one of the Inspection of the inner whole specimen for not less packages (the one that sustained container after all the tests than 30 minutes to a heat the most damage from the showed no damage to the inner flux not less than that of a free-drop through 30 feet) container, its sealing features (cont'd)

(cont'd)

(cont'd)

LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1

12 -

TABLE 3-2 Continued

,b 10 CFR 71.73 Requirements Tests Conducted Results radiation environment of followed the 30 foot free-drop or to the 5-gallon pails that 800* C (1475* F) with an and puncture tests. The thermal would yield either of them emissivity coefficient of at test conducted required exposure ineffective. The paint was least 0.9.

For purposes of to an environment of 1475*

slightly blistered in a small calculation, the surface minimtn for a period of 30 area at the top end of the inner absorptivity nust be either minutes. Since an actual container, but no indication of I

that value which the package gasoline fire with open flames this on either of the 5-gallon

'P "d

may be expected to possess provides the most realistic pails containing UO2 if exposed to a fire or 0.8, means of satisfying the whichever is greater. In requirements of 10 CFR 70 addition, when significant, thermal test, this method was convective heat input must chosen for the BU-7 test.

be included on the basis of still, anblent air at 800* C (1475* F).

Artificial cooling must not be applied after cessation of external heat input and any combustion of materials of construction must be allowed to proceed until it terminates naturally. The effects of solar radiation may be neglected prior to, during, and following the test.

e]

,V (4) Immersion-fissile material.

After the fire test, the package Following immersion as For fissile material, in was allowed to cool down for the described, the package was those cases where water prescribed period of time, and opened and inspected. The inner inleakage has not been then placed in the water container was dry, the silicone assumed for criticality immersion tank under 3-1/2 feet rthber gasket was not damaged, analysis, the specimen must of water. One hundred-twenty and analysis of the UO P "d

2 be immersed under a head of pounds of weights were attached showed there was no significant water of at least 0.9 m to the unit to insure that it increase in the moisture (3 ft) for a period ot' not would sink, it remained

content, less than eight hours and in submerged for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

the attitude for which maximta leakage is expected.

(5) Immersion-all packages. A The BU-7 package was submerged There was. no water leakage in separate, undamaged specimen to a depth of 50 feet above the the inner container after eight rust be subjected to water container for a period of eight hours o' submergence in 50 feet pressare equivalent to hours.

of water.

immersion under a head of water of at least 15 m (50 ft) for a perloc of nat less than e @ t hours. For test purposes, u external pressure cf water of 147 kilopascal (21 psi) gauge is considered to meet these conditions.

m LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1

13 -

~

4.0 CRITICALITY SAFETY EVALUATION

/,

y, 4.1 URANIUM OXIDES IN POWDER FORM - H/U RATIO 10.45 For the contents described in Section.s 2.7.1(1-) and 2.7.2(1) (uranium oxide powder with H/U ratio 1 0.45),

the criticality safety of the BU-7 package is described in Appendices C and D.

These analysis results demonstrate that for these contents, the BU-7 package can be transported as Fissile Class I, pursuant to the applicable sections of 10 CFR 71.

4.2 URANIUM OXIDES IN POWDER FORM - H/U RATIO 11.6

& C/U Ratio 11.27 For the contents described in Sections 2.7.1(2) and 2.7.2(1) (uranium oxide powder with H/U ratio f 1.6 and C/U ratio 1 1.27), the criticality safety of the BU-7

(~)

package is described in Appendix C to this application.

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These analyses results demonstrate that the BU-7 package can be transported as Fissile Class I, pursuant to the applicable sections of 10 CFR 71, for these contents.

4.3 URANIUM OXIDES IN PELLET FORM For the contents described in Sections 2.7.1(3) and 2.7.2(2) (uranium oxide pellets), the criticality safety of the BU-7 package is described in Appendices D and E.

These analysis results demonstrate that for these contents, the BU-7 package can be transported as Fissile Class I, pursuant to the applicable sections of 10 CPR 71.

LICENSE GNM-1097 DATE 12/22/86 PAGE lll DOCKET 71-9019 REVISION 1

t 5.0 TESTING, OPERATING, AND MAINTENANCE 5.1

. TESTING Inner containers are verified for leak tightness by a submerged bubble pressure test at 15.0 psig, minimum.

The test is conducted using a silicone rubber gasket as the only sealing agent between 'the flange and cover.

5.2 OPERATING 5.2.1 Inspection Prior to First Use The BU-7 package is inspected prior to first use to assure that the requirements of 10 CFR 71.85 are met, and to assure that it has been constructed in accordance with the package design as approved by the NRC.

()

5.2.2.

Inspections Prior to. Subsequent Use 1

Prior to subsequent use, each BU-7 package is inspected to assure that the requirements of 10 CFR 71.87 are met, and to assure that the effectiveness of the package has not been degraded.

5.2.3 Quality Assurance Program Constructior. and use of the BU-7 packages will be accomplished in conformance with 10 CFR 71.101 and the l

General Electric Quality Assurance Program as described in the submittal to the U.S. Nuclear Regulatory Commission made on December 27, 1978 and as currently approved on October 9, 1984.

LICENSE SNM-1097 DATE 12/22/86 PAGE 15 -

DOCKET 71-9019 REVISION 1

5.3 MAINTENANCE

_LO All BU-7 packages foured to be unacceptable as a result of inspections conducted either prior to first use or Prior to subsequent use will be identified for the necessary repair or maintenance.

Inspection of the repair or maintenance will be conducted prior to use.

O LICENSE SNM-1097 DATE 12/22/86 PAGE

()

DOCKET 71-9019 REVISION 1

16 -

'6.0 BU-7 TRANSPORT PACKAGE SPECIFICATIONS O

Specifications for the BU-7 transport package are shown on General Electric Drawing 112D1592 in Appendix A.

O l

LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1

17 -

t

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V i

APPENDIX A DRAWING 112D1592

" SHIPPING CONTAINER - MODEL BU-7" O

LICENSE SNM-1097 DATE 12/22/86 PAGE g

DOCKET 71-9019 REVISION 1

A

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l I I IMllLATI " Ptiti 22 - 1/8

  • DIA. x 2.75 MIN. THICMSS FIE EIND*T Railt F0VI GD LIVDJ. FT. MIN. IENSITY)

ER AEC PRIDIAt3 #0 EQJIMNT SFECIFICATIQ( SP - 9 As rtT!FIED BY ORIP ERRTS K/TL-729 #D K/P-6575

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U di IfH,16 GA. COVER WITH i D

CORRUGATION NEAR THE PERIPH WATERTIGHT \\

n SEE NOTE I / 1/16 V DOT 17H,12 GA. CLOSURE RINI DROP FORGED LUGS, DRILLED /d

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THREADED FOR 5/8" DIA. BOLT GASKEI 1/8" THICK $1LICONE 1 INNER LID 45 TO 75 MRWiER (SEE DETAIL ZONE D-2)

(SEE DETAIL ZONE H-7)

FOUR EOUALLY SP CED 1/4" DIA. VENT HOLES.'

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NEAR TOP, COVERED WITH WATERPROOF TAPE j

7/16* DIA THRU 12 HOLES

'x P EQ. SPACED ON A 15-3/4" DIA. B.C.

FLANGE I 1-1/

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.N (SEE DETAll 20 IC FOAM IN$ip A(NOLIC FDAM $ HALL '

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,,o tanRENT $PECT nouns K/TL-729 see N

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3/16 THICK STL. PLATE 55 GALLON, EDT :

h-18 GACE STEEL D N

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ItaiER DRUM 10 GAL., 18 GAGE

- SEE NOTE 2 STEEL DRUM F

GPCSS WEIGHT) 370 LBS. MAX. LOADED, O

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,WITH NOTES:

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1. LEAK TIGHTNESS IS VERIFIED BY A SUBPIRGED BUBBLE PRESSURE TEST lANDNUT.(SEENOTE7)

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AT 15.0 PSIG, MI'llMUM. TEST IS CONDUCTED USING THE SILICONE IU3EER RUBEER CONTAINER GASKET AS THE ONLY SEALING AGENT. EETWEEN

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FLANGE AND COVER.

2. C0fwEXITY OF BOTTOM HEAD: 3/8* MIN TO 3/4" MAX,
3. MINIP2 CAVITY DEPTH REQUIRED TO ACCOMODATE PRODUCT CONTAINERS.

g 4.

ALL FAERICATION AND MACHINING DIMENSIONS ARE NOMINAL UNLESS

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3 i g l OTHERWISE INDICATED.

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DELETED o

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- :l l' x l-1/2' x 3/16* STL 6.

IFTER FIDL ACCEPTANCE INSPECTION, PARK CONT 1.lNER WITH NE H-9) 1/2* (MIN!P.'M) CHARACTERS. USING WHITE PAINT:

J i * <'IE ET*3 (7-9 LBS ER CU.FT.)

GENERAL ELECTRIC COMPANY

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EDDEL EU-7 TYPE A r :: accmomct tim g: wtatat.s knia SP4 on as poeirica av oesp USA / 9019 / AF GROSS CMT V/P-6575.

7.

tFFIX TAMPER SAFE SEAL 10 3/8" DIA. E0LT PER REQUIREPENTS OF 10CFR11.43 (6),

27 25g TOR 0t'E 5/1f.' DIA. INNER CONTAINER BOLTS TO 150 INCH-POUN 8.

7-H, OR UFC RULE 40 SEE f4NE 3 mm UM. h INSIEE DIA.

35.750

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%.025 Hucm wim CDAR OFF l

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gC Id CM PRELIP! NARY 5

g e.d NRC APPROVAL OF DESIGN FICd!PID y

1.D. OF INNER CONTAINER

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13.75 p/

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5/16* - 18 STL BOLT o

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5/16 STL. WASHER (12 EA. REQ'D.)

EQU!PMENT CLASS C O D E _P._

i S AF EIY - RE LATED

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S l ew+ces-A-e 51 7 GASKET PECH Io8'l'%

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Fec n.r - s97 l',,/r, s I s z.c-<

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O APPENDIX B f

" TEST REPORT FOR MODEL BU-7 BULK URANIUM SHIPPING CONTAINER" O

John A.

Zidak 4/25/80 i

l j

LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1

B l

T k."g

/

TEST REPORT FOR MODEL BU '7 BULK URANIUM SHIPPING CONTAINER In accordance with criteria for compliance with CFR49 -

paragraph 173.398 and 10CFR, paragraphs 71.31, 71.32 71.35 and 71.36 BY John A. Zidak Manager Packaging Engineering General Electric Co.

Nuclear Energy Traffic Operation San Jose, California DATE ISSUED April 25, 1980 e

  • ~,

f s

TEST REPORT FOR

/'

MODEL BU-7 BULK URANIUM SHIPPING CONTAINER b' f(

f

1.0 INTRODUCTION

1.1 TEST DESCRIPTION Normal and Hypothetical accident condition tests were conducted on General Electric Model BU-7, Bulk Uranium Shipping Containers in accordance with 10CFR71, " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Cor.ditions." The tests were conducted at the Wilmington Manufacturing Department facility on March 20th and 21st 1980, and April 1st and 2nd 1980.

h The BU-7 Container is intended to be a fissile class I shipping container for shipment of enriched uranium powder.

1.2 PACV. AGING DESCRIPTION J

k Inner containment is a nominal 16-gallon drum closed by a gasketed-bolted lid, centered and supported within an outer 55-gallon drum (3

by a solid insulating media,.and containing two steel pails which

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contain UO2 (See Drawing 112D5231A and Figure 1.)

1. 2.1.

Outer Container A nominal 55-gallon, Uniform Freight Classification Rule 40,18 gauge steel drum with nominal outside dimensions of 22.82" diameter by 36.5" high. Fourl/4" holes near the top of the container are provided for venting and are covered with waterproof tape. The cover is flat 18 gauge steel. The closure ring is 12 gauge steel with 5/8" bolt meeting D0T Specification 17H.

1.2.2.

Inner Container A nominal 16-gallon drum constructed of 18 gauge steel, modified by welding a closure flange to accept a 3/16"'

thick steel lid. The lid is gasketed for resistance to high temperature and attached with twelve 5/16" steel bolts. The inside dimensions are 13.75" diameter by 27" high.

1.2.3.

Insulation The 16-gallon inner containment drum is centrally held hsr within the outer container by, and the space between the

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two drums is completely filled with, solid fire-retardant phenolic foam per USAEC Specification SP-9.

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h.

e l.2.4.

Product Container

{g Two closed 5-gallon containers fabricated of 24 gauge steel, vertically stacked in each BU-7 container.

1.2.5.

Test Weight Each 5-gallon pail contained 45 kgs (99 pounds) of j

natural UO2 powder. Total test weight including weight of the 5-gallon pails is 209 pounds. Gross weight of the BU-7 is between 365 and 375 pounds, depending on variations in weights of BU-7 container populations.

Actual gross weight of the two 5-gallon pails as recorded on the computer weigh sheets was 94.81 kgs (209 pounds) for container S/N K0174, and 95.29 kgs (210 pounds) for container S/N k1878).

2.0 TESTING 2.1 TEST

SUMMARY

The test program consisted of a combination of normal and hypothetical accident condition tests as described in 10CFR71 Appendix A and B.

Three BU-7 containers were utilized in the tests. They were taken from the G.E. inventory of containers at Wilmington and are built to same specifications as all model BU-7 Containers. Serial numbers and tests they were subjected to is as follows:

('

' CONTAINER SERIAL TEST CONDITION WUMBER TESTED WATER SPRAY TEST K0319 DROP TEST 4 FT.

K0319 Normal.Cond.

-i tests PENETRATION TEST K0319 COMPRESSION TEST K0319 30 FEET FREE DROP K0174 K1878 Hypothetical Accident PUNCTURE TEST K0174 K1878 Con tion THERMAL TEST K1878 WATER IMMERSION TEST Kl878 Container No. K0319 was used only for the normal test conditions.

K0174 was drop tested 30 feet impacting on the bottom seam, then puncture tested. Container S/N Kl878 was drop tested 30 feet impacting on the closure ring, then subjected to all remaining hypothetical accident conditions, that were applied sequentially in the order indicated in 10CFR71 Appendix B, to determine their cumulative effect on the package. All tests were monitored by General Electric Fuel Quality Control Engineering, and certified O(-

there completten per test check sheets in the Appendix.

~

m 3

LOADING p

v {f.

2.2.1 Hypothetical Accident Loading

(

Containers K0174 and K1878 were loaded with approximately 45 kilogram:s (99 pounds) of natural U02 powder, in the Fusi Mancfacturing Operation (FMO) powder pack facility, using a corrputer controlled loading and accountability system, see figures ( 2 and 3) the computer punch cards remained with the 5 gallon pails of powder during the tests. (Loading Record Sheets and Request Sheet are in the Appendix).

2.2.2 Normal Condition Loading Container Serial No. K0319 was loaded with lead snot weighing 93 Kg's (205 pounds) gross weight.

2.2.3 Moisture Content Moisture content analysis of the natural uranium powder was made before and after the Hypothetical accident tests.

., 2.3 NORMAL CONDITION TESTS NOT CONDUCTED OI The following normal. conditions tests were not. conducted becau.se their requirements have been satisfied for the following reason:

(

  • Heat:

Temperature of 130*F is within normal operating range for materials of construction.

  • Cold:

Temperature of -40 F is within normal operating range for materials of construction.

  • Reduced Pressure:

Successfully passed this requirement in prior tests. (See GE Packaging Engineering test report dated 2/10/78 included as Appendix 3.)

  • Vibration:

Centainers of this type have withstood years of transport with no occurences of significant damage due to normal vibration.

  • Corner Drop:

Not required since package weight exceeds 110 pounds.

t e

\\

k

I 3.0 TEST RESULTS 3.1 Normal Condition Tests. (container S/N 0319) f 3.1.1 Water Spray Test

(

Container was exposed to a water spray sufficiently heavy to keep all exposed surface except the. bottom wet for a period of 30 minutes. (See Fig. 4).

RESULT There were no signs of water damage to the package.

3.1. 2 Four Foot Drop' Test The container, loaded with 205 pounds of test weight was dropped four feet with the closure ri.ng impacting onto a flat reinforced concrete pad. Test was conducted 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after water spray test.

(See Fig. 5).

4 4

RESULT There was a slight deformation of the outer container closure ring that did not impair its function. No damage to the inner container seal or the 5 gallon pails.

3.1.3 Penetration Test O

(

Container was penetration tested by impacting the f

hemispherical end of a vertical steel cylinder 1-1/4 inches in diameter and weighing 13 pounds and dropped from a height of 40 inches into the top of the container where it is most susceptible to a projectile penetration.

(See Fig. 6).

RESULT There was a slight indentation where the 13 pound bar struck the container. It did not penetrate the package.

3.1.4 Compression Test Weight equal to more than 5 times the weight of the package be applied to top of the containers for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (Minimum weight for BU-7 is 5 times 375 pounds, or 1,875 pounds). Test weight used was 2,440 pounds (.See Fig. 6).

RESULT No damage due to compression loading.

Ci 6

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= -

-.. = -..

3.2 Hypothetical Accident Condition Tests Ta araath tic i accideat coadit$aa * =*=

r coaduct d O(4 in the sequence specified in Appandix B to 10CFR71, to

{

evaluate the ability of the package to with:;tand cumulative damage of the four tests. To establish the drop orientation that covers the most severe damage, two containers (S/N K1878 and K0i74 were selected at random,.then one (k1878 was dropped on its top closure ring and'the other (Serial No. K0174), impacted on the bottom seam as these are the ones most likely to create a breach; impact angle of both tests was approximately 45*.

After completion of the drop test, both containers were puncture tested, then container S/N Kl878 was subjected to the thennal and water immersion tests.

3.2.1 Free Drop The pacirages were raised by.a crane to a 30 foot height at approximately a 45' angle as shown in figure.

l i

7.

The height was determined by a measured, weighted cord hanging from the containers. A quick release mechanism was used to drop the packages, which fell of the containers (See Fig. 8 and 9)g on the corners at approximately a 45' angle, landin i

RESULT Both containers impacted at the pre-determined angles.

(.I Areas at points of impact of both units were without

(

~

N fracture. Beyond this, the only significant damage was a slight opening of the cover where the closure ring of container No. K-1878 was deformed, as shown in Figures 10 thru 14. The bottom corner free fall test of container K0174 caused somewhat more crushing of the container than was experienced in the top drop. There was no evidence of fractures or separation of the containers side from the bottom (See Fig.15 and 16) therefore the container with the slight opening due to the top drop was deemed to have suffered the maxhnum damage.

Past test inspection showed N0 damage to the sealing features of the inner container or to the 5 gallon pail s.

3.3.2 PUNCTURE TEST Containers K-1878 and K-0174 were free dropped through a distance of 40 inches, striking the top end of a vertical steel bar mounted on a reinforced concrete pad. The bar was fabricated per the requirements of 10CFR71, Appendix B (See Fig.17).

A vertical drop with the container impacting on the 18 OL gauge cover near the outer edge was considered the most vulnerable orientation to puncture.

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+,----,+--m--_

,y-----<-%-i--wr,-,-,yw<-,w--=-m-w------_

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3.3.2 PUNCTURE TEST (cont.)

m RESULT

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Both packages were slightly' indented about 1/4 inch, there was no puncture of either container.

(See Figures 18 and 19).

=

3.2.3 THERMAL TEST A Thermal Test of container No. K-1878 followed the 30 foo.t free drop and puncture tests. The thermal test conducted required exposure to an environment of 1475* minimum for a period of 30 minetes. Since an actual gasoline fire with open flames proddes the most realistic means of satisfying the requirements of 10CFR70 thennal test, this method was chosen for the BU-7 test.

Test set up as shown in Fig. 20 was used. The gasoline and' water supplies were. located 100 feet from the fire pan.

A thermocouple mounted on the closure ring adjacent to the slight opening of the container lid was monitored using a Honeywell Model R7353A Dial-0-Troll, Serial No. 7812-3849, which was calibrated using a West millivolt pot that has traceability to the National Bureau of Standards.

l The eight foot square fire kit with container mounted 3 feet O<-

hove the surrace iiowea~ror paroximateir 2 reet or rie=es A.

around all sides of the container.,By using the open gasoline L

fire', the emissivity and absorbtion coefficients were in accordance with those specified in 10CFR71. Appendix B.

3.2.3.1 Test Procedure Approximately 200 gallons of water were fed into the pit resulting in a water level of 5 inches.

Approximately 50 gallons of gasoline were then fed into the steel fire pit to form a layer of fuel about one inch deep on top of the water surface.

I After ignition, (See Fig. 21) the fuel and water supplies were turned on and manually controlled to one gallon per minute of water and 5.8 GPM of fuel to maintain a fire that completely enveloped the BU-7 Container. Figures 22 thru 31 are random photographs taken during the test. The temperature measured on the surface of the test container increased rapidly to 1475* F. (See Figs. 32 and 33]

and exceeded that throughout the test with a maximum temperature of 2000* F. being reached. The full pd fire test continued for 42 minutes burning 300

{

l gallons of fuel during that period.

I I

o l

O

3.2.3.1 Test Procedure (cont.)

RESULTS n{

Inspection of the inner container after V

all the tests showed no damage to the

(

inner container, its sealing features or to the 5 gallon pails that would yield either of them ineffective. The paint was slightly blistered in a small area at the

' top and of the inner container, but no indication of this~ on either of the 5 gallon pails containing UO2 Powder.

3.2.4 Water Imersion Test After the fire test, container No. K-1878 was allowed to cool down for the prescribed period of time, and then placed in the water immersion tank (See Fig. 34) under 31/2 feet of water. One hundred and twenty pounds of weights were attached to the unit to insure that it would sink; it remained submerged j

for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

RESULTS Following immersion as described, container No. K-1878 was opened and inspected. The inner contafner was dry, the silicone rubber gasket was not damaged, and analysis of the

(

UO2 powder showed there was no significant increase in the

(

i moisture content.

N 3.2.5 Post Test Inspection l

Upon completion of the four hypothetical accident condition tests, conducted the sequence prescribed in 10CFR71 container Serial No. Kl878_ was opened and inspected. As prevIously mentioned, there was no damage to the inner containment l

sealing features; the computer weight cards were with the 5 gallon pails; they were not wet and there was no moisture in t

the inner container.

(See Figures 35 thru 38). The top insulation disc was badly charred (See Fig. 39) ind the out-

[

side of the bolted cover had some blistered paint, but there was no structural damage, breach of containment or loss of shielding. Post Test condition of all three containers tested is shown on Figure 40.

I 3.3 Acceptance Criteria Acceptance Criteria for meeting the requirements of 10CFR71( paragraphs 71.35 and 71.36 was as follows No water intrusion to the contents.

C(

No rupture of the product containers or inner container.

No damage to the inner containment sealing features that would yield them ineffective.

-W

3.3 Acceptance Criteria (cont.)

No significant deformation to the outer container that would

(

affect criticality safety consideraticas.

3.4 Conclusion All tests required by 10CFR71, have been conducted, witnessed by Quality Control Engineering and have passed the acceptance criteria.

Test completion check sheets and compliance certificates are included in the Appendix.

0 4

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OL 5

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5/16" ST. BOLTS (QUANTITY OF 12)

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3/16" THK. STL. LID PHEfl0LIC FOAM INSULATION

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FIRE RET. FO.V. PER USAEC n

RESISTANCE.

LT-SPEC. SP 9.5 LB/CU.FT.

A 16 GAL 18 GA STL. DRUM.

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L. 5 ML STEEL PAIL 2 PAILS PER DRUM C0tlTAIN 002 COVER - FLAT 18 GA. STL.

55 ML 18 GA. STL. DRUM CLOSURE RING 22.82" DIA. X 36.5" HIGH.

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12 GA. STL llITH 5/8 BOLTS MEETIflG DOT SPEC.17H FIGURE 1 BU-7 CONTAINER

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1.

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WEIGHTING UO2 POWDER 3.

LOADING 5 GAL. PAILS INTO BU-7 4.

NORMAL CONDITION WATER SPRAY TEST 5.

NORMAL CONDITION 4 FOOT DROP TEST 6.

NORMAL CONDITION PENETRATION AND COMPRESSION TESTS 7.

30 FOOT DROP TEST 8.

CONTAINER NO. K0174 IMPACTING ON THE BOTTOM CORNER 9.

CONTAINER NO. K1878 IMPACTING ON THE CLOSURE RING 10.

SERIAL NO. K-1878 AFTER IMPACT 11.

SERIAL NO. K-1878 AFTER IMPACT 12.

SERIAL NO. K-1878 AFTER IMPACT 13.

SERIAL NO. K-1878 AFTER IMPACT 14.

SERIAL NO. K-1878 AFTER IMPACT 15.

CONTAINER NO. K0174 AFTER 30 FOOT DROP 16.

CONTAINER NO. K0174 AFTER 30 FOOT DROP 17.

CONTAINERS K-1878 AND K-0174 DURING PUNCTURE TEST 18.

CONTAINER NO. K-0174 AFTER PUNCTURE TEST 19.

CONTAINERS NO. K-1878 AFTER PUNCTURE TEST 20.

THERMAL TEST SETUP

(

21.

IGNITION OF FIRE TEST 22.

THERMAL TEST 23.

THERMAL TEST 24.

THERMAL TEST 25.

THERMA'. TEST

~

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THERMAL TEST 27.

THERMAL TEST 28.

THERMAL TEST 29.

THERMAL TEST 30.

THERMAL TEST 31.

THERMAL TEST 32.

HONEYWELL DIAL-0 TROLL SHOWING TEMPERATURE READING DURING THERMAL 33.

HONEYWELL DIAL-0 TROLL SHOWING TEMPERATURE READING DURING THERMAL 34.

WATER IMMERSION TEST 35.

POST TEST INSPECTION 36.

POST TEST INSPECTION O(-

37.

POST TEST INSPECTION 38.

POST TEST INSPECTION h

39.

CHARRED INSULATION DISC 40.

CONTAINEFS AFTER COMPLETION C

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par,E 1 of 3 Oc AeeenDix 1 COMPLIANCE The test referenced in Paragraph 5 have been conducted and satisfactorily meet the acceptance criteria of the test plan.

Container Drawing No. 128ns231 Container Serial No.

K1878 Date Tested 3/20/80. 3/21/80, 4/1/80 and 4/2/80 Oc M,

Y-2-70 Packaging Engineer v

@/F4#

Fuel Quality Control Engineering f

V[2t[8-Licensing & Compliance Audits i

f /,/pd Traffic & Material Distribution W

i I

PAGE 2 of 3

{

APPENDIX 1 COMPLIANCE l

The test referenced in Paragraph 5 have been conducted and satisfactorily meet the acceptance criteria of the test plan.

Container Drawing No. 128D5231 Container Serial No.

K 0174 Date Tested 3/20/80 and 3/21/80 Packaging Engineer 8

K 2.-Pa a

Fuel Quality Control Engineering M M-/DIO Licensing & Compliance Audits t/,1/

Traffic & Material Distribution f/

d

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r OL i

par-E 3 of 3 Oc APeENotx 1 COMPLIANCE The test referenced in Paragraph 5 have been conducted and satisfactorily meet the acceptance criteria of the test plan.

Container Drawing No.

128D5231 Container Serial No.

K 0319 Date Tested April 1, 1980 O(

Y-2.40 Packaging Engineer a

//-/(/-70 Fuel Quality Control Engineering e

Y

/

Licensing & Compliance Audits

/

'777 M

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t Ot

=

PAGE 1 of 3 APPENDIX 2 j

(

TEST CHECK SHEETS Container Drawing No.

/ N 8 8 f23/

Container Serial No.

K /T 78 s

Date Pre Test Visual Inspection

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per Paragraph 5.1 fosporoor#

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Drop Test Penetration Test Compression Test 30 Feet Free Drop i

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Thennal Test

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l Fuel Quality Control Engineering

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PAGE 2 of 3 rxQ{

APPENDIX 2 TEST CHECK SHEETS Container Drawing No. /jE O 5'23/

Container Serial No. KO/7Y Date Pre 'est Visual Inspection per Paragraph 5.1 M G[ta/ro fs2.R8P oot #

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OL

PAGE 3 of 3 i

Oc Aeeenoix 2 TEST CHECK SHEETS Container Drawing No. /#38f2 J/

Container Serial No. kO319 Date Pre Test Visual Inspection per Paragraph 5.1 (aoS#Geod

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Request N).

[O-79 NSR Area No.

(~'s PROCESS AND EQUIPMENT / FACILITIES CHANGE REQUEST U

questor Initiating Component _ M S Installation Responsibility

. Equipment Location C M MO POWDER PACK AREA AND TEST PAD WEST Or FMUA.

Purpose of Change T1.5T LOADED BU-/ AND BU-b COHTAINt.R5 YOR Mt,LIC1.Nbt.

BY G NRC.

NATURAL..

Description of Change STAHDARD PACK b b-tuALLUN l' AIL 5 WIT 11 4D KUb UU

'V' 9

EUA]

LOAD AND SEAL IN { BU-7 AND 1 BU-5 CONTAINERS.

TEST CONTAINERS TO NRC TEST STANDARDS ATTACHED (30-FOOT DROP, 40-INCH, FIRE, ETC.)

Scheduled Project Completion Preliminary NSE Review N dB

.glu/8 Final NSE Review Needed By 3/18/80 Requestor's Signature /Date h 7

4/ly/8 kQ

    • ' L(AIM Nuclear Safety Engineering 3f/

6 1.

Type Analysis Required: *Cri ticality O

  • R diological O

None 2.

New/ Updated NSE Method Sheet Required: Crit.

d Radio. /\\/O None 3.

Anticipated Availability of NSE h q Shee gLf Required

.3

/ o it 4.

Signatures:lCrit a ityhSafe I

1

/J M c io logical Safet

  1. 1---

Remarks:

i-W o r-110 0 <.hJ Llra- -

A 5.

t

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Fuel Quality Control Engineering Np C

1.

Is New/ Changed Quality Instruction Required? Yes No If Yes, Antic'ipated Availability of Instruction 2.

Responsible Fuel Quality Control Engineer 3.

Approval:

Mgr., Fuel Quality Control Engineering Fuei Process Technology //p s.

1.

Is New/ Changed Instruction Required? Yes No If Yes, Anticipated Availab'lity of Instruction I

2.

Responsible FPT Engineer t

3.

Approval: Responsible FPT, Unit flanager SHOP hv rs 4

~-

Subsection Manager Approval b^

'N l

Area Manager 1.

Priority Assignment.For Nuclear Safety Review 2.

Area Manager Approval b' e:c,p Nuclear Safety Engineering Date Approved Request Receihd Date Completed N

Ot. Meneser Accentence of Completed ero3ect Dete

  • Documented information from requestor required per P/P 40-5 Appx. A APPEN9fX 4 NF-1-014 (11pf)

URANIUM POWDER LOA. DING REQUEST

- l' a.

  • 2 APPENDIX 3 Page 1

$0VlAh GENERALQ ELECTRIC

-pC'k RELATIONS AND IfrILITIES OPERATION San Jose, California February 10, 1978 TEST REPORT BU-5 AND BU-7 CONTAINER PRESSURE TEST A.

OBJECTn'E The objective of this test was to verify the integrity of the BU-5

and BU-7 containers for the New Japanese Container Regulations, f]{

The procedures were presented to the Japanese and approved by them.

B.

SibNARY i

The following tests were performed on one BU-5 and one BU-7 con-tainer on Febniary 6,1978 thru February 10, 1978.

2 1.

Both containers were tested under water to 1.50 Kg per 01 i

for eight hours. This was done by submerging them in the test l

tank in Building G, to a depth of 50 feet above the containers.

l 2.

The containers were then pressurized internally and checked for l

1eakage at four increments:

?

a.)

.75 Kg/G1' for tlirea hours b.)

1.0 Kg/01 f r three hours 2

t 2

l c.)

1.25 Kg/01 for three hours l

l d.)

1.5 Kg/Or for three hours i

I x) --

1-

GENER AL $ ELECTRIC

  • (d (

TEST REPORT 2-10-78 Page 2 C.

TEST EQUIPMENT The following equipment was used in the test:

1.

60 feet deep test tank 2.

BU-5 container S/N B-7522 3.

BU-7 container S/N K-0397 4.

Permagage # 175 0 to 60 psi pressure gage, regulator and valves as shown in Figure 1.

D.

CALIBRATION The pressure gage was calibrated prior to testing. Calibration record and curve (Figure 2) are included in this report. Calibra-(a (

)

tion was made with equipment traceable to the National Bureau of Standards conformance.

E.

TEST RESULTS 1.

Water Imersion Test There was no water leakage in the inner containers after eight hours of submergence in 50 feet of water.

2.

Air Pressurization Tests There was no leakage of air from the inner containers when pressurized as shown in Figure 1 and held at pressure incre-ments of.75,1.0,1.25 and 1.50 Kg per square centimeter for periods of three hours for each pressure increment.

CCNCLUSION The BU-5 and BU-7 containers passed all the pressure test require-ments for the New Japanese Container Regulations.

In fact, the tests exceeded their requirements. The water submergence test was for eight hours rather than three, and the BU-7 container was tested at Ot t

O

GENERAL $ ELECTRIC Oc rest ne a r 2-10-78 r

Page 3 2

1.25 gm/cm for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />. There was no leakage in either case.

1 i

/,

Certified By:

Ge7

/

J. A. Zidak W. S. Cdwan, Manager Packaging Engineer Packaging Engineering M/C 512 M/C 512 JA2/da e

.Of l

l g

Q O

D 1

R PRESSIRE-

/

GAGE

--m l

X.

90 PSIG

'C AIR SilPPLY 1

Siur OFF val.VE i

REGULNIDR U

'I -

BLEED VALVE i

BU-7 INNER m.m QWTAINER I

iT I

h

)

s BU-7 GITER g7 CO.VTAINER s

REF (s

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-i j

i INSULATION l

4 4

N/

FIQlRE 1 TEST SETUP

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.a w.

r CON TAINERS.'BU S S/N B-7522 O-8U 7 S/N KO397

'd k T E ST '.. DA'TA'-

~

t DATE TI M E '. PRESSURE PERIOD TEST RESULT I,

9 7 fr K.soAm so 4-w4ree

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1. SERVICDaa, aI-s i-7d 8Y OATE (0

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_. s;xcu. nyv. 2:' -

Mall!TEl'Al'CE RECORD TECHNOLOGY & DEVELOPMENT METROLOGY & CALIBRATION LABOR ATORIES

3. REVIEWED BY DATE
4. F AMILY CODE
5. MF R CODE
6. MODE UDWG NO.
18. RACK /SYS IC NO.

bESSA$LE k

hCMA6AG6 bd b

7. IC NO.
8. ST ATUS
9. PREVIOUS CYCLE N/A La usE 9/A
10. MOS E )PSE D % e. C,aG, 11.
19. OPE R ATION NA
12. D ATE SE RVICE D
13. D ATE OUE
14. CAL HRS 15.MAINT HRS 16.OTHER HRS 17,
20. LOCATION b 'YR)h FW bb 'YRUD 1.O 0.0 0.0 Tmtet 9 FW
21. M ANUF ACTU RE R
22. INSTRUMENT NAME
23. SE RI A L NO.

MA ssi4A.tLTok.N T'fE46u 9 e GrAuGE 84 f EE

24. SPE CIF IC AT SONS
25. PROCEDURE USED I. L d M - 1 ?_ - 00 5' W MFG
26. D AT A ISSUE D F O OTHER (DESCR18El-O YES
27. REPORT NO.

SJ O

28. TYPE OF SERVICE
29. R E C EIV E D 30.LAST SERVICEO
33. LABOR ATORY ENVIRONMENT

!YR FW D !YR

[CALIB R ATION CE RTIFICATION FW TEMPE R ATURE

'C

31. ASSIGNED RECAL L INTERV AL O PREVENTIVE MAINTENANCE hi RELATIVE HUMIDITY

'~

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34. OPE R ATION ALP M

O OuT MES O NO O(r l

CALIBR ATION INSTRUMENTATION USED MFR MODEL DR AWING NEXT OUE MFA MODEL DR AWING NEXTDUE I

O.

IC NO.

CODE NUMBER FOR CAL CODE NUMBER FOR CAL ME eMM-83 24 60063 5 -s-76 s

1 i

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MFR Mats 9 ALLToted MODEL ORAWING NO.

SE R4 AL NO.

Il4MAdA&E 176 Oh! E6 l

i FUNCTION AND/OR Call 0R ATION NOMINAL RANGE TESTED TOLERANCES VALUE 1NITI AL RUN T L(/

FINAERUN 6-60 PSIGr SrAudAno cAuce TE6T o

e o

s

4. 5 6

l0 9.35 lo ts 14.0 5' 15 20 19.0 5 Do

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'l9.60 50 60

59. G0 Go Oc t

O G

APPENDIX C

" CRITICALITY SAFETY ANALYSIS OF POWDER" BU-7 SHIPPING CONTAINER FOR 00 2 O

W. C. Peters 3/6/80 LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1

i

Prepared:

3/6/80 CRITICALITY $AFETY ANALYSIS OF gC g

Sh#

BU-7 SHIPPING CONTAINER FOR UO POWDER 2

1.0 INTRODUCTION

Model BU-7 shipping containers are used by the General Electric Company for the transportation of low-enriched unirradiated uranium oxide powder.

The BU-7 container is a fissile Class I package which is currently licensed for a maximum U-235 enrichment of 4.0% with no more than two five -

gallon containers, each limited to no more than one safe batch of UO, powder.

In addition, it is required that the H/U ratio in the fuel in each five-gallon container must be no more than 0.45.

The purpose of the present analysis is to extend the Fissile Class I certification for the BU-7 to include the following:

1.1 Increased water moderation by increasing the fuel H/U limit from 0.45 to 1.577.

1.2 Replacement of the safe batch limit with a limit of 35 Kg 00 per five-gallon container.

The total BU-7 9

O3 container mass limit is still 89 Kg.

k[/ k 1

1.3 Reduced levels of insulating media (phenolic resin) composition and densities requiring that at least 60%

by weight of each of the constituents of the full density phenolic resin must be present.

1.4 The presence of carbon in the UO fuel provided that the 2

C/U ratio in the UO fuel mixture does not exceed 1.262.

2 All other limits and requirements for the BU-7 container are unchanged.

2.0 ANALYSIS SCOPE The present analysis has been undertaken to demonstrate that the GE Model BU-7 shipping container meets the applicable criticality safety standards for Fissile Class I shipping packages as required by Part 71, Title 10, of the Code of Federal Regulations.

2.1 BU-7 Container Specifications This analysis is valid for the following BU-7 container

(

specifications.

p N

\\

m

('

-v i.

2.1.1 Outer Container g)mp' 18-gauge, 55 gallon steel drum, or similar drums larger in dimensions or with thicker steel walls (reference Drawing 128D5231).

Drums with smaller dimensions or with steel walls which are ' thinner than 18 gauge are'not covered by this analysis.

2.1.2 Insulation Phenolic resin containing the amounts of hydrogen, boron, carbon, nitrogen and chlorine and minimum

~

resin density as shown in - Table 4.1.

2.1.3 Inner Container 16-gallon, 18-gauge steel drum with an inner diameter of 13.75

  • 0.25 inches and an inner height of 27.75
  • 0.25-inches.

This container must have a leak-proof seal and cover as described in Drawing 128D5231.

2.1.4 Contents

()r)

Two five-gallon steel containers or three Ae three-gallon steel containers with an inner g)./

diameter no greater than 11.25 inches and with a total stacked height of no more than'27.64 inches.

The steel containers must be at.least 0.0206 inches thick.

Plastic bags wrapped around the five-gallon container or used as a liner inside of the container are permitted.

2.1.5 Fuel Up to 70 Kg of UO powder per BU-7 container at 3

a U-235 enrichment of no more than 4.0%.

Each five-gallon product container may hold no more The UO powder may be mixed than 35 Kg of UO7

-with water or hydrogen-car $on additions subject to the requirements that the fuel-additive mixture may not exceed:

.1 an H/U ratio of 1.577 l

l

.2 a C/U ratio of 1.262

( )['

In addition, the bulk density of the U0, powder may not exceed 4.5 gm/cc.

,M.

y-r

-,-.---.,,--,r

,--,-%-..,,--------v-.e-+-..-.v,.---.%..

- -.... - - - -,. ~. - -.

-m

,w.

2.2 Fissile Class I Criteria f~s t

/gs I

To demonstrate that the BU-7 shipping container as

~%sd (

described in Section 2.1 meets the criticality safety standards for Fissile Class I packages as defined in Part 71, Title 10, of the' Code of Federal Regulations, j

the following calculations have been performed.

2.2.1 Normal Case The'K.

of an infinite array of BU-7 containers has been calculated for three cases:- full density phenolic resin, 80% of full density phenolic resin and 60% of full density phenolic resin.

2.2.2 Accident Case The K gg of a 256 unit array has been calculated e

for the conditions of optimum interspersed modera-tion.and full reflection of the array.

This analysis was performed for BU-7 containers limited to 2 x 35 = 70 Kg of UO2 as well as for the case of the two product (five gallon) containers filled with powder at a U02 density of 4.5 gm/cc (202 Kg UO2 total).

p 2.2.3 Evaluation of Carbon

()

The most reactive cases in 2.2.1 and 2.2.2 (with 35 Kg UO /five-gall n container limit) were 2

reanalyzed for UO -H O mixtures to which an addi-2 2

tional amount of carbon was added.

The atom density of the carbon was taken to be 80%'of the atom density of hydrogen in the mixture to simulate mixtures of U0,10,000 ppm by weight of 2

water and 40,000 ppm by weight of H-C additives.

l 2.2.4 Accidents Involving a Single BU-7 Container To demonstrate the safety of a single BU-7 con-L tainer under extraordinary upset conditions, two five-gallon product containers have been analyzed

~

for optimum moderation and full reflection by water.

2.2.5 Concrete Reflection The impact of concrete reflection of the most reactive 256 unit array as described in Section 2.2.2 has been analyzed.

l b

3-

~

1 i

.m.,_,__,

.l

?

'~

2.2.6 Code validation

%m#

fTo demonstrate the validity of the computational codes used in this analysis, validation calcula-i tions have been made for the following cases:

.1 Comparison between codes for: -

e Normal case (K. ) BU-7 container e

256 unit array of BU-7 containers with optimum interspersed moderation'and full reflection by water e

A single BU-7 container with 0.075 gm/cc of interspersed water i

e Two five-gallon containers in a vertical j

column with optimally moderated UO and 2

with full reflection by water

.2 Calculation of the K ggs of the low enriched e

U038 low moderated benchark critical experi-ments described in Reference 7.

l-2.3 Analytical Methods (I

i.

The criticality analysis of the BU-7 container has been performed with the General Electric' Company MERIT and I'

GEMER codes and with the KENO IV Monte Carlo Code.. MERIT and GEMER are Monte Carlo neutron transport codes which employ 190 broad group cross section sets generated from ENDF/B-IV and which treat resonance absorption by explicit-ly modelling the resonance parameters on a discrete energy basis.

The difference between MERIT and GEMER is that the

'former has a geomet'ry package especially designed to model HBWR lattices while the latter has an enhanced version of the regular and generalized geometry packages in the KE'NO IV code.

l The KENO.IV Monte Carlo' Code was used in this analysis with 16 group modified Hansen and Roach cross section sets (Reference 5).

4 i

3.0

SUMMARY

AND CONCLUSIONS l

The results of this analysis have demonstrated that the GE Model BU-7 shipping container meets the criticality safety requirements i

of 10 CFR 71 for a Fissile Class I package for the transporta-l tion subject to the conditions specified in Section 2.1 of this

{]}.

analysis.

'In summary, these results are:

V' -

4-3.1 Normal Case

[

The K=

calculated with KENO IV for the normal case BU-7 container is 0.903 + 0.003.

3.2 Accident Case The K,ff calculated with KENO IV for the 256 unit array of BU-7 containers with the most reactive degree of interspersed moderation and with full reflection by water is 0.955 1 0.005 for 202 Kg UO per BU-7 container 2

and 0.750 1 0.005 for 70 Kg UO2 per BU-7 container 3.3 Presence of Carbon The presence of carbon in amounts which, result in a C/U ratio in the fuel of no more than 1.262 increases the K gfeggiy, of the 30-7 container by less than 1.25%.

e Applying this to the values in 3.2 and 3.1 above for BU-7 containers limited to not more than 70 Kg U0 per 7

i; container does not result in critically unsafe reactivities for these cases.

%/(

3.4 Two Five-Gallon- (Product) Containers calculated with KENO IV of two closely packed TheK,gflonproductcontainerswithoptimummoderation five-ga and full reflection by water is K,ff = 0.968 1 0.006 if the U0 contents of.the 2

containers are not restricted (approximately 65 Kg U02 per container) i 1

K,ff = 0.909 1 0.005 if the UO contents of each of the containers are restricted to 35 Kg.

t 3.5 Concrete Reflection Concrete reflection on all six sides of the 256 unit accident array of BU-7 containers (limited to 70 Kg UO 2 per container) results in a K f 0.789 1 0.004, an increase of 5.2% overthewakfer reflected system.

e k_

sd,

N

~

3.6 Code Validation

/"Tk l(.

The validation calculations performed in this analysis

,b,p have demonstrated that 3.6.1 For infinite or finite arrays of BU-7 containers, MERIT'and GEMER predict neutron multiplication factors from 2 to 5% lower than the values calcu-lated by KENO IV.

MERIT and GEMER results are in excellent agreement.

The discrepancy with KENO is due in part to the cross-section sets used in the KENO calculations.

The cross-section sets were determine based only upon the moderation in the fuel mixture.

3.6.2 For a single BU-7 container, MERIT, GEMER and KENO IV all agree with 0.4%.

3.6.3 Likewise, MERIT, GEMER and KENO IV are in excellent agreement for the case of two closely-packed opti-mally moderat2d fully reflected five-gallon con-tainers (with U0 contents of 65.8 Kg or more per 2

container).

3.6.4 For the Rocky Flats low enriched U 0 low moderated 3g benchuarks, the KENO IV calculated Kefg averaged

( )g over the 10 cases is 0.997 + 0.002 and the GEMER

\\

value is 1.003 + 0.003.(for 7 cases)

M

~

4.0 PACKAGE DESCRIPTION BU-7 shipping conta'iners are 55-gallon drums ionstructed of 18 gauge steel which contain an inner 16-gallon, 18 gauge steel drum enclosed in and supported by a phenolic resin liner.

Specifications of the BU-7 shipping container are given in Figure 4.1, Drawing 128D5231, Figure 4. 2 (ANSI MN 2.2-1974, UFC-Rule 40 55-gallon drum) and Figure 4.3 (. NSI MH 2. 5-1974, DOT specification 17H 55 gallon A

drum), and include:

55 gallon drum dimensions:

Diameter 22 inches Height 33 5/8 inches Thickness 0.0428 inches Material Carbon steel 16 gallon drun. inner dimensions:

Diameter 13 15/16 inches Height 27 inches Thickness 0.0428 inches Material Carbon Steel 5 and 3 gallon product container:

Diameter 11 1/4 inches

( )(.

Inner Dimensions Height 13.5 inches (5 gallon) 7.5 inches (3 gallon)

Thickness 0.0208 inches Material Carbon Steel M

M h%

FIGURE 4-BU.; gnIPPING CONTAINER

. ~ -

i }2

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ANSI MH2.2-1974 FIGURE 4.2 - UFC-RULE 40 55-GALLON DRUM O(

23U

=

16 7

7 I.

H 7..

g 2317 32 23h-

- - -Q. A...-

,,v..

s s

- g-I l

.E Il 8 f

l 1

'(

)

l_

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34 4

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(

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l

7

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i 2

3-MIN (SEE NOTE 2)

- M AX j

4

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l I. _. _.._

lI

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b 4

NOTLS:

h].

41) All dimeniions ase in in.hn.

\\JN i2) Minunus.:coniesity us liust.im head is 31s in.h

-B-

.~

ANSI MH2.51974 FIGURE 4.3 - DOT SPECIFICATION 17H 55-GALLON DRUM

(\\

h 23 IG 7

(~ 8 9

P m

.i 2

2 23

=

2 23h

=

^^ '^

"%~iiW;~;Y:~ ~tO g

~'

q 3

o

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Oc

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34 -8 II.

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3 3-MIN 8

(SEE NOTE 21 3 max ra c

n 9

i La4 NOTLS:

OL ill lhese dinienseuns are ai pis.bte to tuth the sap anJ bottom he4Js. Minimum constut) of ea li tic 4J si 1 a in t11 Alldienentions are la in.fici.

V

- 8A -

_ j

The 16 gallon. drum has been modified by the welded attach-('T -

ment of a closure flange to accept a 3/16 inch thick steel cover whida s / (['

is gasketed for resistance to high temperature and is attached

\\sE by twelve 5/16-inch steel bolts.

This gasket has been demon-strated to survive the drop, flame, flood and impact tests required by 10 CFR 71 and insures that the five gallon product pails con-tained within the 16 gallon drum do not come into contact with additional moderating materials (for example, water) as a result of the postulated accident conditions.

Due to the 11.25 inch inner diameter and maximum height of 13.5 inches, a single standard product pail has a volume of no more than 22.5 libes.

This is less than the 29.0 liter. safe volume limit for containers of optimally moderated UO2 powder at en-richments not exceeding 4.0% U-235.

As described in Figure 4.1, the space between the concentric inner 16 gallon and outer 55 gallon drums is completely filled with a solid phenolic resin insulating material.

The chemi-3 cal composition of full density ( 8 + 1 lbs/ft ) phenolic resin is shown in Table 4.1.

Oc s

)

C )( %/

l

D (VV(

TABLE 4.1 CHEMICAL COMPOSITION OF FULL DENSITY PHENOLIC RESIN INSULATION ELENENIAL WEIGIT PEI'. CDC OBCANIC CO! POUNDS-WEIGIT PER CDE Element Full Density Weight Weight Element Per Cent Material Per Cent Hydrogen 4.S Union Carbide Phenolic 65.8 Besin BRL 2760 Boron 3.2 Silicone Surfactant LS30 2.0 Carbon 41.0 Boric Anhydride B-203 8.2 Nitrogen (approx) 0.0 Anhydride Oxalic Acide 8.2 Oxygen 48.6 Freon 113 6.6 luorine (approx) 0.0 Fiberglass Ibving 9.6 g

V Silicone 2.2 011orine 0.5

' Ictal 100.0 100.4 3

Density = 8 + 1 lb/ft Minimm Permissible Density 4.8 lb/ft OL a.

E

. l

({}.0 TECHNICAL CONSIDERATION

\\sI 5.1 Mixtures Densities The mixture atom densities used in this criticality safdty analysis are tabulated in Appendix A.

The 16 group modified Hansen and Roach U-235 and U-238 cross section-sets used in the KENO IV Monte Carlo calcula-tions were taken to be the sets corresponding to min min cr and cr U-235 U-238 with min dF o

g p

as described in Table 5.1 and with no other a satisfying ia*"

a i

e-Thea's are the potential scattering cross section values

/(

(in b arns) corresponding to U-235 and U-238 cross-section g/

sets (Reference 4).

11

EII 5.1 KENO IV RESWANCE ABSORPTICN CROSS SECTICN CAIfUIATICNS v

i a,

{

N 'i g

No where Ng = atom density of isotope i in mixture "i = potential scattering cross section for material i as tabulated below

% = atom density of isotope whose effective resonance absorption cross section is being computed Material / Isotope "i (barns)

Hydrogen 20.0 Carbon 4.7 Oxygen 3.8

. v(

U-235 15.0

j U-238 10.7 Water 43.8 i

S D-v 12 -

i

5.1.1 Moderation of Fuel Mixture n

Jk As noted in Section 4.0, in leakage of water into

\\*/

the 16 gallon inner drum (and consequently into the five or three gallon product containers) does not occur under the postulated accident conditions (drop, flame, flood or imp.act).

The level of modera-tion in the five or three gallon product containers will therefore not change when the BU-7 containers are subject to the postulated accident conditions.

The maximum ncrmal levels of water'or hydrogeneous moderation in the UO2 p wder are:

.1 from 0.3 to 1.0% by. weight of moisture (H O) 2

.2 for certain blends of UO powder up to 4.0%

3 by weight of hydrogen-carbon materials for which e

the hydrogen content is less than the equivalent.of 4.0 weight per cent of water e

the ratio of atoms of hydrogen to atoms of carbon in the additive is no less than one.

(}{

5.1.2 Fuel Mixture Atom densities of the fuel mixture's for 4.0% en-l riched 002 powder and water used in the present analysis are tabulated in Appendix A.

These mixture densities were computed in one of two ways:

.1 Mixtures with 50,000 ppm of water or its equivalent For systems of UO2 powder and water in which the water content is restricted to low volumes, fuel-water mixtures may be determined by taking the maximum 00 density and water density 2

possible.

F,or UO powder, the maximum density 3

possible is less than 4.5 gm/cc unless mechanical presses (etc.) have been used to compress the powder.

Mixtures of UO and 50,000 ppm H O are 2

2 then specified by fUO2 = 4.5 0

fHO=

2

  • 0.05 = 0.23684 gm/cc 2

. 9 5)

{

carbon = 0.80

  • gg (atom densities)

N I

s_e 1 !

- ~

This last condition simulates a mixture of 10,000 r-ppm H 0 and 40,000 ppm of hydrogen-carbon additive

's)3 ([

in whkch the weight fraction of hydrogen is the same

%it as that in water (11.19%) and for which the ratio of hydrogen atoms to carbon atoms (in the additive) is' no less than one.

.2 UO

- H O Mixtures Occupying Minimum Theoretical Volumes 2 Given a weight fraction of water in the mixture, the densities of UO and water are specified by 2

/

3 (UO l

2 HO 2

[1-WFHOb 2

l+

WF r

k 10.96

)

HO 2

and U0

( )(

fHO=1-2 2

h/

10.96 l

As in 5.3.1, maximum permissible carbon content is determined by NC = 0.80

  • NH O

i I

i l

' v 4

14 -

=

l

, {}

5.2 BU-7 Geometry model

%=/

The geometry model used in this analysis is illustrated in Figure 5.1 and the KENO IV and GEMER geometry input is tabulated in Tables 5.2 thru 5.4.

For the normal case, the Figure 5.1 model was spacially reflected on all six sides (J = 0) to simulate an infinite array.

Calculations were then performed for the phenolic resin insulation mixtures in Regions 6 and 8 or for varying amounts of interspersed water in Regions 6, 7, 8, 10 and 12.

Calculations were also performed with interspersed water in Region 4 as well in order to evaluate the impact of close-packed moderation about the five or three gallon product pails.

The three-

-gallon product pails were not explicitly modeled since it is readily evident that they are less reactive than the five-gallon containers (less U02, m re carbon steel and smaller volumes).

4 For the accident analysis, a 256 unit array was defined with the same Table 5.2 - 5.4 geometry but with eight containers in the X and Y directions and four contaiaers in the Z direction.

The 8 x 8 x 4 configuration gives the array d

with the minimum geometrical buckling and is therefore the most reactive case from an array geometry standpoint.

()(

h/

i a

4 4

1 C:)t

-s

FIGURE.5.1: KENO /GEMER GEOMETRY MODEL FOR BU-7. CONTAINER Z

C,) (

h N

y,q w

!.3eg P4-l.

se.,

I" belf rsed M r

. tat -

,3753 U'dfI"N<SpalW. der

.s.i.

es c s is c,

Ca<ba Shel

?.oS

  • ll.%

P z

l P

i h

t A

c

+

Ns0 v,

I,.

9 5

1 A

5 V

i.

p e

e D.C S o

(

,y e

i e

3 I

i c

1 e

0s.

=

1

- e t

u o

  • '.05 [

I y

l w

a t

et t

i UO t

t Nuo

.545

$. i o es

\\

5,"1067 II Il l

ll 11 il 11 2.9291N ll 2.uw/--

ii is i

i g

__gi_

__ii--_i

  • N l

ll Il I

I, OL n

v i

o,oo l'f.asa s is.39 11.7o

17. Set 23.475 25575 2 3. c.t y i.

L hil 0.~,_..

l TABLE 5.2: BU-7 CONTAINER INFINITE ARRAY GEOMETRY MODEL (KENO /GEMER INPUT)

Radius

+ Height

~

or or Region Geometry Type Material

+X

+Y

+Z 1

Cylinder Carbon Steel 14.2875

+

0.05 2

Cylinder UO -H O Fuel Mixture 14.2875

+ 35.05 2

2 3

Cylinder Carbon Steel 14.34

+ 35.1 4

Cylinder Void 17.70

+ 35.1 5

Cylinder Carbon Steel 17.808 35.5763

- 35.2087' 6

Cylinder Phenolic Resin or 23.495 35.5763

- 42.8287 Interspersed Water 7

Cylinder Void or 23.495 36.688

- 42.8287 Interspersed Water 8

Cylinder Phenolic Resin or 28.575 44.308

- 42.8287' Interspersed Water 9

Cylinder Carbon Steel 28.575 44.4167

- 42.9374 10 Cylinder Void or 28.575 4523692

- 44.8424

(-)

Interspersed Water

l

.1 Cylinder Carbon Steel 28.684 45.3692

- 44.8424 12 Cuboid Void or

+28.684

+ 28.684 45.3692 Interspersed Water

- 44.8424 13 Core void

+28.684

+ 28.684 45.3692

- 44.8424 14 Cuboid Void

+28,684

+ 28.684 45.3692

- 44.8424 l

  • Dimensions in cm

()b ui

[

TABLE 5.3:

GEOMETRY MODEL' MODIFICATIONS FOR 35 KG s

(

UO CALCULATIONS (KENO /GEMER INPUT) 2

' + '

Region Geometry Type Material Radius +

I-Height 1*

Cylinder Carbon Steel 14.2875

+ 0.05 1A Cylinder Void 14.2875 0.05 A

2 Cylinder UO

-HO 14.2875 B

-35.05 2

2 Fuel Mixture 2A Cylinder Void 14.2C75 35.05

-35.05 3

Cylinder Carbon Steel 14.34

+ 35.1 Fuel Mixture Height of+

No.

Fuel in Container A,

B,

(

1 12.128

- 2;.922 12.178 gj 2

20.0

- 15.05 20.05 0.05 35.05 3

35.0 Unchanged

+ Dimensions in cm l

i f

Ot v

TABLE 5.4:

GEOMETRY MODEL MODIFICATIONS FOR 8 x 8 x 4 FINITE ARRAY (KENO /GEMER INPUT)

+

~ ++

+

+

Region Geometry Type Material

-X

-Y

-Z 12*

Cuboid Carbon steel

+

28.684

+ 28.684 45.3692

~

13 Core Void

+ 229.472

+229.472

+180.4232 14 Cuboid Full Density

+ 260.0

+260.0

+212.0 Water (or concrete)

O(

s

  • Unchanged
  • Dimensions in cm h.

s.

s(

FIGURE 5.2 - FIVE-GALLON PRODUCT CONTAINER GEOMETRY MODEL A.

SINGLE CONTAINER (FGC)

ID = 28.575 cm UO IH = 35.0 cm 2

+

OD = 28.680 cm HO OH = 35.1 cm 2

Walls - carbon steel s

B.

TWO FIVE-GALLON CONTAINERS Side-by-side Stacked s{

l' H O reflector l'(min)H O reflector 2

2 top Vi*"

l FGC FGC l

FGC l

/

void side i

view FGC I

O] c FGC FGC FGC I

l' H O reflector l' H O reflecton 2

2 l

l lon-

FIGURE 6.1 - K, for U (4.05) 02 - Carb:n Syctcm g -

n..,..

i i

a.

.i.

.....i...

i

.i l

j 2,.

)

.!. I65..i

..i..i N s' i

i

= _.

.........a.

s.

l 8

.;e

. a..

l...a a.

i.

e f.

l 1

i.

1..

3 j

.i..

s g

i 1

j l..

g t

.I i

t.

i

..s

,4 I

O l

H g

x p

I in 3

i D

g,,

.g.

7 i

~

.I.

,1 e

2

.;. 1 4,,l 9.!

g 3

. l 1 1 g

,--.r.-

. _3...,

_A g.

[

i I

l

........ }....

..?.

I.7 3

i

..1...

.o, I

y g

--J l.

j.

....i l

l 3

...... ~.

4 I

IA l

l 4

l l

I i

t

.i l

. a i

- e

...s...

3..

..4..

4 t

N l

t t

+.

l i

e s*

l f

..a t

e

  • i i

n l

1 x

bs.

l

)

i I

t 8

I I

l.

\\

I i

.I I

...y.

g.

..g.._

o....

m......

- 2 g

e g

.4 4

x 4

4

-19B-

=

Tight reflection of the 256 unit array was modeled by 12-inch t

thick slabs of full density water on all six sides of the array.

For the case of concrete reflection, the 12-inch thick slabs were replaced with 16-inch thick concrete slabs (KENO IV material number 300).

One aspect of the Figure 5.1 geometry model that should be noted is that the dimensions used are conservative as compared to the actual BU-7 container described in Figures 4.1 and 4.2.

This especially applies to the use of the 22.5 inch inner diameter for the maximum size of the 55 gallon drum rather than taking credit for the 23h inch diameter of the drum provided by the two or three corrugations along the length of the container.

This constitutes a reduction by at least 4 % in the diameter and 9% in the volume of the drum and is a significant factor of conservatism in the analysis of the 256 unit accident array.

This reduction of 9% in the volume conservatively simulates the collapsing of the rolling heaps on the lateral surface of the drums under the postulated accident conditions (drop, flame, flooding).

It is advised that the geometry model used in this analysis for the BU-7 container is different from that used in the Reference 3 analysis.

The Figure 5.1 model is more con-

. {

servative than the one previously used.

5.3 Five Gallon Product Container Geometry Model The five gallon product containers have been modeled in this analysis as shown in Figures 5.2.

The ID = 28.575 cm, IH = 35.0 cm dimensions slightly overestimate the true size of a five gallon product container (the value is 22.44 liters as compared.to the true value of less than 22.0 liters), and the model is therefore conservative, especially since the carbon steel walls are modeled as being less than 0.0207 inches thick.

k- -

i

6.0 RESULTS j

6.1 BU-7 Container Analysis Tables 6.1 through 6.5 show the results of the MERIT /

GEMER/ KENO IV calculations for the BU-7 container.

6.1.1 Normal Case TABLE 6.1 NORMAL CASE Kos for BU-7 CONTAINER PERCENT OF FULL DENSITY i #

OF PHENOLIC RESIN GEMER MERIT KENO IV 100 0.758 + 0.004 0.753 1 0.004 0.790 1 0.004 80 0.799 1 0.004 0.804 1 0.003 0.843 1 0.004 60 0.853 1 0.004 0.850 1 0.003 0.903 1 0.003 "with 202 Kgs UO2 per BU-7 container These results show tha't the normal case infinite array of BU-7 containers is critically safe and that the phenolic resin serves as an "overmoderating" influence in that die more resin present the lower than K..

Comparison of MERIT, GEMER and KENO show that MERIT and GEMER are in good agreement but that KENO overpredicts the K s relative to them by from five to six per cent.

l l

l l

l s

e l 1

l l

6.1.2 Accident Case - Optimum Interspersed Water

.1 Infinite Arrays

[

These calculations were performed in order to compare MERIT /GEMER and KENO.

(The MERIT geometry package is unable to model the 256 unit finite array.)

t TABLE 6.2 - K.

FOR BU-7 CONTAINER WITH OPTIMUM INTERSPERSED WATER

  • K.

+o INTERSPERSED WATER (gm/cc)

GEMER MERIT KENO IV 0.000 1.111 + 0.003 1.106 + 0.003 1.163 + 0.003 0.025 1.147 + 0.003 1.147 + 0.003 1.182 + 0.004 0.050 1.117 + 0.003 1.116 + 0.003 1.153 + 0.004 Q)s 1.099 + 0.004 0.075 1.067 + 0.003

~

0.100 1.021 + 0.003 1.046 + 0.003 0.200 0.829 + 0.003 0.848 + 0.004 0.500 0.634 + 0.004 0.-6 4 2 + 0. 00 4 1.000 0.610 + 0.004 0.617 + 0.004 i With 202 Kg UO2 per BU-7 container

  • Interspersed water in Regions 6, 7, 8, 10 and 12 (Table 5.2)

')f TABLE 6.3 - K.

FOR BU-7 CONTAINER WITH CLOSE t

~

A PACKED OPTIMUM INTERSPERSED WATER KENO IV Interspersed Water (gm/cc) 1

=

0.000 1.163 1 0.004 0.025 1.185 1 0.003 0,050 1.144 1 0.004 0.075 1.065 1 0.004 0.100 1.008 1 0.004 0.200 0.792 1 0.004 0.500 0.641 1 0.005 1.000 0.657 1 0.004 t

(){

With 202 Kg UO2 per BU-7 container

  • Interspersed water in Region 4 as well as in Regions 6, 7,

8, 10 and 12 (Table 5.2)

Table 6.2 indicates the same trends as shown in Table 6.1.

GEMER and MERIT are in good agreement but KENO IV overpredicts the K.s relative to them by three to five per cent in the region around optimum interspersed moderation.

Table 6.3 indicates that, as is to be expected, a slight shift may exist in 'the density of interspersed water corresponding to optimum moderation, but the impact on the K s is smaller than the Monte Carlo statistical uncertainties.

This is evi-dence that the addition of hydrogen anywhere outside of the UO fuel has been implicitly considered by analyzing the BU-7 3

container arrays for optimum interspersed moderation between containers (and within the 55 gallon drums)..

e

.~

.7 7 -

2 Single container 9-(

To provide a further comparison between MERIT, GEMER and KENO IV, the Keff of a single BU-7 container was cal'culated.

The conditions for this calculation were 202 Kg 00 in the container and 0.075 gm/cc 3

of water in Regions 6, 7, 8, 10 and 12 (see Table 5.2).

The results were:

Code K,ff i

o

.GEMER 0.355 1

0.004 MERIT 0.356 1

0.003 4

KENO IV 0.356 1

0.004 3

Accident Case - 8 x 8 x 4 Arrays of BU-7 Containers The GEMER and KENO IV results for the analysis of the 8 x 8 x 4 arrays of BU-7 containers with optimum interspersed water are given in Tables 6.4 and 6.5.

Table 6.4 is for the case O(

in which the BU-7 containers each hold'202 Kg

  • /

UO (full five-gallon product pails at 4.5gm UO /cc) while Table 6.5 contains the results fo the containers limited to 70 Kg UO each 9

(35 Kg U0 Per five-gallon product paiI).

2

. OL

_s

--w--

w

%*.y

,.gm-,--9.-

y

,w--,---.-w---

e-,

-,--v..

.l

{

I TABLE 6.4 - K s for 8 x 8 x 4 ARRAY eff OF BU-7 CONTAINERS (202 Kg UO PER CONTAINER) 2 Interspersed eff 1

Water (gm/cc)

GEMER KENO IV 0.000 0.853 1 0.004 0.025 0.884 1 0.004 0.906 1 0.004 0.050 0.921 1 0.004 0.955 1 0.005

~

0.075 0.928 1 0.005 0.944 1 0.004 0.100 0.929 1 0.005 0.200 0.802 1 0.003 0.500 0.637 + 0.004

) \\

1.000 0.617 1 0.005 7 The array is tightly reflected on all six sides by 12 inches of water.

No interspersed water is placed in Region 4 (see Table 5.2)

('~)) \\

/

\\_

+

t TABLE 6.5 - K,ggs for 8 x 8 x 4 Array

(~}

of BU-7 Containers (70 Kg

\\#

UO Per Container) 2 KENO IV K,ff ia Height in Height in Height in Interspersed Can of Can of Can of

~

' Water (gm/cc) 12.128 cm 20.0 cm 35.0 cm(Full) 0.000 0.534 + 0.004 0.530 + 0.003 0.532 1 0.003 0.025 0.609 1 0.004 0.624 + 0.005 0.655 1 0.005 0.050 0.637 + 0.004 0.679'+ 0.004 0.731 + 0.004 0.075 0.656 + 0.004 0.693 + 0.004 0.750 + 0.005 0.100 0.641 1 0.004 0.681 + 0.005 0.743 + 0.004 0.200 0.537 + 0.004 0.573 + 0.004 0.623 + 0.004 0.500 0.419 1 0.004 0.410 + 0.004 0.427 + 0.004 1.000 0.417 + 0.004 n/ r 0.406 + 0.004 0.401 + 0.005 L

\\.075 0.149 + 0.002 0.231 + 0.002 0.351 + 0.003 Single BU Cbntainer l

The array is tightly reflected on all sides by 12 inches of water.

I No interspersed water is placed'in Region 4 (see Table 5.2).

l Oi-t/ l I--

It is concluded from those two tables that the BU-7 container

(

array is critically safe under the postulated optimum inter-spersed moderation, full reflection accident condition even if the individual BU-7 container mass limit of 70 Kg 00 is 2

exceeded.

This assumes that the H/U = 1.577 and C/U =

1.262 limits are still met.

As in the previous cases, the KENO IV results around the optimum interspersed water level are one to three per cent higher than the corresponding GEMER values.

(The 8 x 8 x 4 array cannot be modeled in MERIT due to geometry limitations.)

The Keff for the 8 x 8 x 4 array with optimum interspersed water and full reflection and with the 70 Kg U0 limit per 2

container is 0.750 + 0.005 (at 0.075 gm H 0/cc interspersed water.)

For comparison, this case was andlyzed replacing the tight water reflector by a tight 16-inch thick concrete reflector (on all six sides).

The KENO IV Keff for this case was 0.789 + 0.004, an increase of 5.2%.

6.2 EVALUATION OF CARBON ADDITIVES From Reference 8, the relative moderating factor for a mixture of water and carbon can be determined to be:

(~b(

ggj Moderating factor = 20 NH + 0.76 Nc + 0.50 No 1

where N, Nc, and No are the corresponding atom densities for g

hydrogeM, carbon, and oxygen in the moderator.

It follows from this relationship that the worth of carbon as a moderator is 0.76

  • 20 = 0.038 times the worth of hydrogen. Applying this value to the mixture of UO water and hydrogen-carbon additives which is approved fob,the BU-7 container, (an H/U atomic ratio of 1.577 and a C/u atomic ratio of 1.262) then results in an equivalent UO2 - H O mixture with 51438 ppm H 0 as opposed 3

2 to the 50,000 ppm H O limit for the H/U rati5 of 1.577.

2 l

The effect of the additional 1438 ppm H O equivalence can be l

estimated from existing tabulated data 2(Reference 6) to be less than 1.0% in K.

However, as part of the present analysis of the BU-7 container, additional calculations have been made using the KENO IV Monte Carlo code to evaluate the effect of carbon on 4.0% enriched UO systems.

The results of these 2

are given in Tables 6.6 through 6.10.

/D (

k;I'.

YO

,\\

q t

C/ (

TABLE 6.6 K, s of U(4.05) 0

- Carbon Systems 2

s Weight Fraction of Carbon in C/U-235 KENO IV' Mixture Atcmic Ratio K,

+

o 0.00 0.0 0.806 + 0.002 0.10 61.6 0.814 7 0.002 0.20 138.7 0.803 7 0.002 0.30 237.8 0.778 T 0.002 0.40 369.9 0.775 7 0.002 0.50 554.9 0.788 7 0.002 0.60 832.4 0.809 I 0.003 0.70 1294.8 0.867 I 0.003 0.80 2219.6 0.936 7 0.003 0.85 3144.4 1.056 7 0.003 0.875 3884.3 1.122 7.0.003 0.90 4994.1 1.196 7 0.003 0.925 6843.7 1.303 7 0.003 0.95 10543.

1.359 I 0.003

] (A

./

l 0.975 21641.

1.438 { 0.003 0.982 30273.

1.448 + 0.003 g

0.990.

54935.

1.377 + 0.003 i

l

  1. 'Ihe theoretical density of carbon was taken to be 2.25 gms/cc l

O\\

s l I"

I O ( JsLE 6.7 g

MINDLE CRITICAL MASSES OF U(4.05)02 - g 0 CARBON SYSTEMS

\\

KENO IV calc.

Weight Fraction Weight Fractigh C/U-235 Min. Crit.tcal of H O of Carbon Atmic Ratio Mass of UO (K9) 2 2

0.0 0.975 21641 140.9 0.982 30273 128.1 0.990 54935 147.4 0.0 0.00 2208 i

0.05 22.84 1954.5 30.0 1658.0 200.0 861.3 1000.0 419.8 0.0 0.00 337.5 0.10 22.84 277.6 200 262.3 1000 164.0 0.0 0.00 101.0

_C).d(

'O.20 22.84 104.9 200 108.9 1000 93.7 0.0 0.00 74.4 0.30 22.84 70.9 200 76.7 1000 101.8 0.0 0.00 65.9 0.40 22.84 66.2 200 73.2 1000 331.6' 0.00 68.6 0.0 0.50 22.84 73.5 200 96.9 W

P

= 2.25 gn/cc c

t Water reflected s

m

)

%d TABLE 6.8 MINI 1U1 CRITICAL MASSES OF U(4.05) 0 - H O SYSTEMS 2

2 l

KENO IV ralt'1 ated 1

Weight Fraction H/0 Mimnun Critical of H 0 Atcznic Ratio Mass of UO2 (Kg) 3 0.05 1.577 2208.

0.10 3.330 337.5 0.20 7.492 101.0 0.30 12.84 74.4 0.40 19.98 65.9 4

O(

v 0.50 29.97 68.6 0.60 44.95 113.7 i

0.70 69.92 1770.

i l

l l

.O t v,

-4%---,

-.9,.

,m,

I LO LO LO c

m

~

TABLE 6.9:

MERIT VERIFICA".' ION OF KENO IV U0 MINIMUM. CRITICAL MASSES 2

C/U-235 Weight Fraction Critical U02 Critical MERIT Atomic Ratio of Water Radius Mass (Kg)

Keff 1 0

0.30 20.98 74.4 1.0031 1 0.0042 0

0.40 22.84 65.9 1.0041 1 0.0039 0

0.50 26.14 68.6 0.9941 1 0.0033 22.84 0.30 21.12 70.9 0.9895 1 0.0048 22.84 0.40 23.34 66.2 1.0019 1 0.0043 22.84 0.50.

27.23 73.5 1.0016 + 0.0034 1

1000 0.10 36.24 164.0 0.9926 + 0.0048 8

1000 33.01 93.7 0.9963 1 0.0042 1000 37.16 101.8 0.9819 1 0.0039

.L I See Table 6.7 1

I i

1 h

i

TABLE 6.10 - BU-7 CONTAINER ANALYSIS WITH CARBON 0(

s A.

Normal case K,with 60% of full density phenolic resin (202 Kg U02 per BU-7 container)

KENO IV K,without carbon 0.903 1 0.003 KENO IV K,with carbon 0.913 1 0.005 B.

Accident case:

8 x 8 x 4 water reflected array with 70 Kg UO Per BU-7 2

Density of Interspersed H O KENO IV K KENO IV K gg) 2 eff e

(gm/cc)

(without carbon (with carbon i

0.025 0.655 + 0.005 0.663 + 0.004 Or

~

~

,j ).

0.050 0.731 1 0.004 0.731 1 0.004 0.075.

'O.750 1 0.005 0.757 1 0.005 0.100 0.743 1 0.004 0.745 1 0.004 C/U = 1.262 e

Height of fuel in five gallon product pails is 35.0 cm

(

_s 32 -

m T---'

s-n amy-a w-de-w--

--r----

-e w,

_--,e,,-_._

,._--e,-m

,___w-

.-m,-,,_,__,,

. = -

=.

~

. The K. results in Table 6.6 can be compared with the tabulated

. (K=

ralues in Reference 6 for U(4.0) 02 - H2O in which the maximum is no greater than 1.40.

Figure 6.1 is a plot of the Table 6.6 results.

In addition, if all the moderator in the UO 9

moderator mixture in the.BU-7 containers were carbon, TabIe 6.6 indicates.that the K. of the fuel would be less than 0.8.

(An.

H/U ratio of 1.577 and C/u ratio of 1.262 imply an effective "C/U" ratio of 42.737 when using the 0.038 equivalence factor between carbon and hydrogen).

The K. o f a U ( 4. 0 ) 02-HO 2

mixture with 40000 ppm H O (a H/U ratio of 1.577) is greater 2

than 1.0.

Tables 6.7 and 6.8 show minimum critical masses calculated with KENO IV for 'U(4.05) 02 - H 0-C and U(4.05) 0 H 0 systems.

2 2

9 These two tables indicate that the minimum criti5a1 mass occurs for pure UO -H O mixtures and that the presence of carbon there-2 2

fore results in dilution of the fuel mixture.. Table 6.7 clearly establishes however that carbon moderation can be appreciable for under moderated systems such as the BU-7 container.

In this regard, the entries in Table 6.7 for 0.05 weight fraction of water indicate.the impact of the C/U = 1.262 BU-7 container limit.

With no carbon, the minimum critical mass at the H/U ratio With of 1.577 (i.e., 0.05 weight fraction water) is 22C8 Kg U02 a mixture containing carbon with a C/U-235 ratio of 30, (an H/U of about 1.2), the critical mass decreases to 1657.7 Kg UO2' "

(])

33% effect.

Table 6.9 presents a verification of the KENO IV UO minimum criticalmasseswhichwasperformedwiththeMERITkonteCarlo code.

The MERIT code was used to calculate the Keff of the UO2 spheres determined to be critical with KENO IV (via the i

search option).

The results show excellent agreement between MERIT and KENO IV for these UO

- H 0-carbon systems.

2 2

Finally,. Table 6.10 summarizes the results of KENO IV calcula-tions for the BU-7 container normal case and accident case analyses described in Section 6.1 with the addition of carbon in the fuel mixtures..The C/U ratio for these calculations is 1.262.

As can be seen, the addition of the carbon increases the K. and Kefg values by no more than 1.25%.

In both cases, the,BU-7 container system is still subcritical.

Ot

\\/

y y

p---,-,-.-

---,,1g.

,---,ecm.-

, mm n r

6.3 Analysis of five Gallon Product Pails I(

The safety of individual BU-7 containers has been analyzed by calculating the effective neutron multiplication factors of two five gallon product pails under conditions of optimum moderation and full reflection.

The results of these calcula-tions are shown in Tables 6.11 and 6.12.

Table 6.11 gives the results of KENO IV calculations for two five gallon containers placed side by side (and touching) with tight water reflection in all areas except immediately between the two containers.

j The maximum K,ff, for this case are-0.968 + 0.006 for 65.8 Kg UO2 per container and Per container 0.909 j; 0.006 for 35.0 Kg U02 Table 6.12 gives the results of calculations for the two five gallon containers stacked in a vertical column.

Again, the containers are touching and the assembly is tightly reflected by at least 12 inches of water.

The maximum K f r the effs vertical arrangement are:

(

0.964 + 0.005 for 65.8 Kg UO2 per container and 0.904 f; 0.004 for 35.0 Kg UO2 per container Since the BU-7 shipping container is limited to 35.0 Kg per five gallon product pail, the criticality safety of an indivi-

. dual container is established for the case of optimum moderation and full reflection.

l l sj

-m-es+--mne,

9 rs TABLE 6.11 - ANALYSIS OF TWO FIVE GALLON CONTAINERS SIDE BY SIDE A.

Full Containers with Maximum UO Masses 2

KENO IV Weight Fraction Mass of UO 2 of H O in Fuel in Single Keff +

2 Container (Kg) 0.05 156.0 0.805 +

0.004 0.10 110.9 0.890 T 0.005 0.20 65.8 0.968 7 0.006 0.30 43.2 0.947 7 0.006 0.40 29.6 0.909 7 0.005 0.50 20.6 0.841 +

0.003 B.

Containers.with 35 Kg UO Mass Limits 2

s Intermediate Weight Fraction KENO IV K

ff of H O in fuel Minimum He,lgnt Height Full cans 2

in cans in cans 35.0 cm V

0.05 0.581 + 0.004 0.538 + 0.004 0.534 + 0.004

~

(127128 cm)

(20.0 m) 0.10 0.639 + 0.005 0.579 + 0.004 0.537 + 0.004 (12128 an)

(20.0 cm) 0.20 0.801 + 0.005 0.746 + 0.004 0.688 + 0.004

~

(187624 cm)

(25.0 cn) 0.30 0.885 + 0.005 0.851 + 0.004 (287370 cm) 0.40 0.909 + 0.005 (3570 ch) 0.50 0.841 + 0.003 (3570 cm)

Qt 1 v l l l

TABLE 6.12 - ANALYSIS OF TWO FIVE GALLON CONTAINERS STACKED VERTICALLY A.

Full Containers with Maximum UO Masses 2

T Weight Fraction Mass of UO2 in of H O in Fuel Single container bff I i

ff -

2 0.05 156.0 0.804_M.004 0.10 110.9 0.902_+0.006 0.20 65.8 0.964_+0.005 0.955_+0.004 0.953_+0.006 0.30 43.2 0.954_+0.005 0.40 29.6 0.904_+0.004 0.50 20.6 0.850_+0.005 B.

Containers with 35 Kg U0 Mass Limits 2

KENO IV Keffs Weight Fraction Minimum Height Intennediate Full Cans of H O in Fuel in Cans Height in Cans (Height =35.0cm) 2 0.05 0.586+0.005 0.550 + 0.004 0.519 + 0.004 (12.T28 m)

(20.6 cm) k.) (

0.10 0.633+0.004 0.578 + 0,005 0.536 + 0.005 V

(12.T28 m)

(20.0 t,

0.20 0.793 + 0.005 0.736 + 0.005 0.678 + 0.005 (18.674 cm)

(25.6 m) 0.30 0.881 + 0.005 0.851 + 0.005 (28.370 cm) l 0.40 0.904 + 0.004 (34.0 cn) 0.50 0.850 + 0.005 (35.0 cm) l h/k l

-35A-1

4 The Kegg = 0.909 + 0.005 and 0.904 + 0.004 results listed above constitute upper limits for extreme accident conditions since G (.

the moderation limit in the containers is limited by BU-7 specifi-

\\w/

cations to 50,000 ppm H2O or less.

(50,000 ppm is the same as a weight fraction of 0.05.)

In Table 6.12 Keff results have also been presented for MERIT and GEMER calculations of the vertically stacked assembly with 65.8 Kg 002 (weight fraction of water = 0.20).

The MERIT and GEMER results for this case are in excellent agreement and are about 1% lower than the KENO IV result.

Finally, it is noted that the presence of carbon in these containers has been found in Section 6.2 to increase the Keffs by no more tuan 1.25% provided that the H/U = 1.577 and C/U = 1.262 limits are met.

The conditions analyzed in Tables 6.11 and 6.12 would in such accident conditions still correspond to a C/U = 1.262 case but the H/U ratio would exceed 7.5 (see Table 6.8).

In this case the pre-sence of the low level of carbon would have an even smaller effect on the system Keffs.

Nevertheless, if tne system Keffs were to increase by-1.25%, the two 5 gallon containers with 35 Kg UO2 in either geometry arrangement would still be critically safe since effs would be no higher than 0.920.

most K b/v iL/s

/.

o i

6.4 Evaluation of Rocky Flats Low Enriched Low Moderation U 0 38

(

Benchmark Critical Experiments 5(

Reference 7 describes a set of benchmark critical experiments that were. performed by Rockwell International (Rocky Flats Plant) to provide data for low enriched Uranium Oxide systems with low levels of moderation.

The Rocky Flats experiments consisted of a 5X5X5 array of Aluminum tins which contained 4.46% enriched U 03 8 powder and for which the average hydrogen content in the entire assembly resulted in an H/U ratio of 0.77.

Ten different cases were run for the critical experiments corresponding to the type of fully enriched Uranium Drive- (metal, low Uranium content solution or high Uranium content solution) and to the type of reflector (con-crete, metal or plastic).

Measured amounts of water were added to the U308 in the Aluminum tins through drilled holes (56 per tin).

The measured critical parameter in the experiments was the separation distance between halves of the 125 unit array.

Both KENO IV and GEMER calculations have been performed for the Rocky Flats experiments with very detailed modeling of the assem-blies in regular and enhanced KENO IV geometries.

The major area in which the geometry models differed in the true configuration was in the smearing of the holes in the Aluminum tins which were used to add the measured amounts of water.

The impact of this

-smearing has been evaluated however by analyzing the K, of a single Aluminum tin with and without the Aluminum holes.

From

(-) {

KENO IV with enhanced geometry these results are J

K, = 1.0838 1 0.0040 For single oxide can.

without holes

(" smeared")

For single oxide can K,=

1.0830 1 0.0053 with holes ("unsmeared")

Any difference is completely masked by the 0.3 to 0.5% statistics.

Table 6.13 shows the results of the KENO IV and GEMER calculations for the Rocky Flats experiments.

Cases 1-3 were not performed with GEMER because of geometry modeling difficulties.

(These cases re-quire the use of'the enhanced geometry option not currently available in GEMER.)

The results of the benchmark calculations are that KENO IV predicts an average K ff = 0.997 1 0.002 and GEMER predicts an average K *g,'

1.003 _+ 0.00 Oc ss.

7 w--

---:---,--,-rw--t

---e n --

e-w

-=--m-r-----r--w-----

  • we,

I LO LO 10:

TABLE 6.13 - KENO IV AND GEMER CALOULA O NS FOR ROCKY FLATS LOW ENRICHED U g O

~'

)

3

{

LOW MODERATION BENCHMARK CRITICAL EXPERIMENTS j

EXPERIMENT eff i NO.

DRIVER REFLECTOR-KENO CRMER-1 Metal Concrete 1.0060+0.0057 2

Metal Plastic 0.9931+0.0064 i

a j

3 Metal Steel.

1.0075+0.0067 4

High Uranium Concrete 0.9948+0.0052 0.9961+0.0060 Content Solution

~

5 High Uranium Plastic 0.99841,0.0052 1.0115+0.0059 i

' Content Solution

}

d, 6

High Uranium Steel 0.9819+0.0055 0.9816+0.0082 i

m Content Solution 7

Low Uranium Concrete 0.9950+0.0048 1.0219+0.0087 Content Solution i

8 Low Uranium Plastic (Spacing 1) 0.9981+0.0045' 1

Content Solution l.0045+0.0064

+

9 Low Uranium Plastic (Spacing 2) 0.9970+0.0050 1.013810.0079 Content Solution i

10 Low Uranium Steel 0.9979+0.0051 0.9898+0.0080 l

Content Solution i

Average values 0.997+ 0.002 l'.003 + 0.003 I

e

e s I

REFERENCES

,l g_

Q l.

Y-DR-51, " Criticality Analysis of Bulk Uranium oxide Shipping Container," J. T. Thomas 2.

GE-BU-4-1, Rev. 1, " Criticality-Safety Analysis of General Electric's BU-4 Shipping Container for the Transportation of Dry Unirradiated Uranium Dioxide," R. Artigas, 1971 3.

NEDO-11277, "The General Electric Model BU-7 Uranium Shipping Container - Criticality Safety Analysis," R. Artigas, 1974 4.

ORNL-4938, " KENO IV, An Improved Monte Carlo Criticality Program," L. M. Petrie & N. F. Cross, 1975 5.

LAMS-2543, "Six and Sixteen Group Cross Sections for Fast and Intermediate Critical Assemblies," G. E.

Hansen & W. H.

Roach 6.

ARH-600, " Criticality Handbook - Volume II," Atlantic Richfield Hanford Company 7.

NUREG/CR-0674, " Benchmark Critical Experiments on Low-Enriched Uranium Oxide Systems with H/U = 0.77," Systems Group, August 1979 8.

Glasstone, S and Edlund, M.C.,

"The Elements.of Nuclear Reactor

(

Theory," Von Nostrom, 1952, pp. 145-146 l

O i

e v v i

~39-

--. =..

i i.

(

Appendix A.

Mixture Densities i '.

A.1 Fuel Mixtures t-A.2 Phenolic Resin and Carbon Steel A.3 Interspersed Water 4

f i

4 6

4 b

+

l

. O(

v i

1

(

e 1

6 4

I

)

l I

i

Ot u

1

~

(

-.,..,+,-.

--.,r-,

,..--,,,,,.,,~n,--

_,n,,-,

..-- --.- ~,-,

UO -H 0-C MIXTURE DENSITIES

- ~} TABLE.A.1 2

2 V (.

A.

4.5 gm UO2/cc + 0.23684 gm H2 /cc Mixtures 0

Material MERIT /GEMER KENO IV HANSEN-ROACH Atom Density Atom / Material 16 Group (atoms / barn-cm)

Density (atoms /

Material-ID barn-cm)

U-235 4.0657 E-04 4.0657 E-04 92508 i

U-238 9.6344 E-03 9.6344 E-03 92810 Oxygen 2.8001 E-02 2.00828 E-02 8100 Hydrogen 1.58365 E-02 Water 0.237269*

502 1.26692 E-02 6100 Carbon (Optional)

(

Use:

101 Kg UO2 in'5 gallon container occupying entire volume of can (height = 35 cm) or 35 Kg 002 in 5 gallon container occupying minimum volume of can (height = 12.128 cm) l i

~

= 0.23684/0.9982, which is the KENO input density (gm/cc j

in this case - not atoms / barn-cm).

i i

O (

s/

41-

,y

,,,.----_-..w.

,,,..--.ywr&_.,m,.

y,m---,ww<,--y-----%*y et,.w-.--=

~esww -+e=

---ew

'm*

4 I

.l kr V N'.

2.7288 gm UO2/cc + 0.14362 gm H 0/cc 2

MATERIAL MERIT /GEMER KENO IV HANSEN-ROACH Atoia Density Atom / Material 16 Group (atoms / barn-cm)

Density (atoms /

Material ID barn-cm)

U-235 2.46546 E-04 2.46546 E-04 92508 U-238 5.84235 E-03 5.84235 E-03 92810 Oxygen 1.69800 E-02 1.21783 E-02 8100 Hydrogen 9.60334 E-03 t

O.143881 502 Water

(~'h Use:

35 Kg UO2 in 5 gallon container occupying partial volume of can (height = 20.0 cm)

= KENO input density (gm/cc in this case - not atoms / barn-cm).

.,. 4

,7s-

\\_

\\m/

.. 1.5593 gm UO /cc + 0.08207 gm H2 /cc 2

0 l

MATERIAL MERIT /GEMER KENO IV HANSEN-ROACH Atom Density Atom / Material

16. Group (atoms / barn-cm)

Density (atoms /

Material ID barn-cm)

U-235 1.40883 E-04 1.40883 E-04 92508 f

U-238 3.33849 E-03 3.33849 E-03 92810 Oxygen 9.70284 E-03 6.95903 E-03 8100 Hydrogen 5.48763 E-03 Water 0.0822179*

502 Carbon 4.39009 E-03 6100 Use:

35 Kg 002 in 5 gallon container occupying entire volume of can (height = 35 cm) t 4

t KENO input density (gm/cc in this case - not atoms / barn-cm).

?

l I

O(..

v.

e---,-e-.+p-

, r g

--e~

---a

,--e-w,-ee

..e-,,w,.-~~

~.-,, -,

,-,._,,,en

,-n.-,--e-,-

-- a

es s UO -H O MIXTURES

~

r FULL THEORETICAL DENSITY 2

2 1.

KENO Mixtures Atom / Material Density (Atoms / barn-cm)

WF H2O U-235 U-238 Oxygen Water (Material)

(Material)

(Material 8100)

(Material 502) 0.10 4.46'492 E-04 1.058505 E-02 2.20548 E-02 0.550088 (92509)

(92818) 0.20 2.64765 E-04 6.27409 E-03 1.30783 E-02 0.733941 (92510)

(92825) 0.30 1.73810 E-04 4.11875 E-03 8.58547 E-03 0.824960 (92511)

(92831)

.h 9 0 1.19208 E-04 2.82485 E-03 5.88836 E-03 0.881201

'(92512)

(92835) 0.54 8.27944 E-05 1.9619 E-03 4.08969 E-03 0.918040 (92512)

(92840) c' m Oxygen - Material

(

Water

- Material WF H O = 0.20 2.

MERIT /GEMER Mixture:

2 Material Atom Density (atoms / barn-cm)

U-235 2.64765 E-04 U-238 6.27409 E-03 Oxygen 3.75717 E-02 Hydrogen 4.89868 E-02 tPartial density atom densities are determined by the ratio of the height of the fuel in the container to the height of theoretical density mixture in container divided into the l

densities in Table D.1

(.

KENO input density (gm/cc in this case - not atoms / barn-cm).

M

i...

BLE A2 PHENOLIC RESIN AND CARBON STEEL A.

Phenolic Resin Material Full Density 80% Density 60% Density (atoms / barn-cm)

Hydrogen 3.0140 E-03 2.4112 E-03 1.8084 E-03 B-10 4.2688 E-05 3.4151 E-05 2.5613 E-05 B-ll 1.6726 E-04 1.2581 E-04 9.4356 E-05 Carbon 2.3050 E-03 1.8440 E-03 1.3830 E-03 Nitrogen 5.2890 E-05 4.2312 E-05 3.1734 E-05 Oxygen 2.0510 E-03 1.6408 E-03 1.2306 E-03 t

1.997 E-04 1.5976 E-04 1.1982 E-04 Boron x, B.

Carbon Steel Material Densi'ty (atoms / barn-cm)

Carbon 3.921 E-03 Iron 8.3491 E-02 Material 100 1.0000 (Hansen-Roach)

KENO IV Material b.

M

1

(

~

i,LE A.3 INTERSPERSED WATER DENSITIES q

KENO Material MERIT /GEMER Densities Density (atoms / barn-cm)

Hydrogen Oxygen 0.010 6.6866 E-04 3.3433 E-04

-0.025 1.67173 E-03 8.35816 E-04 0.050 3.3433 E-03

- 1.6716 E-03 0.075 5.01489 E-03 2.50745 E-03 0.100 6.6866 E-03 3.3433 E-03 0.200 1.3373 E-02 6.6866 E-03 0.500 3.3433 E-02 1.6715 E-02 1.000 6.6866 E-02 3.3433 E-02

.I i

Material 502 I.

,wy

,,,,w.

,y

,--,w-.

-,--ey.--,

r O APPENDIX D

" CRITICALITY SAFETY ANALYSIS - BU-7, THEORETICAL DENSITY" O

J. T. Taylor January 1986 LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1

D

Page 1 of 2

( )-

Criticality Safety of BU-7 Container The BU-7 container has been licensed as a Fissile Class I shipping container.

For a Fissile Class I container it is necessary-to demonstrate that:

1) an infinite array of normal containers is critically safe with optimum interspersed moderation, and 2) an array of at least 250 containers subjected to the hypothetical shipping accident is critically safe with optimum interspersed water and full water reflection, and 3) a single container with optimum moderated contents and full water reflection is critically safe.

These criticality safety demonstrations are provided for the BU-7 container by three sources.

I)

" Criticality Safety Analysis of BU-7 Shipping Container for Powder", 3/6/80, WC Peters 00 UO2 II)

" Criticality Safety Analysis - BU-7, Theoretical Density",

(}

1/24/86, JT Taylor.CO m

III)

License SNM-1097, Rev(3)6, Table 4.4,

" Safe Batch Limits for

& H 0", 10/23/84.

UO2 2

There are three container contents in the shipping certificate:

A)

Uranium oxide powder with nominal enrichment not greater than 4.0 w/o and H/U atomic ratio not greater than 0.45.

B)

Uranium oxide powder with nominal enrichment not greater than 4.0 w/o, bulk density not greater than 4.5 gm/cc, and H/U atomic ratio not greater than 1.6.

C)

Uranium oxide pellets with nominal enrichment not greater i

than 4.0 w/o and H/U atomic ratio not greater than 0.45.

Content type A is limited to 35 kg/can and 70 kg/BU-7.

Content type B is limited to 35 kg/can and 70 kg/BU-7.

Content type C is limited to the lesser of one safe batch /can and two safe batches /BU-7 or 35 kg/can and 70 kg/BU-7.

flhppendix C of Consolidated Application

(

(2hppendix D of Consolidated Application (3hppendix E of Consolidated Application

Page 2 of 2 Criticality Safety of BU-7 Container O:

(continued)

The following table correlates the required demonstrations, container contents, and analyses.

Contents A

B C

Demonstratio Powder, H/U 10.45 Powder, H/d 11.6 Pellets, H/U10.45

1. Normal Array II I

II

2. Accident II I

II Array

3. Single I

I III Container O

I O

3 January 24, 1986

\\_-)

CRITICALITY ANALYSIS OF BU-7 CONTAINER FOR THEORETICAL DENSITY PELLETS i

I. SCOPE This analysis is performed to demonstrate criticality safety for the BU-7 shipping con tciner at 4.025% U235 enrichment with theoretical densi ty, heterogeneous UO2 and an H-to-U ratio not greater than 0.45.

The container was previously shown safe for-these contents but only up to a bulk UO2 density of 4.2 gm/ce.

II. GENERAL DISCUSSION The BU-7 shipping container consists of a phenolic resin insulation sandwiched between a 30 gallon inner drum and a 55 gallon outer drum.

The inner drum can hold up to two 5 gallon cans or three 2-1/2 or 3 gallon cans. The container is shown in Figure 1. The BU-7 container has been licensed as a Fissile Class I container based on the testing performed in Reference 1.

The original analysis of the BU-7 container by R Artigas is documented in Reference 2. Safety was demonstrated under both normal and accident shipping conditions with filled five gallon containers of U(4.00)O2 at a maximum density mixture with an H-to-U ratio notof 4.2 gm/cc and water as a homogeneous greater than 0.45 (ie:

~1.5 weight (ek /y percent). The most, reactive Hansen-Roach U238 cross-sections (ID# 92801) were used. Because of this, shipments of dry (H-to-U < 0.45) UO2 pellets were covered provided that the bulk density was less than 4.2 gm/cc.

The theoretical packing factor for uniform right cylinders is 0.907 as shown in Attachment 1. The theoretical density of UO2 is 10.96 gm/cc.

Therefore, the theoretical bulk density for pellets (assuming no internal voids) is 9.94 gm/cc which is considerably larger than the maximum density used in the original analysis.

The BU-7 container is limited to twe safe batches of pellets per BU-7. However the original analysis assumed that each five gallon container was full. This assumption avoidt-d the necessity of considering intermediate densities, five versus three gallon containers, spacial distribution of fuel, and intermediate U235 enrichments. Under this assumption, each five gallon container has about 85 kg of UO2. The safe batch limit, however, would result in not more than 24.7 kg of pellets per five gallon container at 4.00% U235 enrichment.

In the current analysis, a maximum UO2 densi ty of 9.39 gm/cc has been used. (This results from a theoretical mixture of UO2 and 0.015 weight fraction water which is slightly conserv ative relative to an H/U ratio of 0.45.) Each five gallon container has 102 kg of UO2, which is greater than was used in the original analysi s. The 102 kg does no t c'omol e t ely fill a five gallon container at UO2 bulk densi ties greater than 4.5 gm/cc but is more than four times the 24.7 kg mass of 4.00%

U235 enriched UO2 pellets allowed by procedural controls.

The current analysis also supports a uniform BU-7 mass limit of 70

( )

km, consistent with Reference 4. The safetv factor between a 70 kg mass limit and the safety demonstration is a factor of about three.

s

January 24, 1986 page 2

CRITICALITY ANALYSIS OF BU-7 CONTAINER FOR THEORETICAL DENSITY PELLETS III. CRITICALITY SAFETY CONTROLS The following controls are necessary to meet thi s analysi s :

Control #1 Moderation - Contents must have an H-to-U ratio not greater than 0.45.

Geometry - Fuel may only be packaged in standard metal containers having radii not greater than 14.37 cm.

Control #2 Mass - Each BU-7 container is limited to not more than two safe batches of UO2 pellets as a function of enrichment and is limited to not more than 89 kg of total contents.

The following assumptions are made for this analysis:

Worst Credible Contents Form: heterogeneous UO2.

Density: 10.96 gm/cc (theoretical)

U235 Enrichment: 4.025%

Mass: 204 kg UO2/BU-7 Boundary Conditions Top: water re'flected array Bottom: water reflected array Sides: water reflected array Interunit Water - optimum Structure BU-7: carbon steel Fuel containers carbon steel Array Size Normal Condition: infinite Accident Condition: 8X8X4 IV. MODEL The current model is based on a 1980 reanalysis of the BU-7 container to demonstrate safety for UO2 powder with up to 50,000 ppm equivalent water moderation (Reference 4).

Two types of configurations are used in this analvsis, consistent with Reference 2. The normal model consists of an infinite close-oacked array of BU-7 containers with the insulation modeled as in Reference 4.

The accident model consists of an 8 by 8 by 4 high close-packed array of 4

vertical BU-7 containers with no insulation but with varying densities of water in the insulation regions.

The fuel mixture was obtained based on a theoretical mixture of U(4.025)02 olus 0.015 weight fraction water. Number densities are shown in the following table.

c.

,_/

January 24, 1986 page 3

CRITICALITY ANALYSIS OF BU-7 CONTAINER FOR THEORETICAL DENSITY PELLETS MATERIAL HANSEN-ROACH NUMBER DENSITY ID #

(ATOMS /BN CM)

U235 92507 8.53896E-04 U238 92801 2.01037E-02 OXYGEN 8100 4.19152E-02 WATER 502 1.43289E-01*

  • MASS DENSITY The most reactive Hansen-Roach U238 cross-sections (ID# 92801) were used as in Reference 1. This enables the homogeneous fuel region to conservatively represent heterogeneous mixtures.

The calculational model contains 102.175 kg of UO2 in each of two five gallon containers. This corresponds to a full container of UO2 at a bulk density of 4.5 gm/cc. The following table shows the fuel height as a function of UO2 density.

RHO-UO2 FUEL HEIGHT (gm/cc)

(cm) 9.39 16.78 6.30 25.00 4.50 35.00 Since bulk censities greater than 4.5 gm/cc result in void regions within the inner container, spatial distribution of the fuel must be considered. Therefore, two models are used to represent the extremes of spatial distribution. The three spatial distributions considered are shown in Figure 2. Use of these three spatial distributions covers the use of five, three, or two and one-half gallon containers since the two five gallon containers have more volume and less metal than three of the smaller containers.

Figure 3 shows an X-Z geometry plot of a single BU-7 container from the model. Figure 4 sh<ss an X-Y plot of the accident array. Figure 5 shows an X-Z plot of the accident array. Sample listings of the GEKENO input are provided in Attachment 2. The model used for this analysis is significantly more reactive than the model used in the original analysis.

V.

CALCULATIONAL RESULTS Table 1 shows the results of calculations performed with the models in Section IV. Figure 6 shows the effect of the fuel density on k-eff for contiguous fuel when each five gallon container is limited to 102.2 kg UO2. Increasing the fuel density reduces the reactivity of the system.

Figure 7 shows the effect of separating the fuel regions within the inner container. The reactivity increases when the regions are seoarated (since a larger effective cross-sectional fuel area results) but is less i

than the smeared condition reactivity. These data show that the smeared

,(,

condition is the most reactive for the svstem being analy:ed.

The maximum k-effective + 3* sigma values are summarized below.

January 24, 1986 page 4

(O CRITICALITY ANALYSIS OF BU-7 CONTAINER FOR THEORETICAL DENSITY PELLETS CALCULATION CONDITION K-EFFECTIVE + 3* SIGMA LIMIT

____1____

BU7N. NORM NORMAL 0.7805 0.900 BU7N-35-125 ACCIDENT 0.9052 0.970 VI. CONCLUSION This analysis has demonstrated criticality safety of the BU-7 shipping container under the postulated shipping accident for not greater than 4.025% U235 enriched UO2 pellets up to and including theoretical density providing the H-to-U ratio within the inner container -does no t exceed 0.45 and the UO2 mass does not exceed 204 kg.

REFERENCES 1.

" Test Report for Model BU-7 Bulk Uranium Shipping Container",

04/25/80, JA Zidak.

2. "The General Electric Model BO-7 Uranium Shipping Container -

Criticality Safety Analysis", 02/74, R Artigas.

3.

" Criticality Safety Evaluation of a Shipping Container for Moderated Low-enriched Uranium Compounds", NUCLEAR TECHNOLOGY, VOLUME 19 07/73, R Artigas.

4.

" Criticality Safety Analysis of BU-7 Shipping Container for UO2 Powder", 03/06/80, WC Peters.

-#^N

% _,)

January 24, 1986 page 5

CRITICALITY ANALYSIS OF BU-7 CONTAINER FOR THEORETICAL DENSITY TELLETS LIST OF TABLES 1.

BU-7 CONTAINER, ARRAY CALCULATIONS, 0.45 H/U LIST OF FIGURES 1.

BU-7 CONTAINER GEOMETRY 2.

SPATIAL DISTRIBUTIONS CONSIDERED

3. X-Z GEOMETRY PLOT OF THE BU-7 CONTAINER
4. X-Y GEOMETRY PLOT OF THE BU-7 ACCIDENT ARRAY
5. X-Z GEOMETRY PLOT OF THE BU-7 ACCIDENT ARRAY 6.

EFFECT OF FUEL DENSITY ON K-EFF (CONTIGUOUS FUEL) 7.

EFFECT OF FUEL SEPARATION WITHIN BU-7 CONTAINER LIST OF ATTACHMENTS h

1. THEORETICAL PACKING FACTL OR ROD'S
2. SAMPLE LISTINGS OF GEKENO BU-7 MODEL INPUT i

January 27, 1986 TABLE 1 - BU-7 CONTAINER RESULTS ACCIDENT CAS(: 8X8X4 ARRAY (204 KG-UO2 PER BU-7, NO' INSULATION)

Fuel Fuel Fuel Interunit k-eff Sigma Histories Height Density Geometry Water (cm)

(gm/cc)

(sm/cc) 35.00 4.50 smeared 0.025 0.7654 0.0031 48500 0.050 0.8337 0.0029 45000 0.125 0.8959 0.0031 48500 0.250 0.8033 0.0032 48500 25.00 6.30 contiguous 0.025 0.7460 0.0035 26500 0.050 0.7942 0.0030 46500 0.125 0.8337 0.0031 34000 0.250 0.7435 0.0033 46500 16.78 9.39 contiguous 0.025 0.7301 0.0033 31500 0.050 0.7626 0.0026 45000 0.125 0.7753 0.0036 44500 0.250 0.7074 0.0028 48500 16.78 9.39 separated 0.025 0.7335 0.0029 44500 0.050 0.7842 0.0036 29000 0.125 0.8110 0.0026 48500 0.250 0.7148 0.0032 47000 NORMAL CASE: INFINITE ARRAY (204 KG-UO2 PER BU-7, W/ INSULATION)

Fuel Fuel Fuel k-eff Sigma Histories Height Density Geometry (em)

(sm/cc) 35.00 4.50 smeared 0.7742 0.0021 45500 g

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  • 6

e October 30, 1985 ATTACHMENT 1 - THEORETICAL PACKING FACTOR FOR RODS The theoretical packing factor for rods is determined as follows based on Figure A1. The triangle represents a unit cell which can be reflected on all three sides to obtain an infinite array of uniform cylinders with a triangular pitch.

Total Area = 0.5

  • base
  • height

= 0.5

  • 2R
  • 2R*COS(30)

Fuel Area

= 3

  • 60/360
  • Pi*R*R

= 0.5

  • Pi*R*R Fuel Area Packing Factor

= ----------

Total Area Pi

= ___________

4

  • COS(30) h

= 0.907 O

FIGURE A1 - THEORETICAL PACKING FACTOR FOR RODS 9

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v

Januarv 17, 1996

\\

ATTACHMENT 2 - GEKENO INPUT LISTING FOR BU7N-35-125 85.227,8U7

,Hnnn, 4.025,WTFRO.015,0,884, 12.W.MB 999.0 100 500 3

16 6

9 5

12 15 1 2R8 4 9 2Z 10.0 1 11 1

-92507 4.09382E-04 1

92801 0.96383E-02 1

8100 2.00953E-02 1

502 0.68697E-01 2

6100 1.3830E-03 2

1102 1.8084E-03 2

5100 1.1982E-04 2

14100 3.1734E-05 2

8100 1.2306E-03 3

100 1.

4 502 0.125 5

502 1.

CYLINDER 3 14.37 0.05 -0.05 16*0.5 CYLINDER 1 14.37 35.05 -35.05 16*0.5 CYLINDER 0 14.37 35.05 -35.05 16*0.5 CYLINDER 3 14.42 25.1 -35.1 1G*0.5 CYLINDER 0 17.70 35.1 -25.1 16*0.5 CYLINDER 3 17.308 35.5763 -35.2087 16*0.5 CYLINDER 4 23.495 35.5763 -42.8287 16*0.5 llg CYLINDER 4 23.495 36.688

-42.8287 16*0.5 CYLINDER 4 28.575 44.308

-42.8287 16*0.5 g

CYLINDER 3 28.575 44.4167 -42.9374 16*0.5 CYLINDER 0 28.575 45.3692 -44.8424 16*0.5 CYLINDER 3 29.634 45.3692 -44.3424 16*0.5 CUBOID 0 28.684 -28.694 28,684 -23.684 45.3692 -44.9424 16+0.5 CORE BDY 0 229.472 -229.472 229.472 -229.472 180.4232 -190.4232 16Z CUBOID 5 260.

-260.

260.

-260.

212.

-212.

16Z

Januarv 22. 1986 ATTACHMENT 2 - GEKENO INPUT LISTING FOR BU7N-16.78S-050 85.227,8U7

,Hnnn, 4.025.NTFRO.015.0.SS4 5.W.MB 999.0 100 500 3

16 6

9 5

12 15 1 2RS 4 9 22 10 0 1 11Z 1

-92507 S.53896E-04 1

92801 2.01037E-02 1

8100 4.19152E-02 1

502 1.43289E-01 2

6100 1.3830E-03 2

1102 1.8084E-03 2

5100 1.1982E-04 2

14100 3.1734E-05 2

8100 1.2306E-03 3

100 1.

4 502 0.050 5

502 1.

CYLINDER 3 14.37 0.05 -0.05 16*0.5 CYLINDER 0 14.37 18.22 -18.22 16*0.5 CYLINDER 1 14.37 35.05 -35.05 16*0.5 CYLINDER 3 14.42 35.1 -35.1 16*0.5 CYLINDER 0 17.70 35.1 -35.1 16*0.5 CYLINDER 3 17.808 35.5763 -35.2087 16*0.5 CYLINDER 4 23.495 35.5763 -42.8287 16*0.5

~s CYLINDER 4 23.495 36.688

-42.8287 16*0.5 CYLINDER 4 28.575 44.308

-42.8287 16*0.5

('

CYLINDER 3 28.575 44.4167 -42.9374 16*0.5 CYLINDER 0 28.575 45.3692 -44.8424 16*0.5 CYLINDER 3 23.684 45.3692 -44.8424 16*0.5 CUBOID 0 28.684 -28.684 28.684 -28.634 45.3692 -44.8424 16*0.5 CORE BDY 0 229.472 -229.472 229.472 -229.472 130.4232 -180.a232 16Z CUBOID 5 260.

-260.

260.

-260.

212.

-212.

16Z m

\\

January 22. 1996 ATTACHMENT 2 - GEtENO INPUT LISTING FOR BU7N. NORM 85.227,8U7

,Hnnn. 4.025,WTFRO.015,0,000, 0.I.MB.

999.0 100 500 3

16 6

9 5

12 13 1 1 1 1 9 1 0 10 0 1 11Z

-1.0 -1.0 -1.0 -1.0 -1.0 -1.0 1

-92507 4.09332E-04 1

92801 0.96393E-02 1

8100 2.00953E-02 1

502 0.68697E-01 2

6100

1..?S30 E-0 3 2

1102 1.3084E-03 2

5100 1.1992E-04 2

14100 3.1734E-05 2

8100 1.2306E-03 3

100 1.

4 502 0.125 5

502 1.

CYLINDER 3 14.37 0.05 -0.05 16*0.5 CYL I NDER-1 14.37 35.05 -35.05 16*0.5 CYLINDER 0 14.37 35.05 -35.05 16*0.5 CYLINDER 3 14.42 35.1 -25.1 16*0.5 CYLINDER 0 17.70 35.1 -35.1 16*0.5 CYLINDER 3 17.808 35.5763 -35.2087 16*0.5 CYLINDER 2 23.495 35.5763 -42.8237 16*0.5

_ _s

(

i CYLINDER 2 23.495 36.688

-42.8297 16*0.5 y;

CYLINDER 2 23.575 44.303

-42.8287 16*0.5 CYLINDER 3 29.575 44.1167 -42.9374 16*0.5 CYLINCER 0 28.575 45.3692 -44.8424 16*0.5 CYLINDER 3 28.684 45.3692 -44.8424 16*0.5 CUSOID 0 28.384 -23.634 28.G34 -28.634 45.3692 -44.8424 1G+0.5

/

m 0

APPENDIX E TABLE 4.4

" SAFE BATCH LIMITS FOR 00 AND H 0" 2

2 NRC LICENSE SNM-1097 CONDITION 9, PART I

,j LICENSE SNM-1097 DATE 12/22/86 PAGE DOCKET 71-9019 REVISION 1

I TABLE 4.4 4

7.((

SAFE BATCH LIMITS FOR UO, & H,0 (Kgs UO2)

)

l Nominal

)

U23s U23s Enrich-Enrich-j ment 00 UO ment UO UO 2

2 2

2 w/o Powderl Pellets 2 w/o Powder l Pellets 2 1.1 2629 510 3.4 34.6 31.0 j

1.2 1391 341 3.6 31.1 28.5

}

1.3 833 246 3.8 28.3 26.4 1.4 583 193 4.0 25.7 24.7 1.5 404 158 4.2 23.7 22.9

)

1.6 293.3 135 4.4 21.9 21.4 1.7 225.0 116 4.6 20.2 20.0 1.8 183.0 102 4.8 19.1 18.8 1.9 150.6 90.5 5.0 18.1 18.1 2.0 127.5 81.6 5.5 15.4 15.4 j

2.1 109.2 73.1 6.0 13.8 13.8 l

2.2 96.8 66.4 7.0 8.3 8.3 j

2.3 84.3 61.0 8.0 6.9 6.9 i

i 2.4 74.7 56.1 9.0 5.9 5.9 2.5 68.9 52.1 10 5.1 5.1 2.6 60.5 48.8 11 4.4 4.4 2.7 56.6 45.4 12 3.9 3.9 j

2.8 52.2 42.9 13 3.5 3.5 j

2.9 47.6 40.1 14 3.3 3.3 3.0 44.5 38.1 15 3.0 3.0 3.2 38.9 34.1 NOTE:

For enrichments not specified above, smooth curve interpolation of safe batch values may be used.

l ilomogeneous mixtures j

Hetergeneous mixtures 2

}

LICENSE SNM-1097 DATE 10/23/84 PAGE DOCKET 70-1113 RCVISION 6

I_4,9

)

i

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