ML19309H294
| ML19309H294 | |
| Person / Time | |
|---|---|
| Site: | 07109853 |
| Issue date: | 01/22/1980 |
| From: | Travis W ENERGY, DEPT. OF |
| To: | |
| Shared Package | |
| ML19309H293 | List: |
| References | |
| NUDOCS 8005130007 | |
| Download: ML19309H294 (4) | |
Text
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OAK RIDGE N ATIONAL LABORATORY O*ERATED OY UNtoN CARBIDE CORPORATION NUCLUR Onl310N O
POST OFrtCE BOX X O AK Rf 0CE, TENM255EE 37610 January 22, 1980 Department of Energy, Oak Ridge Operations Attention:
Mr. J. A. Lenhard, Assistant Manager Post Office Box E Oak Ridge, Tennessee 37830 Gentlemen:
ORNL/EN3/Tli-15, Safety Analysis Report for Packaging the Unirradiated Fuel Shirpir.g Container 00E's approval to ship elements not specifically identified in the subject SARP is requested.
Enclosed are three copies of NBS Scecial Shiaf nL f;.tuest.
This i
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request is being make to facilitate the shipping of ALRR converter elements to ORNL to meet comitments made by N35.
Sincerely yours,
~7M.b; /YL'W)*
M. E. Ramsey, Assistant Director - 5ervictr.
1 MER:gl Enclosures 3:
ec,'w/oenele:
J. A. Cox J.11. Evanr.
R. F. Hibbr.
n U
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- k'b C. C. licpkins E. M. Eini; b
- 11. Po:;tc.a W. R. hacInn.1 W. E. Terry J. T. Thc:rsc File h0
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.i NBS SPECIAL SHIPPING REQUEST I
Due to the anticipated arrival of fresh fuel at NBS it is necessary to ship excess unirradiated fuel to ORNL so that NBS d:: 4 not exceed the fissile material limit-of their criticality statement.
The proggsed loading in the NBS container is four ALRR cogerter elements D
(441g U/ element) and two NBS reactor elements (<210g U/ element). The l
Chairman of the ORNL Criticality Committee has examined the condition of this loading for fissile class I criteria and found it satisfact.ory (reference attached letter and calculation summary, dated March 21,1979).
The cavity cross-section is sufficiently large to accommodate the ALRR elements but they should be padded to a snug fit (polyethylene sheet is recommended) to prevent shipping damage.
In addition the ALRR elements are 1
only about 33 in. long, compared to 68 51/64 in. #cr the NBSRR fuel for which l
the NBS unirradiated shipping containers were designed. A plug of inert material (of the proper length to simulate NBS elements) shall be installed in each cavity to be used for ALRR elements.
The SARP will be updated in the near future to include shipping of the ALRR converter elements and other identified elements that may be shipped in the unirradiated shipping containers.
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Mi e O h' il NUCLEAR DIVISION rs u m INTERNAL CORRESPONDENCE
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March 21, 1979 R. W. Knight, 4508, Room 135, X-10 (4-4354)
HBS Converter Elements i
Mr. T. M. Raby of NBS asked me to examine the use of the NBS fuel element shipping package when loaded with four of the ALRR converter elements
'(441 2
9 sV/ element) and two NBS reactor elements (<210 g 22sU/ element).
I have examined the conditions for Fissile Class I package under the damaged package criteria and find that Fissile Class I criteria are satisfied for the proposed loading.
1 The attachment is a summary of the analyses.
If further in' form $ tion is L
needed, please feel free to call on me.
.f f J. T. Thomas, 6002, Room A-2, X-10 (4-5261)
?
JTT/bbf Enclosure cc/ enc:
J. H. Evans,1000, C239 (4-6381)
T. M. Raby, NBS~
G. E. Whitesides, 6025, IM1, (4-5267)
File-NoRC r
,s 1
ALRR Converter Elements - Shipping Container Evaluation The attachment from T. M. Raby of the National Cureau of Standards (fibs) describes the elements and the analysis performed to justify the storage of The calculations are not applicable to the shipment of these the elements.
elements because the large separation in water does not resemble the spacing in a flooded container. The low keff obtained (0.58) is essentially that of a single element submerged.
Calculations were performed to demonstrate the larger keff obtainable A description of with four converter elements as the spacing is varied.
2 code with the Hansen-Roach 1
the input to the KEN 0 IV Monte Carlo Criticality The effect of spacing, heutron cross section sets is.'given in Table 1.
given as surface separation, on the keff of a 2 x 2 x 1 array reflected and moderated by water is given in the following table:
Surface 2 x 2 x 1 Array _
Separation, cm fff y
0.072 0.956 0.005 0.972 0.920 0.005 l.472 0.863 0.005 A description of the shipping container is given in Table 2 where the materials are those corresponding to the damaged package as described in Ref. 3.
Calculations of an = x = x = array of damaged packages with a-capacity of nine elements in a 3 x 3 x 1 arrangement were performed for the conditions described in Table 3.
These results show the NBS shipping package loaded with four ALRR con-verter elements and two NBS fuel elements (%210 g "U/ element) meet the requirements of a Fissile Class I package and should be assigned a transport index of zero.
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Table 1.
Description of ALRR Converter Element in KENO Monte Carlo Code Region Geometry Material r, cm
+Z l
Cylindrical HO 2.8575 39.52875 2
2 Cylindrical Al 2.9083 3
Cylindrical U-Al (1) 3.0861 4
Cylindrical Al 3.1369 5
Cylindrical HO 3.14290 2
6 Cylindrical Al 3.4798 7
Cylindrical U-A1(2) 3.6068 8
Cylindrical Al 3.6576 9
Cylindrical HO 3.9497 2
10 Cylindrical A1 4.0005 11 Cylindrical U-Al (3) 4.1021 12 Cylindrical Al 4.1529 13 Cylindrical H2O 4.450 14 Cylindrical A1 4.5272'S 15 Cuboid HO Variable 2
Atom Number Densities Material assU 2:su 27Al 180 U-Al (1) 3.9554-3 2.9355-4 4.5311-2 1.3432-2 U-Al (2) 3.6954-3 2.7527-4 5.1205-2 9.3090-3 U-Al (3) 3.0120-3 2.2387-4 5.3501-2 8.3152-3
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Table 2.
NBS Shipping Container Description in KENO Monte Carlo Code Core Reflector Region Geometry Material
+ x/r
+y
+z 1
- Core bdy void 17.373 17.373 39.52875 2
Cuboid H0 17.373 17.373 88.344 2
3 Cylinder foam 25.083 88.344 4
Cylinder foam / wood 25.083 95.400 5
Cylinder char. foam 32.703
+103.11/-102.94 6
Cylinder carbon steel 33.023 103.43 7
Cuboid void 34.00 34.00 105.00 Table 3.
Neutron Multiplication Factor for Unlimited Arrays of Damaged Packages i
No. of Element Calculated Elements Arrangement keff to I
c l
6 EEW 0.801 0.007 EWE 9
EEW 5
WEW 0.819 0.007 EEE WEW 6
EEW 0.895 0.006 EEE WEW 5
(a) 0.812 0.006 (a) as second entry.but with water in Region 7 of the reflector r
a.,,..
References
'l.
L. M. Petrie and N. Cross, " KEN 0 IV -- An Improved Monte Carlo Criticality Program," ORML-4938, Oak Ridge National Laboratory (1975).
2.
G. E. Hansen and W. H. Roach. "Six and Sixteen Group Cross Section Sets for Fast and Intermediate Critical Assemblies," LAMS-2543, Los Alamos Scientific Laboratory (1961).
3.
J. T. Thomas, " Nuclear Criticality Safety Assessment of ORR, NBS, and HFBR Fuel Element Shipping Package," ORNL/CSD/TM-77, Oak Ridge National Laboratory (1979).
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U.S. DEPARTMENT oF ENERGY Y13f)
CERTIFICATE OF COMPLIANCE 10 m M For Radioactive Materials Packages le. Total No. Pages.
9853 1
USA /9853/BF(peg _oR} 1d. Pafe No.
3 Ia Certificate Number Ib. Revision No.
Ic. Package identification No.
- 2. PREAMBLE 2a.
This certificate is issued to satisfy Sections 173.393a.173.394,173.395,and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170-189).
2b.
The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10, Code of Federal Regulations. Part 71," Packaging of Radioactive Material for Transport and Transportation of Radioactive Material Under Certain Conditions."
2c.
This certificate does not t.ieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or ottwr applicable regulatory agencies, including the government of any country through or into which the package will be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or application-(1) Prepared by (%me and address):
(2) Title and Identification of report or application:
(3) Date:
Oak Ridge National Laboratory (a) Safety Analysis Report for Packaging: (a) August 1979 Post Office Box X The Unirradiated Fuel Shipping Container Oak Ridge, TN 37830 Report ORNL/ENG/TM-15 (b)Ltr. M.E. Ramsey to J.A. Lenhard (b) Jan. 22, 1980
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71,as caplicable,and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
a.
Packaging:
(1) Model: ORNL Unirradiated Fuel Shipping Container (2)
Description:
Packaging for unirradiated fissile material as fuel elements.
The fuel ele-ments are positioned in a basket consisting of seven square cavities fabri-cated from 16 gauge plate and a base fabricated from eleven gauge plate.
The plate is Type 300 stainless steel.
Eight 3/8" nuts and bolts retain the basket lid, which is made from 0.125" thick aluminum, in place. The basket is positioned inside a cylindrical outer shell.
The outer shell and lid are fabric.ated from eleven gauge plate and the base is 1/4" thick plate.
The plate for the shell is Type 300 stainless steel.
The outer lid is held in place by six 5/8" nuts and bolts. The basket is supported on 2" x 6" timbers inside the outer shell.
The remaining space around the basket is filled with phenolic foam insulation.
There are different types of packages.
Table I details the design of each container and the types of fuel elements shipped therein.
(b) Contents:
(1) Type and form of material 235 The uranium is enriched to S93%
U and is in the oxide form.
It is contained in fuel plates as reactor fuel elements.
6a. Date of issuance: March 5, 1980 l sb. Expiration Date:
FOR THE U.S. DEPARTMENT OF ENERGY la. Address (of DOE issuing 0tfice) 7b. Signature, Name, $d Title (of DOE Approving Officia0 LAnAam M WM U. S. Department of Energy William H. Travis, Director Post Office Box E Safety and Environmental Control Division Oak Ridge, Tennessee 37830
Paga 2 Certificate No. 9853 - Revision 1 (continuationsheet) 5.
(1) Shipment of fuel elements (see Table I) are as follows:
(a) For each type of shipping container - seven fuel elements containing 370g 23s0 per fuel element.
9L (b) For mixed loading of the NBS shipping container, six fuel elements as follows:
no more than two NBS fuel elements containing 210g 235U per fuel element, and no more than four ALRR fuel elements containing 841g 235U per fuel element.
(2)
Fissile Class:
I i
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TABLE I
SUMMARY
DESIGN DATA CONTAINERS AND FUEL ELEMENTS Container Fuel Elements Gross Outside Inner Basket Nominal Maximum Weight Length Diameter Base Length Cavities Dimensions 2350 Per Type (1b.)
(In.)
(In.)
(In.)
(In.)
(In.) _
Type (In.)
Element (g)
I
- 1. ORNL 580 56 5/8 24 1/2 29 x 29 38 3/4 4x4 A.
ORR" 38 3/8 x 3.033 x 3.397 370 B.
BSR 34 3'S x 2.996 x 3.397 370
&c PCA d
II.
BNL 700 75 1/2 24 1/2 29 x 29 57 1/2 4x4 HFBR 57 1/4 x 2.878 x 3.218 370 3
III.
NBS 850 87 1/8 26 30 1/2 69 3/16 4 1/2 A. NBSRR* 68 51/64 x 3.125 x 3.8125 370 x
x B. ALRR 33 x 3 x 3 841 30 1/2 4 1/2 I0ak Ridge National Laboratory 2Brookhaven National Laboratory 3National Bureau of Standards a0ak Ridge Research Reactor bBulk Shielding Reactor cPool Critical Assembly d
2 High-Flux Beam Reactor eNational Bureau of Standards Research Reactor Ames Laboratory Research Reactor
- Seven cavities per basket; no more than one fuel element per cavity.
ORO REVIEW 0F NUCLEA': CRITICALITY SAFETY EVALUATION (T.*ansmitted in Letter of January 22, 1?80, to J. A. Lenhard)
BY William A. Pryor The KENO IV Code and the Hansen-Roach neutron cross-section sets were used in the nuclear criticality safety calculations. Valida-tion of the combination has been made experimentally.
This is the same combination which was utilized to evaluate the fuel elements currently approved for shipment in these shipping containers.
Since the maximum k is '0.9, sufficient conservatism has been eff incorporated into the limitations for transporting fuel elements 235 with a U content up to 841g.
The calculations verify the prescribed shipping arrangement with four ALRR fuel elements and two NBS fuel elements is Fissile Class I.
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