ML20024A307
| ML20024A307 | |
| Person / Time | |
|---|---|
| Site: | 07109134 |
| Issue date: | 12/02/1982 |
| From: | Matthew Smith EG&G, INC. |
| To: | |
| Shared Package | |
| ML20024A303 | List: |
| References | |
| PR-T-79-012, PR-T-79-012-R01, PR-T-79-12, PR-T-79-12-R1, NUDOCS 8306160670 | |
| Download: ML20024A307 (33) | |
Text
,_ _
c Reen No.
I bbEb Idaho, Inc.
Date:
Decc.mber 2, 1992
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INTERNAL TECHNICAL REPORT ETR Fuel Element Shippino Container AddendumtoPR-T-79-Oll{TR-466)
Test Reactor Technical Support Branch M. C. Smiti.
De:kee By: _M. J. Schell Ao reved By: _0_._R. Mousseau TRTSB TRTS Branch Manager CCE-ID Approvel Letter: C. S. Williams to Approval and Revie-is documented on
! R. W. Kleiin, data:! October 25, 1982 DRR 20919 dated 09-21-82 8306160670 830602 PCR ADOCK 07109134 C
PDR T 5 W-*c~
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$4 E Ga G an.,.
DOCUMENT APPROVAL SIGNATURE SHEET
,otu scas.im n un TYPE OF 00CUMENT 00CUMENT NO.
Internal Technical Report PR-T-79-012 Rev 1 TITLE ETR Fuel Element Shipping Container Addendum to PR-T-79-Oli (TR-466)
M. C. Smith EXT.
PREPARED BY TRTSB CRlGINATED BY EXT.
APPROVAL AND REVIEW SIGNATURES ORGANIZATION DATE D. P. Halls Safety 9-22-82 H. R. Orme Safety 9-22-82 W. S. Tisdale Quality 11-23-82 R. L. Pierce TRTSB 11-16-82 (Sionatures are documented i n DRP 20919) t i
j mm
s Report No. PR-T-79-012 Rev 1 OISTRIBUTION:
N. Bonicelli J. C. Haire A. L. Kologi Sandy Lord - 8 D. R. Vousseau R. L. Pierce Mary Thom F. R. Vanaewiele - 10 Guy Wilson W. Yur<owsky Technical Library - 2 CCS Original e
W e,
FORWARD In July, 1979, EG&G Idaho, Inc. was requested to evaluate the ETR Fuel Element Shipping Container for compliance with existing transport regulations, in order to ship GETR fuel elements from Vallecitos, California to the INEL.
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Technical report PR-T-79-011 (TR-466), "ATR Fuel Element Shipping Container Safety Analysis," was used as a basis for this evaluation.
The safety analysis contained in technical report PR-T-79-Oll (TR-466) was performed utilizing the ATR, ETR, MTR, and SPERT shipping containers.
The report determined the ETR Fuel Element Shipping Container does comply with the existing transport regulations for a Type A quantity, Fissile Class I shipping container.
The ETR and GETR fuel elements are essentially identical in physical size, construction, and fissile material content, the analysis documented in this report has determined the shipment of GETR fuel elements in the ETR shipping container to be safe and pose no threat to the public health and safety.
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CONTENTS
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0.0 General Information 0.1 Introduction 0.2 Package Description 0.3 Authorized Contents of Packaging 0.3.1 Fissile Material Limits 0.3.2 Radioactivity Limits See PR-T-79-Oll (TR-466) page 0-4 0.3.3 Physical and Chemical Form See PR-T-79-Oll (TR-466) page 0-4 0.3.4 Heat Generation See PR-79-011 (TR-466) page 0-4 0.4 Adm1nistrative Controls See PR-T-79-Oll (TR-466) page 0-4 1.0 Structural Evaluation See PR-T-79-Oll (TR-466) page 1-1 1.1 Structural Design See PR-T-79-011 (TR-466) page 1-1 1.2 Weights and Centers of Gravity 1.3 Codes and Standards See PR-T-79-Oli (TR-466) page 1-2 l.3.1 Mechanical Properties See PR-T-79-Oll (TR-466) page 1-2 1.4 Compliance with General Standards for all Packaging See PR-T-79-Oll (TR-466) page 1-2 1.4.1 Chemical and Galvanic Reactions See PR-T-79-Oll (TR-466);page 1-3 1.4.2 Positive Closure See PR-T-79-011 (TR-466) page 1-3 1.4.3 Lifting Devices See PR-T-79-Oll (TR-466) page 1-3 1.4.4 Tie Down Devices See PR-T-79-011 (TR-466) page 1-3 1.5 Standards for Type B and Large Quantity Packaging See PR-T-79-Oli (TR-466) page 1-3 1.6 Compliance with Standards for Normal Conditions of Transport See PR-T-79-Oll (TR-466) page 1-4 1.6.1 Heat see PR-T-79-011 (TR-466) page 1-4 1.6.2 Cold see PR-T-79-Oll (TR-466) page 1-4 1.6.3 Pressure see PR-T-79-011 (TR-466) page 1-4 1.6.4 Vibration see PR-T-79-011 (TR-466) page 1-5 1.6.5 Water Spray see PR-T-79-Oli (TR-466) page 1-5 1.6.6 Free Drop see PR-T-79-Oll (TR-466) page 1-5 1.6.7 Corner Drop see PR-T-79-Oll- (TR-466) page 1-6 1.6.8 Penetration see PR-T-79-011 (TR-466) page 1-6 1.6.9 Compression see PR-T-79-011 (TR-466) page 1-7 i
i
1-7 Compliance with Standards for Hypothetical Accident Conditions See PR-T-79-011 (TR-466) page 1-8 1.7.1 Free Drop see PR-T-79-Oll (TR-466) page 1-9 1.7.2 Puncture see PR-T-79-Oll (TR-466) page 1-10 1.7.3 Thermal see PR-T-79-Oll (TR-466) page 1-16 l.7.4 Water Icmersion see PR-T-79-Oll (TR-466) page 1-16 1.7.5 Summary and Conclusion see PR-T-79-011 (TR-466) page 1-18 1-8 Appendicies l.8.1 Engineering Drawina of ETR Shipping Box 1.
ETR Fuel Assembly Shipping Container Assembly and Detail.
l.8.2 Impact Calculations for Protective Container see PR-T-79-011 (TR-466) page 1-25 1.8.3 Handle Lifting Calculations see PR-T-79-Oll (TR-466) page 1-33 1.8.4 References see PR-T-79-Oll (TR-466) page 1-47 2.0 Thermal Evaluation see PR-T-79-011 (TR-466) page 2-1 2.1 Discussion see PR-T-79-Oll (TR-466) page 2-1 2.2 Summary of Thermal Properties of Materials see PR-T-79-011 (TR-466) page 2-1 2.3 Technical Specifications of Components see PR-T-79-Oll (TR-466) page 2-1 2.4 Thermal Evaluation for Normal Conditions of Transport see PR-T-79-Oll (TR-466) page 2-1 2.5 Hypothetical Thermal Accident Evaluation see PR-T-79-Oll (TR-466) page 2-6 2.5.1 MTR Container see PR-T-79-Oll (TR-466) page 2-7 2.5.2 Analytical Methods see PR-T-79-Oll (TR-466) page 2-11 l
2.5.3 MTR Container with Outer Container see PR-T-79-Oll~
i (TR-466) page 2-12 2.5.4 ATR Container see PR-T-79-Oll (TR-466) page 2-15 2.6 Appendix 2.6.1 Thermal Test on Polyethylene Sheet see PR-T-79-011 (TR-466)-page 2-19 3.0 Containment see PR-T-79-Oll (TR-466) page 3-1 4.0 Shielding see PR-T-79-Oll (TR-466) page 4 s ii
5.0 Criticality Evaluation 5.1 Primary Criticality Analysis 5.2 Independent Criticality Analysis 6.0 Operating Procedures see PR-T-79-011 (TR-466) page 6-1 6.1 Procedure For Loading see PR-T-79-Oli (TR-466) page 6-1 6.2 Procedure For Unloading see PR-T-79-Oll (TR-466) page 6-2 6.3 Preparation of Empty Package For Transport see PR-T-79-Oli (TR-466) page 6-3 7.0 Acceptance and Maintenance Program see PR-T-79-011 (TR-466) page 7-1 7.1 Acceptance Tests see PR-T-79-Oli (TR-466) page 7-1 7.2 Maintenance Program see PR-T-79-Oli (TR-466) page 7-1 7.3 Inspection / Maintenance Plan see PR-T-79-011 (TR-466) page 7-2 7.3.1 Objective see PR-T-79-Oll (TR-466) page 7-2 7.3.2 Procedure see PR-T-79-011 (TR-466) page 7-2 8.0 Quality Assurance see PR-T-79-011 (TR-466) page 8-1 8.1 Determination of Intact Cadmium Sheets 8.2 ETR Fuel Element Container Cadmium Inspection with Neutron Source Appendix A s
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4 0.0 General Information 0.1
==
Introduction:==
The ETR Fuel Element' Shipping Containers are used for the transport of fuel elements for the Engineering Test Reactor (ETR) operated by EG&G Idaho at the Idaho National Engineering Laboratory (INEL). The containers were analytically evaluated to determine their compliance with ERDA 0529 and 10CFR71 governing containers in which fissile materials are transported.
Those tests and evaluations are reported in USA /5705/AF (ERDA-ID) "ATR Fuel Element Shipping Centainers Safety Analysis," Report No. PR-T-79-Oll (TR-466).
,1 Those characteristics which are unique to the ETR container are discussed
.i 1
in this' report. Tne results show that the ETR containers comply with the applicable regulations.
When fissile or radioactive materials are transported, the packaging 0
and contents must meet standards specified in ERDA Manual Chapter 0529,
" Safety Standards for the Packaging of Fissile and Other Radioactive Materials,"
/
its Appendix and also Title 10, Part 71 of the Code of Federal Regulations, V
Packaging of Radioactive Material for Transport to assure protection of the public health and safety. These standards state the reouirements for criticality safety, structural integrity, thermal and shielding capabilities, quality assurance and maintenance and operating instructions. Any package used for the transport of fissile material must be shown to meet these standards, by test or computational methods, before issuance of a Certificate of Compliance. The tests and computational analysis of the ETR Fuel Element Shipping Container to determine compliance with the above standards, as a Type A quantity, Fissile Class 1 container, are reported herein.
0.2 Package Description The ETR Fuel Element Shipping Container is used for shipping new, unirradiated fuel elements from the supplier to the Engineering Test DRR 20919 l Reactor (ETR) at the Idaho National Engineering Laboratory (INEL).* Each container (Nos. 1 through 23) is designed to transport, in a horizontal position 6 ETR fuel elements, in two layers of 3 elements.
Each fuel element contains approximately 500 grams of U-235. The container as shown in figure 1, actually consists of two containers, one inside of the ather.
The inner container, drawing ETR E-1012, is the container originally de igned for the transportation of ETR fuel elements.
It is constructed mainly of 16 gauge steel covering 3/4-inch fire resistant, exterior plywood.
Cadmium sheets.020-inches thick are used for neutron absorption and are located above, below, and:along both sides of the container.
In addition two sheets of cadmium are placed as a spacer between the two layers of fuel elemer.ts. One-quarter inch polyethylene sheets are located external to the upper and louer cadmium 'heets for neutron moderation. Two sheets s
of 1/4-inch polyethylene ~ and one sheet of 1/2-inen polyethylene are placed between the two cadmium sheets'of the spacer, also for neutron moderation.
The lid is held shut by pinned steel hinges.
DRR l
- May also be used to ship from one supplier to another.
20919 i
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i The external dimensions of the inner container are 56.75 inches long by 16.5 inches wide by 10.8 inches high. The cavity is 51.25 inches long by 14.75 inches wide by 8.1 inches high, and contains a spacer 51.1 inches long by 14.75 inches wide by 4.9 inches high. By using the spacer, 6 chlindrical compartment are formed in the inner container for fuel elements or control rod follower pieces.
The outer container was designed to enable the complete package to meet the requirements of ERDA Appendix 0529.
It is constructed by using 18 gauge steel-covered 1-inch exterior, fire resistant plywood, with a steel sheathed 31/2-inch thick aluminum honeycomb shock absorber at each end. The lid is secured to the body by four carbon steel hinges, the leaves of which are welded to the sides of the lid and body near the ends of the lid, 4
The external dimensions of the outer container are 71 inches long.
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by 21.25 inches wide by 15.38 inches high. The cavity is 57 inches long by 17 inches wide by 11.4 inches high.
For lid lifting purposes there are four 20-inch, 60* sections of 4-inch, schedule 49 steel pipe welded to the lid of the outer container.
Each pipe section has three 0.19-inch gusset plates welded between the
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pipe section and lid section at even spaces.
Figure l'shows the shipping
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0.3 Authorized Contents of Packaging The authorized contents and limits are as follows:
0.3.1 Fissile Material Limits The ETR Fuel Element Shipping Containers are authorized for Fissile Class I transport with the following limits:
(a) One solid, unirradiated fuel elemen't er control roc follower piece in each of six compartments, provided they contain no more than 520 grams of uranium-235 per element or follower piece.
DRR 20919 Authorized unirradiated fuel elements:
(a) ETR (b) GETR (c) University elements EG&G Drawing Nos.
(1) Massachusetts Institute of Technology (MIT) 410371 (2) Rhode Island 411650 (3) Virginia:
Standard 409338 Control 409339 Partial 409340 (4) Michigan 409418 (5) Lowell 411650 (b) The uranium must be maintained withi the longitudinal region of the box which contains the cadmium.
(See Appendix A for ETR box insert drawings and Criticality Analyses.)
0.3.2 Radioactivity Limits Refer to P-T-79-Oli (TR-466) page 0-4 0.3.3 Physical and Chemical Form Refer to PR-T-79-Oll (TR-466) ~ page 0-4 0.3.4 Heat Generation Refer to FR-T-79-011 (TR-466) page 0-4
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l 0.4 Administrative Controls Refer to PR-T-79-Oll (TR-466) page 0-4 1.0 Structural Evaluation Refer to PR-T-79-01i (TR-466) page 1-1 1.1 Structural Design Refer to PR-T-79-Oli (TR-466) page 1-1,-
l.2 Weights and Centers of Gravity The Total calculated shipping weight (including fuel element) of the ETR container is 690 pounds. The weight of the contents for fissile shipments other than ETR fuel elements, is unknown. However, the space available for the contents is sufficiently small that gross weight variations will not be large enough to invalidate the stress analysis.
The center of gravity is essentially the geometric center of the container, excluding skids.
1.3 Codes and Standards Refer to PR-T-79-011 (TR-466) page 1-2 1.3.1 Mechanical Properties Refer to PR-T-79-011 (TR-466) page 1-2) 1.4 Compliance with General Standards for all Packaging 1.4.1 Chemical and Galvanic Reactions Refer to PR-T-79-Oll (TR-466) page 1-3 1.4.2 Positive Closure Refer to PR-T-79-Oll (TR-466) page 1-3 1.4.3 Lifting Devices Refer to PR-T-79-Oll (TR-466) page 1-3 1.4.4 Tie Down Devices Refer to PR-T-79-Oli (TR-466) page 1-3 1.5 Standard for Type B and Large Quantity Packaging Refer to PR-T-79-Oli (TR-466) page 1-3 1.6 Compliance with Standards for Normal Conditions of Transport Refer to PR-T-79-Oli (TR-466) page 1-4 1.6.1 Heat Refer to PR-T-79-011 (TR-466) page 1-4 1.6.2 Cold' Refer to PR-T-79-011 (TR-466) page 1-4 _.
l.6.3 Pressure Refer to PR-T-69-Oli (TR-466) page 1-4 1.6.4 Vibration Refer to PR-T-79-Oli (TR-466) page 1-5 1.6.5 Water Spray Refer to PR-T-79-011 (TR-466) page 1-5 1.6.6 Free Droq Refer to PR-T-79-Oli (TR-466) page 1-5 1.6.7 Corner Orop Refer to PR-T-79-Oli (TR-466) page 1-6 1.6.8 Penetration Refer to PR-T-79-Oll (TR-466) page 1-6 1.6.9 Compression Refer to PR-T-70-Oll (TR-466) page 1-7 1.7 Compliance with Standards for Hypothetical Accident Conditions of Transport Refer to PR-T-79-Oll (TR-466) page 1-8 1.7.1 Free Drop Refer to PR-T-79-Oll (TR-466) page 1-9 1.7.2 Puncture Refer to PR-T-79-Oll (TR-466) page 1-10 1.7.3 Thermal Refer to PR-T-79-Oll (TR-466) page 1-16 1.7.4 Water Immersion Refer to PR-T-79-Oli (TR-466) page 1-16 1.7.5 Summary and Conclusion Refer to PR-T-79-Oli (TR-466) page 1-18
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i 1.8.2 ImoactCalcul'ationsfor'PdtectiveContainer Refer to PR-T-79-011'(TR-466) page 1 1.8.3 Hand 1d Liftina Calculations
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Refer to PR-T-79-011 (TR-466) page 1-33 1.8.4 References Refer to PR-T-79-011'(TR-466) page 1-47 l
2.0 Thermal Evaluation Refer to PR-T-79-011 (TR-466) page 2-1 2.1 Discussion Refer to PR-T-79-011 (TR-466) page 2-1 2.2 Summary of Thermal Properties of Materials Refer to PR-T-79-011 (TR-466) page 2-1 2.3 Technical Specifications of Components 7
Refer to' PR-T-79-011 (TR-466) page 2-1 2.4 Thermal Evaluation for Normal Conditions of Transport Refer to PR-T-79-011 (TR-466) page 2-1 2.5 Hypothetical Thermal Accident Evaluation
- i Refer to PR-T-79-011 (TR-466) page 2-6 b
2.5.1 MTR Container i
Refer to PR-T-79-011 (TR-466) page 2-7 2.5.2 Analytical Methods l
Refer to PR-T-79_-011 -(TR-466) -page 2-11 2.5.3 MTR Container with Outer Container
~ Refer to PR-T-79-011- (TR-466) page 2-12 2.5.4 ATR Container
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- Refer to' PR-T-79-011 (TR-466).page 2-15 2.6 Appendix
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2.6.1. - Thermal Test on Polyethelene Sheet Refer to PR-T-79-011 (TR-466)_ page 2-19,
3.0 Containment Refer to PR-T-79-Oll (TR-466) page 3-1 4.0 Shielding Refer to Pr-T-79-Oll (TR-466) page 4-1 5.0 Criticality Evaluation 5.1 Primary Criticality Analysis In order to rule out criticality of dry arrays of the ETR containers, a density analog calculation was run. The results, with conservative parameters, indicated that it would require over one million elements for criticality. Thus the only plausible conditions under which criticality could occur would be that of flooding without intact cadmium plates.
There would have to be complete submergence in order to fill up the most important spaces, i.e. that between the fuel plates. The paramount requirement for the containers is that none of the cadmium be melted out.
One calculation was made utilizing the ETR container with both the top and bottom layers of cadmium melted leaving only the cadmium plates between the bottom and top layers of fuel rods.
The Keff with 678 grams per element ETR fuel was 1.06 and dropped to.975 when the fuel loading-was dropped to 500 grams per element. The criticality of the ETR containers has been analyzed assuming flooded conditions and with the cadmium intact.
The Keff for an infinite array of heavily loaded fuel (456 gm per foot),th was 0.877. An additional calculation was made on the modified container wi of.64.y) fuel separation and using the same loading.
This gave a Keff the add It can be seen that since the hypothetical accident will not adversly affect the structural integrity of the container, an infinite array of containers subjected to the accident and loaded with authorized contents listed in Section 0.3 using the administrative controls listed in 0.4 will remain suberitical with optimum moderation.
5.2 Independent Criticality Analysis Independent criticality calculations on the ETR Fuel Element Shipping Containers were April 301968, (gported by J. K. Fox in a letter to Dr. F. H. Tingey and are stated in this report.
I CI-1086, Protective Shipping Packages for Radioactive and Fissile
!!aterial Containers, by D. A. Tobias, etal,1968, pg 10.
O l !
E
The calculational model was a conservative approximation of the actual shipping container. The containers were modeled to be in an infinite array in the x and y dimensions, with the length (z dimension) of each box and the fuel element therein, being infinitely long. Fissile material loading was the same as that used in the primary criticality analysis, that is, 456 grams of U-235 per foot. The fuel elements in the container were modeled with a separation of 50mm (2 in). Two cal-culations were performed.
In one case all open spaces in the model were filled with water.
In the second case only the ETR e.lement itself contained any water in its interstitial spaces. The calculations were performed with the PDQ code using four-group PHROG and TEMPEST generated cross sections. Values of Xeff for the two types of calculations were 0.69 and 0.66 respectively.
These calculations were originally reviewed by the fluclear Safety -
Committee in 1968. An independent review by EG&G Safety Division was conducted in June 1979 on both the primary and secondary criticality analysis reported herein. Their conclusion was that the original analysis was valid and that an infinite array of containers subjected to the hypothetical accident will remain subcritical with optimum moderation.
6.0 Operating Procedures Refer to PR-T-79-Oll (TR-466) page 6-1 6.1 Procedure for Loading Refer to PR-T-79-011 (TR-466) page 6-1 6.2 Procedure for Unloading Refer to PR-T-79-Oll (TR-466) page 6-1 6.3 Preparation of Empty Package for Transport Refer to PR-T-79-Oll (TR-466) page 6-3 7.0 Acceptance and Maintenance Program Refer to PR-T-79-Oll (TR-466) page 7-1 7.1 Acceptance Tests Refer to PR-T-79-Oll (TR-466) page 7-1 7.2 flaintenance Program Refer to PR-T-79-Oll (TR-466) page 7-1 (2) J. K. Fox letter to Dr. F. H. Tingey, JKF-6-68, " Criticality Considerations
~
of the flew Shipping Container, April 30, 1968.
J -.
7.3 Inspection / Maintenance Refer to PR-T-79-Oll (TR-466) page 7-1 7.3.1 Objective Refer to PR-T-79-Oll (TR-466) page 7-2 7.3.2 Procedure Refer to PR-T-79-Oll (TR-466) page 7-2 8.0- Quality Assurance Refer to PR-T-79-Oll (TR-466) page 8-1 8.1 Determination of Intact Cadmium Sheets
'" ~EG_&G. Quality Division made a visual inspection of all ETR Fuel Element Shipping Containers in July 1979 to determine whether or not the cadmium sheets were intact. All sheets were in place in accordance with applicable drawings.
In addition, a random selection of three containers were subjected to inspection using a 5 curie neutron source and an Eberline neutron detector to check for presence of cadmium. As can be seen in Appendix 8.2, ETR Fuel Element Shipping Container Cadmium Inspection with Neutron Source, all cadmium sheets are in place and intact in accordance with applicable drawings.
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8.2 ETR Fuel Element Shipping Container Cadmium Inspection with Neutron Source i
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O-lp E G e G usano
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~ a INTEROFFICE CORRESPONDENCE July 25, 1979 u.
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D. Wadsworth
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ETR FUEL ELEMEllT SHIPPIttG C0rtTAItlERS - CMA-4-79 ETR Fuel Element Shipping Containers Nos.
1, 9, and 19 were checked for cadmium on July 19, 1979. Mock-ups of the containers were made with and without cadmium. Materials used for the mcck-ups and all measurements were observed by L. V. Wages and I. E. Stepan.
Readings were taken using a 5 curie Pu Be source and a calibrated Eberline Instrument Corporation, MODEL NC-1 Serial No.101, neutron detector.
All measurements were done in accordance with drawings of the containers and all of the data which is attached would indicate cadmium being present as per drawings.
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REFERENCES (1) CI-1086, Protective Shipping Packages for Radioactive and Fissile Material Containers, by D. A. Tobias, March 1968.
(2) PR-T-79-Oll (TR-466), ATR Fuel Element Shipping Container Safety Analysis, by C. E. Friedrich and D. R. Swope, June 1975.
(3)
J. K. Fox letter to Dr. F. H. Tingey, JKF-6-68, " Criticality Considerations of the New Shipping Container, April 30, 1968.
(4)
D. M. Anderson letter to D. Wadsworth, DMA-4-79, "ETR Fuel Element Shipping Containers," July 25, 1979.
D 16
APPENDIX A DRR 20919 for Appendix A j
o A-1
i hEGaGsaano INTEROFFICE CORRESPONDENCE Date:
September 3, 1982 To:
M. A. Thom From:
H. A. Worle
Subject:
FEASIBILITY OF TRANSPORTING VARIOUS ALUMINUM PLATE TYPE FUEL ELEMENTS IN ETR SHIPPING B0XES - Worle-4-82 Refs:
(a)
M. C. Smith, ETR Puel Element Shipping Container Addendwn to PR-T-79-021 (TR-466), PR-T-79-012, August 7,1979 (b)
J. K. Fox ltr to Dr. F. H. Tingey, JKF-6-68, Criticality Considerations of the New Shipping Container, April 30, 1968 Per your request I have reviewed your proposal to use ETR shipping boxes, covered by Certificate of Compliance number 9134, for the shipment of various university research reactor fuel elements. The elements are roughly characterized by the data given in Table 1.
All the element are aluminum plate type fuel, and all except one have fuel contents which are between one fourth and one half that of the ETR elements.
Generally, the fuel region of these elements is smaller in volume than for the ETR element, and for all but the one labeled MIT in Table 1, the linear fuel density, measured in grams of uranium-235 per unit length, is also smaller.
The calculations leading to the approval of ETR shipping boxes for ETR and GETR fuel elements [ reported in Reference (a)] modeled these elements as uniform mixtures of the element constituents and water.
In this connection, the volume and composition of the mixture are the important factors. The ETR element was modeled as a cuboid of the same cross section as the actual element, but with a fissionable material loading of 456 grams uranium-235 per linear foot of element length. The length of this cuboid was modeled as infinite, with an infinite array of such infinitely long boxes, each box containing six elements.
The model described in the previous paragraph is very conservative when applied to ETR fuel elements. The conservatism is much larger when the model represents the fuel elements listed in Table 1.
This is true even for the case of the element designated as MIT. Although this element has a 1%
greater total fissile material content than standard ETR elements, it is even more under-moderated than these elements and occupies a smaller volume.
Several computer calculations were performed with the KENO IV computer code to reproduce the results of the independent analysis [ Reference (b)] for the ETR boxes. The model of Reference (b) was altered in the series of cal-l culations to simulate varying degrees of moderation by varying water density aca ecao m A-3
- .. mn
M. A. Thom September 3, 1982 Worle-3-82 j
Page 2 from 100% to 0% theoretical density. Results are given in Table 2, along with the results cited in Reference (b). They indicate reasonable agreement between the two sets of calculations.
1 A further computer calculation using the more realistic fuel loading of 520 g uranium-235 per ETR fuel element was performed. The result of this, also included in Table 2 indicate the degree of conservatism employed in the original model.
The above findings show that the existing analyses for the transport of ETR and GETR element in the ETR shipping boxes are applicable to the transport of the fuel elements listed in Table 1.
When used for these elements, however, care must be taken that the fuel regions do not extend beyond the region in 3
the box containing the cadmium liner. This could be accomplished with blocks of wood or other material, at.the same time immobilizing the element in its storage position.
The above review should be used as the basis to request an expansion of cer-tificate of compliance No. 9134 to include the elements listed in Table 1.
Note that only the list of approved elements in Section 5(b)(1) need be changed in that certificate.
j If we can be of further assistance in requesting this change from DOE-ID, please feel free to contact me.
ib cc:
R. U. Curl A$
B. L. Rich ^Fr) H. R. Orme A. D. Summers (r) CSG file Central File J. L. Clark (r) G. R. Norman J. D. Ford B. L. Rich file 4
CONCURRENCE:
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Table 1.
Descriptive Parameters of Variables UA Type Fuels MIT RI M
Lowell MI ETR 235 Total U (g) 506 125 220 125 140 500 Enrichment (%)
93 93 93 93 93 93 Chemical Comp.
UAt UAt UAt
- UAt, UA t,
- UAt, x
x Cross Section Dim (mm) 63.5x68.6 76.2x76.2 74.7x82.6 76.2x76.2 74.8x82.5 76.2x76.2 Element ler7th (mm) 660 1003 864 1003 873 1378 Fuel Meat Din.(ave.)
Thickness (mm) 0.76 0.51 0.51 0.51 0.51 0.51
}
Width (mm) 52.7 57.8 47.0 57.8 47.0 62.1 Length (mm) 568 578 610 578 61 0 914 Gap between plates (mm) 1.98 2.54 3.2 2.54 3.05 2.77 n
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Linear fuel density (g/ft) 271.5 66 110 66 70 167 b
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Table 2.
Results of Infinite Array Calculations Calculation k,ff Reference (b)(drainedarray) 0.66' Reference (b) (flooded array) 0.69 KEN 0 (flooded array) 0.638 1 0.007 KEN 0 (80% H O density) 0.659 1 0.009 2
KEN 0 (60% H 0 density) 0.655 1 0.008 2
KEN 0 (40% H O density) 0.662 1 0.007 2
KEN 0 (20% H O density) 0.680 1 0.006 2
KEN 0 (0% H O density) 0.586 1 0.006 2
KENO (flooded array 520 g/ element) 0.489't 0.005 e
- A-6 ua..
a-&
degas idaho INTEROFFICE CORRESPONDENCE Date:
September 17, 1982 To:
M. A. Thom H. A. Worle h From:
Subject:
APPLICABILITY OF ETR SHIPPING BOX REVIEW - Worle-5-82 Ref:
H. A. Worle 1tr to M. A. Thom, Worle-4-82, Feasibility of Transporting Various Aluminum Plate Type Fuel Elements in ETR Shipping Boxes, September 3,1982 My earlier communication to you, above reference, mentioned a Certificate of Compliance No. 9134. That certificate was issued by the Nuclear Regulatory Commission. The ETR shipping boxes in question are also covered by a certifi-cate issued by the Department of Energy. That is Certificate of Compliance No. USA /57051/AF(DOE-ID) Rev. 1.
All comments in my earlier communication (above reference) referring to the NRC certificate also apply to the ETR box parts of the DOE certificate (The DOE certificate addresses both ATR and ETR boxes).
I apologize for this oversight in my previous letter.
ib cc:
R. U. Curl J. D. Ford B. L. Rich (r) H. R. Orme A. D. Summers (r) CSG file J. L. Clark (r) G. R. Norman Central File H. A. Worle file (2) e A-7
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