ML24150A207

NAC International - NAC-LWT, Legal Weight Truck Cask System, Safety Analysis Report, RAI Responses LANL MOX, Revision 24B, Non-Proprietary Version

ML24150A207
Person / Time
Site:	07109225
Issue date:	04/30/2024
From:	NAC International
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML24150A205	List: ML24150A206 ML24150A207
References
ED20240054
Download: ML24150A207 (1)

Text

April 2024 Docket No. 71-9225 Revision 24B NAC-LWT Legal Weight Truck Cask System SAFETY ANALYSIS REPORT RAI Responses LANL MOX NON-PROPRIETARY VERSION Atlanta Corporate Headquarters: Two Sun Court, Suite 220, Peachtree Corners, Georgia 30092 USA Phone 770-447-1144, www.nacintl.com

NAC-LWT Docket No. 71-9225 Page 1 of 7 ENCLOSURE 1 NAC INTERNATIONAL RESPONSES TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION REQUEST FOR ADDITIONAL INFORMATION FOR REVIEW OF THE CERTIFICATE OF COMPLIANCE NO. 9225, NAC-LWT PACKAGE TO INCORPORATE LANL MOX FUEL (DOCKET NO. 71-9225)

April 2024

NAC-LWT Docket No. 71-9225 Page 2 of 7 TABLE OF CONTENTS Page GENERAL INFORMATION....................................................................................................................... 3 STRUCTURAL EVALUATION................................................................................................................. 4

NAC-LWT Docket No. 71-9225 Page 3 of 7 NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION GENERAL INFORMATION 1.0 Clarify the basis for the transfer tube top end spacer requirement to sit below the top of the transfer tube weldment by greater than or equal to the dimension shown in Note 3 of Drawing No. 315-40-188, revision 1P.

The staff is unclear whether this requirement is included to ensure the transfer tubes meet analyzed design requirements, or for ease of operations to ensure the top end spacer will be able to be inserted far enough to preclude interference with the PWR/BWR Rod Transport Canister lid. If the requirement is necessary to ensure design requirements are met, modify the operational steps in section 7.1.22 of the application to verify compliance before shipment.

This information is needed to determine compliance with Title 10 of the Code of Federal Regulations (10 CFR) Section 71.51.:

NAC International Response to General Information RAI 1.0:

This requirement was included to ensure that the transfer tube contents (i.e. fuel rod(s) and spacers) remain within the length of transfer tube cavity. This ensures no interference with pin can lid and that the weight of the transfer tube does not load the contents in the event of an end impact. The operational steps in section 7.1.22 have been revised to include verification that this requirement is met prior to shipment.

NAC-LWT Docket No. 71-9225 Page 4 of 7 NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION STRUCTURAL EVALUATION 2.1.

Provide the calculation package, NAC Calculation No. 14629-315-2000, Rev. 2, LWT Pin Shipment Can Assembly Structural Analysis."

Section 1.0, Synopsis of Results, of the package, Structural Evaluation of LANL MOX Transfer Tube Shipping Configuration for the NAC-LWT Transport Cask, in of the application (Reference 1) indicates that the NAC Calculation No.

14629-315-2000, Rev. 2 bounds the evaluation for the LWT Can Assembly containing the LANL MOX content for normal conditions of transport (NCT) and hypothetical accident conditions of transport (HAC). Provide the calculation package for completion of the staffs review.

This information is needed by the staff to determine compliance with 10 CFR 71.73(c)(1).

NAC International Response to Structural Evaluation RAI 2.1:

NAC Calculation No. 14629-315-2000, Rev. 2, LWT Pin Shipment Can Assembly Structural Analysis, is provided in Enclosure 3.

NAC-LWT Docket No. 71-9225 Page 5 of 7 NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION STRUCTURAL EVALUATION 2.2.

Provide responses to the following questions related to the package, Calculation No.

50077-2002, Rev. 0, in Enclosure 2 of the application (Reference 1) and Subsection 2.6.12.18, LANL MOX Fuel Transfer Tubes and Divider Plates, and Subsection 2.7.7.20, LANL MOX Fuel Transfer Tube and Divider Plate, of Revision 24A of the SAR, in Enclosure 5 of the application:

a.

Two-dimensional (2-D) structural analyses were performed using the ANSYS finite element (FE) program to demonstrate structural integrity of the divider plate under normal conditions of transport (NCT) and hypothetical accident conditions (HAC).

Provide the engineering assumptions made for the analyses (e.g., theories of plane stress, plane strain, elasticity, plasticity, etc.).

b. The divider plate is a three dimensional (3-D) structural component in X-, Y-and Z-directions, not a 2-D component in X-and Y-directions. Justify that why the 2-D analyses are more realistic and conservative than 3-D analyses to characterize the performance of the divider plate for drops (end, side and oblique) under NCT and HAC.

c.

Drawing No. 315-40-188-01 shows a cross sectional view of the NAC-LWT shipping configuration of LANL MOX fuel rod and Figure A-1 in Calculation No.: 50077-2002, Rev. 0 shows the ANSYS FE mesh used for the flat side drop analyses of the divider plate under NCT and HAC, which are from Enclosures 5 and 2 of the application, respectively (Reference 1):

i.

Indicate whether a spacer provided in a gap between a divider plate and a rod transfer can assembly wall is a full-or partial-support spacer (length and width)?

ii.

What are the magnitudes of the forces applied at the nodal points in the FE mesh for the flat side drop and oblique drop analyses under HAC?

iii.

What are the corresponding induced maximum membrane and bending stresses of the cross section at the end of the divider plate when it impacts the wall for both flat side drop and oblique drop analyses under HAC?

iv.

What is the purpose of placing the divider plate in the rod transfer can assembly? The rod transport canister assembly contains 16 transfer tubes (Drawing No. 315-40-189) loaded with the LANL MOX fuel rods. If a divider

NAC-LWT Docket No. 71-9225 Page 6 of 7 plate (Drawing No. 315-40-189) is used to maintain the position of the transfer tubes (four in each quadrant) inside the rod transport canister, explain how the position of those four transfer tubes in a quadrant are maintained under HAC?

v.

Demonstrate that stability (i.e., buckling) of the LANL MOX fuel rod cladding in a quadrant is maintained during an end drop under HAC.

This information is needed by the staff to determine compliance with 10 CFR 71.73(c)(1).

Reference:

1.

The NAC Application for Revision 74 to Certificate of Compliance No. 9225 for the Model NAC-LWT Package, Docket No. 71-9225, January 11, 2024:

• Enclosure 2 - List of Calculations, NAC-LWT SAR, Revision 24A,

• Enclosure 4 - List of Drawing Changes, NAC-LWT SAR, Revision 24A, and

• Enclosure 5 - NAC-LWT, LOEP and SAR Pages Revision 24A.

NAC International Response to Structural Evaluation RAI 2.2:

NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Docket No. 71-9225 Page 7 of 7 NAC International Response to Structural Evaluation RAI 2.2 (continued):

NAC PROPRIETARY INFORMATION REMOVED

ED20240054 Page 1 of 3 No. 71-9225 for NAC-LWT Cask Proposed Changes for Revision 75 of Certificate of Compliance LANL MOX Fuel NAC-LWT SAR, Revision 24B April 2024

ED20240054 Page 2 of 3 CoC Sections (revised)

CoC Page 4 of 34 5.(a)(3)(ii)

Drawings (continued) 315-40-188, Rev 1P, LWT TRANSPORT CASK SHIPPING CONFIGURATION, LANL MOX 315-40-189, Rev 1P, TRANSFER TUBE DETAILS, LANL MOX CoC Sections (new)

CoC Page 20 of 34 5.(b)(1)

Type and form of material (continued)

(xxiv) LANL MOX Fuel Rods Parameter PNNL EXXON UO2 ROD 1063 530-000 NIS5 Max. rod OD (inch) 0.565 0.451 0.229 0.55 0.63 0.5 Min. wall thick. (inch) 0.035 0.035 0.015 0.015 0.015 0.015 Rod material Zr Alloy Zr Alloy SS304 Zr Alloy Zr Alloy SS316 Max. active length (inch) 35.6 70 36.1 47.913 18 13.5 Max. pellet OD (inch) 0.486 0.372 0.1988 0.48 0.56 0.31 Max. # of rods per transfer tube 4

2 8

3 1

3 Max. # of tubes per cask 16 16 16 6

1 4

Fuel form Oxide Oxide Oxide Oxide Oxide or Carbide Carbide 235U wt%

0.712 0.712 94 0

0 94 240Pu wt%1 16 16 0

10 10 4

Pu wt%

5.36 6.31 0

100 100 20 U-235 (g/rod) 6.76 7.71 159.9 0

0 159.58 U (g/rod) 949.85 1083.44 170.11 0

0 169.76 Pu (g/rod) 56.29 76.35 0

1378.77 922.01 42.38 Total U/Pu (g/rod) 1006.14 1159.79 170.11 1378.77 922.01 212.14 1 Fissile Pu-239 and Pu-241 comprise the remaining plutonium. A 9 to 1 ratio of Pu-239 to Pu-241 is used.

ED20240054 Page 3 of 3 CoC Page 31 of 34 5.(b)(2)

Maximum quantity of material per package (continued)

(xxv)

For LANL MOX Fuel Rods, as described in Item 5.(b)(1)(xxiv):

Up to sixteen (16) transfer tubes filled with LANL MOX Fuel Rods can be loaded in the PWR/BWR transport can assembly. Different LANL MOX fuel types may be loaded in the same package but only one fuel type may be loaded into any one Transfer Tube (up to 16 transfer tubes containing PNNL, EXXON, or UO2 fuel rods may be mix loaded into a cask; up to 6 transfer tubes containing ROD1063 fuel rods may loaded into a cask but shall not be mix loaded with other materials in the cask; up to 4 transfer tubes of NIS5 and up to one transfer tube of 530-000 may be mixed loaded in a cask). If needed for operational convenience a Divider Assembly may be used to segregate Transfer Tubes. A Transfer Tube spacer is required at the top and bottom end of any transfer tube loaded with fuel rods. Transfer Tube spacers may be used to separate contents but are not required. As required, empty transfer tubes with or without spacers shall be loaded such that the total number of transfer tubes in the PWR/BWR transport can assembly is sixteen (16). The maximum total heat load per cask is limited to 25 watts.

CoC Page 32 of 34 5.(c)

Criticality Safety Index For, LANL MOX Fuel Rods described in 5.(b)(1)(xxiv) and limited in 5.(b)(2) (xxv) 25.0

ED20240054 Page 1 of 2 No. 71-9225 for NAC-LWT Cask List of Calculations NAC-LWT SAR, Revision 24B April 2024

ED20240054 Page 2 of 2 List of Calculations, NAC-LWT SAR, Revision 24B Contents:

1. 14629-315-2000, Rev. 2

2. 50077-2002, Rev. 1

3. 50077-6001, Rev. 3 CALCULATIONS WITHHELD IN THEIR ENTIRETY PER 10 CFR 2.390

ED20240054 Page 1 of 3 No. 71-9225 for NAC-LWT Cask List of SAR Changes NAC-LWT SAR, Revision 24B April 2024

ED20240054 Page 2 of 3 List of SAR Changes, NAC-LWT SAR, Revision 24B Chapter 1

Page 1-ii, modified List of Figures to reflect a change in the chapter where indicated.

Page 1-iii, modified List of Tables to reflect a change in the chapter where indicated.

Page 1-vi, modified List of Drawings to reflect a change in the chapter where indicated.

Page 1-6, modified text in Table 1.1-1 where indicated.

Page 1.1-4, modified text in last paragraph where indicated.

Page 1.2-22, modified text in last paragraph where indicated.

Page 1.2-23, modified text where indicated.

Page 1.2-24 thru Page 1.2-68, text flow change.

Page 1.2-69, modified Table 1.2-20 where indicated.

Chapter 2

Page 2-iii, modified Table of Contents to reflect changes in the chapter where indicated.

Page 2-iv, modified Table of Contents to reflect changes in the chapter where indicated.

Page 2-ix, modified List of Figures to reflect a change in the chapter where indicated.

Page 2.2.1-3, modified text in column 2 of Table 2.2.1-1 where indicated.

Page 2.2.1-5, modified text in column 2 of Table 2.2.1-2 where indicated.

Page 2.6.12-2, modified in first full paragraph where indicated.

Page 2.6.12-125, modified text near the top of Section 2.6.12.15 where indicated.

Page 2.6.12-147, modified Sections 2.6.12.18 and 2.6.12.18.1, and deleted last row of embedded table in section 2.6.12.18.1 where indicated.

Page 2.6.12-148, modified the 1st paragraph in Section 2.6.12.18.2, and deleted all remaining text in section where indicated.

Page 2.6.12-149, modified text in Section 2.6.12.19 where indicated.

Page 2.7.7-110, modified Sections 2.7.7.20 and 2.7.7.20.1, and deleted last row of embedded table in section 2.7.7.20.1 where indicated.

Page 2.7.7-111, modified 1st and 3rd paragraphs on the page, and deleted all remaining text in section where indicated.

Chapter 3

Page 3.1-2, modified paragraph in the middle of the page where indicated.

Chapter 4

No changes.

ED20240001 Page 3 of 3 Chapter 5

No changes.

Chapter 6

Page 6-viii, modified List of Figures to reflect changes within the chapter where indicated.

Page 6-xix, modified List of Tables to reflect changes within the chapter where indicated.

Page 6.7.7-1, modified text in last the paragraph of the page where indicated.

Page 6.7.7-3, replaced illustrations in Figure 6.7.7-1.

Page 6.7.7-6, modified text in Section 6.7.7.3 and added new heading 6.7.7.3.1 where indicated.

Pages 6.7.7-7 thru 6.7.7-10, modified text near the middle of the page and added new Section 6.7.7.3.2; added new heading 6.7.7.3.3 and modified additional text where indicated.

Page 6.7.7-11, replaced Figure 6.7.7-3.

Pae 6.7.7-12 thru 6.7.7-16, added new Figures 6.7.7-4 thru 6.7.7-8.

Page 6.7.7-17, modified text in column 3 of Table 6.7.7-3; replaced Table 6.7.7-4; modified text in column 3 of Tables 6.7.7-5 thru 6.7.7-6 where indicated.

Page 6.7.7-18 thru 6.7.7-19 modified text in column 3 of Table 6.7.7-7; replaced or added new Tables 6.7.7-8 thru 6.7.7-14 where indicated.

Chapter 7

Page 7.1-94, modified text in the first paragraph of Section 7.1.22 where indicated.

Page 7.1-95, modified text in the first two paragraphs near the top of the page in Section 7.1.22 where indicated.

Page 7.1-96, modified Items 19 and 23 where indicated.

Page 7.1-97, added new Item 25 where indicated.

Page 7.1-98, text flow changes.

Chapter 8

No changes.

Chapter 9

Page 9-8, corrected a typographical error which called out 1987 instead of 1997 version of the code.

ED20240054 Page 1 of 2 No. 71-9225 for NAC-LWT Cask List of Drawing Changes NAC-LWT SAR, Revision 24B April 2024

ED20240045 Page 2 of 2 List of Drawing Changes, NAC-LWT SAR, Revision 24B 315-40-188, LWT TRANSPORT CASK SHIPPING CONFIGURATION, LANL MOX, Rev 2P 315-40-189, TRANSFER TUBE DETAILS, LANL MOX, Rev 3P NAC PROPRIETARY INFORMATION REMOVED

ED20240054 No. 71-9225 for NAC-LWT Cask List of Effective pages and NAC-LWT SAR, Revision 24B April 2024

April 2024 Docket No. 71-9225 Revision 24B NAC-LWT Legal Weight Truck Cask System SAFETY ANALYSIS REPORT Volumes 1 thru 3 Changed Pages NON-PROPRIETARY VERSION Atlanta Corporate Headquarters: Two Sun Court, Suite 220, Peachtree Corners, Georgia 30092 USA Phone 770-447-1144, www.nacintl.com

NAC-LWT Cask SAR April 2024 Revision 24B LIST OF EFFECTIVE PAGES Page 1 of 4 Chapter 1 1-i............................................... Revision 47 1-ii thru 1-iii............................. Revision 24B 1-iv thru 1-v............................... Revision 47 1-vi........................................... Revision 24B 1-1 thru 1-3............................. Revision 24A 1-4 thru 1-5................................ Revision 47 1-6............................................ Revision 24B 1-7........................................... Revision 24A 1-8 thru 1-9................................ Revision 47 1-10......................................... Revision 24A 1.1-1........................................... Revision 47 1.1-2........................................ Revision 24A 1.1-3........................................... Revision 47 1.1-4......................................... Revision 24B 1.2-1 thru 1.2-4.......................... Revision 47 1.2-5........................................ Revision 24A 1.2-6........................................... Revision 47 1.2-7 thru 1.2-11..................... Revision 24A 1.2-12 thru 1.2-21...................... Revision 47 1.2-22 thru 1.2-69.................... Revision 24B 1.3-1........................................... Revision 47 1.4-1........................................... Revision 47 1.5-1........................................... Revision 47 95 drawings in the Chapter 1 List of Drawings Chapter 1 Appendices 1-A through 1-G Chapter 2 2-i thru 2-ii................................. Revision 47 2-iii thru iv............................... Revision 24B 2-v thru vi................................ Revision 24A 2-vii thru 2-viii........................... Revision 47 2-ix........................................... Revision 24B 2-x thru 2-xxv............................. Revision 47 2-1............................................... Revision 47 2.1.1-1 thru 2.1.1-2..................... Revision 47 2.1.2-1 thru 2.1.2-3..................... Revision 47 2.1.3-1 thru 2.1.3-8..................... Revision 47 2.2.1-1 thru 2.2.1-2..................... Revision 47 2.2.1-3...................................... Revision 24B 2.2.1-4......................................... Revision 47 2.2.1-5...................................... Revision 24B 2.3-1............................................ Revision 47 2.3.1-1 thru 2.3.1-13................... Revision 47 2.4-1............................................ Revision 47 2.4.1-1......................................... Revision 47 2.4.2-1......................................... Revision 47 2.4.3-1......................................... Revision 47 2.4.4-1......................................... Revision 47 2.4.5-1......................................... Revision 47 2.4.6-1......................................... Revision 47 2.5.1-1 thru 2.5.1-11................... Revision 47 2.5.2-1 thru 2.5.2-17................... Revision 47 2.6.1-1 thru 2.6.1-7..................... Revision 47 2.6.2-1 thru 2.6.2-7..................... Revision 47 2.6.3-1......................................... Revision 47 2.6.4-1......................................... Revision 47 2.6.5-1 thru 2.6.5-2..................... Revision 47 2.6.6-1......................................... Revision 47 2.6.7-1 thru 2.6.7-137................. Revision 47 2.6.8-1......................................... Revision 47 2.6.9-1......................................... Revision 47 2.6.10-1 thru 2.6.10-15............... Revision 47 2.6.11-1 thru 2.6.11-12............... Revision 47 2.6.12-1....................................... Revision 47 2.6.12-2.................................... Revision 24B 2.6.12-3 thru 2.6.12-146............. Revision 47

NAC-LWT Cask SAR April 2024 Revision 24B LIST OF EFFECTIVE PAGES (Continued)

Page 2 of 4 2.6.12-125................................ Revision 24B 2.6.12-126 thru 2.6.12-146........ Revision 47 2.6.12-147 thru 2.6.12-19........ Revision 24B 2.7-1........................................... Revision 47 2.7.1-1 thru 2.7.1-117................ Revision 47 2.7.2-1 thru 2.7.2-23.................. Revision 47 2.7.3-1 thru 2.7.3-5.................... Revision 47 2.7.4-1........................................ Revision 47 2.7.5-1 thru 2.7.5-5.................... Revision 47 2.7.6-1 thru 2.7.6-4.................... Revision 47 2.7.7-1 thru 2.7.7-109................ Revision 47 2.7.7-110 thru 2.7.7-111.......... Revision 24B 2.8-1........................................... Revision 47 2.9-1 thru 2.9-26........................ Revision 47 2.10.1-1 thru 2.10.1-3................ Revision 47 2.10.2-1 thru 2.10.2-49.............. Revision 47 2.10.3-1 thru 2.10.3-18.............. Revision 47 2.10.4-1 thru 2.10.4-11.............. Revision 47 2.10.5-1...................................... Revision 47 2.10.6-1 thru 2.10.6-19.............. Revision 47 2.10.7-1 thru 2.10.7-66.............. Revision 47 2.10.8-1 thru 2.10.8-67.............. Revision 47 2.10.9-1 thru 2.10.9-9................ Revision 47 2.10.10-1 thru 2.10.10-97.......... Revision 47 2.10.11-1 thru 2.10.11-10.......... Revision 47 2.10.12-1 thru 2.10.12-31.......... Revision 47 2.10.13-1 thru 2.10.13-17.......... Revision 47 2.10.14-1 thru 2.10.14-38.......... Revision 47 2.10.15-1 thru 2.10.15-10.......... Revision 47 2.10.16-1 thru 2.10.16-5............ Revision 47 Chapter 3 3-i thru 3-v................................. Revision 47 3.1-1........................................... Revision 47 3.1-2......................................... Revision 24B 3.1-3......................................... Revision 24A 3.2-1 thru 3.2-11......................... Revision 47 3.3-1............................................ Revision 47 3.4-1 thru 3.4-62......................... Revision 47 3.4-63 thru 3.4-66.................... Revision 24A 3.4-67 thru 3.4-124..................... Revision 47 3.5-1 thru 3.5-50......................... Revision 47 3.6-1 thru 3.6-12......................... Revision 47 Chapter 4 4-i thru 4-iii................................ Revision 47 4.1-1 thru 4.1-4........................... Revision 47 4.2-1 thru 4.2-4........................... Revision 47 4.3-1 thru 4.3-4........................... Revision 47 4.4-1............................................ Revision 47 4.5-1 thru 4.5-43......................... Revision 47 Chapter 5 5-i thru 5-xv................................ Revision 47 5-1 thru 5-3................................. Revision 47 5-4 thru 5-5.............................. Revision 24A 5.1.1-1......................................... Revision 47 5.1.1-2...................................... Revision 24A 5.1.1-3 thru 5.1.1-14................... Revision 47 5.1.1-15.................................... Revision 24A 5.1.1-16 thru 5.1.1-22................. Revision 47 5.2.1-1 thru 5.2.1-7..................... Revision 47 5.3.1-1 thru 5.3.1-2..................... Revision 47 5.3.2-1......................................... Revision 47 5.3.3-1 thru 5.3.3-8..................... Revision 47 5.3.4-1 thru 5.3.4-27................... Revision 47 5.3.5-1 thru 5.3.5-4..................... Revision 47 5.3.6-1 thru 5.3.6-22................... Revision 47 5.3.7-1 thru 5.3.7-19................... Revision 47

NAC-LWT Cask SAR April 2024 Revision 24B LIST OF EFFECTIVE PAGES (Continued)

Page 3 of 4 5.3.8-1 thru 5.3.8-25.................. Revision 47 5.3.9-1 thru 5.3.9-27.................. Revision 47 5.3.10-1 thru 5.3.10-14.............. Revision 47 5.3.11-1 thru 5.3.11-47.............. Revision 47 5.3.12-1 thru 5.3.12-26.............. Revision 47 5.3.13-1 thru 5.3.13-18.............. Revision 47 5.3.14-1 thru 5.3.14-22.............. Revision 47 5.3.15-1 thru 5.3.15-9................ Revision 47 5.3.16-1 thru 5.3.16-5................ Revision 47 5.3.17-1 thru 5.3.17-43.............. Revision 47 5.3.18-1 thru 5.3.18-2................ Revision 47 5.3.19-1 thru 5.3.19-9................ Revision 47 5.3.20-1 thru 5.3.20-29.............. Revision 47 5.3.21-1 thru 5.3.21-45.............. Revision 47 5.3.22-1 thru 5.3.22-34.............. Revision 47 5.3.23-1 thru 5.3.23-49.............. Revision 47 5.3.24-1 thru 5.3.24-7................ Revision 47 5.3.25-1 thru 5.3.25-18.............. Revision 47 5.4.1-1 thru 5.4.1-6.................... Revision 47 Chapter 6 6-i............................................... Revision 47 6-ii........................................... Revision 24A 6-iii thru 6-vii............................. Revision 47 6-viii......................................... Revision 24B 6-ix thru 6-xviii.......................... Revision 47 6-xix......................................... Revision 24B 6-1 thru 6-2............................. Revision 24A 6.1-1 thru 6.1-5.......................... Revision 47 6.1-6 thru 6.1-7....................... Revision 24A 6.2-1........................................ Revision 24A 6.2.1-1 thru 6.2.1-3.................... Revision 47 6.2.2-1 thru 6.2.2-3.................... Revision 47 6.2.3-1 thru 6.2.3-7.................... Revision 47 6.2.4-1........................................ Revision 47 6.2.5-1 thru 6.2.5-5..................... Revision 47 6.2.6-1 thru 6.2.6-3..................... Revision 47 6.2.7-1 thru 6.2.7-2..................... Revision 47 6.2.8-1 thru 6.2.8-3..................... Revision 47 6.2.9-1 thru 6.2.9-4..................... Revision 47 6.2.10-1 thru 6.2.10-3................. Revision 47 6.2.11-1 thru 6.2.11-3................. Revision 47 6.2.12-1 thru 6.2.12-4................. Revision 47 6.3.1-1 thru 6.3.1-6..................... Revision 47 6.3.2-1 thru 6.3.2-4..................... Revision 47 6.3.3-1 thru 6.3.3-9..................... Revision 47 6.3.4-1 thru 6.3.4-10................... Revision 47 6.3.5-1 thru 6.3.5-12................... Revision 47 6.3.6-1 thru 6.3.6-9..................... Revision 47 6.3.7-1 thru 6.3.7-4..................... Revision 47 6.3.8-1 thru 6.3.8-7..................... Revision 47 6.3.9-1 thru 6.3.9-7..................... Revision 47 6.3.10-1 thru 6.3.10-2................. Revision 47 6.4.1-1 thru 6.4.1-10................... Revision 47 6.4.2-1 thru 6.4.2-10................... Revision 47 6.4.3-1 thru 6.4.3-35................... Revision 47 6.4.4-1 thru 6.4.4-24................... Revision 47 6.4.5-1 thru 6.4.5-51................... Revision 47 6.4.6-1 thru 6.4.6-22................... Revision 47 6.4.7-1 thru 6.4.7-13................... Revision 47 6.4.8-1 thru 6.4.8-14................... Revision 47 6.4.9-1 thru 6.4.9-9..................... Revision 47 6.4.10-1 thru 6.4.10-18............... Revision 47 6.4.11-1 thru 6.4.11-7................. Revision 47 6.5.1-1 thru 6.5.1-13................... Revision 47 6.5.2-1 thru 6.5.2-4..................... Revision 47 6.5.3-1 thru 6.5.3-2..................... Revision 47 6.5.4-1 thru 6.5.4-46................... Revision 47 6.5.5-1 thru 6.5.5-15................... Revision 47 6.5.6-1 thru 6.5.6-20................... Revision 47

NAC-LWT Cask SAR April 2024 Revision 24B LIST OF EFFECTIVE PAGES (Continued)

Page 4 of 4 6.5.7-1 thru 6.5.7-18.................. Revision 47 Appendix 6.6 6.6-i thru 6.6-iii.......................... Revision 47 6.6-1........................................... Revision 47 6.6.1-1 thru 6.6.1-111................ Revision 47 6.6.2-1 thru 6.6.2-56.................. Revision 47 6.6.3-1 thru 6.6.3-73.................. Revision 47 6.6.4.-1 thru 6.6.4-77................. Revision 47 6.6.5-1 thru 6.6.5-101................ Revision 47 6.6.6-1 thru 6.6.6-158................ Revision 47 6.6.7-1 thru 6.6.7-84.................. Revision 47 6.6.8-1 thru 6.6.8-191................ Revision 47 6.6.9-1 thru 6.6.9-53.................. Revision 47 6.6.10-1 thru 6.6.10-38.............. Revision 47 6.6.11-1 thru 6.6.11-53.............. Revision 47 6.6.12-1 thru 6.6.12-20.............. Revision 47 6.6.13-1 thru 6.6.13-22.............. Revision 47 6.6.14-1 thru 6.6.14-7................ Revision 47 6.6.15-1 thru 6.6.15-45.............. Revision 47 6.6.16-1 thru 6.6.16-33.............. Revision 47 6.6.17-1 thru 6.6.17-7................ Revision 47 6.6.18-1 thru 6.6.18-34.............. Revision 47 6.6.19-1 thru 6.6.19-3................ Revision 47 6.7.1-1 thru 6.7.1-19.................. Revision 47 6.7.2-1 thru 6.7.2-16.................. Revision 47 6.7.3-1 thru 6.7.3-39.................. Revision 47 6.7.4-1 thru 6.7.4-28.................. Revision 47 6.7.5-1 thru 6.7.5-16.................. Revision 47 6.7.6-1 thru 6.7.6-22.................. Revision 47 6.7.7-1...................................... Revision 24B 6.7.7-2..................................... Revision 24A 6.7.7-3...................................... Revision 24B 6.7.7-4 thru 6.7.7-5................. Revision 24A 6.7.7-6 thru 6.7.7-13................ Revision 24B Chapter 7 7-i................................................ Revision 47 7-ii........................................... Revision 24A 7-iii............................................ Revision 47 7.1-1 thru 7.1-93......................... Revision 47 7.1-94 thru 7.1-98.................... Revision 24B 7.2-1 thru 7.2-17......................... Revision 47 7.2-18 thru 7.2-20.................... Revision 24A Chapter 8 8-i................................................ Revision 47 8.1-1 thru 8.1-15......................... Revision 47 8.2-1 thru 8.2-6........................... Revision 47 8.3-1 thru 8.3-4........................... Revision 47 Chapter 9 9-i................................................ Revision 47 9-1 thru 9-7................................. Revision 47 9-8............................................ Revision 24B 9-9 thru 9-11............................... Revision 47

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1-ii List of Figures Figure 1.2.3-1 Aluminum Clad TRIGA Fuel Element...................................................... 1.2-24 Figure 1.2.3-2 Aluminum Clad Instrumented Fuel Element............................................. 1.2-25 Figure 1.2.3-3 Stainless Steel Clad TRIGA Fuel Element................................................ 1.2-26 Figure 1.2.3-4 Stainless Steel Clad Instrumented Fuel Element......................................... 1.2-27 Figure 1.2.3-5 Standard Fuel Follower Control Rod Element.......................................... 1.2-28 Figure 1.2.3-6 TRIGA Fuel Cluster and Rod Details........................................................ 1.2-29 Figure 1.2.3-7 HTGR Fuel Handling Unit........................................................................ 1.2-30 Figure 1.2.3-8 RERTR Fuel Handling Unit...................................................................... 1.2-31 Figure 1.2.3-9 Typical TPBAR Assembly........................................................................ 1.2-32 Figure 1.2.3-10 TPBAR Consolidation Canister Sketch..................................................... 1.2-33 Figure 1.2.3-11 Failed PWR/BWR Fuel Rod Capsule........................................................ 1.2-34 Figure 1.2.3-12 NAC-LWT with TPBAR Consolidation Canister Payload....................... 1.2-35 Figure 1.2.3-13 PULSTAR Fuel Assembly........................................................................ 1.2-36 Figure 1.2.3-14 Spiral Fuel Assembly Cross-Section Sketch............................................. 1.2-37 Figure 1.2.3-15 MOATA Plate Bundle Sketches................................................................ 1.2-38 Figure 1.2.3-16 TPBAR Waste Container and Extension Weldment Sketch........................ 1.2-39 Figure 1.2.3-17 NAC-LWT with TPBAR Waste Container Payload................................. 1.2-40 Figure 1.2.3-18 ANSTO Damaged Fuel Can (DFC)........................................................... 1.2-41 Figure 1.2.3-19 SLOWPOKE Fuel Element....................................................................... 1.2-42 Figure 1.2.3-20 NRU and NRX Fuel Assemblies (Before Cropping and Potential Removal of Flow Tube)............................................................................. 1.2-43 Figure 1.2.3-21 HEUNL Container..................................................................................... 1.2-44 Figure 1.2.3-22 EFN, Moly and Booster Rod Illustrations................................................. 1.2-45 Figure 1.2.3-23 WESF Capsule Illustrations....................................................................... 1.2-46 Figure 1.2.3-24 BUP-500 Capsule Illustrations.................................................................. 1.2-47 Figure 1.2.3-25 LANL MOX Fuel Rod Generic Rod Components.................................... 1.2-48

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1-iii List of Tables Table 1.1-1 Terminology and Notation................................................................................. 1-4 Table 1.2-1 Characteristics of Design Basis TRIGA Fuel Elements Acceptable for Loading in the Poisoned TRIGA Basket....................................................... 1.2-49 Table 1.2-2 Characteristics of Design Basis TRIGA Fuel Elements Acceptable for Loading in the Nonpoisoned TRIGA Basket................................................ 1.2-50 Table 1.2-3 Characteristics of Design Basis TRIGA Fuel Cluster Rods.......................... 1.2-51 Table 1.2-4 Fuel Characteristics........................................................................................ 1.2-52 Table 1.2-5 PWR Fuel Characteristics............................................................................. 1.2-55 Table 1.2-6 BWR Fuel Characteristics............................................................................. 1.2-56 Table 1.2-7 Characteristics of General Atomics Irradiated Fuel Material (GA IFM)...... 1.2-57 Table 1.2-8 Typical Production TPBAR Characteristics................................................. 1.2-58 Table 1.2-9 PULSTAR Fuel Characteristics.................................................................... 1.2-59 Table 1.2-10 Spiral Fuel Assembly Characteristics........................................................... 1.2-60 Table 1.2-11 MOATA Plate Bundle Characteristics.......................................................... 1.2-61 Table 1.2-12 Typical TPBAR Segment Characteristics in Waste Container..................... 1.2-62 Table 1.2-13 Solid, Irradiated Hardware Characteristics................................................... 1.2-63 Table 1.2-14 SLOWPOKE Fuel Rods................................................................................ 1.2-64 Table 1.2-15 NRX / NRU Fuel Assemblies / Rods............................................................ 1.2-65 Table 1.2-16 HEUNL Characteristics................................................................................. 1.2-66 Table 1.2-17 SLOWPOKE Fuel Core................................................................................ 1.2-67 Table 1.2-18 EFN Rod, Booster Rod, and Moly Target..................................................... 1.2-68 Table 1.2-19 SrF2 Capsules................................................................................................ 1.2-68 Table 1.2-20 LANL MOX Fuel Rod Characteristics......................................................... 1.2-69

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1-vi List of Drawings (continued) 315-40-180 Rev 4P LWT Transport Cask Assembly, HEUNL Contents Rev 0NP 315-40-181 Sheets 1 - 2 Rev 6P Container Assembly, HEUNL Rev 0NP 315-40-182 Sheets 1 - 2 Rev 3P Container Spacer, HEUNL Rev 0NP 315-40-183 Rev 1P Container Guide, HEUNL Rev 0NP 315-40-185 Rev 0 LWT Transport Cask Assembly, SLOWPOKE Contents 315-40-186 Sheets 1 - 2 Rev 2 Fuel Core Basket Assembly, SLOWPOKE 315-40-187 Sheets 1 - 2 Rev 1 Basket Lid Assembly, SLOWPOKE 315-40-190 Rev 0P LWT Transport Cask Shipping Configuration, WESF Capsules, Zeno Rev 0NP 315-40-191 Rev 2P WESF Capsules Basket Assembly, Zeno Rev 0NP 315-40-192 Rev 2P WESF Capsules Container Assembly, Zeno Rev 0NP 315-40-193 Rev 1P LWT Lid Spacer, WESF Capsules, Zeno Rev 0NP 315-40-195 Rev 1P LWT Transport Cask Shipping Configuration, BUP-500, Zeno Rev 0NP 315-40-196 Rev 2P BUP-500 Basket Assembly, Zeno Rev 0NP 315-40-197 Rev 1P BUP-500 Cavity Spacer, Zeno Rev 0NP 315-40-188 Sheets 1 - 2 Rev 2P LWT Transport Cask Shipping Configuration, LANL MOX Rev 0NP 315-40-189 Sheets 1 - 2 Rev 3P Transfer Tube Details, LANL MOX Rev 0NP

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1-6 Table 1.1-1 Terminology and Notation (contd) x up to sixteen (16) transfer tubes filled with LANL MOX Fuel Rods.

Transfer Tubes must be loaded in the PWR/BWR Transport Can Assembly. Transfer Tube Spacers are required at the top and bottom end of each tube. Transfer Tube Spacers may be used to separate contents but are not required. Empty Transfer Tubes without spacers may be loaded. Different LANL MOX fuel types may be loaded in the same package but only one fuel type may be loaded into any Transfer Tube. Also, only one (1) Transfer Tube containing one (1) 530-000 type rod may be included in the cask payload. See Table 1.2-20 for additional limitations.

Impact Limiters Aluminum honeycomb energy absorbers located at the ends of the cask.

Intact LWR Fuel Spent nuclear fuel that is not Damaged LWR Fuel, as defined herein.

(Assembly or Rod)

To be classified as intact, fuel must meet the criteria for both intact cladding and structural integrity. An intact fuel assembly can be handled using normal handling methods, and any missing fuel rods have been replaced by solid filler rods that displace a volume equal to, or greater than, that of the original fuel rod.

Damaged LWR Fuel Spent nuclear fuel that includes any of the following conditions that (Assembly or Rod) result in either compromise of cladding confinement integrity or recognition of fuel assembly geometry.

1. The fuel contains known or suspected cladding defects greater than a pinhole leak or a hairline crack that have the potential for release of significant amounts of fuel particles.

2. The fuel assembly:

i. is damaged in such a manner as to impair its structural integrity; ii. has missing or displaced structural components such as grid spacers; iii. is missing fuel pins that have not been replaced by filler rods that displace a volume equal to, or greater than, that of the original fuel rod; iv. cannot be handled using normal handling methods.

3. The fuel is no longer in the form of an intact fuel assembly and consists of, or contains, debris such as loose pellets, rod segments, etc.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.1-4 shall be limited to that defined for the authorized PWR content condition as described in Chapter 5.

The NAC-LWT cask provides a testable containment for the contents during both normal operations and hypothetical accident conditions, satisfying the requirements of 10 CFR 71.51.

Any number of NAC-LWT casks may be shipped at one time, each on its own vehicle.

The NAC-LWT has two leaktight configurations as defined by ANSI N14.5. The standard configuration is provided by a closure lid with a metal containment seal and alternate vent and drain port covers provided with Viton containment O-rings. The second configuration is provided by a closure lid with a metal containment seal and Alternate B vent and drain port covers provided with metal seals. The metal port cover seal containment configuration is required to be utilized for all TPBAR contents and may be used for other contents. The NAC-LWT standard, Viton O-ring containment configuration is not authorized for TPBAR contents.

NAC-LWT casks may be shipped in a closed International Shipping Organization (ISO) container when containing all fuel contents other than PWR and BWR fuel assemblies. NAC-LWT casks containing PWR and BWR fuel assemblies are to be transported on an open trailer with a personnel barrier.

The terminology of MTR, DIDO and TRIGA fuel elements will be used independent of whether the element contains low, medium or high enriched uranium (i.e., LEU, MEU or HEU), except when required for analysis or loading purposes.

TPBAR contents may be placed into a consolidation canister, waste container or 5x5 rod insert (also referred to as a rod holder) in a PWR/BWR Rod Transport Canister. Segmented TPBARs are only permitted within the waste container. The three TPBAR shipping configurations are individually placed within one of the two TPBAR basket assemblies (one with a 7-inch bottom spacer and the alternative TPBAR basket assembly with a 6.5-inch alternative bottom spacer),

depending on container configuration.

LANL MOX Fuel Rods must be loaded in the PWR/BWR transport can assembly using a maximum of sixteen (16) transfer tubes. A Transfer Tube spacer is required at the top and bottom end of the tube. Transfer Tube spacers may be used to separate contents but are not required. The PWR/BWR Transport Can Assembly may be used with any of the lids and corresponding PWR insert and basket assembly. Different LANL MOX fuel types may be loaded in the same package but only one fuel type may be loaded into any Transfer Tube. Table 1.2-20 provides additional limitations on the number of LANL MOX Fuel Rods allowed in a given transfer tube, along with the maximum number of transfer tubes with a given type of fuel rod allowed in a single package.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-22 1.2.3.16 SLOWPOKE Fuel Core One SLOWPOKE fuel core containing up to 298 undamaged SLOWPOKE fuel rods may be transported in the NAC-LWT. The SLOWPOKE fuel core is packaged in the SLOWPOKE fuel core basket. A spacer is attached to the SLOWPOKE fuel core basket lid locating the fuel core at the bottom of the basket. The basket is transported with empty intermediate and bottom MTR-42 basket modules to provide axial spacing. The SLOWPOKE fuel core basket is therefore located next to the NAC-LWT cask lid.

The SLOWPOKE fuel core primary components are up to 298 undamaged SLOWPOKE fuel rods, a center tube, and upper and lower plates. SLOWPOKE fuel rods are composed of highly enriched uranium-aluminum alloy fuel meat within aluminum cladding. As discussed in Section 1.2.3.12, criticality in a SLOWPOKE core during reactor operations is achieved by the use of a thick beryllium neutron reflector surrounding the core. The beryllium reflector is not part of the packaged contents. A sketch of a SLOWPOKE fuel rod is provided in Figure 1.2.3-19. Key physical, radiation protection and thermal characteristics of the SLOWPOKE fuel core, i.e.,

parameters documented in the analytical chapters to be safely transported, are listed in Table 1.2-17.

1.2.3.17 SrF2 Capsules There are two types of SrF2 capsules, the WESF capsules, and the BUP-500 capsules. The WESF capsules must be loaded into the WESF capsule container assemblies prior to being loaded into the WESF basket assembly within the NAC-LWT cavity. The WESF LWT lid spacer and all six (6) WESF capsule container assemblies must be installed. A sketch of the WESF capsules is provided in Figure 1.2.3-23. The WESF capsule basket assembly design is presented in NAC drawing 315-40-191. The BUP-500 capsules must be loaded into the BUP-500 basket assembly within the NAC-LWT cavity. One spacer must be installed on either side of a capsule. A single BUP-500 capsule may be loaded with a short spacer installed in place of the second BUP-500 capsule. A sketch of the BUP-500 capsule is provided in Figure 1.2.3-24. The BUP-500 basket assembly design is presented in NAC drawing 315-40-196.

Key physical, radiation protection, and thermal characteristics of the SrF2 capsules are listed in Table 1.2-19.

1.2.3.18 LANL MOX Fuel Rods The NAC-LWT cask is analyzed and evaluated for the transport of up to 16 Transfer Tubes.

Transfer Tubes must be loaded in the PWR/BWR transport can assembly. As needed, stainless steel dunnage may also be inserted into the PWR/BWR transport can assembly to provide additional configuration control as indicated in NAC drawing 315-40-189. The evaluated characteristics for the authorized LANL MOX Fuel Rods are provided in Table 1.2-20. Different LANL MOX fuel types may be loaded in the same package, subject to the limitations provided

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-23 in Table 1.2-20, but only one fuel type may be loaded into any single Transfer Tube. Additional restrictions are as follows:

PNNL, EXXON, and UO2 rods may be mix loaded into a cask - all 16 transfer tubes may be loaded.

ROD1063 rods may not be mix loaded with other materials - only 6 transfer tubes may be loaded (10 empty in a shipment).

NIS5 rods and the 500-000 rod may be mix loaded with a limit of 4 tubes of NIS5 and one tube of 500-000 (11 empty tubes to be loaded).

A sketch of a generic LANL MOX Fuel Rod is provided in Figure 1.2.3-25.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-24 Figure 1.2.3-1 Aluminum Clad TRIGA Fuel Element

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-25 Figure 1.2.3-2 Aluminum Clad Instrumented Fuel Element

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-26 Figure 1.2.3-3 Stainless Steel Clad TRIGA Fuel Element

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-27 Figure 1.2.3-4 Stainless Steel Clad Instrumented Fuel Element

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-28 Figure 1.2.3-5 Standard Fuel Follower Control Rod Element

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-29 Figure 1.2.3-6 TRIGA Fuel Cluster and Rod Details FUEL ROD 22.5 in. maximum 31.0 in. maximum 0.015 Thick Minimum Aluminum bottom cluster fitting Aluminum top fitting for handling Compression spring

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-30 Figure 1.2.3-7 HTGR Fuel Handling Unit

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-31 Figure 1.2.3-8 RERTR Fuel Handling Unit

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-32 Figure 1.2.3-9 Typical TPBAR Assembly

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-33 Figure 1.2.3-10 TPBAR Consolidation Canister Sketch Note: Material of construction is stainless steel.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-34 Figure 1.2.3-11 Failed PWR/BWR Fuel Rod Capsule Note: Material of construction is stainless steel.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-35 Figure 1.2.3-12 NAC-LWT with TPBAR Consolidation Canister Payload

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-36 Figure 1.2.3-13 PULSTAR Fuel Assembly

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-37 Figure 1.2.3-14 Spiral Fuel Assembly Cross-Section Sketch Note: Nominal dimensions

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-38 Figure 1.2.3-15 MOATA Plate Bundle Sketches Note: 14-plate bundle configuration. Dimensions are reference values. Bundles with a reduced number of plates retain the plate pitch and compensate by wider side plates and outside spacers to retain overall bundle dimensions.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-39 Figure 1.2.3-16 TPBAR Waste Container and Extension Weldment Sketch Note: Material of construction is stainless steel.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-40 Figure 1.2.3-17 NAC-LWT with TPBAR Waste Container Payload

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-41 Figure 1.2.3-18 ANSTO Damaged Fuel Can (DFC)

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-42 Figure 1.2.3-19 SLOWPOKE Fuel Element (Units in inches)

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-43 Figure 1.2.3-20 NRU and NRX Fuel Assemblies (Before Cropping and Potential Removal of Flow Tube)

NRU NRX (Units in inches)

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-44 Figure 1.2.3-21 HEUNL Container NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-45 Figure 1.2.3-22 EFN, Moly and Booster Rod Illustrations EFN Rod Moly Target(s)

Booster Rod Note: Illustration are for general layout of the various rod/target designs. Moly sketch represents short Moly target. Axial detail varies for double length target.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-46 Figure 1.2.3-23 WESF Capsule Illustrations

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-47 Figure 1.2.3-24 BUP-500 Capsule Illustrations NOTES Strength Member Material: AMS-5711 Hastelloy S Bar Replacement Strength Member housing and caps may be fabricated from ASTM A240 or A276 Type 304 Stainless Steel

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-48 Figure 1.2.3-25 LANL MOX Fuel Rod Generic Rod Components

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-49 Table 1.2-1 Characteristics of Design Basis TRIGA Fuel Elements Acceptable for Loading in the Poisoned TRIGA Basket TRIGA HEU (Notes 1, 2, 6 & 7)

TRIGA LEU (Notes 1, 2, 6 & 7)

TRIGA LEU (Notes 1, 2, 6 & 7)

Fuel Form Clad U-ZrH rod Clad U-ZrH rod Clad U-ZrH rod Maximum Element Weight, lbs 13.2 13.2 13.2 Maximum Element Length, in 47.74 47.74 47.74 Element Cladding Stainless Steel Stainless Steel Aluminum Clad Thickness, in 0.02 0.02 0.03 Active Fuel Length, in 15 15 14-15 (Note 4)

Element Diameter, in 1.478 max.

1.478 max.

1.47 max.

Fuel Diameter, in 1.435 max.

1.435 max.

1.41 max.

Maximum Initial U Content/Element, kilograms 0.196 0.845 0.205 Maximum Initial 235U Mass, grams 137 169 41 Maximum Initial 235U Enrichment, weight percent 70 20 20 Zirconium Mass, grams (Note 5) 2060 1886-2300 2300 Hydrogen to Zirconium Ratio, max.

(Note 5) 1.6 1.7 1.0 Maximum Average Burnup, MWd/MTU 460,000 (80% 235U) 151,100 (80% 235U) 151,100 (80% 235U)

Minimum Cooling Time 90 days (Note 3) 90 days (Note 3) 90 days (Note 3)

Notes:

1.

Mixed TRIGA LEU and HEU contents authorized.

2.

TRIGA Standard, instrumented and fuel follower control rod type elements authorized.

3.

Maximum decay heat of any element is 7.5 watts.

4.

Aluminum clad fuel with 14-inch active fuel is solid and has no central hole with a zirconium rod.

5.

Zirconium mass and H/Zr ratio apply to the fuel material (U-Zr-Hx) and do not include the center zirconium rod.

6.

Listed TRIGA fuel elements have a 0.225-inch diameter zirconium rod in the center.

7.

Dimensions listed are as-fabricated (unirradiated) nominal values.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-50 Table 1.2-2 Characteristics of Design Basis TRIGA Fuel Elements Acceptable for Loading in the Nonpoisoned TRIGA Basket TRIGA HEU (Notes 1, 2, 6)

TRIGA LEU (Notes 1, 2, 6)

TRIGA LEU (Notes 1, 2, 6)

Fuel Form Clad U-ZrH rod (Note 4)

Clad U-ZrH rod (Note 4)

Clad U-ZrH rod (Note 4)

Maximum Element Weight, lbs 13.2 13.2 13.2 Maximum Element Length, in 47.74 47.74 47.74 Element Cladding Stainless Steel Stainless Steel Aluminum Minimum Clad Thickness, in 0.01 0.01 0.01 Active Fuel Length, in (Note 5)

(Note 5)

(Note 5)

Maximum Element Diameter, in 1.5 max.

1.5 max.

1.5 max.

Fuel Diameter, in (Note 5)

(Note 5)

(Note 5)

Maximum Initial U Content/Element, kilograms 0.198 0.186 0.845 1.447 0.205 Maximum Initial 235U Mass, grams 138 175 169 275 41 (Notes 7, 8)

(Notes 7, 8)

Maximum Initial 235U Enrichment, weight percent 71 95 25 25 25 (Notes 7, 8)

(Notes7, 8)

Zirconium Mass, grams (Note 5)

(Note 5)

(Note 5)

Hydrogen to Zirconium Ratio, max.

(Note 5)

(Note 5)

(Note 5)

Maximum Average Burnup, MWd/MTU 460,000 583,000 151,100 (80% 235U) 151,100 (80% 235U)

(80% 235U)

Minimum Cooling Time 90 days (Note 3) 90 days (Note 3) 90 days (Note 3)

Notes:

1.

Mixed LEU and HEU TRIGA fuel element, and LEU and HEU TRIGA fuel cluster rod, as defined in Table 1.2-3, contents authorized.

2.

TRIGA Standard, instrumented and fuel follower control rod type elements authorized.

3.

Maximum decay heat of any element is 7.5 watts.

4.

Element may contain zirconium rod in the center.

5.

See criticality analyses in Chapter 6, Section 6.4.5.6, for the evaluations determining critical fuel characteristics.

6.

Dimensions listed are as-fabricated (unirradiated) nominal values.

7.

Elements limited to loading in top and bottom basket module only.

8.

Elements limited to a maximum of three per basket module cell.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-51 Table 1.2-3 Characteristics of Design Basis TRIGA Fuel Cluster Rods Element Type TRIGA Fuel Cluster Rod Max. Rod Length (in) 31.0 Max. Active Length (in) 22.5 Clad Material Incoloy 800 Min. Clad Thickness (in) 0.015 Fuel Material U-ZrH Max. Pellet Diameter (in) 0.53 Max. Rod Weight (kg) 0.65 Min. U in U-ZrH (wt %)

43.0 (LEU) or 9.5 (HEU)1 Max. 235U in U (wt %)

19.9 to 93.3 235U Mass (g) 55.0 (LEU) or 46.5 (HEU)

Max. H to Zr Ratio 1.7 1 Equivalent to a maximum zirconium mass of 357 g for LEU fuel and 457 g for HEU fuel material. Lower weight percents are permitted, provided the maximum zirconium mass limits are not exceeded.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-52 Table 1.2-4 Fuel Characteristics Parameter PWR Fuel Assembly BWR Fuel Assembly PWR Rods High Burnup PWR Rods PWR MOX Fuel Rods6 High Burnup BWR Rods 7 x 7 High Burnup BWR Rods1 8 x 82 Maximum Number of Assemblies, Elements or Rods 1

2 25 rods 25 rods 16 rods 25 rods 25 rods Maximum Overall Weight, lbs 1650 750 N/A N/A N/A N/A N/A Maximum Overall Length, in 178.25 176.1 162 162 162 176.1 176.1 Maximum Active Fuel Length, in 150 150 150 150 153.5 150 150 Fuel Rod Cladding Zirc Zirc Zirc Zirc Zirc Zirc Zirc Maximum Uranium, kg U 475 198 58.2 65.6 41.67 198 198 Maximum Initial 235U, wt %

See below3 4.0 5.0 5.0 7.0 max/2.0 min, fissile Pu8 5.0 5.0 Maximum Burnup, MWd/MTU 35,000 30,000 60,0004 80,000 62,500 60,000 - 80,000 80,000 Maximum Unit Decay Heat, kW 2.5 1.1 0.564 0.92 0.143 0.84 0.84 Maximum Cask Decay Heat, kW 2.5 2.2 1.41 2.3 2.3 2.1 2.1 Minimum Cool Time, yr 2

2 150 days 150 days 90 days 210 - 270 days5 150 days 1 High burnup rods are loaded in a fuel assembly lattice or rod holder. Up to 14 rods, loaded in a rod holder, may be classified as damaged. The lattice may be irradiated.

2 Includes rods from all larger BWR assembly arrays (e.g., 9x9, 10x10).

3 See Table 1.2-5 for maximum PWR fuel enrichment by fuel type.

4 Up to 2 of the 25 PWR rods may have a maximum burnup of 65,000 MWd//MTU.

5 Minimum cool time for high burnup BWR 7x7 rods is determined by extent of burnup. See Section 5.3.8 and Table 5.3.8-23.

6 Up to 16 PWR MOX fuel rods or a combination of up to 16 MOX PWR and UO2 PWR fuel rods can be loaded.

7 Maximum fuel mass is 2.6 kg HM/rod.

8 Maximum 5.0 wt % 235U for UO2 rods.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-53 Table 1.2-4 Fuel Characteristics (Continued)

Parameter Metallic Fuel Metallic Fuel Metallic Fuel MTR HEU MTR MEU MTR LEU TRIGA LEU Element TRIGA HEU Element TRIGA Cluster Rod Maximum Number of Assemblies, Elements or Rods 15 rods (sound) 9 rods (failed) 3 rods (severely failed in filters) 421 42 422 140 140 560 Maximum Overall Weight, lbs 1805 1805 1805 30 (max)3 30 (max) 3 30 (max) 3 13.2 (max) 3 8.82 (nom.)

13.2 (max) 3 1.53 Maximum Overall Length, in 120.5 120.5 120.5 25.44 26.14 26.14 47.745 47.745 31.0 Maximum Active Fuel Length, in 120.0 120.0 120.0 24.8 25.6 25.6 15 15 22.5 Fuel Rod Cladding Al Al Al Al Al Al Al or SS Al or SS Incoloy 800 Maximum Uranium, kg U 54.5 54.5 54.5 0.422 0.511 0.950 3.3682 0.824 0.196 0.0505 (HEU) 0.2894 (LEU)

Maximum Initial 235U, wt %

Natural Natural Natural 94 946 25 20 70 95 (HEU)/20 (LEU)

Maximum Burnup, MWd/MTU 1,600 1,600 1,600 Variable up to 660,0007 Variable up to 293,300 Variable up to 139,300 151,100 (80% 235U) 460,000 (80% 235U) 600,000 (HEU)/

139,300 (LEU)

(80% 235U)

Maximum Unit Decay Heat, kW 0.036 0.036 0.036 Variable8 0.0308 0.0308, 10 0.0075 0.0075 0.001875 Maximum Cask Decay Heat, kW 0.54 0.54 0.54 1.26 1.26 1.26 1.05 1.05 1.05 Minimum Cool Time, yr 1

1 1

Variable8 Variable8 Variable8 Variable9 Variable9 Variable9 1 For NISTR fuel, 42 assemblies may be cut in half, producing 84 fuel-bearing pieces. Each fuel-bearing piece may contain up to 0.211 kgU.

2 MTR fuel elements having 235U content >490 g (>23.5 g per plate) are limited to a total of 4 elements in a 7-element basket. Basket openings 1, 2 and 3 shall be blocked by cell block spacers to ensure that MTR elements are not loaded in these openings. Therefore, depending on the number of such 4-element baskets, the maximum number of elements per cask will be reduced accordingly.

3 Maximum weight of fuel element(s), spacer(s) and fuel can, as applicable, per basket module cell shall be 80 pounds.

4 For MTR fuel elements, which are cut to remove nonfuel-bearing hardware prior to transport, a nominal 0.28 inch of nonfuel or spacer hardware will remain above and below the active fuel region to allow for fuel handling operations. The HFBR element, with an element length of 57.24 inches, must be cut prior to shipment. For HEU MTR elements having

>380 g 235U but less than 460 g 235U, a minimum of 2.0 cm (0.8 inch) of nonfuel hardware and/or spacers/plates shall be provided at the ends of the element.

5 Permissible fuel element length is limited to basket cavity length, which is a minimum 47.74 inches for the basket top module, 30.94 inches for the intermediate modules, and 32.64 inches for the bottom module.

6 Typical MEU enrichment is 45 wt% 235U. Criticality analysis supports up to 94 wt% under the MEU fuel definition.

7 Maximum burnup is 660,000 MWd/MTU for 380g 235U and 577,500 MWd/MTU for 460g 235U.

8 Minimum cool times for MTR fuel, down to 90 days, shall be determined using the procedure presented in Section 7.1.5.

9 Minimum cool times for TRIGA fuel elements and fuel cluster rods, down to 90 days, are determined so that the maximum decay heat of any element to be shipped is 7.5 watts and any fuel cluster rod is 1.875 watts.

10 Up to five LEU MTR fuel assemblies with 40 W may be loaded per basket module with total heat load for the basket module 210 W. Fuel assembly selection shall be determined using the procedure presented in Section 7.1.5.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-54 Table 1.2-4 Fuel Characteristics (Continued)

Parameter DIDO HEU DIDO MEU DIDO LEU Number of Fuel Cylinders per Assembly 4

4 4

Maximum Overall Weight (lb)1 15 15 15 Minimum Plate Thickness, in 0.051 0.051 0.051 Minimum Clad Thickness (Al), in 0.00984 0.00984 0.00984 Maximum 235U per Element, g 190 190 190 Maximum Initial 235U, wt %

94 94 94 Minimum Initial 235U, wt %

90 40 19 Maximum Uranium, kg U 0.2111 0.4750 1.0000 Minimum Active Fuel Height, in 23.13 23.13 23.13 Minimum Element Height2, in 24.21 24.21 24.21 Maximum Burnup, MWd/MTU 577,460 256,650 121,910 Maximum Unit Decay Heat3, kW 0.025 0.025 0.025 Maximum Cask Decay Heat, kW 1.05 1.05 1.05 Minimum Cool Time4, yr Variable Variable Variable 1

Maximum weight of fuel element(s), spacer(s) and fuel can, as applicable, per basket module cell shall be 80 pounds.

2 Element height provides for spacing of fissile material. An optional spacer may be used to maintain spacing if the element is cut shorter than 24.21 inches.

3 Maximum unit decay heat of 0.025 kW allowed only in conjunction with spacers for top basket (see Section 7.1.4). The per element heat load is limited to 0.018 kW with no top basket spacer. For DIDO fuel elements loaded into a top ANSTO basket module, the maximum decay heat load is limited to 0.010 kW per element (with or without DFC).

4 Minimum cool times for DIDO fuel assemblies, down to 180 days, shall be determined using the procedure presented in Section 7.1.4.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-55 Table 1.2-5 PWR Fuel Characteristics Fuel Type No. of Fuel Rods Max.

Assembly Length (in.)

Max.

Assembly Weight (lb)

Max.

Enrich.

(wt %)

Max.

MTU Pitch (in.)

Rod Dia.

(in.)

Clad Thick.

(in.)

Pellet Dia.(in.)

Max.

Active Length (in.)

B&W 15 x 15 208 165.63 1515 3.5 0.4750 0.5680 0.430 0.0265 0.3686 144.0 B&W 17 x 17 264 165.72 1505 3.5 0.4658 0.5020 0.379 0.0240 0.3232 143.0 CE 14 x 14 176 157.00 1270 3.7 0.4037 0.5800 0.440 0.0280 0.3765 137.0 CE 16 x 16 236 178.25 1430 3.7 0.4417 0.5060 0.382 0.0250 0.3250 150.0 WE 14 x 14 Std 179 159.71 1302 3.7 0.4144 0.5560 0.422 0.0225 0.3674 145.2 WE 14 x 14 OFA 179 159.71 1177 3.7 0.3612 0.5560 0.400 0.0243 0.3444 144.0 WE 15 x 15 204 159.71 1472 3.5 0.4646 0.5630 0.422 0.0242 0.3659 144.0 WE 17 x 17 Std 264 159.77 1482 3.5 0.4671 0.4960 0.374 0.0225 0.3225 144.0 WE 17 x 17 OFA 264 160.10 1373 3.5 0.4282 0.4960 0.360 0.0225 0.3088 144.0 Ex/ANF 14 x 14 WE 179 160.13 1271 3.7 0.3741 0.5560 0.424 0.0300 0.3505 144.0 Ex/ANF 14 x 14 CE 176 157.24 1292 3.7 0.3814 0.5800 0.440 0.0310 0.3700 134.0 Ex/ANF 15 x 15 WE 204 159.70 1433 3.7 0.4410 0.5630 0.424 0.0300 0.3565 144.0 Ex/ANF 17 x 17 WE 264 159.71 1348 3.5 0.4123 0.4960 0.360 0.0250 0.3030 144.0

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-56 Table 1.2-6 BWR Fuel Characteristics Fuel Type No. of Fuel Rods No. of Water Rods Max.

Assembly Length (in.)

Max.

Assembly Weight (lb)

Max.

MTU Pitch (in.)

Rod Dia.

(in.)

Clad Thick.

(in.)

Pellet Dia. (in.)

Max. Active Length (in.)

GE 7 x 7 49 0

175.9 678.9 0.1923 0.738 0.563 0.037 0.477 146 GE 8 x 8-1 63 1

175.9 681.0 0.1880 0.640 0.493 0.034 0.416 146 GE 8 x 8-2 62 2

175.9 681.0 0.1847 0.640 0.483 0.032 0.410 1501 GE 8 x 8-4 60 4

176.1 665.0 0.1787 0.640 0.484 0.032 0.410 1501,2 GE 9 x 9 74 23 176.1 646.0 0.1854 0.566 0.441 0.028 0.376 1501,4 79 2

176.1 646.0 0.1979 0.566 0.441 0.028 0.376 1501,4 Ex/ANF 7 x 7 49 0

171.3 619.1 0.1960 0.738 0.570 0.036 0.490 144 Ex/ANF 8 x 8-1 63 1

171.3 562.3 0.1764 0.641 0.484 0.036 0.4045 145.2 Ex/ANF 8 x 8-2 62 2

176.1 587.8 0.1793 0.641 0.484 0.036 0.4045 150 Ex/ANF 9 x 9 79 2

176.1 575.3 0.1779 0.572 0.424 0.03 0.3565 150 74 23 176.1 575.3 0.1666 0.572 0.424 0.03 0.3565 150 1 6 natural uranium blankets on top and bottom.

2 May have 1 large water hole - 3.2 cm ID, 0.1 cm thickness.

3 2 large water holes occupying 7 fuel rod locations - 2.5 cm ID, 0.07 cm thickness.

4 Shortened active fuel length in some rods.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-57 Table 1.2-7 Characteristics of General Atomics Irradiated Fuel Material (GA IFM)

Parameter RERTR HTGR Maximum Number of Assemblies, Elements or Rods 13 intact; 7 sectioned N/A Maximum Loaded Enclosure Weight, lbs 76.0 71.5 Maximum Fuel Weight, lbs 23.73 23.52 Maximum Overall Length, in 29.92 N/A Maximum Active Fuel Length, in 22.05 N/A Fuel Material U-ZrH UC2, UCO, UO2, (Th,U)C2, (Th,U)O2 Fuel Rod Cladding Incoloy 800 N/A Maximum Uranium, kg U 3.86 0.21 Maximum Initial 235U, wt %

19.7 93.15 Maximum Burnup, MWd/MTU N/A N/A Maximum Unit Decay Heat, W 11.0 2.05 Maximum Cask Decay Heat, W 13.05 13.05 Earliest Shipment Date 1/1/96 1/1/96 Maximum Activity, Ci 2920 483

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-58 Table 1.2-8 Typical Production TPBAR Characteristics1 1

Refer to Section 1.5, Chapter 1 Appendices, Unclassified DOE Reference Documents and Drawings.

2 Beginning of life, nominal, unirradiated dimensions.

3 Primary dose contribution: 1.1x 104 Ci 60Co/cask 4

The bounding weight employed in the structural analysis.

Parameter Description Value Maximum Number of TPBARs per Consolidation Canister 300 Number of Consolidation Canisters per Cask 1

TPBAR Clad Material 316 L Stainless Steel Rod Length2, in 153.04 Rod Diameter2, in 0.381 Maximum Rod Heat Load, W 2.31 Maximum Cask Heat Load, kW 0.693 Maximum Tritium Content per Rod, gram 1.2 Maximum Activity per Cask3, Ci 3.84 x 106 Loaded TPBAR Consolidation Canister Maximum Weight, pounds4 1,000 Maximum Event Failed Tritium Release (Ci/rod)

<55 Minimum Cooling Time, days 30

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-59 Table 1.2-9 PULSTAR Fuel Characteristics Description Value Maximum Pellet Diameter (inch) 0.423 Minimum Element (Rod) Cladding Thickness (inch) 0.0185 Minimum Element (Rod) Diameter (inch) 0.470 Maximum Active Fuel Height (inch) 24.1 Element (Rod) Length (inch) 26.2 Rod Pitch (inch) 0.525 u 0.607 Assembly Length (inch) 38 Box Outside Width (inch) 2.745 u 3.155 Box Thickness (inch) 0.06 Maximum Assembly or Loaded Can Weight (lb) 1 80 Maximum PULSTAR Can Content Weight (lb)2 39.6 Maximum Enrichment (wt % 235U) 6.5 Maximum 235U Content per Element (g) 33 No. of Elements (Rods) per Assembly 25 No. of Elements (Rods) per Can2 25 Maximum Depletion (%235U) 45 Minimum Cool Time (yrs) 1.5 Maximum Heat Load per Assembly (W) 30 Maximum Heat Load per Element (W) 1.2 1 Listed weight is the maximum weight evaluated for the structural calculation to bound all payload configurations, including loaded cans, and spacers. Nominal PULSTAR assembly weight is 45 pounds.

2 The contents of a PULSTAR can are restricted to the equivalent of the fuel material in 25 PULSTAR fuel elements and of the displaced volume of 25 intact PULSTAR fuel elements. Fuel material may be in damaged form including fuel debris. The listed weight represents the can content limit established by the structural analyses.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-60 Table 1.2-10 Spiral Fuel Assembly Characteristics 1

Cropped to fit within ANSTO fuel basket module nominal height of 28.3 inches.

2 Criticality evaluations reduced inner and outer shell thickness to 0.01 cm to provide additional moderator within the assembly.

3 Typical assembly weight is 7.9 pounds. Bounding structural analysis weight is listed. Bounding weight includes DFC and fuel plates.

4 Thermal and shielding evaluation employed 18 W per element. Based on cool time constraint, 15.7 W represents maximum heat load. Spiral fuel elements with degraded cladding loaded into aluminum DFCs shall be limited to a maximum decay heat of 10 W per element.

5 Spiral fuel is constrained to DIDO MEU cool time limits as a function of burnup. Minimum cool times for the spiral assembly, down to 270 days, shall be determined using the procedure presented in Section 7.1.4 for 18 W DIDO MEU fuel.

Parameter Value Number of elements per assembly 10 Fuel element type Curved plate Nominal dimensions of element (cm) 0.147 u 7.33 u 63.5 (individual plate)

Chemical form of fuel meat U-Alx-alloy Cladding material Aluminum Nominal over-all dimensions (cm) 63.818 (height) u 10.16 diameter1 Max total weight of 235U (g) 160 (total per assembly)

Maximum enrichment (wt % 235U) 95 Side plate material Aluminum (inner and outer tubes)

Nominal side plate - dimensions (cm)

Inner 6.045 OD, 5.82 ID x 63.818 Outer 10.16 OD, 9.85 ID x 63.8182 Max. assembly weight (lb) 183 Assembly maximum heat load (W) 15.74 Burnup/cool time limit Variable5

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-61 Table 1.2-11 MOATA Plate Bundle Characteristics Parameter Value Maximum number of elements per assembly 14 Nominal dimensions of element (cm) 66 cm long, 7.6 cm wide and 0.203 cm thick Nominal dimensions of fuel meat (cm) 58.4 cm long, 6.99 cm wide and 0.1016 cm thick (bounding active fuel width evaluated to a maximum of 7.32 cm)

Chemical form of fuel meat U-Alx-alloy Cladding material Aluminum Nominal clad thickness (cm) 0.05 cm (evaluated to 0.01 cm minimum)

Plate spacer thickness (cm) 0.147 min, 0.152 max (evaluated to 0.18 maximum)

Maximum weight of 235U (g) per plate 22.3 Maximum enrichment (wt % 235U) 92 Nominal side plate thickness (cm) 0.635 (bounding evaluation replaced by cavity moderator)

Max. assembly weight (lb) 181 Maximum heat load per assembly (W)2 3 (total for 14 fuel plates)

Maximum burnup 30,000 MWd/MTU or 4.1 % depletion 235U Minimum cool time (years) 10 1 Typical assembly weight is 13.6 pounds. Bounding structural analysis weight is listed. Bounding weight includes DFC and fuel plates.

2 Actual heat load at limiting burnup and cool time < 1 Watt. Thermal evaluations at 3 Watt per bundle.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-62 Table 1.2-12 Typical TPBAR Segment Characteristics in Waste Container Parameter/Description Value Maximum Number of TPBAR Segments and Debris per Waste Container, equivalent number of TPBARs 55 Number of Waste Containers per Cask 1

Waste Container Material 316L Stainless Steel Maximum Tritium Content per TPBAR equivalent, gram 1.2 Maximum Activity per Cask, Ci 6.66 x10+5 Maximum Heat Load per Waste Container, watts 127 Maximum Loaded Waste Container Weight, pounds 7001 Minimum Cooling Time, years 90 1 Design basis weight of a loaded waste container is 700 pounds. Applying a maximum payload of 55 TPBARs, with storage canister, yields a maximum weight of 662 pounds. Use of shrouds to contain segments and/or TPBAR debris reduces overall waste container weight due to a reduction in TPBAR payload capacity resulting from the reduced container free volume.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-63 Table 1.2-13 Solid, Irradiated Hardware Characteristics1 Parameter Value Maximum Content Weight 4,000 pounds 2 Maximum Content Length 171.5 inches 3 Hardware Material Solid, irradiated and contaminated fuel assembly structural or reactor internal component hardware 4 Maximum Cask Heat Load 1.0 KW Maximum Activity per Cask, Ci 6.0 x 10E+6 Maximum Source Term, gamma/sec 6.0 x 10E+15 Maximum Source Term, MeV/sec 1.0 x 10E+15 1

Maximum content weight includes any spacers, containers or dunnage loaded in the cavity with the irradiated hardware.

2 Length of cavity is limited to 171.5 inches by the installation and use of an irradiated hardware spacer bolted to the underside of the closure lid.

3 Appropriate secondary containers will be used to prevent any contact and cross-contamination between the carbon steel contents and the stainless steel internals of the cask cavity.

4 The irradiated hardware contents may contain fissile material, provided the quantity of fissile material does not exceed a Type A quantity and does not exceed the mass limits of 10 CFR 71.53.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-64 Table 1.2-14 SLOWPOKE Fuel Rods Parameter Value Maximum Cask Heat Load 5 W Maximum Canister Heat Load 0.625W Payload Limit (lb/canister) 25 Maximum 235U per rod (g) 2.800 Maximum U per rod (g) 3.111 Minimum Cool Time 14 yr Maximum Burnup (GWd/MTU or wt% 235U Depletion) 30 GWd/MTU 4.5 wt% 235U Notes:

1.) Heat load limit established by thermal analysis.

2.) Fissile material (235U) mass limit established by criticality analysis.

3.) Fuel (U) mass, cool time, burnup/depletion limit established by shielding analysis.

4.) Payload weight limit established by structural analysis and includes both fuel and canister weight.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-65 Table 1.2-15 NRX / NRU Fuel Assemblies / Rods Parameter NRU (HEU)

NRU (LEU)

NRX Maximum Cask Heat Load 640 W Maximum Per Tube Heat Load 35.6 W Payload Limit (lb/tube) 20 Maximum 235U per rod (g) 43.24 43.68 79.05 Maximum U per rod (g) 48.0 230 87.0 Minimum Cool Time (yr) 19 3

18 Maximum Burnup (MWd) 364 363 375 Maximum235U Depletion (%)

87.4 83.6 85.1 Notes:

1.) Heat load limit established by thermal analysis.

2.) Fissile material (235U) mass limit established by criticality analysis.

3.) Fuel (U) mass, cool time, burnup/depletion limit established by shielding analysis.

4.) Payload weight limit established by structural analysis and includes both fuel, caddy weight and dunnage.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-66 Table 1.2-16 HEUNL Characteristics Parameter Value Maximum HEUNL payload per Container 15.35 gal Maximum Cask Heat Load 4.65 W Maximum Per Container Heat Load 1.16 W Maximum HEUNL Heat Load 0.02 W/L Maximum Curie Content (gamma emitters) 1 9.0 Ci/L Maximum 235U content2 7.4 g 235U/L Maximum 235U enrichment 2 93.4 wt%

1 Maximum Curie content defined by source term and shielding evaluations.

2 Maximum 235U content and enrichment defined by criticality evaluation.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-67 Table 1.2-17 SLOWPOKE Fuel Core Parameter Value Maximum Cask Heat Load (W) 45 Payload Limit (lb) 15 Maximum Number of Rods per Core 298 Maximum Initial 235U per rod (g) 2.83 Maximum Initial Enrichment (wt % 235U) 95.3 Maximum Initial 235U per core (g) 837 Minimum Initial Enrichment (wt% 235U) 90 Minimum Cool Time 2 weeks Maximum Core Average Depletion (%235U) 2.1%

Notes:

1 Heat load limit established by thermal analysis.

2 Maximum number of rods per core, fissile material (235U) initial mass per rod limit, and maximum initial enrichment established by criticality analysis.

3 Fissile material (235U) initial mass per fuel core, minimum initial enrichment, depletion percentage, and cool time established by shielding analysis.

4 Payload weight limit established by structural analysis.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-68 Table 1.2-18 EFN Rods, Booster Rods, and Moly Targets Parameter Short Moly Double Length Moly EFN Boosters Maximum Per Caddy Heat Load (W) 0.3 0.8 8

0.2 Payload Limit (lb/tube) 20

1. Rod/Targets (Equivalent) 20 36 36 16 Maximum 235U per rod (g) 1.1 2.41 13 18.1 Minimum Cool Time (yr) 38 8

23 37 Maximum 235U Depletion (%)

94.8 30.4 87.4 2.9 Maximum Initial Enrichment (wt% 235U) 94 Notes:

1.) Fissile material (235U) mass limit established by criticality and shielding analysis.

2.) Cool time, burnup/depletion limit established by shielding analysis.

3.) Payload weight limit established by structural analysis and includes both fuel, caddy/caddy plug weight and dunnage.

4.) Depletion percentage may be generated on a per assembly basis for EFN rods and Booster rods and on a rod basis for the Moly Targets. Assemblies are disassembled into rods/rods segments prior to loading into caddy. Moly rods are disassembled into the component targets.

Table 1.2-19 SrF2 Capsules Parameter WESF Capsules BUP-500 Capsules Maximum Cask Heat Load (W) 2400 2200 Maximum Per Capsule Heat Load (W) 400 1100 Maximum Activity per Cask (Ci90Sr) 1.062E+06 3.52E+05 Payload Limit (lb) 396 300

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 1.2-69 Table 1.2-20 LANL MOX Fuel Rod Characteristics Parameter PNNL EXXON UO2 ROD 1063 530-000 NIS5 Max. rod OD (inch) 0.565 0.451 0.229 0.55 0.63 0.5 Min. wall thick. (inch) 0.035 0.035 0.015 0.015 0.015 0.015 Rod material Zr Alloy Zr Alloy SS304 Zr Alloy Zr Alloy SS316 Max. active length (inch) 35.6 70 36.1 47.913 18 13.5 Max. pellet OD (inch) 0.486 0.372 0.1988 0.48 0.56 0.31 Max. # of rods per transfer tube 4

2 8

3 1

3 Max. # of tubes per cask 16 16 16 6

1 4

Fuel form Oxide Oxide Oxide Oxide Oxide or Carbide Carbide 235U wt%

0.712 0.712 94 0

0 94 240Pu wt%

16 16 0

10 10 4

Pu wt%

5.36 6.31 0

100 100 20 U-235 (g/rod) 6.76 7.71 159.9 0

0 159.58 U (g/rod) 949.85 1083.44 170.11 0

0 169.76 Pu (g/rod) 56.29 76.35 0

1378.77 922.01 42.38 Total U/Pu (g/rod) 1006.14 1159.79 170.11 1378.77 922.01 212.14 Note:

1.) Fissile Pu-239 and Pu-241 comprise the remaining plutonium. A 9 to 1 ratio of Pu-239 to Pu-241 bounds the range of Pu-240 weight fractions analyzed herein.

2.) Maximum number of tubes for ROD1063 and NIS5 is governed by the damaged fuel evaluation.

NAC-LWT Cask SAR April 2024 Revision 24B Table of Contents (continued)

NAC International 2-iii 2.6.12.12 TPBAR Basket with the PWR/BWR Rod Transport Canister................................................................................... 2.6.12-92 2.6.12.13 SLOWPOKE Fuel Canister Assembly................................... 2.6.12-95 2.6.12.14 NRU/NRX Fuel Basket......................................................... 2.6.12-107 2.6.12.15 HEUNL Containers............................................................... 2.6.12-125 2.6.12.16 SLOWPOKE Fuel Core Basket............................................ 2.6.12-138 2.6.12.17 SrF2 Baskets.......................................................................... 2.6.12-141 2.6.12.18 LANL MOX Fuel Transfer Tubes....................................... 2.6.12-147 2.6.12.19 Conclusion............................................................................ 2.6.12-149 2.7 Hypothetical Accident Conditions............................................................................... 2.7-1 2.7.1 Free Drop (30 Feet)....................................................................................... 2.7.1-1 2.7.1.1 End Drop..................................................................................... 2.7.1-2 2.7.1.2 Side Drop.................................................................................... 2.7.1-5 2.7.1.3 Oblique Drops........................................................................... 2.7.1-10 2.7.1.4 Shielding for Lead Slump Accident.......................................... 2.7.1-18 2.7.1.5 Bolts - Closure Lid (Hypothetical Accident - Free Drop)........ 2.7.1-19 2.7.1.6 Crush......................................................................................... 2.7.1-20 2.7.1.7 Rod Shipment Can Assembly Analysis.................................... 2.7.1-21 2.7.2 Puncture........................................................................................................ 2.7.2-1 2.7.2.1 Puncture - Cask Side Midpoint................................................... 2.7.2-1 2.7.2.2 Puncture - Center of Cask Closure Lid....................................... 2.7.2-3 2.7.2.3 Puncture - Center of Cask Bottom.............................................. 2.7.2-6 2.7.2.4 Puncture - Port Cover.................................................................. 2.7.2-9 2.7.2.5 Puncture Accident - Shielding Consequences.......................... 2.7.2-17 2.7.2.6 Puncture - Conclusion............................................................... 2.7.2-17 2.7.3 Fire

........................................................................................................... 2.7.3-1 2.7.3.1 Discussion................................................................................... 2.7.3-1 2.7.3.2 Thermal Stress Evaluation.......................................................... 2.7.3-1 2.7.3.3 Bolts - Closure Lid (Hypothetical Accident - Fire).................... 2.7.3-3 2.7.3.4 Inner Shell Evaluation................................................................. 2.7.3-4 2.7.3.5 Conclusion.................................................................................. 2.7.3-5 2.7.4 Immersion - Fissile Material......................................................................... 2.7.4-1 2.7.5 Immersion - Irradiated Nuclear Fuel Packages............................................ 2.7.5-1 2.7.5.1 Method of Analysis..................................................................... 2.7.5-1 2.7.5.2 Closure Lid Stresses.................................................................... 2.7.5-1 2.7.5.3 Outer Bottom Head Forging Stresses......................................... 2.7.5-2 2.7.5.4 Cask Cylindrical Shell Stresses.................................................. 2.7.5-3 2.7.5.5 Containment Seal Evaluation...................................................... 2.7.5-5 2.7.6 Damage Summary......................................................................................... 2.7.6-1 2.7.7 Fuel Basket / Container Accident Analysis.................................................. 2.7.7-1 2.7.7.1 Discussion................................................................................... 2.7.7-1 2.7.7.2 PWR Basket Construction.......................................................... 2.7.7-1 2.7.7.3 PWR Basket Analysis................................................................. 2.7.7-1 2.7.7.4 BWR Basket Construction.......................................................... 2.7.7-3

NAC-LWT Cask SAR April 2024 Revision 24B Table of Contents (continued)

NAC International 2-iv 2.7.7.5 Metallic Fuel Basket Analysis.................................................... 2.7.7-6 2.7.7.6 MTR Fuel Basket Construction.................................................. 2.7.7-8 2.7.7.7 Conclusion................................................................................ 2.7.7-18 2.7.7.8 PWR Spacer.............................................................................. 2.7.7-18 2.7.7.9 TRIGA Fuel Basket Thirty-Foot Drop Evaluation................... 2.7.7-24 2.7.7.10 DIDO Fuel Basket Construction............................................... 2.7.7-47 2.7.7.11 General Atomics IFM Basket Construction.............................. 2.7.7-51 2.7.7.12 TPBAR Basket Analysis........................................................... 2.7.7-54 2.7.7.13 ANSTO Basket Analysis.......................................................... 2.7.7-66 2.7.7.14 TPBAR Basket with the PWR/BWR Rod Transport Canister. 2.7.7-70 2.7.7.15 SLOWPOKE Fuel Canister Assembly..................................... 2.7.7-72 2.7.7.16 NRU/NRX Fuel Basket............................................................. 2.7.7-89 2.7.7.17 HEUNL Container.................................................................... 2.7.7-98 2.7.7.18 SLOWPOKE Fuel Core Basket for the Accident Conditions of Transport............................................................................. 2.7.7-103 2.7.7.19 SrF2 Baskets............................................................................ 2.7.7-105 2.7.7.20 LANL MOX Fuel Transfer Tubes.......................................... 2.7.7-110 2.8 Special Form

...................................................................................................... 2.8-1 2.9 Spent Fuel Contents..................................................................................................... 2.9-1 2.9.1 PWR and BWR Fuel Rods............................................................................... 2.9-1 2.9.2 TRIGA Fuel Elements..................................................................................... 2.9-1 2.9.2.1 End Drop........................................................................................ 2.9-2 2.9.2.2 Side Drop....................................................................................... 2.9-3 2.9.3 PULSTAR Intact Fuel Elements...................................................................... 2.9-5 2.9.4 ANSTO Fuels................................................................................................... 2.9-6 2.9.4.1 MARK III Spiral Fuel Assemblies................................................ 2.9-6 2.9.4.2 MOATA Plate Bundles................................................................ 2.9-10 2.9.4.3 DIDO Fuel Assemblies................................................................ 2.9-14 2.9.5 SLOWPOKE Fuel Core Assembly................................................................ 2.9-21 2.9.5.1 Normal Conditions of Transport.................................................. 2.9-21 2.9.5.2 Accident Conditions of Transport................................................ 2.9-22 2.9.5.3 SLOWPOKE Structural Calculation............................................ 2.9-24 2.9.6 SrF2 Capsules................................................................................................. 2.9-25 2.10 Appendices.............................................................................................................. 2.10.1-1 2.10.1 Computer Program Descriptions................................................................. 2.10.1-1 2.10.1.1 ANSYS..................................................................................... 2.10.1-1 2.10.1.2 RBCUBED - A Program to Calculate Impact Limiter Dynamics.................................................................................. 2.10.1-2 2.10.2 Finite Element Model Description.............................................................. 2.10.2-1 2.10.2.1 Boundary and Loading Conditions Used in the 30-Foot Drop Finite Element Analysis................................................... 2.10.2-2 2.10.3 Finite Element Evaluations......................................................................... 2.10.3-1 2.10.3.1 Isothermal Plot - Hot Case........................................................ 2.10.3-1 2.10.3.2 Isothermal Plot - Cold Case...................................................... 2.10.3-1

NAC-LWT Cask SAR April 2024 Revision 24B List of Figures (continued)

NAC International 2-ix Figure 2.6.12-20 Stress Linearization Paths in Closure Lid.......................................... 2.6.12-134 Figure 2.6.12-21 Stress Linearization Paths in Fill/Drain Ports.................................... 2.6.12-137 Figure 2.7.1-1 30-Foot Bottom End Drop with 130°F Ambient Temperature and Maximum Decay Heat Load.................................................................. 2.7.1-30 Figure 2.7.1-2 30-Foot Bottom End Drop with -40°F Ambient Temperature and Maximum Decay Heat Load.................................................................. 2.7.1-31 Figure 2.7.1-3 30-Foot Bottom End Drop with -40°F Ambient Temperature and No Decay Heat Load.............................................................................. 2.7.1-32 Figure 2.7.1-4 30-Foot Top End Drop with 130°F Ambient Temperature and Maximum Decay Heat Load.................................................................. 2.7.1-33 Figure 2.7.1-5 30-Foot Top End Drop with -40°F Ambient Temperature and Maximum Decay Heat Load.................................................................. 2.7.1-34 Figure 2.7.1-6 Circumferential Load Distribution for Cask Side Drop Impact............. 2.7.1-35 Figure 2.7.1-7 Six Term Fourier Series Representation of Circumferential Load Distribution for Cask Side Drop Impact................................................ 2.7.1-36 Figure 2.7.1-8 NAC-LWT Cask Critical Sections (30-Foot Side Drop with 100°F Ambient Temperature)........................................................................... 2.7.1-37 Figure 2.7.1-9 Circumferential Load Distribution for Cask Oblique Drop Impact....... 2.7.1-38 Figure 2.7.1-10 30-Foot Top Corner Drop with 130°F Ambient Temperature - Drop Orientation = 15.74 Degrees.................................................................. 2.7.1-39 Figure 2.7.1-11 30-Foot Top Oblique Drop with 130°F Ambient Temperature -

Drop Orientation = 30 Degrees.............................................................. 2.7.1-40 Figure 2.7.1-12 30-Foot Top Oblique Drop with 130°F Ambient Temperature -

Drop Orientation = 45 Degrees.............................................................. 2.7.1-41 Figure 2.7.1-13 30-Foot Oblique Drop with 130°F Ambient Temperature - Drop Orientation = 60 Degrees....................................................................... 2.7.1-42 Figure 2.7.1-14 30-Foot Top Corner Drop with -40°F Ambient Temperature - Drop Orientation = 15.74 Degrees.................................................................. 2.7.1-43 Figure 2.7.1-15 30-Foot Top Oblique Drop with -40°F Ambient Temperature -

Drop Orientation = 30 Degrees............................................................. 2.7.1-44 Figure 2.7.1-16 30-Foot Top Oblique Drop with -40°F Ambient Temperature -

Drop Orientation = 45 Degrees.............................................................. 2.7.1-45 Figure 2.7.1-17 30-Foot Top Oblique Drop with -40°F Ambient Temperature -

Drop Orientation = 60 Degrees.............................................................. 2.7.1-46 Figure 2.7.1-18 30-Foot Bottom Oblique Drop with 130°F Ambient Temperature -

Drop Orientation = 15.74 Degrees......................................................... 2.7.1-47 Figure 2.7.1-19 30-Foot Bottom Oblique Drop with 130°F Ambient Temperature -

Drop Orientation = 30 Degrees.............................................................. 2.7.1-48 Figure 2.7.1-20 30-Foot Bottom Oblique Drop with 130°F Ambient Temperature -

Drop Orientation = 45 Degrees.............................................................. 2.7.1-49 Figure 2.7.1-21 30-Foot Bottom Oblique Drop with 130°F Ambient Temperature -

Drop Orientation = 60 Degrees.............................................................. 2.7.1-50

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 2.2.1-3 Table 2.2.1-1 Weights of the NAC-LWT Cask Major Components (cont.)

Component Weight (pounds)

Axial Center of Gravity Location (inches)

HEUNL Container & Spacer7 1,446 104 HEUNL Payload 704 98 SLOWPOKE Fuel Core Basket & Five MTR Baskets 1,160 108 SLOWPOKE Fuel Core Payload 15 164 WESF Basket, Lid Spacer & Container8 1,972 99 WESF Payload 396 99 BUP-500 Basket 1,694 97 BUP-500 Payload & Spacers9 408 98 LANL MOX Payload 1,490 95 7 Includes 4 HEUNL Containers, Container Guide and Container Spacer.

8 Includes 1 Lid Spacer and 6 WESF Containers.

9 Two BUP-500 canisters (150 lbs each) are loaded with three spacers (36 lbs each) to maintain axial position. The C.G. is presented in the loaded configuration.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 2.2.1-5 Table 2.2.1-2 Weights and Center of Gravity Locations for the NAC-LWT Cask Shipping Configurations (contd)

Component Weight (pounds)

Axial Center of Gravity Location (inches)

Package - Loaded for Shipment TPBARs in the PWR/BWR Rod Transport Canister 49,109 99.2 Package - Empty for Shipment (TPBAR Basket for PWR/BWR Rod Transport Canister) 47,783 99.1 Package - Loaded for Shipment (SLOWPOKE Fuel, Four Unit Basket) 1 49,030 99.1 Package - Empty for Shipment (SLOWOKE Fuel, Four Unit Basket) 48,190 98.9 Package - Loaded for Shipment (NRU/NRX Basket with Fuel Assemblies and Caddy containing rods/targets) 41,111 97.0 Package - Empty for Shipment (NRU/NRX Basket) 40,751 96.8 Package - Empty for Shipment (HEUNL) 48,656 99.2 Package - Loaded for Shipment (HEUNL) 49,360 99.2 Package - Loaded for Shipment (SLOWPOKE Fuel Core, Basket, Five MTR Baskets)2 48,400 99.3 Package - Empty for Shipment (SLOWPOKE Fuel Core Basket, Five MTR Baskets)2 48,400 99.3 Package - Empty for Shipment (WESF) 49,180 99.1 Package - Loaded for Shipment (WESF) 49,576 99.1 Package - Empty for Shipment (BUP-500) 48,902 99.0 Package - Loaded for Shipment (BUP-500) 49,310 99.0 Package - Loaded for Shipment (LANL MOX Fuel Rods) 49,572 99.2 Package - Empty for Shipment (LANL MOX Fuel Rods) 49,377 99.2 Package - Design for Shipment 52,000 98.93 1 A fuel weight of 30 lbs/assembly is used to compute the weight for this table as compared to the maximum weight for the SLOWPOKE canister of 25 pounds.

2 Weight rounded up to nearest 100 pounds.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 2.6.12-2 provided for the cask drain tube. The drain tube is connected to a fitting on the cask body, and is used to drain or fill the cask during cask loading or unloading operations.

For the shipment of up to 25 PWR or BWR rods, or up to 16 PWR MOX rods (or mixed MOX and UO2 rods), a canister with insert will be utilized to position the fuel rod contents within the PWR basket. Similarly, LANL MOX Fuel Rods may be loaded in up to 16 transfer tubes in the canister within the PWR basket. The canister for the fuel rods will be fabricated from Type 304 stainless steel (minimum thickness 0.12 inch) and will be designed to allow positive handling of the canister during loading and unloading operations. The size, shape, closure design and capacity of the canister will vary depending on the requirements of the shipping and/or receiving facilities. A spacer fabricated from stainless steel will be utilized, as required, to position the PWR/BWR rod canister longitudinally within the NAC-LWT cask cavity. A PWR insert fabricated from 6061-T651 aluminum is used to laterally position the rod canister within the PWR basket. The total weight of the fuel rods, canister and basket insert will be less than the maximum PWR fuel assembly payload weight of 1,650 pounds. Therefore, the up to 25 fuel rods content condition is bounded by the current PWR basket analyses.

2.6.12.3 PWR Basket Analysis The minimum ambient temperature during normal transport, -40°F, combined with the maximum decay heat load produces an average inner wall temperature of 151°F. The 6061-T6 aluminum alloy expands approximately 1.5 times more per degree Fahrenheit than stainless steel.

Assuming that both the cask and basket respond linearly, the maximum as-designed gap between the basket and the cavity, when the basket is centered in the cavity, is 0.094 in. Since aluminum expands faster than stainless steel, any increase in temperature will serve to decrease the basket-cavity gap. Since the gap is small, it is assumed that there is no relative motion between the basket and cask, and that the basket is in contact bearing on the inner shell during a side drop.

The basket bearing loads are transmitted to the inner shell and cask structure.

2.6.12.3.1 Bearing Stress Calculation The bearing stress is calculated using Case 6 (Roark, page 320), which models the cylindrical basket in a circular groove. The maximum compressive stress is calculated using:

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 2.6.12-125 2.6.12.15 HEUNL Container 2.6.12.15.1 Finite Element Models HEUNL Container FEA Model The finite element model (FEA) was constructed of ANSYS SOLID45 3D elements and CONTAC52 gap elements. Both the HEUNL container and contained fluid were modeled. There NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 2.6.12-147 2.6.12.18 LANL MOX Fuel Transfer Tubes The LWT Transport Cask LANL MOX shipping configuration (drawing 315-40-188) consists of the LWT cask body assembly, the PWR basket assembly, PWR insert and the rod transport canister assembly, containing 16 transfer tubes (drawing 315-40-189) loaded with the LANL MOX Fuel Rods. As needed, stainless steel dunnage may also be inserted into the rod transport cannister assembly to provide additional configuration control. Note that LANL MOX shipping configuration utilizes the same rod transport can assembly and supporting cask internal structures used to ship high burnup rods within a 4x4 or 5x5 insert. In the LANL MOX configuration, the insert (4x4 or 5x5) is replaced by 16 transfer tubes and the content weight for the rod transport canister including permitted dunnage is 130 pounds less than that for the high burnup configuration. The rod transport canister assembly is evaluated in Section 2.6.7.10 and Section 2.7.1.7 for normal and accident conditions, respectively, for the transport of high burnup rod configuration. The content weight and material property temperatures used in the evaluation of the rod transport canister bound those of the LANL MOX configuration. Therefore, the rod transport canister assembly evaluations (as documented in Sections 2.6.7.10 and 2.7.1.7) are bounding and applicable to the same rod transport canister assembly with LANL MOX content.

No further evaluation is required for the rod transport canister assembly or other cask internal structures.

The following sections present the evaluation of the transfer tubes for the end drop and side drop of normal conditions of transport. Note that the maximum heat load for LANL MOX fuel is 25 Watts per cask. Material properties and allowable stresses used in the evaluation are determined at a conservative temperature of 300°F since the maximum temperature for the LANL MOX configuration is less than 300°F during normal conditions of transport.

Additionally, the transfer tube assembly may be fabricated from Type 304 or 316 stainless steel.

Since, the mechanical properties of Type 316 stainless steel are greater than or equal to those of Type 304 stainless steel, the properties of Type 304 are considered in the transfer tube analyses for NCT and HAC.

2.6.12.18.1 Transfer Tubes - End Drop In the end drop condition, the transfer tubes are subjected to inertia load due to self-weight (Wt) with a normal condition end drop acceleration (gend) of 15.8g per Table 2.6.7-32. The transfer tubes are evaluated for membrane stresses () as shown in the following table. Design Stress Intensity (Sm) is used as the allowable stress limit for primary membrane stresses per Table 2.1.2-2. The transfer tubes are made of Type 304 stainless steel. Sm is 20.0 ksi for Type 304 stainless steel at 300°F. As shown in the following table, the margins of safety are Large.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 2.6.12-148 Transfer tube spacer may be used between the LANL MOX Fuel Rods inside the transfer tube.

The membrane stress for the tube spacer is calculated to be 0.74 ksi using a bounding weight of 12.2 lb. for the transfer tube content (with the end drop acceleration of 15.8g), a cross-sectional area of 0.26 in2. The margin of safety is also Large based on a design stress intensity of 14.9 ksi (Sm for Type 430 stainless steel at 300°F).

The shear stress in the optional fillet weld between the transfer tube wall and the end cap is evaluated. In the end drop, the weld is subjected to the inertia load of the transfer tube wall (43.9 lb.) only. The shear stress in the weld is calculated to be 1.13 ksi based on the effective area of the fillet weld (0.039 in2). The margin of safety is +2.7 based on the allowable stress of 0.6Sm for shear stress and a weld quality factor of 0.35 (ASME B&PV Code,Section III, Subsection NG, Table NG-3352-2). Sm is 20 ksi for the base metal (Type 304 stainless steel at 300°F).

2.6.12.18.2 Transfer Tubes - Side Drop The transfer tubes have an identical geometry and equivalent or slightly stronger material compared to the 5x5 insert tubes used for the high burnup shipping configuration, which were evaluated for the side drop conditions of transport in Section 2.6.7.10. The temperature used for the evaluation of the insert tubes in Section 2.6.7.10 is significantly higher than the maximum temperature of the LANL MOX transfer tubes. The loaded tube weight used in evaluation in Section 2.6.7.10 is higher than the bounding weight of one loaded LANL MOX transfer tube weldment. The margin of safety for bending stress due to side drop is +1.07 for the 5x5 insert tubes. Therefore, the tube side drop evaluations for the high burnup configuration are applicable and bounding for the LANL MOX transfer tubes and no additional side drop evaluations are required for the LANL MOX transfer tubes.

NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 2.6.12-149 2.6.12.19 Conclusion NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 2.7.7-110 2.7.7.20 LANL MOX Fuel Transfer Tubes As discussed in Section 2.6.12.18, the LWT Transport Cask LANL MOX shipping configuration consists of the LWT cask body assembly, the PWR basket assembly, PWR insert and the rod transport canister assembly, containing 16 transfer tubes loaded with LANL MOX Fuel Rods.

The evaluation of the rod transport canister assembly in Section 2.7.1.7 for accident conditions of transport for the high burnup rod configuration are bounding and applicable to the same rod transport canister assembly with LANL MOX content. No further evaluation is required for the rod transport canister assembly or other cask internal structures. The following sections present the evaluation of the transfer tubes for the end drop and side drop of accident conditions of transport.

2.7.7.20.1 Transfer Tubes - End Drop In the end drop condition, the transfer tubes are subjected to inertia load due to self-weight (Wt) with an end drop acceleration (gend) of 60g (bounding g-load for 30-foot end drop as shown in Table 2.6.7-33). The transfer tubes are evaluated for membrane stresses ( as shown in the following table. 0.7xUltimate strength (Su) is used as the allowable stress limit for primary membrane stresses for accident conditions per Table 2.1.2-2. The transfer tubes are made of Type 304 stainless steel. Su is 66.2 ksi for Type 304 stainless steel at 300°F. As shown in the following table, the margins of safety are Large.

NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 2.7.7-111 Transfer tube spacer may be used between the LANL MOX Fuel Rods inside the transfer tube.

The membrane stress for the tube spacer is calculated to be 2.82 ksi using a bounding weight of 12.2 lb. for the transfer tube content (with the end drop acceleration of 60g), a cross-sectional area of 0.26 in2. The margin of safety is also Large based on an allowable (0.7Su) of 37.1 ksi (Su is 53.0 ksi for Type 430 stainless steel at 300°F).

The shear stress in the optional fillet weld between the transfer tube wall and the end cap is evaluated. In the end drop, the weld is subjected to the inertia load of the transfer tube wall (43.9 lb.) only. The shear stress in the weld is calculated to be 4.28 ksi based on the effective area of the fillet weld (0.039 in2). The margin of safety is +0.25 based on the allowable stress of 1.7 x 0.4 x Yield Strength (Sy) for shear stress (ASME B&PV Code, Appendix F, F-1337and NF-3324.5, Table NF-3324.5(a)-1) and a weld quality factor of 0.35 (ASME B&PV Code,Section III, Subsection NG, Table NG-3352-2). Sy is 22.4 ksi for the base metal (Type 304 stainless steel at 300°F).

2.7.7.20.2 Transfer Tubes - Side Drop Based on the discussion in Section 2.6.12.18.2 comparing the geometry, material, temperature, and loaded tube weight between the tube evaluations for the high burnup shipping configuration and the LANL MOX fuel shipping configuration, the evaluations for the side drop accident conditions for the 5x5 insert tubes as presented in Section 2.7.1.7 for the high burnup configuration are applicable and bounding for the LANL MOX transfer tubes and no additional side drop evaluations are required for the LANL MOX transfer tubes.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 3.1-2 or a 5 x 5 insert as presented on the drawings provided in Section 1.4). The high burnup PWR and BWR rods may also be placed in a fuel assembly lattice. Damaged PWR/BWR fuel rods must be placed in a rod holder. The 16 PWR MOX fuel rods are required to be placed in a rod holder with a 5 x 5 insert. Along with the maximum 16 PWR MOX rod contents (or combination of PWR MOX and UO2 PWR fuel rods), the remaining tubes may be loaded with burnable poison rods or other intact components with negligible heat loads (total additional heat load of less than 10 watts). Up to four (4) SLOWPOKE fuel canisters each containing up to 100 SLOWPOKE fuel rods with a maximum decay heat load of 0.625 Watts/canister can be loaded in a MTR basket module. For SLOWPOKE fuel contents, only the top and upper intermediate MTR-28 modules may be loaded. The empty intermediate basket modules and bottom basket modules are installed as axial spacers. The total package decay heat for SLOWPOKE fuel contents in the fuel canister is 5 Watts. In addition, a SLOWPOKE fuel core can be loaded in a SLOWPOKE fuel basket, which is placed on top of empty intermediate basket modules and a bottom MTR-42 fuel basket module. The maximum decay heat of the fuel core is 45 Watts.

LANL MOX Fuel Rods are loaded in up to sixteen (16) transfer tubes, which in turn are loaded in the PWR/BWR transport can assembly. The total allowed heat load for this payload is 25 watts per cask.

An intact PWR fuel assembly with a maximum decay heat load of 2.5 kW is used in a majority of the thermal analyses. The failed fuel basket analysis in Section 3.6 uses a decay heat load of 30 Watts. The 42 MTR fuel assembly basket in Section 3.4.1.3 uses a decay heat load of 1.26 kW. A decay heat load of 1.05 kW is conservatively used for the TRIGA fuel basket analysis and a decay heat load of 0.693 kW is used for the TPBAR basket analysis. The maximum heat load for the PULSTAR fuel is 0.840 kW per cask. The maximum heat load for the maximum number of 16 PWR MOX fuel rods is 2.3 kW per cask (143 W per PWR MOX rod). The maximum heat load for the maximum number of (18) NRU or NRX fuel rod assemblies is 0.64 kW per cask. The maximum heat load for the damaged NRU or NRX fuels remains at 0.64 kW per cask, but 0.80 kW (0.64kWx1.25) per cask is used in thermal evaluation considering the concentration of the NRU/NRX rods. The NRU/NRX basket may also be loaded with EFN rods, Booster rods, or Moly targets and the maximum heat load for a basket slot having this content is less than 8 Watts per basket location. This is bounded by the 35.6 Watts per basket location (640 Watts per cask/18 tubes) for NRU or NRX fuels. The maximum heat load for four (4) HEUNL containers filled to capacity is 4.65 Watts per cask. As long as the decay heat load is within the design limit of 2.5 kW, any of the fuel types and other radioactive material that the NAC-LWT cask is analyzed to transport are bounded by the cask body thermal analyses of the design basis PWR assembly.

The primary heat rejection design criteria for the NAC-LWT cask are that:

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6-viii List of Figures (continued)

Figure 6.7.4-10 VISED X-Z Cross-Section of HEUNL with Inward Shift....................... 6.7.4-16 Figure 6.7.4-11 Cask Cavity Moderator Study Reactivity Results for HEUNL............... 6.7.4-16 Figure 6.7.5-1 MCNP Model Sketch of the NAC-LWT Cask with SLOWPOKE Fuel Core.................................................................................................... 6.7.5-3 Figure 6.7.5-2 VISED Sketch of LWT Radial View - SLOWPOKE Fuel Core.............. 6.7.5-4 Figure 6.7.5-3 VISED Sketch of LWT Axial View - SLOWPOKE Fuel Core - Normal Conditions - Cask Top Portion.................................................................. 6.7.5-5 Figure 6.7.5-4 VISED XY Slice of SLOWPOKE Fuel Core with Spread, Nominal Rod Pitch Configuration.......................................................................... 6.7.5-10 Figure 6.7.5-5 VISED XY Slice of SLOWPOKE Fuel Core with Center Cells Filled, Maximum Rod Pitch Configuration......................................................... 6.7.5-11 Figure 6.7.5-6 SLOWPOKE Fuel Core, Fuel Rod Pitch Study Results.......................... 6.7.5-12 Figure 6.7.5-7 SLOWPOKE Fuel Core Moderator Density Study Results (Percent Full Density Water)......................................................................................... 6.7.5-13 Figure 6.7.5-8 VISED XZ Slice of SLOWPOKE Fuel Core with Licensed Basket Model....................................................................................................... 6.7.5-14 Figure 6.7.6-1 EFN, Moly and Booster Rod Illustrations................................................. 6.7.6-8 Figure 6.7.6-2 Caddy NRU HEU Sample Model - 36 Rods - 3 Center Rods.................. 6.7.6-9 Figure 6.7.6-3 Caddy NRU HEU Sample Model - 37 Rods - 1 Center Rod.................... 6.7.6-9 Figure 6.7.6-4 Caddy NRU HEU Sample Model - 37 Rods Hex Array......................... 6.7.6-10 Figure 6.7.6-5 Caddy NRU Complete Clad Removal keff-Pattern and # Rod Segment Study......................................................................................... 6.7.6-10 Figure 6.7.6-6 Caddy NRU Clad Removal versus Minimum Clad keff Study................. 6.7.6-11 Figure 6.7.6-7 NRU to EFN Comparison keff Study........................................................ 6.7.6-11 Figure 6.7.6-8 Moly Rod Segment keff Study.................................................................. 6.7.6-12 Figure 6.7.6-9 Moly Inner Alternate Model with Caddy Moved Out............................. 6.7.6-13 Figure 6.7.6-10 Moly Inner Alternate Model with Rod Segments Moved Out................. 6.7.6-13 Figure 6.7.6-11 Booster Rod Clad Removal keff-Pattern and # Rod Segment Study....... 6.7.6-14 Figure 6.7.6-12 Booster Rod Maximum Reactivity Segment Configuration (57 Rods Segments)................................................................................. 6.7.6-14 Figure 6.7.6-13 Caddy NRU Moderator Density Study.................................................... 6.7.6-15 Figure 6.7.6-14 Booster Moderator Density Study............................................................ 6.7.6-15 Figure 6.7.7-1 VISED Sketch of LWT Radial View - Normal Conditions (Cask and Basket Detail)............................................................................ 6.7.7-3 Figure 6.7.7-2 VISED Sketch of LWT Axial View - Normal Conditions........................ 6.7.7-4 Figure 6.7.7-3 LANL MOX Fuel Rods Moderator Density Study.................................. 6.7.7-11 Figure 6.7.7-4 LANL MOX Fuel Rods Damaged Fuel Height Study............................. 6.7.7-12 Figure 6.7.7-5 LANL MOX Fuel Rods Damaged Fuel Underloading Rod Loading Patterns..................................................................................................... 6.7.7-13 Figure 6.7.7-6 LANL MOX Fuel Rods Damaged Fuel Underloading Results -

ROD1063 at 6 Tubes................................................................................ 6.7.7-14 Figure 6.7.7-7 LANL MOX Fuel Rods Damaged Fuel Underloading Results - NIS5 at 4 Tubes and 530-000 at 1 Tube............................................................ 6.7.7-15 Figure 6.7.7-8 LANL MOX Fuel Rods Moderator Density Study - Damaged Fuel...... 6.7.7-16

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6-xix List of Tables (continued)

Table 6.7.5-8 Area of Applicability for SLOWPOKE Fuel Core Validation................ 6.7.5-16 Table 6.7.5-9 Comparison of Modeled and Licensed Basket Reactivity for the SLOWPOKE Fuel Core.......................................................................... 6.7.5-16 Table 6.7.6-1 NRU Physical and Material Comparison to EFN, Moly, and Booster Rods/Targets............................................................................................ 6.7.6-16 Table 6.7.6-2 Caddy NRU Complete Clad Removal keff as a Function of Number of Rod Segments..................................................................................... 6.7.6-17 Table 6.7.6-3 Caddy NRU Comparison of a Full Cask Load versus Outer Tubes Only.............................................................................................. 6.7.6-17 Table 6.7.6-4 Caddy NRU Minimum Clad (0.02 cm equivalent Clad Thickness)........ 6.7.6-17 Table 6.7.6-5 Caddy NRU to EFN Comparison............................................................ 6.7.6-18 Table 6.7.6-6 Study on Moly Target with NRU in Outer Tube Locations.................... 6.7.6-18 Table 6.7.6-7 Booster Rod Complete Clad Removal keff as a Function of Number of Rod Segments..................................................................................... 6.7.6-19 Table 6.7.6-8 Caddy NRU Model with Minimum Clad Moderator Density Study....... 6.7.6-20 Table 6.7.6-9 Booster Rod Model with No Clad Moderator Density Study.................. 6.7.6-21 Table 6.7.6-10 Limitation on EFN and Booster Rods and Moly Targets........................ 6.7.6-22 Table 6.7.7-1 LANL MOX Fuel Rods Basket/Cask Compositions and Number Densities...................................................................................... 6.7.7-5 Table 6.7.7-2 LANL MOX Fuel Rods Compositions and Number Densities................. 6.7.7-5 Table 6.7.7-3 LANL MOX Fuel Rods Reactivity as a Function of Rod Type.............. 6.7.7-17 Table 6.7.7-4 LANL MOX Fuel Rods Reactivity as a Function of Divider Thickness and Rod Pitch......................................................................... 6.7.7-17 Table 6.7.7-5 LANL MOX Fuel Rods Reactivity Summary for Accident Condition Array Cases............................................................................ 6.7.7-17 Table 6.7.7-6 LANL MOX Fuel Rods Reactivity Summary for Single Cask Containment Fully Reflected Cases........................................................ 6.7.7-17 Table 6.7.7-7 LANL MOX Fuel Rods Reactivity Summary for Normal Condition Array Cases............................................................................ 6.7.7-18 Table 6.7.7-8 LANL MOX Fuel Rods Reactivity Summary for Damaged Fuel Height Study............................................................................................ 6.7.7-18 Table 6.7.7-9 LANL MOX Fuel Rods Reactivity Summary for Damaged Fuel Underloading Study................................................................................. 6.7.7-18 Table 6.7.7-10 LANL MOX Fuel Rods Reactivity Summary for Accident Condition Array Cases - Damaged Fuel.................................................................. 6.7.7-18 Table 6.7.7-11 LANL MOX Fuel Rods Reactivity Summary for Single Cask Containment Fully Reflected Cases - Damaged Fuel............................. 6.7.7-19 Table 6.7.7-12 LANL MOX Fuel Rods Summary of Maximum Reactivity Configurations......................................................................................... 6.7.7-19 Table 6.7.7-13 LANL MOX Fuel Rods MOX Comparison to Area of Applicability..... 6.7.7-19 Table 6.7.7-14 LANL MOX Fuel Rods UO2 Comparison to Area of Applicability....... 6.7.7-19

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-1 6.7.7 LANL MOX Fuel Rods This section includes input, analysis method, results, and criticality benchmark applicability evaluations for the NAC-LWT cask containing a payload of up to 16 transfer tubes loaded with LANL MOX Fuel Rods, see list in Table 1.2-20. The fuel rods may be composed of uranium oxide fuel pellets, plutonium oxide fuel pellets, mixed oxide fuel pellets, plutonium carbide fuel pellets, or mixed carbide fuel pellets.

6.7.7.1 Package Fuel Loading The NAC-LWT cask may transport up to 16 transfer tubes with undamaged fuel rods. There are six unique rod types that bound the rods intended for shipment. Characteristics and quantity limits of the design basis fuel rods are presented in Table 1.2-20. Each of the rods is significantly shorter than the transfer tube array. The allowed number of rods per transfer tube shown in Table 1.2-20 are based on the number of rods that will physically fit into a transfer tube, except for fuel type 530-000, where only one rod is authorized per transfer tube, despite there being space for more than one.

6.7.7.2 Criticality Model Specifications This section describes the models that are used in the criticality analyses for the NAC-LWT cask containing up to 16 transfer tubes loaded with LANL MOX Fuel Rods. The rods consist of natural uranium mixed with plutonium, highly enriched uranium with no plutonium, plutonium rods with no uranium, or highly enriched uranium with plutonium. The models are analyzed separately under normal conditions and hypothetical accident conditions to ensure that all possible configurations are subcritical.

The model uses the MCNP6.2 code package with the ENDF/B-VI cross-section set. No cross-section pre-processing is required prior to MCNP implementation. MCNP uses the Monte Carlo technique to calculate the keff of a system. In these analyses, approximately 1000 cycles with 10,000 neutron histories per cycle are tracked through the system. There are no statistical differences between MCNP6.2 and MCNP5, which was used for the UO2 and MOX validations in Section 6.5.4.

Description of Calculational Models The MCNP model of the NAC-LWT cask with up to 16 transfer tubes includes a 4x4 array of transfer tubes in the PWR insert and can weldment. No credit is taken for the divider plate; this is acceptable as parasitic absorption is removed from the system and the maximum rod pitch is larger. The cask is explicitly modeled and identical to the model shown in Figure 6.7.1-1.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-3 Figure 6.7.7-1 VISED Sketch of LWT Radial View - Normal Conditions (Cask and Basket Detail)

NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-6 6.7.7.3 Criticality Calculations This section presents the criticality analysis for the NAC-LWT cask with up to 16 transfer tubes loaded with LANL MOX Fuel Rods. As stated above, there are six rod types that bound the rods intended for shipment. The rods consist of natural uranium mixed with plutonium, highly enriched uranium with no plutonium, plutonium rods with no uranium, or highly enriched uranium with plutonium.

The baseline evaluation considers undamaged fuel. As no structural evaluations were performed to assure stability of the rods during HAC, the HAC criticality evaluation is augmented with a damaged fuel evaluation.

6.7.7.3.1 Criticality Evaluation - Undamaged Fuel Criticality results are divided into individual sets of analyses.

Evaluate the NAC-LWT accident configuration to determine the bounding fuel type(s) and rod pitch.

Run the optimum moderator density evaluation.

Evaluate normal condition and single cask containment reflected cases.

Rod Type Study Each of the six rod types is evaluated to determine the bounding fuel type using the thin divider plate and the maximum pitch. Results are shown in Table 6.7.7-3, summarized as follows:

Due to their high plutonium contents, the 530-000 and ROD1063 rods are significantly more reactive than the other rods. These rods are modeled with one and three rods axially per tube, respectively. The contents are limited to one 530-000 rod per tube (and one tube per cask) and three ROD1063 rods per tube (12 tubes per cask). Rod 530-000 is either oxide or carbide. The carbide form (denoted by the -C suffix) is significantly more reactive than the oxide form (denoted by the -O suffix).

The NIS5 carbide rods are modeled with 3 rods axially per tube. These rods are subcritical (keff+2 < 0.51).

The UO2 rods have a small area that allows for more than one rod in the x/y plane.

Therefore, two and four rods per elevation are also considered. These rods are subcritical (keff+2 < 0.67) with up to four rods per elevation (eight per tube).

The PNNL and Exxon rods are natural uranium with a relatively small amount of plutonium. The PNNL rods are modeled with four axially per tube and the Exxon rods are modeled with two axially per tube. These rods are subcritical (keff+2 < 0.41).

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-7 Based on these results, a mixed loading need not be considered. In particular, with the payload limited to a maximum of one 530-000 rod/tube per cask and three ROD1063 rods per tube (12 tubes per cask), 16 tubes of ROD1063 (48 rods per cask) represents a bounding reactivity configuration. ROD1063 is used for the studies that follow.

The next step varies the pitch (for ROD1063). Results are shown in Table 6.7.7-4. The maximum pitch is the most reactive. This configuration maximizes the H/U-235 ratio.

Optimum Moderator Density Evaluation ROD1063 is evaluated at various internal and external moderator densities, including preferential flooding of the fuel region. For the preferential flooding scenarios, the square container containing the rod array is evaluated at a moderator density independent of that in the remainder of the cask cavity. Figure 6.7.7-3 contains the moderator density plot. The maximum reactivity is achieved by a preferentially flooded fuel region and void cavity and cask exterior. This result was to be expected as it provides maximum neutronic coupling within the four-cask array.

Results are summarized in Table 6.7.7-5.

Single Cask Containment (Fully Reflected) and Normal Condition Array Evaluations A single cask evaluation is performed to comply with 10 CFR 71.55(b)(3).

The containment for the NAC-LWT is the cask inner shell. While no operating condition results in a removal of the cask outer shell and lead gamma shield, the most reactive preferential flooded and fully flooded cases are reevaluated by removing the lead and outer shells (including neutron shield), and reflecting the system by 20 cm water at full density on the X, Y, and Z faces. Single cask, containment fully reflected reactivities are summarized in Table 6.7.7-6.

A normal condition infinite cask array is also evaluated. As indicated by the evaluations of the accident conditions array, including the radial neutron shield reduces system reactivity by eliminating neutronic interaction between casks. Normal condition cask array results are summarized in Table 6.7.7-7.

6.7.7.3.2 Criticality Evaluation - Damaged Fuel As no structural evaluations were performed to assure stability of the rods during HAC, the HAC criticality evaluation is augmented with a damaged fuel evaluation. The required transfer tube spacers at the top and bottom of the transfer tube will assure gross fuel material confinement within the handling tube. No credit is applied to intermediate handling tube spacers for separation of fissile material. A conservative criticality evaluation removes all rod structural material (e.g., clad and end plugs) and evaluates optimal moderation within the handling tube via fuel/water mixture height studies.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-8 Material Homogenization The first step in developing the damaged fuel model is the material homogenization. The fuel/water mixture is smeared across the cross-sectional area of the transfer tube. The height of the fuel/water mixture is varied in 5 cm increments to capture the maximum reactivity height.

The minimum mixture height is governed by the fuel volume and the maximum mixture height is governed by the transfer tube interior height.

Rod Type Study Only the most reactive rod types from the undamaged fuel evaluation require study. A full cask load of 16 transfer tubes is evaluated at the maximum pitch. As expected, maximum reactivity values are greater than those shown in Section 6.7.7.3.1 due to optimizing the H/U or H/Pu ratio.

Results are shown in Figure 6.7.7-4 and Table 6.7.7-8, summarized as follows:

ROD1063 will require an underloaded cask. A mixture height below the minimum shown in the graph (215 cm) is not physically feasible.

Up to eight UO2 rods per tube have keff+2 < 0.77.

The NIS5 rods (analyzed using ELR1) have keff+2 < 0.73. These rods are logical candidates for also loading 530-000 (only one in the inventory).

The PNNL and EXXON rods have keff+2 < 0.47. For PNNL rods, a mixture height above the maximum shown in the graph (415 cm) is not physically feasible.

Underloading Study Underloadings are evaluated for the ROD1063 loading and NIS5/530-000 mixed loading.

Varying rod patterns are evaluated for each of these underloadings, shown in Figure 6.7.7-5.

A six tube configuration is analyzed for ROD1063 with 10 empty tubes. Results are shown in Figure 6.7.7-6 and Table 6.7.7-9. The maximum reactivity is less than that in Section 6.7.7.3.1 for undamaged rods in 16 transfer tubes. Loadings of six tubes at 2 rods/tube and 1 rod/tube yields decreased reactivity.

The NIS5 rods are evaluated using four tubes in addition to one tube with one 530-000 rod (the remaining 11 tubes are empty). Results are shown in Figure 6.7.7-7 and Table 6.7.7-9.

Optimum Moderator Density Evaluation The UO2 rods are the most reactive for damaged fuel for a full loading of 16 transfer tubes.

These rods are evaluated at various internal and external moderator densities including preferential flooding of the fuel region. For the preferential flooding scenarios, the square container containing the rod array is evaluated at a moderator density independent of that in the

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-9 remainder of the cask cavity. Figure 6.7.7-8 contains the moderator density plot. The maximum reactivity is achieved by a preferentially flooded fuel region and void cavity and cask exterior.

This result was to be expected as it provides maximum neutronic coupling within the four-cask array. Results are summarized in Table 6.7.7-10. An additional configuration, with flooded transfer tubes and 0.0001 g/cm3 water outside of the tubes, yields keff+2 of 0.44879.

Single Cask Containment (Fully Reflected) Evaluation A single cask evaluation is performed to comply with 10 CFR 71.55(b)(3).

The containment for the NAC-LWT is the cask inner shell. While no operating condition results in a removal of the cask outer shell and lead gamma shield, the most reactive preferential flooded and fully flooded cases are reevaluated by removing the lead and outer shells (including neutron shield), and reflecting the system by 20 cm water at full density on the X, Y, and Z faces. Single cask, containment fully reflected reactivities are summarized in Table 6.7.7-11.

6.7.7.3.3 Maximum Reactivities and Comparison to USL The maximum keff+2 results for three primary analysis groups (single cask, normal array, and accident array) are summarized in Table 6.7.7-12. Two normal condition array cases are included as the cask remains dry through all operating conditions, while 10 CFR 71 requires a normal condition maximum reactivity moderator density case. The listed values represent the maximum system reactivity adjusted for Monte Carlo run uncertainty and are below the lower of the two system USLs.

No benchmarks for mixed heterogeneous UO2 and MOX rod systems are publicly available.

Therefore, individual benchmarks are established for UO2 and MOX systems. The more limiting USL is applied to the results. Per Section 6.5.4, the USL for an array of UO2 rods is 0.9376 and 0.9331 for an array of MOX rods for a k of 0.0045 between the two fuel types. The evaluations demonstrated that MCNP, with its associated cross-sections, accurately predicts system reactivities containing either fuel rod type.

The focus of the evaluations is a wet (flooded) system, as no reasonable extrapolation of the data provided would indicate a safety concern for a dry system at the requested fissile material levels.

While it is recognized that code performance and bias are potentially affected by the difference in the energy level of neutron causing fission, the benchmarks accounted for the basic phenomena, and the computer code is capable of tracking particles at their relevant energy levels.

Table 6.7.7-13 compares the rod/material combinations to the area of applicability for ROD1063.

ROD1063 is PuO2 only; therefore, the hypothetical configuration is significantly outside the area of applicability of the benchmark calculation. There is no statistically significant trend of

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-10 reactivity versus energy and any relative changes in USL postulated from the extrapolation is not significant.

As the shipment includes uranium oxide rods, the maximum reactivity uranium oxide rod configuration characteristics are compared to its area of applicability in Table 6.7.7-14.

Exceeding the area of applicability for enrichment, pellet diameter, rod diameter, and H/235U ratio in the UO2 benchmark cases is acceptable as none of these variables has a trend that is statistically significant. Similarly, there is no statistically significant trend of reactivity versus energy and any relative changes in USL postulated from the extrapolation is not significant.

Table 6.7.7-12 and Table 6.7.7-13 also include relevant parameters for damaged fuel. Although homogenized fuel material was not validated, the relative magnitudes of energy of average neutron lethargy causing fission, water to fuel volume ratio, and H/235U atom ratio are similar to those of undamaged fuel. Therefore, the conclusions reached above for undamaged fuel are applied to damaged fuel.

Table 1.2-20 lists the bounding characteristics for the fuel rods evaluated in this section.

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-11 Figure 6.7.7-3 LANL MOX Fuel Rods Moderator Density Study NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-12 Figure 6.7.7-4 LANL MOX Fuel Rods Damaged Fuel Height Study NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-13 Figure 6.7.7-5 LANL MOX Fuel Rods Damaged Fuel Underloading Rod Loading Patterns NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-14 Figure 6.7.7-6 LANL MOX Fuel Rods Damaged Fuel Underloading Results -

ROD1063 at 6 Tubes NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-15 Figure 6.7.7-7 LANL MOX Fuel Rods Damaged Fuel Underloading Results - NIS5 at 4 Tubes and 530-000 at 1 Tube NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-16 Figure 6.7.7-8 LANL MOX Fuel Rods Moderator Density Study - Damaged Fuel NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-17 Table 6.7.7-3 LANL MOX Fuel Rods Reactivity as a Function of Rod Type Table 6.7.7-4 LANL MOX Fuel Rods Reactivity as a Function of Divider Thickness and Rod Pitch Table 6.7.7-5 LANL MOX Fuel Rods Reactivity Summary for Accident Condition Array Cases Table 6.7.7-6 LANL MOX Fuel Rods Reactivity Summary for Single Cask Containment Fully Reflected Cases NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-18 Table 6.7.7-7 LANL MOX Fuel Rods Reactivity Summary for Normal Condition Array Cases Table 6.7.7-8 LANL MOX Fuel Rods Reactivity Summary for Damaged Fuel Height Study Table 6.7.7-9 LANL MOX Fuel Rods Reactivity Summary for Damaged Fuel Underloading Study Table 6.7.7-10 LANL MOX Fuel Rods Reactivity Summary for Accident Condition Array Cases - Damaged Fuel NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC International 6.7.7-19 Table 6.7.7-11 LANL MOX Fuel Rods Reactivity Summary for Single Cask Containment Fully Reflected Cases - Damaged Fuel Table 6.7.7-12 LANL MOX Fuel Rods Summary of Maximum Reactivity Configurations Table 6.7.7-13 LANL MOX Fuel Rods MOX Comparison to Area of Applicability Table 6.7.7-14 LANL MOX Fuel Rods UO2 Comparison to Area of Applicability NAC PROPRIETARY INFORMATION REMOVED

NAC-LWT Cask SAR April 2024 Revision 24B NAC international 7.1-94 a.

If the dose rate is less than 2 mSv/h (200 mrem/hr) at all accessible points on the external surface of the package, and the TI is less than 10, the package meets the requirements of 10 CFR 71.47 (a).

b. If the dose rate is greater than 2 mSv/h (200 mrem/hr), but is less than 10 mSv/h (1000 mrem/hr) at any point on the external surface of the package, or the TI is greater than 10, the package must be shipped as exclusive use and meet the requirements of 10 CFR 71.47 (b), (c) and (d). If the dose rate and shipping requirements of 10 CFR 71.47 (b), (1), (2), (3) and (4) cannot be met, the package cannot be shipped.

c.

If the dose rate is > 10 mSv/h (1000 mrem/hr) at any point on the external surface of the package, the package exceeds the limits of 10 CFR 71.47 and cannot be shipped.

40.

Determine the appropriate Criticality Safety Index (CSI) assigned to the package contents in accordance with the CoC, and indicate the correct CSI on the Fissile Material label applied to the package per 49 CFR 172, Subpart E.

41.

Complete the shipping documents, carrier instructions (as required), and apply appropriate placards and labels.

7.1.22 Procedure for the Dry Loading of LANL MOX Fuel Rods This section describes the procedures for loading the NAC-LWT cask with LANL MOX Fuel Rods. The LANL MOX Fuel Rods are required to be loaded into Transfer Tubes prior to being loaded into the PWR/BWR Rod Transport Canister. The PWR Fuel Basket Assembly will contain the PWR insert, PWR/BWR Rod Transport Canister, Transfer Tubes, Fuel Rods, and Transfer Tube spacers, as required. The PWR Fuel Basket Assembly may contain a Divider Plate. The PWR/BWR Rod Transport Canister, 315-40-098, Assembly 96, 97, 98 or 99 is used without the corresponding internal inserts, 315-40-098, items 7, 8 or 19. Any of the 315-40-098 assemblies may be used.

The maximum decay head load of a loaded Canister shall be 25 Watts.

The maximum content weight per basket shall be 1,479 lbs. See Table 2.2.1-1 for details.

LANL MOX Fuel Rods variants include the following rod types: PNNL, Exxon, UO2, ROD1063, 530-000, and NIS5. Fuel rods of different types may NOT be placed into a single Transfer Tube, however different rod types are allowed within the same package, subject to the limitations in Table 1.2-20. Only one 530-000 type fuel rod may be loaded in a given package, which can include other transfer tubes loaded with other fuel rod types.

The Transfer Tubes consist of the Transfer Tube weldment, tube bottom end spacer, specified LANL MOX fuel rod(s), Transfer Tube Spacer (as required), and final tube top end spacer.

Transfer Tube Spacers are required at the top and bottom end of each tube except for Transfer

NAC-LWT Cask SAR April 2024 Revision 24B NAC international 7.1-95 Tubes being used as spacers, which may be completely empty. Spacers may be used to separate the contents but are not required. A measurement shall be taken of the Top End Spacer to verify it can sit below the top of the Transfer Tube Weldment by greater than or equal to 0.5 inch. The Transfer Tubes shall be arranged up to a 16-tube configuration. Empty Transfer Tubes may be loaded to act as spacers if desired to obtain a full 16-tube complement for the shipment.

The PWR/BWR Transport Canister and optional Divider Plate will be preloaded into the NAC-LWT prior to loading of the loaded Transfer Tubes. The Transfer Tubes with LANL MOX Fuel Rods will be loaded with the required stack-up of Tube End Spacers, Fuel Rods, and Transfer Tube Spacers per the specific loading plan for the approved contents. The Transfer Tubes will then be placed into the NAC-LWT individually filling each section of the divider plate. Transfer Tubes may be loaded without fuel rods and considered spacers in the event of a partially loaded shipment.

The procedure for dry loading the Transfer Tubes is as follows:

1.

Perform a receiving survey of the ISO and trailer and inspect for damage. The cask user shall verify by reference to the NAC provided Certificate(s) of Conformance that the identified NAC-LWT cask and associated lift yoke are within the allowable annual maintenance period specified on the certificate(s) prior to loading and release for transport.

2.

Position the trailer in the designated cask unloading area. Level the trailer. Set the trailer brakes and chock the wheels to prevent unintended movement.

3.

Licensees shall receive and survey the NAC-LWT cask for radiation and removable contamination (for both gross beta-gamma and alpha) per 10 CFR 20 and 49 CFR 173.

Open the ISO container front and/or rear doors and record the survey results. If radiation or contamination levels exceed the limits of 49 CFR 173.441 or 173.443, respectively, the user/licensee shall notify the shipper, NAC, and ensure the appropriate notifications are completed.

Note:

Verify that the package nameplate displays the correct package identification number in accordance with the CoC.

4.

Complete the radiation and contamination surveys of the cask as additional surfaces become accessible. Clean the cask surfaces, as required.

5.

Remove the roof from the ISO container and cross members, if installed.

6.

If installed, ensure the TIDs match the shipment documentation.

7.

Remove any TIDs that may be present and remove the top impact limiter.

8.

Remove the vent and drain port covers. Prior to reinstallation of the port covers, carefully inspect the port cover O-ring seals and, if the O-rings show any damage, replace them with approved spares. Ensure that the replacement O-rings are properly installed and seated. Visually inspect the vent and drain quick-disconnect nipples and replace them, if necessary.

Note:

For Alternate B port covers, replace the metallic O-ring with an approved spare prior to reinstallation.

NAC-LWT Cask SAR April 2024 Revision 24B NAC international 7.1-96 9.

Visually inspect the neutron shield tank fill, drain, and level inspection plugs for signs of neutron shield fluid leakage. If leakage is detected or suspected, verify shield tank fluid level and correct, as required.

10.

Inspect the Horizontal Lid Removal Tool and hex head screws to ensure there is no damage. Replace any bolts that are damaged prior to attaching the Horizontal Lid Removal Tool to the LWT Lid.

11.

Attach the rigging to the rear lift lug of the Horizontal Lid Removal Tool and position next to the NAC-LWT Lid.

12.

Install the Horizontal Lid Removal Tool to the LWT Lid 13.

Remove the rigging from the rear lift lug and attach the rigging to the Horizontal Lid Removal Tool center Lift Lug.

14.

Loosen and remove all closure lid bolts.

Note: Prior to installation, inspect the lid bolts and replace any that are damaged.

15.

Remove the closure lid and set it on a support that is suitable for radiological control and for maintaining the cleanliness of the closure lid. Prior to installation, carefully inspect the Teflon O-ring seal in the underside of the closure lid. If the O-ring shows any damage, replace it. Remove the metallic O-ring from the groove and discard.

Clean and visually inspect the groove and lid recess seating surfaces for cleanliness, damage, or degradation. If the groove and lid recess seating surfaces are acceptable, install a new metallic O-ring with an approved spare. Ensure the replacement O-rings are properly installed and seated.

16.

Visually inspect the inner cavity for foreign material, free water, or damage. Note deficiencies and correct as required.

17.

Remove any shipping dunnage as necessary.

18.

Clean all accessible surfaces, including the lid sealing surface.

19.

Verify the PWR Fuel Basket assembly, PWR Insert, and PWR/BWR Rod Transport Canister are properly installed and no damaged occurred during transport.

a.

If the Divider Plate is used, ensure it is properly installed and no damaged occurred during transport.

20.

Loosen all PWR/BWR Rod Transport Canister lid bolts and ensure disengagement from the rod canister.

21.

Remove PWR/BWR Rod Transport Canister lid.

22.

Ensure the specific loading configuration for the shipment and contents to be loaded comply with the NAC-LWT CoC.

23.

Ensure the LANL MOX Fuel Rods are in their specified location within the Transfer Tubes prior to inserting them into the NAC-LWT.

Note: Criticality requirements govern the proper configuration of Transfer Tubes in the NAC-LWT cask and fuel tubes within the Transfer Tubes. See Table 1.2-20 for limitations. Ensure the correct fuel rods, end spacers, and tube spacers are placed in the approved loading configuration. See Step 25 for Top End Spacer minimum clearance length within the Transfer Tube Weldments.

24.

Insert each Transfer Tube into the NAC-LWT per specific loading configuration one by one (up to 16 Transfer Tubes). Either with fuel rods or without.

NAC-LWT Cask SAR April 2024 Revision 24B NAC international 7.1-97 25.

Once the Transfer Tubes are loaded for shipment, ensure the Top End Spacer sits below the top of the Transfer Tube Weldments by greater than or equal to 0.5 inch for all Transfer Tube Weldments containing fuel rods.

Note: If the Top End Spacers are sitting less than 0.5 inch below the Transfer Tube Weldments, the loading configuration of the fuel rods within the Transfer Tube Weldment(s) shall be reconfigured to ensure the 0.5 inch or greater clearance distance is met.

26.

Install the rod canister lid and torque to 35 +/- 5 in-lbs.

27.

Install the closure lid onto the cask using the Horizontal Lid Removal Tool. Ensure the rigging is attached to the center Lift Lug of the Horizontal Lid Removal Tool prior to lifting 28.

Visually verify that the lid is properly seated.

29.

Install lid bolts hand tight.

30.

Remove the rigging from the center Lift Lug and attach to the Rear Lift Lug prior to unbolting the Horizontal Lid Removal Tool.

31.

Unbolt the Horizontal Lid Removal Tool and remove from the closure lid.

32.

Tighten all 12 closure lid bolts to 260 +/- 20 ft-lbs in three passes using the torque sequence indicated on the closure lid.

33.

Connect the Vacuum Drying System (VDS) to the cask vent valve and evacuate the cask cavity by vacuum pump to less than or equal to 10 torr (13 mbar) and continue vacuum pumping for a minimum of 15 minutes.

34.

At the end of the evacuation period, isolate the cask cavity from the vacuum pump and monitor the cask cavity pressure for a minimum of 10 minutes. If the pressure rise is less than 5 torr (6.7 mbar), the cavity is verified as dry of free water. If the pressure rise is greater than 5 torr (6.7 mbar), resume vacuum drying until the dryness verification results are satisfactory.

35.

Backfill the cask cavity with helium to 0 psig (1 atmosphere, absolute), +1, -0 psi and disconnect the VDS from the vent valve.

36.

Perform a helium leakage test of the closure lid containment O-ring using a Helium Mass Spectrometer Leak Detector (MSLD) in accordance with the requirements of SAR Section 8.1.3.1.

37.

Install the vent and drain alternate port covers and torque the bolts to 100 +/-10 inch-pounds.

38.

If an alternate port cover containment O-ring seal was replaced, perform a helium leakage test on the affected port cover using a Helium MSLD in accordance with the requirements of SAR Section 8.1.3.2.2.

39.

If the alternate port cover containment seal was inspected and accepted for reuse, perform a gas pressure drop leakage test on the affected port cover as follows.

a.

Install a pressure test fixture to the port cover test port, including a calibrated pressure gauge with a minimum sensitivity of 0.25 psi.

b.

Pressurize the port cover seal annulus to 15 psig, +1, -0 psi.

c.

Isolate the gas supply and observe the pressure gauge for a minimum of five minutes.

NAC-LWT Cask SAR April 2024 Revision 24B NAC international 7.1-98 d.

The acceptance criterion for the test is no measurable drop in pressure during the minimum test time. An acceptable test assures that the minimum assembly verification leakage test sensitivity is achieved.

40.

Survey the cask surface for removable contamination and radiation dose rates.

Decontaminate the cask, if required.

Note:

Removable contamination levels and radiation levels shall comply with 49 CFR 173.443 and 173.441, respectively.

41.

Verify the correct installation of the cask tie-down strap. Install the top impact limiter and verify the correct installation of the bottom impact limiter.

42.

Install a TID to one of the top impact limiter ball lock pins. Record TID identification number on the loading/shipping documentation.

43.

Install roof cross-members, if used and replace ISO container roof.

44.

Complete a Health Physics survey on the external surfaces of the package and record the results. Complete dose rate measurements at the package surface, at 1 meter from the package surface, and at 2 meters from the vertical plane of the side of the transport vehicle. The maximum dose rate at 1 meter from the package is the transport index (TI). Ensure compliance with 10 CFR 71.87(i) and observe the following criteria.

a.

If the dose rate is less than 2 mSv/h (200 mrem/hr) at all accessible points on the external surface of the package, and the TI is less than 10, the package meets the requirements of 10 CFR 71.47 (a).

b.

If the dose rate is greater than 2 mSv/h (200 mrem/hr), but is less than 10 mSv/h (1000 mrem/hr) at any point on the external surface of the package, or the TI is greater than 10, the package must be shipped as exclusive use and meet the requirements of 10 CFR 71.47 (b), (c) and (d). If the dose rate and shipping requirements of 10 CFR 71.47 (b), (1), (2), (3) and (4) cannot be met, the package cannot be shipped.

c.

If the dose rate is > 10 mSv/h (1000 mrem/hr) at any point on the external surface of the package, the package exceeds the limits of 10 CFR 71.47 and cannot be shipped.

45.

Determine the appropriate Criticality Safety Index (CSI) assigned to the package contents in accordance with the CoC, and indicate the correct CSI on the Fissile Material label applied to the package per 49 CFR 172, Subpart E.

46.

Complete the shipping documents, carrier instructions (as required), and apply appropriate placards and labels.

NAC-LWT Cask SAR May 2024 Revision 24B NAC International 9-8 Tang, S., SAS4: A Monte Carlo Cask Shielding Analysis Module Using an Automated Biasing Procedure, ORNL/NUREG/CSD-2/V1/R5, Volume 1, Section S4, September, 1995.

Bucholz, J.A., Landers, N.F., and Petrie, L.M., ORNL/NUREG/CSD-2/V3/R5, Section M7, The Material Information Processor For Scale, September 1995.

Greene, M., Westfall, R.M., and L.M. Petrie, ORNL/NUREG/CSD-2/V2/R5, NITAWL-II:

Scale System Module For Performing Resonance Shielding And Working Library Production September 1995.

Jordan, W.C., ORNL/NUREG/CSD-2/V3/R5, Section M4, Scale Cross-Section Libraries, September 1995.

Landers, N. F., and Petrie L.M, ORNL/NUREG/CSD-2/V1/R5, Section C4, CSAS: Control Module For Enhanced Criticality Safety Analysis Sequences, September 1995.

Mele, Ravink and Trkov, TRIGA Mark II Benchmark Experiment, Part I Steady State Operation, Jozef Stefan Institute, Nuclear Technology, Vol. 105, January 1994.

Petrie L.M., and Landers, N.F., ORNL/NUREG/CSD-2/V2/R5, Section F11, KENO-Va: An Improved Monte Carlo Criticality Program with Supergrouping, September 1995.

Tomsio, M., Characterization of Triga Fuel, ORNL/Sub/86-22047/3, GA-C18542, Oak Ridge National Laboratory, Oak Ridge, Tennessee, October 1986.

Krieth, F., and Bohn, M.S., Principals of Heat Transfer, 5th Edition, West Publishing Company, 1993.

Incropera, F.P., and DeWitt, D.P., Fundamentals of Heat and Mass Transfer, 4th Edition, John Wiley and Sons, 1996.

Owen, D.B., Factors for One-Sided Tolerance Limits and for Variables Sampling Plans, SCR-607, 1963.

ANSI N14.5-1997, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment, American National Standards Institute, 1997.

ANSI/ANS - 8.1-1983, Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors.