IAEA/USA Interregional course on
Preparations to Ship Spent Nuclear Fuel (1997)
SAMPLE APPENDIX A
FOR GENERIC MTR ASSEMBLY
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Contact:
Mr. Trent Andes
Westinghouse Savannah River Co.
Building 707-C, Room 383
Aiken, SC 29808
Tel.: +1-803-557-9483
Fax: +1-803-557-9080
E-mail: [email protected]
IAEA/USA Interregional Training Course
Technical and Administrative Preparations Required for Shipment of Research Reactor Spent
Fuel to its Country of Origin
13-24 January 1997
Argonne, IL
Lecture L.3.1a
SAMPLE APPENDIX A
FOR GENERIC MTR ASSEMBLY
presented by
Trent Andes
Westinghouse Savannah River Co.
APPENDIX A AGREEMENT
SPENT NUCLEAR FUEL ACCEPTANCE CRITERIA
No. _________UNDER CONTRACT NO. __________________________
WITH _______________________________________________________
THIS AGREEMENT, entered into this ______ day of ____________, 19____, constitutes
an agreement by the U.S. Department of Energy (hereinafter called DOE) to receive
under the terms and conditions of Contract No. , the specification material
described herein. This agreement provides a detailed description of the material
to be delivered to DOE in accordance with this contract and also enumerates
the specifications and requirements which the Customer must meet. Failure of
the material delivered hereunder to comply with the specifications and requirements
given in this agreement will result in the material being non-specification
material. A separate Appendix A Agreement will be required for each element
or assembly which is different in Description. All dimensions must be given
in centimeters and all weights in grams.
A. Correspondence
1. Customer Contact
Laboratory/ Research Center/University | Savannah River Site |
Reactor Name | Material Test Reactor |
City, State, Country | Aiken, SC, USA |
Customer Name | Trent C. Andes |
Customer Signature | |
Title | Reactor Manager |
Phone Number | 803-557-9483 |
Fax Number | 803-557-9080 |
Date | 06 January 1997 |
2. Department of Energy Contact
All correspondence / inquiries regarding this document and the information
contained herein shall be directed to:
U.S. Department of Energy
Savannah River Operations Office
Spent Fuel Storage Division
P.O. Box A
Aiken, SC 29801
Phone and facsimile inquiries may be made to:
Phone: (803)-557-3759
Fax: (803)-557-3763
B. Definitions
The following definitions are applied to the Specification Material described in this Agreement:
Fuel Element -The smallest integral unit of clad fuel containing source
or special nuclear material (e.g., plate, tube, rod, disc, etc.).
Assembly - A group of elements combined in a structural unit. The assembly
is usually that fuel structure which is removed from the reactor as an individual
unit.
C. Form and Composition of Specification Material
1. Drawing Identification
The following design or fuel fabrication drawing(s), six (6) copies of which
are attached and which are incorporated herein by reference thereto, constitute(s)
a comprehensive and accurate illustration of the fuel elements and assemblies
to be delivered under this Contract.
Drawing No. / Rev. No. / English Title |
5001 / A / 19 Plate MTR Assembly |
5002 / A / Type 8 Fuel Plate (Flat) |
5003 / A / Type 8 Fuel Plate (Formed) |
5004 / A / Type 9 Fuel Plate (Flat) |
5005 / A / Type 9 Fuel Plate (Formed) |
5006 / A / Fuel Compact - Enriched, Type 8 and Type 9 |
5007 /A / Side Plate |
5008 / A / End Box |
Note: If fuel is cropped (cut), drawings should indicate the location of the
cut(s).
2. Material Description
The following tables summarize the description of fuel elements and assemblies to be delivered under this contract. Where dimensions are required, the nominal dimensions from the fuel element and assembly drawings must be used. If changes in dimensions have occurred due to cropping or other modification, the best estimate of the maximum change in these dimensions must be given. Weights must be dry, unirradiated weights . Where isotopic weights of SNM are required, tolerances shall be specified.
(a.1) Fuel 'Element' Description (If more than one type of element per assembly, divide the space to describe each type of element or duplicate this page as necessary.)
Fuel element type (curved or flat plate, tube, rod, disc, etc.) | curved plate (Type 9, outer) |
Nominal dimensions (include clad & bond, cm)a | 68.90 x 7.10 x 0.164 |
Nominal dimensions of fuel meat (cm)a, b | 59.79 x 6.24 x 0.05 |
Nominal total weight of fuel element (g) | 227.0 |
Chemical form of fuel meat (e.g. UAlx-alloy, U3O8-Al, U3Si2-Al, etc.) | U3O8 in Aluminum matrix |
Nominal total weight of fuel meat (g) | 62.0 |
Weight of total U (g ± g uncertainty) | 12.45 ± 0.27 |
Weight of U-235 (g ± g uncertainty) | 11.58 ± 0.25 |
Matrix material, weight (g) | 101 Al powder; 47.0 |
Cladding material & method of sealing | 6061 Al; roll-bonded |
Clad thickness (cm), total clad weight (g) | 0.057; 165.0 |
Bonding material, if any (Na, Al-Si, etc.) | N/A |
Bond thickness (cm), weight (g) | N/A |
Other materials contained in the fuel element: (include dimensions and weights) | N/A |
(a) For curved plate type element, state dimensions for flat form.
(b) As formed in element.
(a.2) Fuel 'Element' Description (If more than one type of element per assembly, divide the space to describe each type of element or duplicate this page as necessary.)
Fuel element type (curved or flat plate, tube, rod, disc, etc.) | curved plate (Type 8, inner) |
Nominal dimensions (include clad & bond, cm)a | 62.55 x 7.10 x 0.1275 |
Nominal dimensions of fuel meat (cm)a, b | 59.79 x 6.24 x 0.05 |
Nominal total weight of fuel element (g) | 164.0 |
Chemical form of fuel meat (e.g. UAlx-alloy, U3O8-Al, U3Si2-Al, etc.) | U3O8 in Aluminum matrix |
Nominal total weight of fuel meat (g) | 62.0 |
Weight of total U (g ± g uncertainty) | 12.45 ± 0.27 |
Weight of U-235 (g ± g uncertainty) | 11.58 ± 0.25 |
Matrix material, weight (g) | 101 Al powder; 47.0 |
Cladding material & method of sealing | 6061 Al; roll-bonded |
Clad thickness (cm), total clad weight (g) | 0.039; 102.0 |
Bonding material, if any (Na, Al-Si, etc.) | N/A |
Bond thickness (cm), weight (g) | N/A |
Other materials contained in the fuel element: (include dimensions and weights) | N/A |
(a) For curved plate type element, state dimensions for flat form.
(b) As formed in element.
(b) Fuel 'Assembly' Description
Total number of elements | 19 plates (2 outer, 17 inner) |
Over-all dimensions (cm)a | 108.27 x 8.35 x 7.61 |
Over-all weight (g) | 6026.8 |
Total weight of U (g ± g uncertainty) | 236.55 ± 5.13 |
Total weight of U-235 (g ± g uncertainty) | 220.02 ± 4.75 |
Enrichment (%) | 93.01 |
Canning material (Al, SST)b | N/A |
Canning dimensions (cm), weight (g) | N/A |
Method of can sealing (screw, weld, etc) | N/A |
Side plate material | 6061-T6 Al |
Side plate - quantity, dimensions (cm), weight per plate (g) | 2; 68.9 x 8.05 x 0.475; 580 |
Side plate - outer slot depth & width (cm) | 0.22; 0.18 |
Side plate - inner slot depth & width (cm) | 0.22; 0.14 |
Spacer material | N/A |
Spacer - quantity, dimensions (cm), weight per spacer (g) | N/A |
End box material | 356.0-T6 Al alloy (ASTM B-26) |
End box - quantity, dimensions (cm), weight per box (g) | 2; 20.88 x 7.41 x 7.24; 760.0 |
Braze or weld material | N/A |
Braze or weld dimensions (cm), weight (g) | N/A |
Other structural material in assembly (e.g. dummy plates, thermocouples, etc., include quantity, dimensions, material, & weight (g)) | Pins, 8, 6mm x 8mm, Al-Mg-Si, 0.6 |
(a) Has the assembly been cropped? Yes No (Circle One) If yes, indicate dimensions
& weights in terms of the cropped assembly
(b) When fuel assemblies have casings, describe using these entries.
Do the fuel elements contain Sodium (Na)? Yes No (Circle One)
D. Fuel Identification
Each separately removable unit in a shipment batch must be identified by a durable tag or by embossing. Identification of the Units to be delivered under this Appendix A Agreement are as follows (NOTE: Customer shall list actual assembly identification numbers):
L-006, -007, -008, -009, -010, -013, -014, -015, -016, -017, -018, -019, -020,
-021
Identification numbers are vibro-etched into two opposing sides of each assembly.
E. Fuel Irradiation Specifications
1. Fuel Irradiation History - General Summary
Irradiation history varies for each assembly. Post irradiation data was generated using ORIGEN.
2. Post-Irradiation Specifications
The average and maximum SNM content post-irradiation is to be specified in grams per assembly. The best available value should be given and the uncertainty stated. The irradiation history for each assembly is to be provided according to Section F.
SNM Material |
Average (g) |
Maximum (g) |
Uncertainty |
Total U | 161.40 | 163.21 | ± 5% |
Total Pu | 0.35 | 0.38 | ± 5% |
Total Np | 0.25 | 0.29 | ± 5% |
Total Th | |||
U-232 | |||
U-233 | |||
U-235 | 132.37 | 135.14 | ± 5% |
U-236 | 13.62 | 14.79 | ± 5% |
Pu-239 | 0.27 | 0.29 | ± 5% |
Pu-241 | 0.02 | 0.02 | ± 5% |
F. Fuel Irradiation History - Assembly Specific Data
The irradiation history for each assembly is to be provided according to the format specified below. Additional tables may attached (if necessary).
Assembly | Pre-Irradiation |
Post-Irradiation |
||||||||||||
Unique ID No. | U grams | U-235 grams | U grams | U-235 grams | U-236 grams | Np-237 grams | Pu grams | Pu-239 grams | Pu-241 grams | Time In Reactor (days) | Cooling Time (days) | Power Level mwd/assy | Burnup % | Decay Heat (Watts) as of: 7/27/9 |
L-006 | 236.65 | 220.11 | 162.82 | 134.08 | 13.34 | 0.24 | 0.35 | 0.27 | 0.02 | 1378 | 2866 | 2102.50 | 39.09 | 2.18 |
L-007 | 237.18 | 220.60 | 163.21 | 134.54 | 13.27 | 0.24 | 0.33 | 0.26 | 0.02 | 1367 | 2784 | 2094.63 | 39.01 | 2.19 |
L-008 | 236.76 | 220.21 | 162.79 | 134.04 | 13.35 | 0.24 | 0.34 | 0.26 | 0.02 | 1367 | 2784 | 2096.63 | 39.13 | 2.20 |
L-009 | 236.89 | 220.33 | 163.72 | 135.14 | 13.18 | 0.26 | 0.38 | 0.28 | 0.02 | 1539 | 2524 | 2301.78 | 38.66 | 2.22 |
L-010 | 236.86 | 220.30 | 159.99 | 130.72 | 13.87 | 0.27 | 0.38 | 0.29 | 0.02 | 1743 | 2320 | 2364.16 | 40.66 | 2.37 |
L-013 | 236.80 | 220.25 | 161.56 | 132.58 | 13.58 | 0.25 | 0.34 | 0.25 | 0.02 | 1851 | 2065 | 2075.40 | 39.81 | 2.41 |
L-014 | 237.68 | 221.07 | 161.45 | 132.46 | 13.59 | 0.23 | 0.33 | 0.25 | 0.02 | 1392 | 2524 | 2065.87 | 40.08 | 2.30 |
L-015 | 237.36 | 220.77 | 161.50 | 132.51 | 13.59 | 0.25 | 0.35 | 0.27 | 0.02 | 1456 | 2163 | 2135.03 | 39.98 | 2.43 |
L-016 | 237.23 | 220.65 | 162.61 | 133.83 | 13.38 | 0.28 | 0.38 | 0.29 | 0.02 | 1602 | 2163 | 2356.25 | 39.35 | 2.37 |
L-017 | 237.0 | 220.43 | 162.61 | 133.83 | 13.38 | 0.27 | 0.36 | 0.28 | 0.02 | 1602 | 2163 | 2356.25 | 39.29 | 2.37 |
L-018 | 237.72 | 221.10 | 154.98 | 124.79 | 14.79 | 0.26 | 0.36 | 0.28 | 0.02 | 2426 | 1493 | 2317.50 | 43.56 | 3.40 |
L-019 | 236.75 | 220.20 | 162.20 | 133.34 | 13.46 | 0.24 | 0.35 | 0.27 | 0.02 | 1573 | 1960 | 2275.22 | 39.45 | 2.49 |
L-020 | 236.40 | 219.88 | 156.99 | 127.18 | 14.41 | 0.29 | 0.37 | 0.29 | 0.02 | 2079 | 1449 | 2427.20 | 42.16 | 3.02 |
L-021 | 237.13 | 220.55 | 163.10 | 134.14 | 13.49 | 0.18 | 0.29 | 0.26 | 0.02 | 1463 | 1960 | 2118.55 | 39.18 | 2.52 |
G. Specifications for Failed/Warped Fuel Units
Fuel elements or assemblies distorted beyond specified dimensional limits must
be considered on an individual basis. The Customer should provide DOE with complete
dimensional information for each failed/warped unit at least 120 days before
delivery.
If material normally removed from the element or assembly by the Customer cannot be removed due to fuel failure, warpage, or other reasons, the Customer must notify DOE at least 270 days before delivery giving complete dimensional, material, and weight information. Detailed structural drawings are also required by DOE.
H. Cask and Basket Identification
The fuel being received under this Appendix A contract must be identified with a specific cask and basket type.
Cask | Basket | Number of Assemblies/Cask |
LWT | (2) 7 Square | 14 |