IAEA/USA Interregional course on
Preparations to Ship Spent Nuclear Fuel (1997)
PREPARATION OF APPENDIX A CONTRACT
FORMS
FOR THE SAVANNAH RIVER SITE
PDF version available
DOWNLOAD full paper in PDF format.
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 3.1a
PREPARATION OF APPENDIX A CONTRACT FORMS
FOR THE SAVANNAH RIVER SITE
by
Trent Andes
Westinghouse Savannah River Co.
The Department of Energy (DOE) Appendix A contract form is the source document from which all Savannah River Site (SRS) storage, shipping, and disposition analyses are based. These analyses support, in most cases, the safe operation of the site's nuclear operations. The importance of an accurate and complete Appendix A, therefore, can not be overemphasized. As a result of problem areas that have been noted in recent Appendix A reviews, this document is being provided to enable the standardized completion of an Appendix A form. In addition, the Appendix A form itself has been revised to readily support description of the standard research reactor fuel type. The new form and the preparation guidelines will benefit the Reactor Operators by reducing the review and approval time at SRS.
I. General Comments
Schedule
Receipt of spent fuels by SRS is dependent upon the availability of the Appendix
A and applicable prints well in advance (at least 270 days) before intended
shipment date.
Dimensions
All dimensions must be given in centimeters except in the case of small components
such as connecting pins or handles where units may be identified in millimeters.
Use of different units must be noted.
Weights
All weights must be given in grams.
Drawings
The description must agree with the material described in the Appendix A and
should be a comprehensive illustration of the fuel. Typical drawings to be provided
include over-all assembly, fuel plate, side plate, dummy plate, end fitting,
spacer, handle, fabrication detail prints, etc. Six (6) copies of each drawing
shall be provided.
Cropping
Indication for cropped fuel assemblies is located in Section C.2.b.. Changes
in weights and dimensions due to cropping shall be reflected in the appropriate
description and cropping lines shall be marked for each affected drawing.
Sodium
Fuel assemblies containing sodium are not permitted in SRS spent fuel facilities.
Other
If available, provide two (2) copies of the manufacturer's fuel specification
forms or equivalent.
II. Appendix A Form
A. Section C.1. Drawing Identification:
Include Drawing No., Revision No., and Title.
B. Section C.2. Material Description:
1. Fuel "Element" Description:
Notes:
- Weights are dry and unirradiated.
- If the assembly contains more than one element type (e.g. inner plate, outer
plate), the Fuel "Element" Description table column may be divided
or the entire page duplicated. Renumbering of pages is acceptable if table
is duplicated.
State as flat plate, curved plate, tube, or etc.
Required to:
a) cross-check drawings
b) support criticality analyses methodology
Nominal dimensions
State element dimensions as:
plate - length , width, and thickness
tube - length, outside diameter, and inside diameter
Dimensions for curved plate elements should be stated in their flat or pre-rolled
form.
Required to:
a) cross-check drawings
b) support criticality analyses methodology
Nominal dimensions of fuel meat
State fuel meat dimensions as:
plate - length , width, and thickness
tube - length, outside diameter, and inside diameter
Dimensions for curved plate elements should be stated in their flat or pre-rolled
form.
Required to:
a) cross-check drawings
b) support criticality analyses methodology
c) assembly cropping
Nominal total weight of fuel element
Total weight of element is the tabulation of fuel meat, cladding, and any additional
weight contributors.
Required to:
a) cross-check of final calculated values
Chemical form of fuel meat
State fuel meat / form description. Research reactor fuel meat is typically
found as a dispersant in matrix. Common form received is UAlx in Aluminum matrix.
SAMPLE APPENDIX A
FOR GENERIC MTR ASSEMBLY
PDF version available
DOWNLOAD full paper in PDF format.
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 |