Argonne National Laboratory
RERTR
Reduced Enrichment for Research and Test Reactors
Nuclear Engineering Division at Argonne
U.S. Department of Energy

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: trent.andes@srs.gov

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.
Fuel element type

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: trent.andes@srs.gov


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
(± g or ± %)

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

2016 RERTR Meeting

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2015 RERTR Meeting

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For more information visit RERTR-2015.

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ARGONNE NATIONAL LABORATORY, Nuclear Engineering Division, RERTR Department
9700 South Cass Ave., Argonne, IL 60439-4814
A U.S. Department of Energy laboratory managed by UChicago Argonne, LLC
 

Last modified on July 29, 2008 11:34 +0200