ML20210B797
| ML20210B797 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 05/02/1986 |
| From: | Brown K, Jeffrey Reed, Wages L EG&G IDAHO, INC. |
| To: | |
| Shared Package | |
| ML20210B763 | List: |
| References | |
| TRTR-4, NUDOCS 8609180167 | |
| Download: ML20210B797 (54) | |
Text
r O ~e o ENCLOSURE A 4
SPECIFICATION TRTR-4 FOR UNIVERSITY OF MISSOURI ;
FUEL ELEMENTS ASSEMBLED FOR THE UNIVERSITY OF MISSOURI RESEARCH REACTOR Date May 2.1986 REVIEWS J. D. Reed K. R. Brown Mechanical Engineering PRP Technical Support L. V. Waaes R. Hultch by K. R. Brown Quality Engineering - South University of Missouri APPROVAL
- 0. R. Nousseau
- Manager, PRPTS EG&G Idaho, Inc.
P.O. Box 1625 Idaho Falls, 10 83415 Reviews & approval documented on DRR 25504 dated 04-29-86 agg"$00 b!
P
V U TRTR-4 s May 2, 1986 SPECIFICATION FOR UNIVERSITY OF MISSOURI FUEL ELEMENTS ASSEMBLED FOR THE UNIVERSITY OF MISSOURI RESEARCH REACTOR Specification TRTR-4 EG&G Idaho, Inc.
P.O. Box 1625 Idaho Falls, ID 83415 i
', 11
a ,
s TRTR-4 May 2, 1986 INDEX Page 1.0 SCOPE .......................................................... 1 2.0 APPLICABLE DOCUMENTS ........................................... 3 3.0 REQUIREMENTS ................................................... 6 4.0 MATERIAL 5 OF CONSTRUCTION ...................................... 16 5.0 TEST AND INSPECTION REQUIREMENTS ............................... 18 6.0 DELIVERY SU8MITTALS ............................................ 20 7.0 PACKAGING AND SHIPPING ......................................... 21 8.0 ACCEPTANCE INSPECTION .......................................... 22 FIGURES Figure 1 ............................................................ 23 TABLES TABLE I .........................................,................... 24 TABLE II ............................................................ 25 Attachment I - Requirements for Radiographing fuel Plates . . . . . . . . . I-1 Attachment II - Specification for Aluminum Powder for Matrix ....... II-1 Material in TRT Reactor Fuel Attachment III - Specification for Reactor Grade Uranium-Aluminide .. III-1 (UAlg) Powder Attachment IV - Specification for Enriched U-Metal for UA1 x - IV-l Reactor Fuel Elements 1
ti) l l
I
, TRTR-4 i 9
i May 2, 1986 j SPECIFICATION FDR
- UNIVERSITY OF MISSOURI FUEL ELEMENTS ASSEMBLED FOR THE UNIVERSITY OF MISSOURI RESEARCH REACTOR Specification TRTR-4 1.0 SCOPE
1.1 INTRODUCTION
This Specification details the materials, components, testing, 1 inspection, and Quality Control requirements for the fabrication of. Fuel l Elements for the University of Missouri Research Reactor at the University of i Missourt.
t 1.2 DEFINITIONS
- For the purpose of this Specification, the following terms are identified: (Capitalization shall denote the use of a defined term).
. 1.2.1 Batch. A quantity of UA1* produced at one operation.
l 1.2.2 81 ended. To mix or mingle constituents of a Batch.
l 1.2.3 Development. A determination of processes, equipment, and parameters required to produce a product in compliance with this Specification.
1.2.4 Doobone Area. Thickening of Fuel Core at ends of Fuel Plates.
This may occur during the rolling process.
1.2.5 Oummy Fuel Element. An Element consisting of unfueled simulated Fuel Plates.
i.
l l
1
i TRTR-4
. Jun2 14, 1985 1.2.6 Failure. The condition arising when representative samples, which are the basis for process control and product acceptance, do not meet the requirements of this Specification.
- l 1.2.7 Fuel Core'. The uranium-bearing region of iach Fuel Plate. The term " Core" is also used in this Specification to mean Fuel Core.
1.2.8 Fuel Element. An assembly of Fuel Plates and hardware q
components, as defined in Section 4.
The term " Element" is also used in this Specification to mean Fuel Element.
1.2.9 Fuel Plate. The Fuel Core complete with aluminum frame and cladding. The term " Plate" is also used in this Specification to mean Fuel Plate.
1.2.10 In-Process Controls. Checks made during Production to assure that the Manufacturing processes, equipment, and personnel arc capable of producing a product meeting specified requirements.
1.2.11 Lot. A group of sequentially numbered pieces handled as a unit or material traceable to a common processing step. A Lot when used in reference with Fuel Plates shall consist of a minimum of sixteen (16) Fuel
! Plates.
1.2.12 Manufacture (ing). All fabrication, assembly, test, inspection, and Quality Control processes.
1.2.13 Production. That phase of the program, follcwing Qualification, -
during which the product is in Manufacture.
1.2.14 Purchaser. EG&G Idaho, Inc.
1.2.15 Qualification. A demonstration that the Manufacturing processes and equipment can produce a product in compliance with this Specification.
2 l _ _ _ __ _ _ __ _ _ ._ __ - - -_ _ --- - - - - - - - ~ - - - - - - - - - - - - - - - -
4 '
TRTR-4 May 2, 1986 1.2.16 Quality Control. The sampling plans, inspections, and tests required during Production to assure that the product is in compliance with this Specification.
1.2.17 Rejection. Refusal of acceptance of materials, parts, components, or assembly products as part of the contract requirements of this program because of noncompliance with this Specification.
1.2.18 Reaualification. A demonstration that a single or group of Manufacturing processes, equipment, and personnel can produce a product in
- compliance with this Specification after the original Qualification has been l completed. Requalification is required for a change in material, process, or operator.
1.2.19 Specification. All parts and attachments of this document,'its references, drawings, and standards, as may be modified from time to time by l contractual document.
1.2.20 Subtier Supplier. Any vendor selected by the Supplier to furnish
- materials, services, or manufactured parts to the Supplier.
1.2.21 Supplier. The primary vendor selected by EG&G Idaho, Inc. to Manufacture the product.
l 1.2.22 User. University of Missouri Research Reactor facility.
2.0 APPLICA8LE DOCUMENTS 2.1 APPLICABLE DOCUMENTS f The following documents are a part of this Specification. Where there is i
a conflict between the documents cited and the revision in effect at time of contract signing, the Supplier shall notify the Purchaser of the conflict and use the latest revision unless otherwise directed.
l
> TRTR-4 Jane 14,1985 2.1.1 Technical Society Standard.
l l
ASTM A 276 Stainless and Heat-Resisting Steel Bars and Shapes ASTM B 26 Aluminum-Alloy Sand Castings ASTM B 209 Aluminum-Alloy Sheet and Plate i ASTM B 211 Aluminum-Alloy Bars, Rods, and Wire ASTM B 221 Aluminum-Alloy Extruded Bars, Rods, Wire, Shapes, and Tubes -
ASTM B 618 Aluminum-Alloy Investment Casting ASTM E 8 Methods of Tension Testing of Metallic Materials 2.1.2 _American Society of Mechanical Engineers.
ANSI Y-14.5 Dimensioning and Tolerancing for Engineering Drawings 2.1.3 Drawings. (EEG Idaho, Inc.)
409406 University of Missouri, Test Research Training Reactor 4. MURR Fuel Plate 409407 l University of Missouri, Test Research Training Reactor 4, MURR UAl Fuel Element x
2.1.4 Reactor Development and Technology (RDT).
RDT F2-4T Quality Verification Program Requirements i
P 1
TRTR-4 May 2, 1986 MIL-C-45662 Calibration System Requirements '
RDT FS-1T Cleaning and Cleanliness Requirements for Nuclear Components, Sections 4 and 6.
2.1.5 American Weldina Society.
AWS A5.10 Aluminum and Aluminum-Alloy Welding Rods and Bare Electrodes AWS AS.9 Corrosion-Resisting Chromium and Chromium-Nickel Steel Welding Rods and 8are Electrodes 2.1.6 EG&G Idaho. Inc.
Attachment I Requirements for Radiographing Fuel Plates Attachment II Specification for Aluminum Powder for Matrix Material in TRT Reactor Fuel Attachment III Specification for Reactor Grade Uranium-Aluminide (UA1,) Powder Attachment IV Specification for Enriched U-Metal for UA1, Reactor Fuel Elements.
IN-F-9-ATR Specification for Advanced Test Reactor, Rev. 6 Mark VII Zone Loaded Fuel Elements 5
' TRTR-4
, June 14,1985 3.0 REQUIREMENTS 3.1 RECORDS AND REPORTS 3.1.1 Three (3) copies of the following data and records shall be supplied to the Purchaser, prior to fabrication of the initial Element, for review and approval. One (1) information copy will be supplied to the User by the Supplier.
(1) All shop drawings of Fuel Element components and assemblies to be used in the fabrication of the Fuel Element.
(2) Integrated Manufacturing and Inspection Test Plan.
(3) A detailed description as to the manner by which the Supplier proposes to assign Fuel Plate U-235 content. Included in the description must be sampling, analytical, and Quality Control procedures; and a statement as to the estimated absolute accuracy of the assigned Fuel Plate and Fuel Element U-235 content.
(4) Procedure for void fraction determination for Fuel Plates 1, 2, 23, and 24, in compliance with Table II. '
i (5) Qualification data package.
l 3.1.2 Concurrently with or prior to the shipment of each item, the Supplier shall provide the Purchaser with the following items: -
Certification of material compliance to the requirement of (1)
- this Specification including any chemical and physical test results pertaining thereto.
6
3 .,_ ._ _ __ _ _ __._ _ _ _ _ __ _.
TRTR-4 May 2, 1986 (2) Certification of product compliance to the requirements of this Specification except, as the case may be, for previous Purchaser-approved deviations, such deviations to be detailed in the certification.
(3) Inspection reports to the requirements of Section 5.1.9.
(4) Plate radiographs to the requirements of Section 5.1.3.
3.1.3 Three (3) copies of the following reports are required by this Specification:
- (1) Monthly Reports - A monthly report using Line of Balance, PERT, or siellar reporting techniques detailing program l progress against a previously submitted schedule shall be supplied by the Supplier to the Purchaser and User by the fifteenth working day of each month.
(2) Failure Notification - Ouring Production, complete records shall be kept by the Supplier. In the event of a Failure, the time, nature, description, corrective action taken, and proposed further corrective action shall be reported to the l
Purchaser within five working days after such Failure.
3.2 MANUFACTURING PROCEDURES l All programs, processes, and procedures, and all changes and modifications j thereto, to be used to Manufacture the product shall be submitted to the i Purchaser prior to use for review and approval. These shall include:
3.2.1 Supplier's specification for all material used.
4 3.2.2 Identification of Subtier Suppliers.
l 7
' TRTR-4
&ne 1401985 3.2.3 The complete Development program, including material, process, equipment, and test procedures.
3.2.4 All fabrication, assembly, cleaning, surface treating, handling, and demonstration procedures.
(1) The Fuel Plate fabrication procedure must include the provision that the Fuel Plates will be first hot rolled, a
then cold rolled. The final reduction of the Fuel Plate k thickness shall be accomplished by cold rolling after the Fuel Plate has been blister tested in accordance with Section 5.1.5. The final reduction shall be approximately 55 followed by annealing if required.
2 3.2.5 All test, inspection, Production, and Quality Control procedures, including all nondestructive tests, and all standards and sample sectioning
! drawings.
- 3.2.6 The In-Process Controls, sampling programs, and procedures.
t l
3.2.7 The Quality Control sampling program and procedures.
i
- 3.2.8 All rework or repair programs and procedures.
3.2.9 All final inspection, washing, packaging, storage, and shipping i procedures.
3.3 QUALIFICATION - FUEL PLATE AND FUEL ELEMENT -
i 3.3.1 All Fuel Plates and Elements shall be inspected for the following:
i i
- (1) Fuel Core Density - The 5 voids in the Fuel Cores of all Fuel Plates 1, 2, 23 and 24 shall comply with Table !!.
I l
t l 8 l
a .
a TRTR-4 May 2, 1986 (2) Clad-Core-Clad Dimensions - A minimum of one (1) randomly selected Fuel Plate will be sectioned in accordance with Figure 1 and evaluated to the. requirements of the applicable drawings during initial Fuel Plate Qualification only. Once the Fuel Plate Process is qualifted, a minimum of three (3) randomly selected fuel plates per lot will be inspected by
' Min-Clad' scanning at a depth of 0.010 inches. If any one
)
of the random sample Fuel Plates is not acceptable, the l entire lot will be inspected at a depth of 0.008 inches for acceptance. The ' Min-Clad' criteria is established by the IN-F-9-ATR specification and associated documents.
(3) Internal Defects and Sond Integrity - All Fuel Plates produced shall be evaluated to the requirements of Section 3.4.1(4) by ultrasonic and blister testing of each Fuel Plate. Any indication of nonbond, volds, blisters, lamination, or other discontinuities in excess of 0.06 inch diameter over the core and 0.12 inch over frame region, shall place the item in Failure.
(4) Core Configuation - All Fuel Plates shall be evaluated to the. requirements of Section 3.4.1(3) by the procedure of Section 5.1.4.
l (5) Surface Finish and Defects - All Fuel Plates shall be f evaluated to the requirements of Section 3.4.1(5) by the procedures of Section 5.1.6.
i l
I f
9
}
. TRTR-4 Juno 14,1985 i
(6) Cleanliness and Surface Contamination (Fuel) - All Fuel Plates shall be evaluated to the requirements of ,
Section 3.4.1(6) by the procedures of Section 5.1.8.
(7) Mechanical Integrity - The Supplier shall assemble three (3) three-inch-long dummy sections of a Fuel Element. Each section shall be evaluated to the requirements of the procedures of Section 5.1.10. -
(8) Dimensional - The Supplier shall fabricate a Dummy Fuel Element which shall be evaluated to the dimensional requirements of this Specification.
(9) Riveting - Riveting of the side plates to the end boxes shall be performed in accordance with the rivet manufacturer's recomendations.
3.3.2 In-Process Controls. The Supplier shall establish a process control program whereby checks are made on Manufacturing processes, operational procedures, intermediate product characteristics, and equipment to demonstrate process stability. These In-Process Controls shall include, but not necessarily be limited to, the following:
(1) Evaluation of Fuel Plates with regard to the requirements of the following sections:
Section 3.4.,1 (2) by the procedures of Section 5.1.3 Section 3.4.1 (3) by the procedures of Section 5.1.4 Section 3.4.1 (5) by the procedures of Section 5.1.6 Section 3.4.1 (6) by the procedures of Section 5.1.8 10
v .
TRTR-4 May 2, 1986 (2) Destructive analysis to the requirements of Section 3.4.1(4) I and clad-core-clad dimensions by sectioning, in accordance with Figure 1, a minimum of one (1) Fuel Plate per Lot of Fuel Plates during initial qualification only. )
(3) Fabrication of three-inch test specimens and pull tests shall conform to Section 5.1.10. A minimum of three specimens will be tested for every Production run of Elements fabricated (e.g., forward, center, and aft axial locations). Swaging of test specimens will be interspersed in the normal Production process without previous adjustment of the operation.
3.3.3 Recua11fication. Unless otherwise approved by the Purchaser.
Requalification will be limited to swaging. Process Requalification shall meet the same requirements as the original Qualification. All Requalification work shall meet all the requirements of this Specification unless specifically exempted by the Purchaser. The Supplier shall notify the Purchaser of any intended Requalification work, and shall submit the results and data therefrom.
Production may be resumed when the Supplier has met all of the requirements of this section and received written approval from Purchaser.
3.4 PRODUCT REQUIREMENTS The Fuel Element Orawing Number 409407 consists of twenty four (24) Fuel Plates, two (2) side plates, two (2) combs, two (2) end fittings, two (2) out
'RR rollers, two (2) in rollers, four (4) socket head shoulder screws, four (4) 5504 hexagon nuts, sixteen (16) rivets, and two (2) comb pins. The Fuel Elements have Fuel Plates attached to the side plates by mechanical means; end fittings attached to the fuel section by riveting; and combs attached to the fuel Plates by pinning.
1 11
TRTR-4
&no 14,1985 3.4.1 Fuel Plates.
(1) Fuel Loading - The fuel loading of each individual Fuel Plate shall be per Table I.
(2) Fuel Homogeneity - Density of the fuel per 0.080-inch-diameter Fuel Core area shall not differ by more than 1201 from the average for all Fuel Core locations, except in the <
area one (1) inch from each end of the Fuel Core where the variance may be 1301 in a region not to exceed 1/2 inch in the Fuel Plate longitudinal direction. A "high" region shall be defined as a location for which the fuel density per 0.080-inch-diameter Fuel Core area exceeds 205 of the Fuel Plate average. The average fuel density of the "high" region and four regions taken at the corners of a 1/2 inch square synnetric about the "high" region shall be less than 205.
Between the minimum and maximum permissible fuel core length boundary, fuel underload condition shall not be evaluated.
(3) Core Configuration - The outline of the Fuel Core shall be within the largest and smallest areas as defined by the Fuel Core Drawing 409406 dimensions and their respective tolerances.
There shall be a fuel free region at least 0.115-inch wide along the entire length of both sides of each Fuel Plate. A fuel flake of 0.010 inch diameter or a group of flakes equivalent diameter no greater than 0.010 inch diameter is -
l allowed. No particles shall be within 0.015 inches of the edge of the Fuel Plate.
- Inr the end region of the Fuel Plate 0.050 inch minimum from the Fuel Plate end, a 0.060 inch diameter fuel particle or a
! group of particles of equivalent diameter no greater than 0.060 inch is allowed.
l t
12 e., , ,-..,e..e..,.----m . - - ,-,-c-w.-i-,w.--w_
' TRTR-4 May 2, 1986 The fuel particles or equivalent groups of particles shall be separated by at least 0.125 inch when more than one such flaking condition exists in a region.
Stray fuel particles may be removed from fuel plate edges by filing, provided the filed out area is no deeper into the DRR edge of the plate than 0.50 inches, no longer than 25504 0.250 inches, and at least 1.0 inches apart. In addition any filed out area must be at least 0.50 inches from the end of the fuel plate.
(4) Internal Defects and Bond Integrity - A metallurgical bond with a minimum 50% grain growth across the clad / fuel and
- clad / frame interfaces is required. Internal defects shall be examined and evaluated as described in Section 5.1.5.
(5) Surface Finish and Defects - The finished Fuel Plates shall be free from pits, dents, scratches, and other areas of metal removed in excess of 0.005 inch deep, except in the Dogbone Area, 1 inch from end of Core. In this area, such depressions shall be limited to 0.003 inch deep.
(6) Cleanliness - The Supplier shall take all precautions necessary to maintain a high standard of cleanliness, in an l area as defined in ROT F5-1T Section 4.4 Clean Room, Clean Area, and Controlled Work Area during fabrication to ensure l
l that no foreign materials or corrosion products are present !
in the finished Fuel Plates and Elements. The finished Fuel !
Elements shall be completely free of dirt, scum, scale, graphite, grease, and other foreign materials inside and outside.
13 ,
' TRTR-4
. June 14 0 1985 (7) Identification - Each finished Fuel Plate shall be identified by a number stamped into the top 1/4 inch of the Fuel Plate, not in excess of 0.006 inches in depth.
Positive identification must be maintained relative to the complete fabrication history, including the Plate Lot, fuel blend, basic material Lots, heat or melt, Manufacturing cycle, and Quality Control phases.
(8) Storage - All Fuel Plates that have received final cleaning shall be contained in clean ployethylene bags while (1) awaiting final' assembly, (2) being transferred into storage, and (3) being maintained in storage. Any material exposed to contamination shall be reinspected to the requirements of Section 3.4.l(6).
Void fraction determination for Fuel Plates 1, 2, 23, and 24 '
(9) shall be in compliance with Table II.
3.4.2 Fuel Elements.
(1) Each Fuel Elenent shall contain 775.0 + 7.8 grams of U-235 per Table I.
(2) Material - All material used or contained in the product shall comply with all the requirements of this Specification unless exenpted by written document by the Purchaser.
(3) Cleanliness - The standards of cleanliness required for the i Fuel Plates by Section 3.4.l(6) are also required for the Fuel Elements.
I t
i 6
b 14
\
' TRTR-4 1 May 2, 1986 i (2) Material - All material u';ed or contained in the product )
shall comply with all the requirements of this Specification l
unless exempted by written document by the Purchaser. 1 (3) Cleanliness - The standards of cleanliness required for the Fuel Plates by Section 3.4.1(6) are also required for the :
Fuel Elements.
DRR
^" I~ * "' " " '" *
- 25504 plates by mechanical swaging.
(5) Riveting - Riveting will be to the requirements of Section 3.3.1(9).
($) Surface Finish and Defects - The requirements of Section 3.4.1(5) for Fuel Plates in Fuel Elements are also required for Fuel Elements.
(7) Identification.- Each Fuel Element shall have an identifying number such as M0-XXX. The number shall be placed on the outside of the side plate and opposite ends and shall consist of 2-inch block letters engraved by a method approved by the customer. The fuel Elements shall he numbered serially. Tne Perchaser w)11 provide serial numbers.
(8) Storage . All Fuel Elements that have received final cleaning shall te sealed in clean polyethylene bags while (1) being transferred into storage, (2) being maintained in storage, tr.d (3) being prepared for shipment or packaging. ,
i Any material exposed te contamination stall be reinspected according to the requirements of Section 3.4.1(6).
l 15
TRTR-4 Jun3 14,1985 4.0 MATERIALS OF CONSTRUCTION 4.1 The materials requirement for the components comprising the Fuel Element are as specified below:
t Componen_t Number Required Specification s Side Plates 2 Aluminus-Alloy 6061-T6 or 6061-T651 ASTM B 209 l
. t Combs 2 Aluminum Alloy 6061-T6 or 6061-T651 ASTM 8 209 or ASTM 8 221 End Fitting 2 Aluminum Alloy 6061-T6 or 6061-T651, ASTM B 209 or ,
. ASTM 8 221 Alloy 356-T6 or 356-T71, ASTM S 618 or ASTM S 26 Det Roller 2 ASTM A 276, 304 SST In Roller 2 ASTM A 276, 304 SST Nat. Hexagen 4 303 SST, Pic Design Cat. 38 Part # Y8-8 Fuel Bearing Plates 24 See Drawing 409407 Pins (Comb Attachment) 2 Aluminum Alloy 6061-T6 or ;
6061-T651 ASTM 8 211 or Weld Filler Wire Alloy 4043, I AWS AS.10 l
16
, , _ . . - _. ._-_,,,_.,,m...
. _ . , _ + , . _ . , _ . . .
_ . s- , _ , - - , . _ _ _ _ , ~
, TRTR-4 May 2, 1986 Component Number Required Snecification Socket Heat Shculder 4 303 SST Plc Design Cat. 38 Screw Part No. 4424 Rivets 16 Cherry Fasteners. Santa Ana, CA, DRR ownsend Division, Textron, .
25504 Inc. Cat No. 2162-6-5 Welding Rods and AR 1R 312. AWS A 5.9 Electrodes e
4.1.1 Euel Cores. The Fuel Cores of the Fuel Plates shall be UA1, internetallic powder dispersed 'in aluminum alloy powder as required in ,
Attachments II and III. Two (2) one-gram samples of each blended UAlr. 84tch shall be obtained by the Supplier for the Purchaser and held at the Supplier's plant for the Purchaser's use. During the course of the subcontract, any and all sanples not called for and in the possession of the Supplier will be considered part of the Supplier's scrap.
a.1.2 Frames. The frame shall be aluminum plate alloy 6061 per ASTM t 209 unclad or clad on both sides with hiloy 1100. Thickness of alloy 1100 on each side shall be as specified in Section 4.1.3. Maximum allowable boren content shall be 30 ppe.
4.1.3 Cover Plate. The fuel cladding shall be aluminum alloy 6061, ASTM B 209 clad on one side with alloy 1100. Each cover plate shall have an alloy 1100 clad thickness no less than 3% and a nominal maximum of 6% provided the three sigma limit does not exceed 7.5%. Compliance with the clad thickness requirenents may be accomplished by a Supplier-developed statistical sampling
- and analytical method approved by the Purchaser. Maximum allcwahle boron l content shall be 30 ppe.
l A
^
'17
, TRTR-4
, Ane 140 1985
! 5.0 TEST AND INSPECTION REQUIREMENTS 5.1 The following tests and inspections shall be performed by the Supplier to j assure that the product quality is in accordance with the requirements of the j Specification.
il 5.1.1 Materials. A " Certification of Chemical Analysis" or a certified
- Mill Test Report shall be supplied to the Purchaser for each Lot of material i used in the fabrication of Fuel Elements. This certificate shall give the i
] actual results of the chemical analysis for the material. All materials shall be traceable to the Fuel Elements f abricated from these materials. -
l 5.1.2 Fuel Loading. The requirements of Section 3.4.1(1) for fuel l loading shall be established in accordance with Section 3.1.l(3) by the :
Supplier subject to the approval of the Purthaser.
I
{ 5.1.3 h ogeneity. Plate homogeneity requirements of Section 3.4.1(2)
- and Attachment 1 shall be complied with by a one-piece radiograph of all Fuel l Plates from each Fuel Plate Lot and evaluation of the radiograph by calibrated densitometer measurements. The Suppl'ier shall be required to provide the Purchaser with calibration data relating light transmission through plate
) radiographs, using a densitometer with 0.080-inch-diameter aperture, to fuel i density. At the Purchaser's option " density wedges" may be provided by the
! Supplier to be exposed simultaneously with each Plate and from which fuel -
density variation can be detemined.
5.1.4 Fuel Core Configuration. Compliance with Fuel Core configuration l requirements of Section 3.4.1(3) shall be by visual inspection of Fuel Plate l radiographs. Visual radiograph inspections will be performed without magnifi-
! cation on a light table having a light range of 450-600 footcandles at the table surface and the area darkened to give a light range of 5-15 featcandles eighteen inches above the light table with radiographic film in pla:e on the i table.
i
$ 18 i l
.--n - ,- - - ,,---.-,..~ ,, _ - , - ~ . . _ , . _ _ _ _ .___.---_.--_...n,,,- .n-_,
- TRTR-4 May 2, 1986 5.1.5 Bond Inteority. Compliance with internal defects and bond integrity requirements of Section 3.4.1(4) shall be established by ultrasonic examination and by performing a blister test on all Fuel Plates. The blister test shall be performed after hot rolling, but before cold rolling, by heating each plate to a temperature of 900* 1 13*F, holding at that temperature for a period of two hours, removing from furnace, and allowing to air cool. Any Fuel Plate exhibiting blisters indications larger than O'.06 inch diameter over the Core and 0.12 inch over frame region, shall be rejected. The ultrasonic examination shall take precedence over questionable indications.
5.1.6 Surface Finish and Defects. Compliance with surface finish and defect requirements of Section 3.4.1(5) and Section 3.4.2(6) shall be established by 100% visual inspection without magnification of all Plates and Elements.
5.1.7 Clad-Core-Clad Dimension. Compliance with the requirements of the applicable drawings with regard to clad-core-clad dimensions shall be established in accordance with Section 3.3.1(2).
5.1.8 Cleanliness. Fuel Plate and Element cleanliness requirements of Section 3.4.1(6) and Section 3.4.2(3) shall be established by visual inspection of 100% of the Fuel Plates and Elements and by In-Process Controls. The surfaces of each Fuel Plate and the completed Fuel Element shall be counted for radioactive contamination. The alpha count shall be less than five (5) dpm per 100 square centimeters and the beta-gamma count shall be less than two-hundred (200) dmp per 100 square centimeters.
5.1.9 Dimensional Inspection. Compliance with all external dimensions of the fuel plates, all coolant flow channels, and the external dimensions of the fuel element shall be by 100% inspection, except outside dimensions of fuel plates shall be performed on three (3) randomly selected fuel plates per lot. If any one of these three is discrepant, then the entire lot must be dimensionally inspected. All dimensions of this specification shall apply at a temperature of 70* 1 5'F.
19
, 'TRTR-4 j Jun2 14,1985 j Each coolant channel gap dimension shall be inspected by means of a system that provides (1) continuous graphical trace of gap dimensions half way between the combs and side plates. The coolant channel gap shall be within the tolerance specified in DWG. 409407. Results of this test, along with the resulting graphic trace, shall be submitted to the Purchaser.
5.1.10 Mechanical Integrity. Mechanical integrity shall be established by the Supplier by performing " pull tests" per ASTM E 8 on the specimens required by Section 3.3.2(4). " Roll swaged" joints between the Fuel Plates and side plates shall be able to withstand a load of not less than 150 pounds per lineal inch of side plate joint.
5.1.11 Riveting. The inspection of the riveting used to join the side plates to the end fittings shall conform to the rivet manufacturer's recomendations.
i 6.0 DELIVERY SU8MITTALS 6.1 Two copies (except as noted) of the following data and records shall accompany the shipments:
6.1.1 Certification of product compliance to the requirements of this i
Specification to include any test data pertaining thereto.
6.1.2 Dimensional data as required by Section 5.1.9.
i 6.1.3 Individual Fuel Plate uranium data including:
Supplier's core compact data sheets Serial number with Batch identification Uranium content Fuel Plate Core weight 20
TRTR-4 May 2, 1986 U-235 enrichment Total U-235 content Core void density data l
6.1.4 Individual Fuel Element Composition data including: '
Serial number of the Fuel Element Uranium content U-235 content Serial number of each Fuel Plate in the Fuel Element 6.1.5 Radiation count from Fuel Plate and Fuel Element exterior, as required by Section 5.1.8. The counting period, counter, background, efficiency, and type of counter used shall be reported.
6.1.6 Results of pull tests specified in Section 5.1.10.
6.1.7 List of all applicable waivers and deviations and related Fuel Plates or Fuel Elements 6.1.8 One copy of Radiographs as specified in Section 5.1.3.
6.1.9 One copy of ultrasonic examination traces.
7.0 PACKAGING AND SHIPPING 7.1 The User will provide certified shipping containers for the Fuel Elements.
7.2 The Supplier is responsible for loading the Fuel Elements into the shipping containers in a sealed polyethylene bag in a clean dry condition free of extraneous materials.
21
i- '
TRTR-4 1 Juna 14,1985 {
7.3 The Supplier shall take all necessary precautions during packing to prevent damage to the Fuel Elements during shipment. Each container shall be provided with a tamper-proof seal. The container's loading and shipping documents shall be prepared in accordance with all applicable regulations.
7.4 The Supplier shall arrange for shipment of Fuel Elements in increments no greater than 5 Kg' U-235 as directed by User.
8.0 ACCEPTANCE INSPECTION 8.1 INSPECTION, EXAMINATION, AND TEST All materials, workmanship, and procedures shall be subject to inspection, examination, and test by the Purchaser, and to Rejection by the Purchaser for noncompliance with the Specifications at any and all times during Manufacture, and at any and all places where such Manufacture is carried on. Final inspection and acceptance or Rejection will be made by the Purchaser at the Supplier's plant. The Purchaser shall have the right to reject any one or more of the finished products for defects in workmanship, or defects in any of the materials comprising the finished product which otherwise fail to meet the Specification.
s 8.2 DEVIATIONS FORM SPECIFICATIONS l ,
Notwithstanding other provisions of these Specifications, the Purchaser may, at his option, when requested in writing, waive certain minor deviations from requirements of the Specifications and drawings where the Failure to meet any specific requirement either alone or in combination with other such Failures will not, in the opinion of the Purchaser.. significantly reduce the efficiency or performance of the assembly. Acceptance of a Fuel Element by the Purchaser with or.e or more such deviations from the Specifications shall not be construed to mean the Purchaser approves or will approve similar deviations in Elements not yet delivered under the contract.
22
.. - _ _- _ - - _ ~ - .
FUEL PLATE SAM LING PROCEDURES FOR DESTRUCTIVE TESTS I
- 1. T Samples. Transverse to be taken equally spaced along Fuel Core length.
- 2. L Samples, Longitudinal to be taken at centerline and to include the Dogbone Area.
-> 1 ->.T2 +T3 ->- T4 l
_ _ _. _. _ q I
1 l ~~
I
- 5 g u t ( .,
I
_ _ _ _ . _ _ . _ _ . _ . . __ _ _ _ _ __ _I
"=
mi
+ -~
+ + .
+
I i
Figure 1
.. TRTR-4
. Juns 14, 1985 TABLEI Nominal U-235 Loading for MURR 775 Gram Elements Plate Number U-235 Content (grams) + 1.0%
1 19.260 2 20.393 3 21.526 4 22.659 5 23.793 6 24.926 7 26.059 8 27.192 9 28.325 10 29.459 11 30.592 12 31.725
.13 32.858 14' 33.992 15 35.125 16 36.258 17 37.391 18 38.524 19 39.658 20 40.791 21 41.924 22 43.057 _
23 44.191 24 45.324 775 grams 24
- TRTR-4 May 2, 1986 TABLE II Fuel Core Density The percent voids in the Fuel Cores of Fuel Plates 1, 2, 23, and 24 of each Element shall fall within the range of 4.00 to 11.00. Failure of Plates 1, 2, 23, 24.of any Element to meet this Specification shall be cause for Rejection. The percent voids in a Fuel Core shall be determined as follows:
V -V
- C ct V5 x (100%)
c where:
V% = percent voids in fuel core V
e
- volume of fuel core Vct " calculated theoretical core volume The actual core volume shall be calculated as follows:
Wp -W V, = Yp- pgj where:
V p
= volume of fuel plate Wp = weight of fuel plates W = weight of fuel core pal = density of aluminum used for fuel plat'e cladding The theoretical core volume shall be calculated by one of the following
, ~ methods:
y UA1x , A1 (3) ct , p0A1x #Al 25
1 1
TRTR-4 June 14, 1985 l
l TABLE II (continued) l where:
WUAlx
= weight of UAlx powder used in the fuel core WAl
= weight of aluminum matrix powder used in the fuel core pal = density of aluminum matrix powder pVAlx
= density of UAlx powder <
The density of the UAlx powder used shall be calculated as follows:
pVAlx (grams /cc) = F 2 x (8.14) + F3 x (6.80) + F4 x (5.7) where-F 2
= weight fraction of UAl 2 in UA1 x
powder F
3
=
weight fraction of UA13 in UAl x powder F
4
=
weight fraction of UA14 in UAl x powder ,
The weight fractions shall be determined by X-ray diffraction examination.
Ye t = c - W1 , 3 , Wxsal (2)
Pm 6.8 2.7 Where:
Wf = weight of fuel powder in core (corrected for compacting loss)
Wual3
=
calculated weight of UA13 in core Wxsal = calculated weight of excess aluminum Wu = weight of total uranium in core S
26
a .
' TRTR-4 May 2, 1986 TABLE II (continued)
Vet - theoretical core volume We = core weight Pm = density of aluminum powder in core matrix.
The successful bidder shall submit to the Purchaser for approval the procedures used, data, and result of void fraction determinations on Plates 1, 2, 23, and 24 prior to any Element assembly.
27
. TRTR-4, Attachment I May 2, 1986 b
REQUIREMENTS FOR RADI0 GRAPHING FUEL PLATES EG&G Idaho, Inc.
P.O. Box 1625 Idaho Falls, ID 83415 l
l l
l l
- TRTR-4, Attachment I May 2, 1986 REQUIREMENTS FOR RADI0 GRAPHING FUEL PLATES 1.0 SCOPE This specification provides requirements for radiographing reactor Fuel Plates, acceptable film quality, and film identification.
2.0 REQUIREMENTS A procedure must be written to specify the details for achieving acceptable Fuel Plate radiographs. The procedure must include the requirements given in this specification.
2.1 EQUIPMENT SETUP The voltage shall be 100 k.v.p. with focal spot size 5 mm maximum. The distance between the focal point and the Plate shall be at least twice the length of the Plate. The focal point shall be centered laterally and longitudinally over the Plate or group of Plates.
2.2 FILM 2.2.1 The image outline shall be clear and sharp; the film shall be free of runs, streaks, scratches, blurs, and cassette defects that will affect the area covered by the Fuel Plates.
2.2.2 The film density of all points of the radiograph that correspond to Fuel Plate border locations outside the~ Plate Core shall provide densitometer readings between 1.5 and 2.5. Film density as read over the nominal density standards shall provide densitometer readings between 0.9 and 1.5.
I-1
' TRTR-4, Attachment I
. June 14,1985 2.2.3 The film shall be an extreme sensitivity, extra fine grain, high contrast, double emulsion, industrial X-ray type, (Kodak type M or equal) which is acceptable by the Purchaser. Development of the film shall be in accordance with the manufacturer's reconnendation.
2.3 FILM IDENTIFICATION A system of identification of the film shall be provided by the Supplier which shall show as a minimum:
(1) Subcontract number (2) Plate Lot number (3) Plate size and serial number (4) Orientation of density standard (5) Density standard identification (6) Date of radiography (7) Kilovoltage, current, and focal spot size (8) Type of film l -
l-1 I-2
~
TRTR-4. Attachment II May 2, 1986 SPECIFICATION FOR ALUMINUM POWDER FOR MATRIX MATERIAL IN TRT REACTOR FUEL EG&G Idaho, Inc.
P.O. Box 1625 Idaho Falls, ID 83415
. _ _ . _ _ _ _ _ _ _ . _ _ - . . . . , . . _ _ _ - . - _ . - - . . - . _ - - , , _ , . - - , - - , , . . . . - - . . - - - - ~ . - . - - , , , , .
. TRTR-4 Attachment II May 2, 1986 SPECIFICATION FOR ALUMINUM POWDER FOR MATRIX MATERIAL IN TRT REACTOR FUEL 1.0 SCOPE 1.1 This specification covers the requirements for spherical aluminum powder to be used to adjust fuel density and to act as a binder in uranium-aluminide-based reactor fuel.
2.0 APPLICA8LE DOCUMENTS 2.1 STANDARDS, SPECIFICATIONS, DRAWINGS, AND ATTACHMENTS Applicable portions of the following documents are explicitly specified in the body of and therefore form a part of the specification. Where there is a conflict between the cited documents and the latest revision thereof, the Supplier shall notify the Purchaser of the conflict and use the latest revision unless otherwise directed by the Purchaser.
SPECIFICATIONS American Society for Testino and Materials (ASTM) l ASTM B 214-66 Method of Test for Steve Analysis of Granular Metals Powders.
Military Specifications MIL-A-81335 Aluminum Powder Spherical (11-8-65)
II - 1
._ _ 1 _ _ ._____.__ ..
TRTR-4. Attachment II
, Juna 14,1985 3.0 REQUIREMENTS 3.1 CHEMICAL COMPOSITION The spherical aluminum powder'shall be at least 98.5 wt.% free metallic aluminum (as determined using the test method described in Section 4.4.2 of MIL-A-81335) . The limits on impurities shall be as specified in Table I and -
no single impurity element shall exceed 0.05% except those listed.
TABLE I Limits on Impurities in Aluminum Powder _ wt. %
Cadmium - 0.002 Max Lithium 0.008 Max Boron 0.001 Max Silicon + Iron 0.25 Max Zinc 0.10 Max Copper 0.20 Max Al 023 0.7 Max 3.2 PHYSICAL CONFIGURATION The powder shall be smooth-surfaced and generally spherical. The powder shall also be dry (as specified for volatiles, and oil and grease in Section 3.3 of MIL-A-81335) and free from foreign material by visual examination as defined in Section 4.5 of this specification. Unless otherwise approved by the Purchaser, 98.8K of the powder shall pass through a 100-mesh U.S. Standard sieve. -
4.0 QUALITY ASSURANCE PROVISIONS 4.1 SUPPLIER RESPONSIBILITY Unless otherwise specified by the contract or purchase order, the Supplier shall be responsible for performing all tests and inspections required by this specification prior to submitting the material to the Purchaser for acceptance.
II - 2
. TRTR-4 Attachment II May 2, 1986 ,
l l
The Supplier may utilize his own facilities or any commercial laboratory that is acceptable to the Purchaser. The results of all tests shall be recorded as quantitative data and made available to the Purchaser as stipulated by Section 6.1 of this specification.
4.2 MATERIAL !
For the purpose of inspection or testing, the aluminum material that is made to meet the requirements of this specification, shall have been produced in one facility and acquired by the Supplier at one time.
4.3 SAMPLING The powder in each lot shall be sampled and tested for compliance with the requirements of this specification. Sampling shall be by probe (or other means acceptable to the Purchaser) from three separate, randomly selected areas. Powders from different containers may be combined provided that traceability to original Lot (s) is maintained and that the powders are well mixed and blended so that three truly representative samples can be obtained from the container being sampled.
4.4 ACCEPTANCE TEST l
A chemical analysis shall be made on the samples from each container of powder to determine compliance with the requirements of Section 3.1.
Noncompliance shall be cause for Rejection.
4.5 EXAMINATION Powders from the samples taken as required in Section 4.3 shall be examined (at a magnification of at least 20X) for compliance with the particle size specified in Section 3.2 shall be determined by the test method given by ASTM 8 214-66. Compliance with the specification for dryness given in Section 3.2 shall be determined by the methods described in Section 4.4.3 and 4.4.4 of MIL-A-81335.
! II - 3
+
~ TRTR-4, Attachment II Jun2 14,1985 5.0 PREPARATION FOR DELIVERY 5.1 PACKING The powder shall be packaged in moisture and vapor-proof containers and sealed. The containers shall be of a quality that is acceptable by common carrier and adequate to provide safe, undamaged delivery of the product to the ~
- destination specified by the contract or purchase order.
5.2 CONTAINER MARKING The exterior of the container shall be marked (in legible l'etters at least 1/2 inch high) with at least the following information:
(1) Mate. rial type (2) Number of this specification (3) Lot number (4) Purchaser order number (5) Supplier's name and location l
(6) " Ship-to" address.
l 6.0 NOTES AND DATA l
l 6.1. QUALITY VERIFICATION TEST RESULTS I
t-Six (6) copies of the certified test results (see Section 4.1) shall be submitted to the Purchaser prior to the shipment of any material. One (1) copy of such reports shall accompany the shipment as a packing slip.
II - 4
- . , . . , -.-,-,.._-_,._.--,-___,,.,___,_-~___,#_.,__--_..,-,---.___,,,,,__.___._____,_,_,,__,,_,_.-____-________,.--._,-__-m_.__
- TRTR-4, Attachment III May 2, 1986
.l SPECIFICATION FOR REACTOR GRADE URANIUM-ALUMINIDE (UA1x) POWDER 4
EG&G Idaho, Inc.
P.O. Box 1625 Idaho Falls, ID 83415 i
r l
T TRTR-4. Attachment III May 2, 1986 ;
l SPECIFICATION FOR REACTOR GRADE URANIUM-ALUMINIDE (UA1,) PDWDER 1.0 SCOPE The specification covers uranium-aluminide (UA1,) powder for use in frabricating dispersion-type nuclear Fuel Plates, and its Manufacture.
1.1 CLASSIFICATION
- The uranium-aluminide powder shall be of-the following types, as specified (see Section 6.2):
- Type I - Depleted uranium Type II - Enriched uranium 2.0 APPLICA8LE D00MENTS j 2.1 STANDARDS, SPECIFICATIONS, DRAWINGS, AND ATTACHMENTS The following documents form a part of this specification except as
{ modified by this' specification. Where there is a conflict between the l documents cited and the latest revision thereof, the Supplier shall notify the Purchaser of the conflict and use the latest revision unless otherwise directed by the Purchaser.
ASTM 8 212 Test for Apparent Density of Metal Powders l
ASTM 8 213 Test for Flow Rate of Metal Powders i
l ASTM S 214 Method of Test for Steve Analysis of Granular Metal Powder ,
ASTM 0 480 Aluminum Powder and Paste Sampling and Testing ,
III - 1 -
_ __. _ _ __ _._.. _ .. _ _ _ __ _._ _ __ _ _ _ _ . _ _ _ . _ ___._______..J
l TRTR-4 Attachment III Juna 14,1985 l
1 100-14605 Annual Report of Division Chemistry Analytical Branch for 1962 l
3.0 REQUIREMENTS 3.1 MATERIALS The uranium isotopic composition or enrichment values of the uranium-aluminide shall be reported to the Purchaser and shall be such to comply with this specification. The aluminum-alloy composition shall be reported to the Purchaser and shall comply with this specification.
3.2 COMPOSITION 3.2.1 Uranium Isotopic Composition. The uranium isotopic composition shall be defined as follows:
Type I - Depleted uranium: shall contain less than 0.172 wt% U-235.
Type II - Enriched uranium: shall contain greater than.
0.712 wt% U-235. as specified (see Section 6.2).
l t
(1) Fully Enriched Uranium Isotopic Composition - At the 95%
confidence level, the uranium-aluminide Type II (see
! Section 1.1) shall have the following isotopic composition:
I U-235 Content 93.0% j; 1.0 wt% of total U U-238 Content 6.05 j; 1.0 wt% of total U U-236 Content 0.700 max. wt% of total U U-234 Content 1.2 max. wt% of total U l
III - 2 l
. TRTR-4, Attachment III May 2, 1986 3.2.2 Chemical Composition. At the 95% confindence level, the uranium content of the uranium-aluminide powder shall be: 69.0 1 3.0 wt%.
The balance of the chemical composition shall be aluminum as specified in Section 3.1 and impurities as specified in Section 3.2.2(1).
1
- (1) Uranium-Aluminide Impurity Content - Depleted and enriched uranium-aluminide shall contain no more than the following amounts of individual impurities.
Element Maximus Allowable Amount Oxygen '0.60 wtX Carbon 0.18 wt%
Nitrogen 0.045 wtX Hydrogen 0.020 wt%
Novolatile matter, minimum 99.0 wt%
Cas11y extracted fatty and oily matter, maximum 0.2 wt%
The total impurity content shall not exceed the equivalent boron content (EBC) of 30 parts per million on a weight basis relative to uranium.
The ESC of each element shall be calculated by the following formula:
E8C (impurity) - E8C ppm x impurity ppm The following listed elements shall be included in the calculation of the E8C. The Supplier shall make and report impurity E8C analyses of all Type II uranium-aluminide powder for the elements listed below.
i 3
III - 3
. TRTR-4, Attachment III
,' June 14,1985 BORON EQUIVALENTS FOR IMPURITIES IN URANIUM EBC IM URITY ppm Barium 0.000122 ,
-Beryllium 0.000015 Baron 0.999999 Calcium 0.0001 58 Cadmium 0.325097 -
Chromium 0.000799 Cobalt 0.009239 Copper 0.000868 Iron 0.000672 Lead 0.000011 Magnesium 0.000040 Mangenese 0.003443 Molybdenum 0.000403 Nickel 0.001122 Phosphorus 0.000087 Silicon 0.000066 Silver 0.008236 ;
Tin 0.000072 Tungsten 0.001496 ;
Vanadlum 0.001406 I Zinc 0.000241 l Zirconium 0.000029 Samarium 0.524575 !
Europium 0.433973 l Gadolinum 4.19458 Dysprosium 0.097064 3.3 PHYSICAL PROPERTIES 3.3.1 Particle Size. The uranium-aluminide powder shall be -100, +325 U.S. Standard mesh particles. However, a blend may contain up to 25 wt% of
-325 U.S. Standard mesh particles. -
3.3.2 Crystalline Constituents. The finished ground and sized uranium-aluminide powder shall contain at least 50 wt% UA1 3 as determined by X-ray diffraction procedures.
3.3.3 Powder Density. Bulk and powder density values will be determined and provided for information purposes only. '
III - 4 1
." TRTR-4, Attachment III May 2, 1986 4.0 OUALITY ASSURANCE PROVISIONS 4.1 GENERAL QUALITY ASSURANCE PROVISIONS 4.1.1 Performance of Inspections and Tests. Unless otherwise specified in the procurement documents, the Supplier is responsible for the performance of all inspections and tests to the requirements of Sections 3.2 and 3.3, prior to submission of the acceptance sample for Purchaser inspection and acceptance.
> 4.1.2 Results of Examinations and Tests. Unless otherwise specified, the Supplier may utiltze his own facilities or any commercial laboratory acceptable to the Purchaser. Results of all examinations and tests performed
- under the Quality Assurance Section shall be complete and supplied to the Purchaser.
4.2 CLASSIFICATION OF TESTS All tests required herein for product assurance are classified as acceptance tests, for which necessary sampling techniques and methods of 3
testing are specified in this section.
4.3 INSPECTION PROVISIONS 4.3.1 Batch. The amount of uranium-aluminum intermetallic UA1, powder mixture which is handed as a unit or traceable to a comon step. Each l production quantity which is blended together to form the Batch will have the same chemical and physical characteristics.
, 4.3.2 Sampling. A representative sample of uranium-aluminide shall be taken by the Supplier from each 8atch for the purpose of determining isotopic l
composition, chemical, and physical properties.
l l
l l
III - 5
. _ _ _ _ _ _ . - - . _ . _ . . ~ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ . , _ _ _ _ _ ---
I
~. TRTR-4, Attacnmerot III
. JJn:2 14. 1985 4.4 INSPECTION ,
t r
Unless otherwise specified in the procurement docuwnts, all samples l t
shall be analyzed to determine compliance with the requirements of this l specification. Any Batch that does not conform to this : specification, as determined by analysis of the sample (Section 4.3.2), shall be rejecte'd.
4.5 TESTS -
I 4.5.1 Isotopic Composition. The isotopic composition of the uranium-aluminide shall be determined for compliance with Section 3.2.1. The test '
method shall be by mass spectrographic analysis or equivalent. l 4.5.2 Chemical Composition. The uranium and aluminum content of the l uranium-aluminide powder shall be determined for compliance with Section 3.2.2.
6 (1) Impurity Content - The impurity content of the uranium- ,
aluminide powder shall be determined for compliance with the requirements of Section 3.2.2(1). Analysis shall be performed for all of the elements listed in this section, both metallic and nonmetalic. Samples shall be as specified -
in Section 4.3.2. If the presence of elements other than ,
those specified is suspected because of the raw materials used, the Manufacturing process used, or, if discovered in the course of routine analysis, further analysis shall be I made to determine that the equivalent boron content, EBC, .
does not exceed the specified level of 30 ppm. Test methods ,
l for nonvolatile matter and easily extracted fatty and oily '
matter are given in ASTM D 480. '
4.5.3 Physical Properties.
l
' \
(1) Particle Size - To assure adequate distribution of particle size range, the uranium-aluminide powder shall be tested for 1 compliance with Section 3.3.1 in accordance with ASTM 8 214. 1 III - 6 1
1
~ - - - - -- . -.- - , _ . - . - ~ , - - . - . , - , . - , -.,-.,,-,,,-,__,.,,n, ,.._., , n , _ , ,,,n,, , . _ . _ . ._ 1
., ~
- TRTR-4, Attachment III May 2,1986 4
(2) Crystalline Constituents - The crystalline constituent of the uranium-aluminide powders shall be determined by X-ray diffraction.
t
. (3). Fuel Density - The bulk fuel density shall be determined in
.accordance with ASTM B 2T2. The absolute particle density shall be detertained by helius' displacement at desertbed in
]
ID0-14f,05. pass 91. (This document is available from Offi.ce
- of Technical Services, U.S. Derartwent of Commerce,
! Washington, D.C.).
(4) Flow Rate - The flew rate of the fuel powder shall be l
determined in accordance with ASTM B 213. The drying step l called for in the procedcre shall be conducted ur. der vacuus (10 10pR or better) instead of inir.
4.6 WEPQ4TS OF 755T3 4
5 ine follow b g certiftad test reports shall be provided by the Suppiter
, and approved by the Purchaser prior to use.
(1) Malytii:a1 results on raw naterialc used to preptre l uranium-aluminide.
f ( 2') Analytical results pa finished ground and sized UA1, fuel powder. These results shall include (1) uranium content.
( (2) aluisinum content (3) inpurity content, (4) calculated
'dguivalent boron-content of imourtties, (5) isotopte
, composition, (6) amount of nonvolatile matter, and (7) the ameutt of easiiy extracted fatty and oil mattar.
III - 7 L_ _
i
TRTR-4, Attachment III June 14,1985 ;
(3) The results of physical property determinations made on the ;
finished ground Md sized UAlx fuel powders. These results shall include (1) x-ray diffraction results, (2) bulk density, (3) particle density, (4) tieve analysis, and (5) flow rate.
4.6.1 Certified Reports. Certified reports of the uranium and aluminum starting materials and uranium-aluminide powders which the Supplier accepts shall be kept ccc:plete and made available to the Purchaser. '
5.0 PREPARATION 07 DELIVERY 5.1 FACKAGING I
Packaging cf the uranium-aluminide shall be in accordacce with applicable DOE ano DOT regulations covering this type of material and as specif fed in the '
procurement documents (see Section 6.2).
5.2 MARKING In addition to DOE marking requirements for this type of material, the outside of each container shall be' narked clearly with the following information: *
(1) Material type (2) Number, date of this specification ]
i (3) Manufacturing Lot number !
(4) Net weight of uranium-aluminide (UAlg ) and calculated weights of uranium and U-235.
(5) Purchase order number.
l III - 8 l
l
TRTR-4. Attachee2t III May 2, 1986 ,
6.0 NOTES AND DATA 6.1 OUALITY VERIFICAfION TEST RESULTS Six (6) copies of the certified test results (see Section 4.6) shall be submitted to the Purchaser prior to the shipment of any material. One copy of such reports shall accompany the shipment as a packing slip.
Included in the test results must be sampling, analytical and Quality Control procedures; a statement as to the estimated accuracy and precision of the test values and Development and Production data in support cf the accuracy and pr.ecision estimate. ,
6.2 ORDERING DATA e
The procurement dccuments shall spectfy the fo31owing: l (1) Title, r. umber, date of this specification (2) Type of uranium-aluminide pcwder (see section 1.1) ;
i (3) Percent cf U-235 enrichment (see Section 3.2.1) 4 (4) Packagir.g requirements (see Section 5.1).
^
6,3 ACCOUNTABILITY Forms for the transfer of the accountability and the finanical responsibility for the nuclear material shall be submitted prior to or at the time of shipment of any material to the Purchaser.
l l
l III - 9 -
. _ - ~ _ _ _ _ _ . _ _ _ _ _ ___ _ _ - . _ . _ _ . . _ _ .
- v
~
~
TRTR-4, Attachment IV May 2, 1986
'te. ,
SPECIFICATION FOR ENRICHED U-METAL FOR UAl x REACTOR FUEL ELEMENTS EG&G Idaho, Inc.
P.O. Box 1625 Idaho Falls, ID 83415 i
l
v
- TRTR-4, Attachment IV May 2, 1986 SPECIFICATION FOR ENRICHED U-METAL FOR UAl, REACTOR FUEL ELEMENTS 1.0 SCOPE The specification covers uranium metal for use in fabricating dispersion-type nuclear Fuel Plates.
2.0 APPLICABLE DOCUMENTS None.
3.0 TECHNICAL REQUIREMENTS 3.1 RANUFACTURING PROCESS The uranium metal shall be produced by vacuum melting and casting.
3.2 PHYSICAL PROPERTIES The uranium metal shall be supplied in . fracture (broken or sheared) pieces from the casting. The preferred nominal piece size is 150 grams.
3.3 ISOTOPIC COMPOSITION The isotopic composition of the uranium metal shall be as follows:
Isotope Limit (wt.% of Total U)
U-234 1.2 maximum U-235 93.0 i 1.0 U-236 0.700 maximum U-238 6.0 1 1.0 t 1
IV - 1 l
TRTR-4, Attachment IV
. .. Juna 14,1985 3.4 CHEMICAL COMPOSITION The uranium content of the metal shall be 99.85% minimum. Individual impurities shall not exceed the following:
Element Parts Per Million Aluminum 100.0 Beryllium 10.0 Boron 3.0 Cadmium 0.2 Calcium 50.0 Carbon 200.0 Cobalt 5.0 l
Copper 50.0 Chromium 50.0 Iron + Nickel 400.0 Lithium 10.0 Magnesium 50.0 -
Manganese 15.0 Molybdenum 100.0 Lead 5.0 Silicon 100.0 Sodium 25.0 Hydrogen 35.0 Nitrogen 100.0*
0xygen 100.0
- Nitrogen content of less than 50 ppm is desirable.
3.5 CLEANING l All uranium material shall be pickled to remove visually detectable slag, reductants, or oxides other than thin films of uranium oxides showing inter-ference colors. The uranium is to be thoroughly rinsed with demineralized water to remove acid residues after pickling.
l IV - 2
. TRTR-4. Attachment IV May 2, 1986 4.0 QUALITY ASSURANCE PROVISIONS 4.1 TESTS AND INSPECTIONS The fabricator shall be responsible for performing all tests and
~
inspections required by this specification prior to shipment of the material.
The results of all tests shall be recorded as quantitative data and furnished to the User as stipulated by Section 6.1.
4.2 LOT OR BATCH A production Lot is defined as the uranium material from one casting.
4.3 SAMPLING The uranium metal from each Lot-shall be sampled and tested in accordance with the requirements of this specification.
4.4 ACCEPTABLE TESTS The following tests shall be conducted on all Lots of material.
4.4.1 Isotopic Composition. The isotopic composition of each Lot of uranium metal shall be determined by Mass Spectrograph 1c Analysis or squivalent method. The isotopic concentration shall be in conformance to Section 3.3 4.4.2 Chemical Composition. The chemical composition and impurities, I
with the exception of hydrogen, nitrogen, and oxygen, shall be dstermined on cach Lot of material. The results shall be in conformance to Section 3.4.
l i
IV - 3
s- ,
TRTR-4, Attachment IV
,.* Juna 14,1985 4,
s 5.0 PREPARATION FOR DELIVERY 5.1 PACKAGING Packaging and shipping containers shall comply with DOE and D0T
, Regulations in effect at the time of delivery.
'. s 5.1.1 The metal shall be packaged in moisture-proof containers.
1, .
5.1.2 Lots of material will be kept separate.
, , i 5.2 CONTAINER MARKING The exterior of the container 'shall be marked (in legible letters at least 1/2 inch high) with at least the following information:
(1) Material type (2) Lot number (3) Project number (4) " Ship To" address l
l (5) NOTICE: " The contents of this shipment shall be unpacked
- s>
l, only under the supervision of the ve,ndor's Special Nuclear Materials Management Representative."
1 s
I
\'
l' IV .4 l
o TRTR-4. Attachment IV May 2, 1986 I
6.0 NOTES AND DATA 6.1 QUALITY VERIFICATION TEST RESULTS The Supplier shall provide a statement of assigned precision-and accuracy of the test methods used.
Three (3) copies of the Certified Test Results (see Section 4.1) shall be mailed to the Purchaser.
. IV - 5
,. _- _ ____-_ _ _____