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ASTM B876-96

(Specification)

Standard Specification for Borated Dispersion Strengthened Copper Plate, Sheet, Strip, and Rolled Bar for Nuclear Application (Withdrawn 2002)

Standard Specification for Borated Dispersion Strengthened Copper Plate, Sheet, Strip, and Rolled Bar for Nuclear Application (Withdrawn 2002)

SCOPE
1.1 This specification establishes the requirements for plate, sheet, strip, and rolled bar copper alloy UNS No. C15815, dispersion strengthened copper (DSC), which has been modified by the addition of natural or enriched boron for absorption of neutrons.  
1.1.1 The products made to this specification are under consideration for use in storage containers for spent nuclear fuel.  
Note 1- Dispersion strengthened copper is thermally stable high-strength copper which retains a high percentage of its strength at elevated temperature. In addition, it does not recrystallize or soften after exposure to high temperatures almost to the melting point of copper. Since dispersion strengthened copper uses inert aluminum oxide particles to strengthen the copper matrix, the thermal conductivity of the copper is not significantly decreased.  
Note 2- Borated dispersion strengthened coppers covered by this specification, because of their particular structure and specialized properties, may require special care in their fabrication and welding.  
1.2 The values stated in inch-pound units are the standard. SI units are provided for information only.

General Information

Status
Withdrawn
Publication Date
09-Sep-1996
Withdrawal Date
09-Apr-2002
ICS
27.120.10 - Reactor engineering
77.150.30 - Copper products
Technical Committee
B05 - Copper and Copper Alloys
Drafting Committee
B05.01 - Plate, Sheet, and Strip
Current Stage
Ref Project

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ASTM B876-96 - Standard Specification for Borated Dispersion Strengthened Copper Plate, Sheet, Strip, and Rolled Bar for Nuclear Application (Withdrawn 2002)ASTM B876-96 - Standard Specification for Borated Dispersion Strengthened Copper Plate, Sheet, Strip, and Rolled Bar for Nuclear Application (Withdrawn 2002)
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ASTM B876-96 - Standard Specification for Borated Dispersion Strengthened Copper Plate, Sheet, Strip, and Rolled Bar for Nuclear Application (Withdrawn 2002)
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Standards Content (Sample)

Designation: B 876 – 96
AMERICAN SOCIETY FOR TESTING AND MATERIALS
100 Barr Harbor Dr., West Conshohocken, PA 19428
Reprinted from the Annual Book of ASTM Standards. Copyright ASTM
Standard Specification for
Borated Dispersion Strengthened Copper Plate, Sheet, Strip,
1
and Rolled Bar for Nuclear Application
This standard is issued under the fixed designation B 876; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
1. Scope E 255 Practice for Sampling Copper and Copper Alloys for
4
Determination of Chemical Composition
1.1 This specification establishes the requirements for plate,
E 478 Test Methods for Chemical Analysis of Copper
sheet, strip, and rolled bar of copper alloy UNS No. C15815,
5
Alloys
dispersion strengthened copper (DSC), which has been modi-
fied by the addition of natural or enriched boron for absorption
3. Terminology
of neutrons.
3.1 For definitions of terms related to copper and copper
1.1.1 The products made to this specification are under
alloys refer to Terminology B 846.
consideration for use in storage containers for spent nuclear
3.2 Definitions of Terms Specific to This Standard:
fuel.
3.2.1 bursts, n—surface breaks caused by pressure from
NOTE 1—Dispersion strengthened copper is a thermally stable high-
within.
strength copper which retains a high percentage of its strength at elevated
3.2.2 copper, dispersion strengthened, n—a material con-
temperature. In addition, it does not recrystallize or soften after exposure
sisting of copper and a finely dispersed, substantially insoluble,
to high temperatures almost to the melting point of copper. Since
metallic or nonmetallic phase such as aluminum oxide.
dispersion strengthened copper uses inert aluminum oxide particles to
3.2.3 cracks, n—narrow breaks or opening in the surface.
strengthen the copper matrix, the thermal conductivity of the copper is not
significantly decreased.
3.2.4 laps, n—surface defects, appearing as seams, caused
NOTE 2—Borated dispersion strengthened coppers covered by this
by folding over hot metal, fins, or sharp corners and then
specification, because of their particular structure and specialized proper-
rolling or forging them into the surface, but not welding them.
ties, may require special care in their fabrication and welding.
4. Ordering Information
1.2 The values stated in inch-pound units are the standard.
SI units are provided for information only.
4.1 The purchase order or contract for product under this
specification should include the following information:
2. Referenced Documents
4.1.1 ASTM designation and year of issue,
2.1 The following documents in the current issue of the
4.1.2 Copper UNS designation,
Book of Standards form a part of this specification to the extent
4.1.3 Temper (Section 7) or condition (Section 10),
referenced herein:
4.1.4 Dimensions: thickness and width, or diameter,
2.2 ASTM Standards:
4.1.5 Type of edge, if required (Section 9),
B 248 Specification for General Requirements for Wrought
4.1.6 Length,
Copper and Copper-Alloy Plate, Sheet, Strip, and Rolled
4.1.7 How furnished: straight lengths or coils,
2
Bar
4.1.8 Quantity, and
B 249 Specification for General Requirements for Wrought
4.1.9 Total weight, each size.
2
Copper and Copper-Alloy Rod, Bar, and Shapes
4.2 The following options are available under this specifi-
B 601 Practice for Temper Designations for Copper and
cation and should be specified in the purchase order or contract
2
Copper Alloys—Wrought and Cast
when required:
2
B 846 Terminology for Copper and Copper Alloys
4.2.1 Stress relief treatment, (5.3),
3
E 8 Test Methods of Tension Testing of Metallic Materials
4.2.2 Certification (Specification B 248),
4.2.3 Mill test report (Specification B 248),
4.2.4 Condition or finish requirement (10.2), and
1
This specification is under the jurisdiction of ASTM Committee B-5 on Copper
4.2.5 The composition, thickness, and condition of the
and Copper Alloys and is the direct responsibility of Subcommittee B05.01 on Plate,
Sheet, and Strip.
Current edition approved Sept. 10, 1996. Published November 1996.
2 4
Annual Book of ASTM Standards, Vol 02.01. Annual Book of ASTM Standards, Vol 03.05.
3 5
Annual Book of ASTM Standards, Vol 03.01. Annual Book of ASTM Standards, Vol 03.06.
1

---------------------- Page: 1 ----------------------
B 876
copper jacket or its removal shall be determined by agreement 9.2 Straightness:
1
between the supplier and the purchaser. 9.2.1 ⁄2 in. (12.7 mm) in 6 ft (1.83 m), up to and including
1 in. (25.4 mm) thick.
5. Materials and Manufacture
3
9.2.2 ⁄8 in. (9.5 mm) in 6 ft (1.83 m), over 1 in. (25.4 mm)
5.1 Dispersion strengthened copper is made by a powder thick.
metallurgical process. A copper-aluminum alloy is prepared by
9.3 Edges—Edge requirements shall be
...

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ASTM
ASTM E853-23(Practice)
Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results

SIGNIFICANCE AND USE
3.1 The objectives of a reactor vessel surveillance program are twofold. The first requirement of the program is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region resulting from exposure to neutron irradiation and the thermal environment. The second requirement is to make use of the data obtained from the surveillance program to determine the conditions under which the vessel can be operated throughout its service life.  
3.1.1 To satisfy the first requirement of 3.1, the tasks to be carried out are straightforward. Each of the irradiation capsules that comprise the surveillance program may be treated as a separate experiment. The goal is to define and carry to completion a dosimetry program that will, a posteriori, describe the neutron field to which the material test specimens were exposed. The resultant information will then become part of a database applicable in a stricter sense to the specific plant from which the capsule was removed, but also in a broader sense to the industry as a whole.  
3.1.2 To satisfy the second requirement of 3.1, the tasks to be carried out are somewhat complex. The objective is to describe accurately the neutron field to which the pressure vessel itself will be exposed over its service life. This description of the neutron field must include spatial gradients within the vessel wall. Therefore, heavy emphasis must be placed on the use of neutron transport techniques as well as on the choice of a design basis for the computations. Since a given surveillance capsule measurement, particularly one obtained early in plant life, is not necessarily representative of long-term reactor operation, a simple normalization of neutron transport calculations to dosimetry data from a given capsule may not be appropriate (1-67).  
3.2 The objectives and requirements of a reactor vessel's support structure's surveillance program are much less stringent, and at present, are limited to ...
SCOPE
1.1 This practice covers the methodology, summarized in Annex A1, to be used in the analysis and interpretation of neutron exposure data obtained from LWR pressure vessel surveillance programs and, based on the results of that analysis, establishes a formalism to be used to evaluate present and future condition of the pressure vessel and its support structures2 (1-74).3  
1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods (see Master Matrix E706) (1, 5, 13, 48, 49).2 In order to make this practice at least partially self-contained, a moderate amount of discussion is provided in areas relating to ASTM and other documents. Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, and exposure units.  
1.3 This practice is restricted to direct applications related to surveillance programs that are established in support of the operation, licensing, and regulation of LWR nuclear power plants. Procedures and data related to the analysis, interpretation, and application of test reactor results are addressed in Practice E1006, Guide E900, and Practice E1035.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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  • Standard
    9 pages
    English language
    sale 15% off