ASTM C992-20a

Standard Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment

ABSTRACT
This specification defines essential criteria for all material combinations in boron-based neutron-absorbing material systems used for nuclear spent fuel storage racks in nuclear light water reactors, spent-fuel assemblies, or disassembled components. The boron-based neutron absorbing materials normally consist of metallic boron or a boron-containing boron compound supported by a matrix of aluminum, steel, or other materials. Material systems covered in this specification should always be capable of maintaining a B10 areal density that can support the required subcriticality depending on the design specification for service life.
SCOPE
1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system.  
1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials.  
1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 ± 0.2 % by weight (depending upon the geological origin of the boron). Boron enriched in boron-10 could also be used.  
1.4 The materials systems described herein shall be functional (that is, always be capable to maintain a boron-10 areal density such that subcriticality is maintained depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool).  
1.5 Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.  
1.6 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.  
1.7 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.

General Information

• Status: Published
• Publication Date: 30-Jun-2020
• ICS: 27.120.01 - Nuclear energy in general
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.03 - Neutron Absorber Materials Specifications

Standards Content (Sample)

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.
Designation:C992 −20a
Standard Specification for
Boron-based Neutron Absorbing Material Systems for Use
1
in Nuclear Fuel Storage Racks in Pool Environment
This standard is issued under the fixed designation C992; 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 (´) indicates an editorial change since the last revision or reapproval.
1. Scope 2. Referenced Documents
2
1.1 This specification defines criteria for boron-based neu- 2.1 ASTM Standards:
tron absorbing material systems used in racks in a pool C859 Terminology Relating to Nuclear Materials
environment for storage of nuclear light water reactor (LWR) C1187 Guide for Establishing Surveillance Test Program for
spent-fuel assemblies or disassembled components to maintain Boron-based Neutron Absorbing Material Systems for
sub-criticality in the storage rack system. Use in Nuclear Fuel Storage Racks in Pool Environment
E105 Practice for Probability Sampling of Materials
1.2 Boron-based neutron absorbing material systems nor-
E2971 TestMethodforDeterminationofEffectiveBoron-10
mally consist of metallic boron or a chemical compound
Areal Density in Aluminum Neutron Absorbers using
containing boron (for example, boron carbide, B C) supported
4
Neutron Attenuation Measurements
by a matrix of aluminum, steel, or other materials.
ASTM Dictionary of Engineering Science and Technology
2
1.3 In a boron-based absorber, neutron absorption occurs
2.2 Other ASTM Document:
primarily by the boron-10 isotope that is present in natural
ASTM Dictionary of Engineering Science and Technology
borontotheextentof18.3 60.2 %byweight(dependingupon 3
2.3 ANSI Standard:
thegeologicaloriginoftheboron).Boronenrichedinboron-10
ANSI N45.2.2 Packaging, Shipping, Receiving, Storage and
could also be used.
Handling of Items for Nuclear Power Plants
4
1.4 The materials systems described herein shall be func-
2.4 ASME Standard:
tional (that is, always be capable to maintain a boron-10 areal
ASME NQA-1 QualityAssurance Requirements for Nuclear
density such that subcriticality is maintained depending on the
Facility Application
5
design specification for the service life in the operating
2.5 U. S. Government Documents:
environment of a nuclear spent fuel pool).
10CFR50 Title 10, CFR, Energy Part 50—Licensing of
Production and Utilization Facilities
1.5 Observance of this specification does not relieve the
10CFR72 Title 10, CFR, Energy Part 72—Licensing Re-
useroftheobligationtoconformtoallapplicableinternational,
quirements for the Storage of Spent Fuel in an Indepen-
national, and local regulations.
dent Spent Fuel Storage Installation (ISFSI)
1.6 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the
3. Terminology
responsibility of the user of this standard to establish appro-
3.1 Definitions:
priate safety, health, and environmental practices and deter-
3.1.1 Fordefinitionsoftermsusedinthisspecification,refer
mine the applicability of regulatory limitations prior to use.
to Terminology C859 or theASTM Dictionary of Engineering
1.7 This international standard was developed in accor-
Science and Technology.
dance with internationally recognized principles on standard-
ization established in the Decision on Principles for the
Development of International Standards, Guides and Recom-
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
mendations issued by the World Trade Organization Technical
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on
Barriers to Trade (TBT) Committee.
the ASTM website.
3
Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
4th Floor, New York, NY 10036, http://www.ansi.org.
1 4
This specification is under the jurisdiction of ASTM Committee C26 on Available from American Society of Mechanical Engineers (ASME), ASME
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on International Headquarters, Two Park Ave., New York, NY 10016-5990, http://
Neutron Absorber Materials Specifications. www.asme.org.
5
Current edition approved July 1, 2020. Published July 2020. Originally approved Available from U.S. Government Printing Office, Superintendent of
in 1983. Last previous edition approved in 2020 as C992 – 20. DOI: 10.1520/ Documents, 732 N. Capitol St., NW, Washington, DC 20401-0001, http://
C0992-20A. www.access.gpo.gov.
Copyright © ASTM International, 100 Barr Ha
...

This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation: C992 − 20 C992 − 20a
Standard Specification for
Boron-based Neutron Absorbing Material Systems for Use
1
in Nuclear Fuel Storage Racks in Pool Environment
This standard is issued under the fixed designation C992; 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 (´) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment
for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in
the storage rack system.
1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing
boron (for example, boron carbide, B C) supported by a matrix of aluminum, steel, or other materials.
4
1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to
the extent of 18.3 6 0.2 % by weight (depending upon the geological origin of the boron). Boron enriched in boron-10 could also
be used.
1.4 The materials systems described herein shall be functional (that is, always be capable to maintain a boron-10 areal density
such that subcriticality is maintained depending on the design specification for the service life in the operating environment of a
nuclear spent fuel pool).
1.5 Observance of this specification does not relieve the user of the obligation to conform to all applicable international,
national, and local regulations.
1.6 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.
1.7 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.
2. Referenced Documents
2
2.1 ASTM Standards:
C859 Terminology Relating to Nuclear Materials
C1187 Guide for Establishing Surveillance Test Program for Boron-based Neutron Absorbing Material Systems for Use in
Nuclear Fuel Storage Racks in Pool Environment
E105 Practice for Probability Sampling of Materials
E2971 Test Method for Determination of Effective Boron-10 Areal Density in Aluminum Neutron Absorbers using Neutron
Attenuation Measurements
ASTM Dictionary of Engineering Science and Technology
2
2.2 Other ASTM Document:
ASTM Dictionary of Engineering Science and Technology
3
2.3 ANSI Standard:
ANSI N45.2.2 Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants
1
This specification is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on Neutron Absorber
Materials Specifications.
Current edition approved Jan. 1, 2020July 1, 2020. Published February 2020July 2020. Originally approved in 1983. Last previous edition approved in 20162020 as
C992 – 16.C992 – 20. DOI: 10.1520/C0992-20.10.1520/C0992-20A.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
3
Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http://www.ansi.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

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C992 − 20a
4
2.4 ASME Standard:
ASME NQA-1 Quality Assurance Requirements for Nuclear Facility Application
5
2.5 U. S. Government Documents:
10CFR50 Title 10, CFR, Energy Part 50—Licensing of Production and Utilization Facilities
10CFR72 Title 10, CFR, Energy Part 72—Licensing Requirements for the Storage of Spent Fuel in an Independent Spent Fuel
Storage Installation (ISFSI)
3. Terminology
3.1 Definitions:
3.1.1 For definitions of terms used in this specification, refer to Terminology C859 or the ASTM Dictionary
...