ASTM C992-16
(Specification)Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in a Pool Environment
Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in a 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 and health practices and determine the applicability of regulatory limitations prior to use.
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Designation:C992 −16
Standard Specification for
Boron-Based Neutron Absorbing Material Systems for Use
1
in Nuclear Fuel Storage Racks in a 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 C1187 Guide for Establishing Surveillance Test Program for
Boron-Based Neutron Absorbing Material Systems for
1.1 This specification defines criteria for boron-based neu-
Use in Nuclear Fuel Storage Racks In a Pool Environment
tron absorbing material systems used in racks in a pool
E105 Practice for Probability Sampling of Materials
environment for storage of nuclear light water reactor (LWR)
E2971 TestMethodforDeterminationofEffectiveBoron-10
spent-fuel assemblies or disassembled components to maintain
Areal Density in Aluminum Neutron Absorbers using
sub-criticality in the storage rack system.
Neutron Attenuation Measurements
1.2 Boron-based neutron absorbing material systems nor-
ASTM Dictionary of Engineering Science and Technology
mally consist of metallic boron or a chemical compound
3
2.2 ANSI and ASME Standards:
containing boron (for example, boron carbide, B C) supported
4
ANSI N45.2.2 Packaging, Shipping, Receiving, Storage and
by a matrix of aluminum, steel, or other materials.
Handling of Items for Nuclear Power Plants
1.3 In a boron-based absorber, neutron absorption occurs
ASME NQA-1 QualityAssurance Requirements for Nuclear
primarily by the boron-10 isotope that is present in natural
Facility Application
borontotheextentof18.3 60.2 %byweight(dependingupon
4
2.3 U. S. Government Documents:
the geological origin of the boron). Boron, enriched in
10CFR50 Title 10, CFR, Energy Part 50 — Licensing of
boron-10 could also be used.
Production and Utilization Facilities
1.4 The materials systems described herein shall be func-
10CFR72 Title 10, CFR, Energy Part 72 — Licensing
tional – that is always be capable to maintain a boron-10 areal
Requirements for the Storage of Spent Fuel in an Inde-
density such that subcriticality is maintained depending on the
pendent Spent Fuel Storage Installation (ISFSI)
design specification for the service life in the operating
environment of a nuclear spent fuel pool.
3. Terminology
1.5 Observance of this specification does not relieve the
3.1 Terms shall be defined in accordance with Terminology
useroftheobligationtoconformtoallapplicableinternational,
C859 or the ASTM Dictionary of Engineering Science and
national, and local regulations.
Technology
1.6 This standard does not purport to address all of the
3.2 Definitions of Terms Specific to This Standard:
safety concerns, if any, associated with its use. It is the
3.2.1 accelerated testing—a procedure for investigating the
responsibility of the user of this standard to establish appro-
potential for long-term changes in physical properties or
priate safety and health practices and determine the applica-
chemical composition of a material important to safety, caused
bility of regulatory limitations prior to use.
byasystemoperatingparametersuchastemperature,chemical
environment or radiation.
2. Referenced Documents
3.2.1.1 Discussion—The procedure uses a value of the
2
2.1 ASTM Standards:
identified parameter that is outside the normal bound of the
C859 Terminology Relating to Nuclear Materials
operating parameter being investigated, in order to (1) increase
the rate of degradation, if any, (2) identify the operating limit
1
This specification is under the jurisdiction of ASTM Committee C26 on
for acceptable limit of the parameter, and (3) to provide
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on
information that might assist in interpreting the degradation
Neutron Absorber Materials Specifications.
Current edition approved Jan. 15, 2016. Published February 2016. Originally
approved in 1983. Last previous edition approved in 2011 as C992 – 11. DOI:
10.1520/C0992-16.
2 3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or Available from theAmerican National Standards Institute, 11W. 42nd St., 13th
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Floor, New York, NY 10036.
4
Standards volume information, refer to the standard’s Document Summary page on Available from Superintendent of Documents, U. S. Government Printing
the ASTM website. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
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C992−16
mechanism(s) involved. In this
...
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 − 11 C992 − 16
Standard Specification for
Boron-Based Neutron Absorbing Material Systems for Use
in Nuclear Spent Fuel Storage Racks in a Pool
1
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 B10boron-10 areal
density such that subcriticality Keff <0.95 or Keff <0.98 or Keff < 1.0 is maintained depending on the design specification for the
service life in the operating environment of a nuclear spent fuel pool.
1.5 A number of acceptable boron-based absorbing materials combinations are currently available while others are being
developed for use in the future. This specification defines criteria essential and applicable to all materials combinations and
identifies parameters a buyer should specify to satisfy a unique or particular requirement.
1.5 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or
requirements for health and safety. 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 and health practices and determine the applicability of regulatory
limitations prior to use.
2. Referenced Documents
2
2.1 ASTM Standards:
A240/A240M Specification for Chromium and Chromium-Nickel Stainless Steel Plate, Sheet, and Strip for Pressure Vessels and
for General Applications
B209 Specification for Aluminum and Aluminum-Alloy Sheet and Plate
C750 Specification for Nuclear-Grade Boron Carbide Powder
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 a Pool Environment
E105 Practice for Probability Sampling of Materials
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 Feb. 1, 2011Jan. 15, 2016. Published February 2011February 2016. Originally approved in 1983. Last previous edition approved in 20062011
as C992 – 06.C992 – 11. DOI: 10.1520/C0992-11.10.1520/C0992-16.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C992 − 16
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
3
2.2 ANSI and ASME Standards:
ANSI 45.2.2N45.2.2 Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants
ANSI-ASMEASME NQA-1 Quality Assurance Requirements for Nuclear Facility Application
4
2.3 U. S. Government Documents:
10CFR50 Title 10, CFR, Energy Part 50 — Licensing of Production and Utilization Facilities
10CFR72 Title 10,
...
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