ASTM C992-11
(Specification)Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
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 B10 areal density such that subcriticality Keff 0.95 or Keff 0.98 or Keff 1.0 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.
1.6 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.
General Information
Relations
Buy Standard
Standards Content (Sample)
NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation:C992 −11
StandardSpecification for
Boron-Based Neutron Absorbing Material Systems for Use
1
in Nuclear Spent Fuel Storage Racks
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
2.1 ASTM Standards:
1.1 This specification defines criteria for boron-based neu-
A240/A240M Specification for Chromium and Chromium-
tron absorbing material systems used in racks in a pool
Nickel Stainless Steel Plate, Sheet, and Strip for Pressure
environment for storage of nuclear light water reactor (LWR)
Vessels and for General Applications
spent-fuel assemblies or disassembled components to maintain
B209 Specification for Aluminum and Aluminum-Alloy
sub-criticality in the storage rack system.
Sheet and Plate
1.2 Boron-based neutron absorbing material systems nor-
C750 Specification for Nuclear-Grade Boron Carbide Pow-
mally consist of metallic boron or a chemical compound
der
containing boron (for example, boron carbide, B C) supported
C859 Terminology Relating to Nuclear Materials
4
by a matrix of aluminum, steel, or other materials.
C1187 Guide for Establishing Surveillance Test Program for
Boron-Based Neutron Absorbing Material Systems for
1.3 In a boron-based absorber, neutron absorption occurs
Use in Nuclear Spent Fuel Storage Racks
primarily by the boron-10 isotope that is present in natural
E105 Practice for Probability Sampling of Materials
borontotheextentof18.3 60.2 %byweight(dependingupon
ASTM Dictionary of Engineering Science and Technology
the geological origin of the boron). Boron, enriched in
3
2.2 ANSI Standards:
boron-10 could also be used.
ANSI 45.2.2 Packaging, Shipping, Receiving, Storage and
1.4 The materials systems described herein shall be func-
Handling of Items for Nuclear Power Plants
tional – that is always be capable to maintain a B10 areal
ANSI-ASME NQA-1 Quality Assurance Requirements for
density such that subcriticality Keff <0.95 or Keff <0.98 or
Nuclear Facility Application
4
Keff<1.0dependingonthedesignspecificationfortheservice
2.3 U. S. Government Documents:
life in the operating environment of a nuclear spent fuel pool.
10CFR50 Title 10, CFR, Energy Part 50 — Licensing of
Production and Utilization Facilities
1.5 A number of acceptable boron-based absorbing materi-
10CFR72 Title 10, CFR, Energy Part 72 — Licensing
als combinations are currently available while others are being
Requirements for the Storage of Spent Fuel in an Inde-
developed for use in the future. This specification defines
pendent Spent Fuel Storage Installation (ISFSI)
criteria essential and applicable to all materials combinations
and identifies parameters a buyer should specify to satisfy a
3. Terminology
unique or particular requirement.
3.1 Definitions of Terms Specific to This Standard:
1.6 The scope of this specification does not comprehen-
3.1.1 Terms shall be defined in accordance with Terminol-
sively cover all provisions for preventing criticality accidents
ogy C859 or theASTM Dictionary of Engineering Science and
or requirements for health and safety. Observance of this
Technology, except as defined as follows:
specification does not relieve the user of the obligation to
3.1.2 accelerated testing—a procedure for investigating the
conform to all applicable international, national, and local
potential for long-term changes in physical properties or
regulations.
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
1
This specification is under the jurisdiction of ASTM Committee C26 on Standards volume information, refer to the standard’s Document Summary page on
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on the ASTM website.
3
Neutron Absorber Materials Specifications. Available from theAmerican National Standards Institute, 11W. 42nd St., 13th
Current edition approved Feb. 1, 2011. Published February 2011. Originally Floor, New York, NY 10036.
4
approved in 1983. Last previous edition approved in 2006 as C992 – 06. DOI: Available from Superintendent of Documents, U. S. Government Printing
10.1520/C0992-11. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C992−11
chemical composition of a material important to safety, caused 4.2.3 Boron-10 isotopic content of the neutron absorbing
byasystemoperatingparametersuchastemperature,chemical material
...
This document is not anASTM standard and is intended only to provide the user of anASTM 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:C992–06 Designation: C992 – 11
Standard Specification for
Boron-Based Neutron Absorbing Material Systems for Use
1
in Nuclear Spent Fuel Storage Racks
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 B10 areal density such
that subcriticality Keff <0.95 or Keff <0.98 or Keff < 1.0 depending on the design specification for the service life (approximately
40 years) 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.
1.6 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.
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 Spent Fuel Storage Racks
E105 Practice for Probability Sampling of Materials
ASTM Dictionary of Engineering Science and Technology
3
2.2 ANSI Standards:
ANSI 45.2.2 Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants
ANSI-ASME NQA-1 Quality Assurance Requirements for Nuclear Facility Application
4
2.3 U. S. Government Documents:
Title 10,10CFR50 Title 10, CFR, Energy Part 50 (10CFR50)— Licensing of Production and Utilization Facilities
Title 10,10CFR72 Title 10, CFR, Energy Part 72 (10CFR72)— Licensing Requirements for the Storage of Spent Fuel in an
Independent Spent Fuel Storage Installation (ISFSI)
1
ThisspecificationisunderthejurisdictionofASTMCommitteeC26onNuclearFuelCycleandisthedirectresponsibilityofSubcommitteeC26.03onNeutronAbsorber
Materials Specifications.
Current edition approved Feb. 15, 2006.1, 2011. Published March 2006.February 2011. Originally approved in 1983. Last previous edition approved in 19972006 as
C992–89(1997).C992 – 06. DOI: 10.1520/C0992-06.10.1520/C0992-11.
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM 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.
3
Available from the American National Standards Institute, 11 W. 42nd St., 13th Floor, New York, NY 10036.
4
Available from Superintendent of Documents, U. S. Government Printing Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1
---------------------- Page: 1 ----------------------
C992 – 11
3. Terminology
3.1 Definitions of Terms Specific to This Standard:
3.1.1 Terms shall be defined in accordance with Terminology
...
Questions, Comments and Discussion
Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.