ASTM C992 - 11

    Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks

    Active Standard ASTM C992 | Developed by Subcommittee: C26.03

    Book of Standards Volume: 12.01


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    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.

    This abstract is a brief summary of the referenced standard. It is informational only and not an official part of the standard; the full text of the standard itself must be referred to for its use and application. ASTM does not give any warranty express or implied or make any representation that the contents of this abstract are accurate, complete or up to date.

    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, 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.


    2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.

    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

    U. S. Government Documents

    10CFR72 Title 10, CFR, Energy Part 72 -- Licensing Requirements for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation (ISFSI)

    ANSI Standards

    ANSI-ASMENQA-1 Quality Assurance Requirements for Nuclear Facility Application


    ICS Code

    ICS Number Code 27.120.01 (Nuclear energy in general)

    UNSPSC Code

    UNSPSC Code 15131500(Nuclear fuel)


    DOI: 10.1520/C0992-11

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