ASTM C992 - 20

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

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

    ANSI Standard

    ANSI N45.2.2 Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants

    ASME Standard

    ASME NQA-1 Quality Assurance Requirements for Nuclear Facility Application

    U. S. Government Documents

    10CFR50 Title 10, CFR, Energy Part 50Licensing of Production and Utilization Facilities

    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


    ICS Code

    ICS Number Code 27.120.01 (Nuclear energy in general)

    UNSPSC Code

    UNSPSC Code 15131500(Nuclear fuel)


    Referencing This Standard
    Link Here
    Link to Active (This link will always route to the current Active version of the standard.)

    DOI: 10.1520/C0992-20

    Citation Format

    ASTM C992-20, Standard Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment, ASTM International, West Conshohocken, PA, 2020, www.astm.org

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