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    ASTM E1035 - 18

    Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures

    Active Standard ASTM E1035 | Developed by Subcommittee: E10.05

    Book of Standards Volume: 12.02

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    Significance and Use

    3.1 Prediction of neutron radiation effects to pressure vessel steels has long been a part of the design and operation of light water reactor power plants. Both the federal regulatory agencies (see 2.3) and national standards groups (see 2.1 and 2.2) have promulgated regulations and standards to ensure safe operation of these vessels. The support structures for pressurized water reactor vessels may also be subject to similar neutron radiation effects (1, 3-6).6 The objective of this practice is to provide guidelines for determining the neutron radiation exposures experienced by individual vessel supports.

    3.2 It is known that high energy photons can also produce displacement damage effects that may be similar to those produced by neutrons. These effects are known to be much less at the belt line of a light water reactor pressure vessel than those induced by neutrons. The same has not been proven for all locations within vessel support structures. Therefore, it may be prudent to apply coupled neutron-photon transport methods and photon induced displacement cross sections to determine whether gamma-induced dpa exceeds the screening level of 3.0 × 10-4, used in this practice for neutron exposures. (See 1.3).

    1. Scope

    1.1 This practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear reactor vessel support structures located in the vicinity of the active core. This practice includes guidelines for:

    1.1.1 Selecting appropriate dosimetric sensor sets and their proper installation in reactor cavities.

    1.1.2 Making appropriate neutronics calculations to predict neutron radiation exposures.

    1.2 The values stated in SI units are to be regarded as standard; units that are not SI can be found in Terminology E170 and are to be regarded as standard. Any values in parentheses are for information only.

    1.3 This practice is applicable to all pressurized water reactors whose vessel supports will experience a lifetime neutron fluence (E > 1 MeV) that exceeds 1 × 1017 neutrons/cm 2 or exceeds 3.0 × 104 dpa.(1)2 (See Terminology E170.)

    1.4 Exposure of vessel support structures by gamma radiation is not included in the scope of this practice, but see the brief discussion of this issue in 3.2.

    1.5 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. (For example (2))

    1.6 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.

    ASTM Standards

    E170 Terminology Relating to Radiation Measurements and Dosimetry

    E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance

    E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)

    E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance

    E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance

    E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance

    E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance

    E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance

    E1018 Guide for Application of ASTM Evaluated Cross Section Data File

    ASME Standard

    Boiler and Pressure Vessel Code, Section III Avail

    ICS Code

    ICS Number Code 27.120.20 (Nuclear power plants. Safety)

    UNSPSC Code

    UNSPSC Code 95121803(Nuclear power station)

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

    DOI: 10.1520/E1035-18

    Citation Format

    ASTM E1035-18, Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures, ASTM International, West Conshohocken, PA, 2018, www.astm.org

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