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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 This practice is applicable to all pressurized water reactors whose vessel supports will experience a lifetime neutron fluence (E > 1 MeV) that exceeds 1 X 17 neutrons/cm2 or 3.0 X 10-4 dpa.2 (See Terminology E170.)

1.3 This standard may involve hazardous materials, operations, and equipment. This standard does not purport to address all of the safety problems associated with its use. It is the responsibility of whoever uses this standard to consult and establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Keywords

Dosimetry; Ferritic materials; Neutron radiation; Nuclear reactor vessels; Radiation exposure-nuclear materials/applications; Structural analysis; Support structures; radiation exposures for nuclear reactor vessel support structures,; practice; ICS Number Code 27.120.20 (Nuclear power plants. Safety)

To find similar documents by ASTM Volume:

12.02 (Nuclear (II), Solar, and Geothermal Energy)

To find similar documents by classification:

27.120.20 (Nuclear power plants. Safety Radiation protection, see 13.280)

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