ASTM International - ASTM E1035-85(1996)
Standard Practice for Determining Radiation Exposures for Nuclear Reactor Vessel Support Structures
|Publication Date:||1 January 1996|
|ICS Code (Nuclear power plants. Safety):||27.120.20|
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.