Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
|Publication Date:||1 November 2008|
|ICS Code (Nuclear power plants. Safety):||27.120.20|
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:
Selecting appropriate dosimetric sensor sets and their proper installation in reactor cavities.
Making appropriate neutronics calculations to predict neutron radiation exposures.
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 1017 neutrons/ cm2 or 3.0 X 10−4 dpa.2 (See Terminology E 170.)
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.
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 and health practices and determine the applicability of regulatory limitations prior to use.
2 Based on data from Table 5 of Master Matrix E 706 and Reference 5.