Standard Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E706(IC)

1.1 This practice covers analytical and analytical-experimental approaches that can be used to determine the variation in neutron exposure (fluence E > 1.0 MeV, dpa, etc.) and exposure rate and energy spectrum between surveillance locations and points in the pressure vessel wall. Procedures for reporting the results of these analyses with assigned uncertainties are also suggested. This practice deals with the physics-dosimetry aspects of surveillance programs and must be used in conjunction with other Matrix E 706 standards to provide extrapolations based on metallurgical damage correlations.

1.2 The physics-dosimetry relationships determined from this practice may be used to estimate pressure vessel damage through application of Practice E 693 and Guide E 900 standards, using fluence (E > 1.0 MeV), dpa, or damage function derived exposure parameters as independent exposure variables. Supporting the application of these standards is E 944, E 1018, E 1005, and E 854 standards, identified in 2.1.

1.3 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.