ASTM International

Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
 N E185

Annotation

This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. New advanced lightwater small modular reactor designs with a nominal design output of 300 MWe or less have not been specifically considered in this practice. This practice includes the minimum requirements for the design of a surveillance program, selection of vessel material to be included, and the initial schedule for evaluation of materials

This practice was developed for all light-water moderated nuclear power reactor vessels for which the predicted maximum fast neutron fluence (E > 1 MeV) exceeds 1 ? 1021 neutrons/m2 (1 ? 1017 n/cm2) at the inside surface of the ferritic steel reactor vessel

This practice does not provide specific procedures for monitoring the radiation induced changes in properties beyond the design life. Practice E2215 addresses changes to the withdrawal schedule during and beyond the design life

The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only

NOTE 1—The increased complexity of the requirements for a lightwater moderated nuclear power reactor vessel surveillance program has necessitated the separation of the requirements into three related standards. Practice E185 describes the minimum requirements for design of a surveillance program. Practice E2215 describes the procedures for testing and evaluation of surveillance capsules removed from a reactor vessel. Guide E636 provides guidance for conducting additional mechanical tests. Asummary of the many major revisions to Practice E185 since its original issuance is contained in Appendix X1