Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
|Publication Date:||1 June 2019|
|ICS Code (Reactor engineering):||27.120.10|
This practice covers the evaluation of test specimens and dosimetry from light water moderated nuclear power reactor pressure vessel surveillance capsules.
Additionally, this practice provides guidance on reassessing withdrawal schedule for design life and operation beyond design life.
This practice is one of a series of standard practices that outline the surveillance program required for nuclear reactor pressure vessels. The surveillance program monitors the irradiation-induced changes in the ferritic steels that comprise the beltline of a light-water moderated nuclear reactor pressure vessel.
This practice along with its companion surveillance program practice, Practice E185, is intended for application in monitoring the properties of beltline materials in any lightwater moderated nuclear reactor.2
Modifications to the standard test program and supplemental tests are described in Guide E636.
The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.