ASTM International - ASTM E2215-16
Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
Organization: | ASTM International |
Publication Date: | 1 December 2016 |
Status: | inactive |
Page Count: | 7 |
ICS Code (Reactor engineering): | 27.120.10 |
significance And Use:
4.1 Neutron radiation effects are considered in the design of light-water moderated nuclear power reactors. Changes in system operating parameters may be made throughout the service life of the... View More
scope:
1.1 This practice covers the evaluation of test specimens and dosimetry from light water moderated nuclear power reactor pressure vessel surveillance capsules.
1.2 Additionally, this practice provides guidance on reassessing withdrawal schedule for design life and operation beyond design life.
1.3 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.
1.4 This practice along with its companion surveillance program practice, Practice E185, is intended for application in monitoring the properties of beltline materials in any light-water moderated nuclear reactor.2
1.5 Modifications to the standard test program and supplemental tests are described in Guide E636.
1.6 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.