ASTM E 2215 : 2010
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
Hardcopy , PDF
11-11-2014
English
01-03-2010
Committee |
E 10
|
DocumentType |
Standard Practice
|
Pages |
6
|
PublisherName |
American Society for Testing and Materials
|
Status |
Superseded
|
SupersededBy | |
Supersedes |
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 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 radiation-induced changes in the ferritic steels that comprise the beltline of a light-water moderated nuclear reactor pressure vessel.
1.3 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.
1.4 Modifications to the standard test program and supplemental tests are described in Guide E636.
1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
ASTM E 853 : 2018 | Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results |
ASTM E 706 : 2016 | Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards |
ASTM E 1253 : 2013 | Standard Guide for Reconstitution of Irradiated Charpy-Sized Specimens |
ASTM E 531 : 2013 | Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials (Withdrawn 2022) |
ASTM E 1214 : 2011 : R2018 | Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance |
ASTM E 900 : 2015 : EDT 1 | Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials |
ASTM E 2956 : 2014 | Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels |
ASTM E 509/E509M : 2014 | Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels |
ASTM E 636 : 2014 : EDT 1 | Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels |
ASTM E 185 : 2016 | Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels |
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