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ASTM E 185 : 2016 : REDLINE

ASTM E 185 : 2016 : REDLINE

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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

Available format(s)

PDF

Superseded date

09-24-2021

Language(s)

English

Published date

12-19-2016

Publisher

American Society for Testing and Materials

CONTAINED IN VOL. 12.02, 2016 Defines 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.

1.1This 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 light-water 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.

1.2This 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/m 2 (1 × 1017 n/cm2) at the inside surface of the ferritic steel reactor vessel.

1.3This 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.

1.4The 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 light-water 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. A summary of the many major revisions to Practice E185 since its original issuance is contained in Appendix X1.

Note 2:This practice applies only to the planning and design of surveillance programs for reactor vessels designed and built after the effective date of this practice. Previous versions of Practice E185 apply to earlier reactor vessels. See Appendix X1.

Committee
E 10
DocumentType
Redline
Pages
10
PublisherName
American Society for Testing and Materials
Status
Superseded
SupersededBy

ASTM E 1214 : 2011 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E 706 (IIIE)
ASTM E 1253 : 2013 : REDLINE Standard Guide for Reconstitution of Irradiated Charpy-Sized Specimens
ASTM E 1214 : 2011 : R2018 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
ASTM E 1214 : 2011 : EDT 1 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
AWS D3.7 : 2004 GUIDE FOR ALUMINUM HULL WELDING
ASTM E 1297 : 2008 : R2013 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
ASTM E 1006 : 2013 : REDLINE Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
ASTM E 531 : 2013 : REDLINE Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials (Withdrawn 2022)
ASTM E 1005 : 2016 : REDLINE Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
ASTM E 509/E509M : 2014 : REDLINE Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
ASTM E 2956 : 2014 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
ASTM E 560 : 2001 Standard Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E706(IC) (Withdrawn 2009)
ASME PV CODE 11 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS
ASTM E 1297 : 2008 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
ASTM E 1018 : 2009 : R2013 : EDT 1 Standard Guide for Application of ASTM Evaluated Cross Section Data File
ASTM E 1018 : 2009 Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
ANS 51.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
ASTM E 1018 : 2009 : R2013 Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)
ASTM E 706 : 2016 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
ANS 52.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS

ASTM E 482 : 2016 : REDLINE Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
ASTM E 2956 : 2014 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
ASTM E 1253 : 2013 : REDLINE Standard Guide for Reconstitution of Irradiated Charpy-Sized Specimens
ASTM E 170 : 2017 : REDLINE Standard Terminology Relating to Radiation Measurements and Dosimetry
ASME PV CODE 3 APP DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - APPENDICES
ASME PV CODE 11 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS
ASTM E 8/E8M : 2016-09 TEST METHODS FOR TENSION TESTING OF METALLIC MATERIALS

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