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ASTM International - ASTM E185-10

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

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Organization: ASTM International
Publication Date: 1 March 2010
Status: inactive
Page Count: 8
ICS Code (Reactor engineering): 27.120.10
significance And Use:

Predictions of neutron radiation effects on pressure vessel steels are considered in the design of light-water moderated nuclear power reactors. Changes in system operating parameters often are... View More

scope:

1.1 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. 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.

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

1.3 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.

1.4 This practice does not provide specific procedures for monitoring the radiation induced changes in properties beyond the design life, but the procedure described may provide guidance for developing such a surveillance program.

1.5 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 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 a surveillance program. Practice E2215 describes the procedures for testing and evaluation of surveillance capsules removed from a surveillance program as defined in the current or previous editions of Practice E185. 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.

Document History

December 1, 2016
Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
1.1 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...
June 1, 2015
Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
1.1 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...
June 1, 2015
Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
1.1 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...
ASTM E185-10
March 1, 2010
Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
1.1 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...
June 10, 2002
Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
1.1 This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in the beltline of light-water...
January 10, 1998
Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)
1.1 This practice covers procedures for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in the beltline of light-water cooled nuclear power reactor...
January 1, 1982
Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E 706 (IF)
A description is not available for this item.
January 1, 1979
Standard Practice for Conducting Surveillance Tests For Light-Water Cooled Nuclear Power Reactor Vessels
A description is not available for this item.
January 1, 1973
Standard Recommended Practice for Surveillance Tests For Nuclear Reactor Vessels
A description is not available for this item.
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