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ASTM International - ASTM E185-98

Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)

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Organization: ASTM International
Publication Date: 10 January 1998
Status: inactive
Page Count: 8
ICS Code (Reactor engineering): 27.120.10
scope:

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 vessels. This practice includes guidelines for designing a minimum surveillance program, selecting materials, and evaluating test results.

1.2 This practice was developed for all light-water cooled nuclear power reactor vessels for which the predicted maximum neutron fluence ( > 1 MeV) at the end of the design lifetime exceeds 1 X 10 17 n/cm (1 X 10 21 n/m ) at the inside surface of the reactor vessel.

1.3 This practice does not provide 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.

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...
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...
ASTM E185-98
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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