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ASTM E185-98

Historical Revision

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

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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.


SDO ASTM: ASTM International
Document Number E185
Publication Date Jan. 10, 1998
Language en - English
Page Count 8
Revision Level 98
Supercedes
Committee E10.02
Publish Date Document Id Type View
Sept. 1, 2021 E0185-21 Revision
Dec. 1, 2016 E0185-16 Revision
June 1, 2015 E0185-15E01 Revision
June 1, 2015 E0185-15 Revision
March 1, 2010 E0185-10 Revision
June 10, 2002 E0185-02 Revision
Jan. 10, 1998 E0185-98 Revision
Not Available E0185-82E02 Revision
Not Available E0185-79 Revision
Not Available E0185-73 Revision