Technical Committees / Committee E10 /
Committee E10.02 on Behavior and Use of Nuclear Structural Materials
Showing results 1-8 of 8 matching ACTIVE standards under the jurisdiction of E10.02 E10 Home
E185-10 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels See also WK40938 proposed revision
E509-03(2008) Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels See also WK38162 proposed revision
E531-13 Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials See also WK35990 proposed revision See also WK40101 proposed revision
E636-10 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH) See also WK36079 proposed revision See also WK40958 proposed revision See also WK40959 proposed revision
E900-02(2007) Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF) See also WK34875 proposed revision
E1214-11 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E 706 (IIIE)
E1253-13 Standard Guide for Reconstitution of Irradiated Charpy-Sized Specimens See also WK35991 proposed revision
E2215-10 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
Showing results 1-1 of 1 matching Proposed New Standards under the jurisdiction of E10.02 E10 Home
WK33543 New Guide for Use of SiC as a Temperature Monitor for Reactor Vessel Surveillance
E184-79(1994) Standard Practice for Effects of High-Energy Neutron Radiation on the Mechanical Properties of Metallic Materials, E706 (IB) (Withdrawn 2002)
E453-79(2001) Standard Practice for Examination of Fuel Element Cladding Including the Determination of the Mechanical Properties (Withdrawn 2008)