Long-Term Aging of NPP Ferritic Steels and Components
Author:
Affiliation:
1. National Nuclear Laboratory, D5 Culham Science Centre, Abingdon, Oxfordshire OX14 3DB, GB
2. EDF Energy, Barnett Way, Gloucester GL4 3RS, GB
3. Electric Power Research Institute, 3420 Hillview Ave., Palo Alto, CA 94304, US
Publisher
ASTM International
Reference46 articles.
1. Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors, ASTM E185-66 (West Conshohocken, PA: ASTM International, 1966).
2. Standard Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels, ASTM E185-73 (West Conshohocken, PA: ASTM International, approved March 1, 1973).
3. Mechanical Property and Neutron Spectral Analyses of the Big Rock Point Reactor Pressure Vessel;Serpan;Nuclear Engineering and Design,1970
4. Interaction of Neutron and Thermal Environmental Factors in the Embrittlement of Selected Structural Alloys for Advanced Reactor Applications;Serpan;Nuclear Engineering and Design,1970
5. A. L. Lowe Jr., “Thermal Aging Capsule Results from Oconee Nuclear Station—Unit 1,” in Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels: An International Study, ed. L. E. Steele (West Conshohocken, PA: ASTM International, 1983), 146–154, https://doi.org/10.1520/STP31854S
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