Radiation embrittlement in the pressure-vessel steels of nuclear power plants
- Iowa State Univ. of Science and Technology, Ames, IA (USA)
The issues surrounding the radiation embrittlement of pressure-vessel steels have a broad range. On one side, there are questions of deeply fundamental scientific significance, like the mechanisms of the interaction of radiation with matter and the radiation damage it causes. On the other, there are questions of public policy, with serious technological, economic and safety implications. The older nuclear power plants are a major concern, particularly the PWRs, where pressure vessels are more seriously embrittled. In a recent study of residual life assessment of major light-water reactor components, the reactor pressure vessel was judged, for PWRs, to be the most critical major component as far as plant safety is concerned. The most likely degradation sites are the circumferential and axial weldments in the beltline of the vessel, and neutron embrittlement is believed to be the most important potential degradation mechanism.
- OSTI ID:
- 7261810
- Journal Information:
- Journal of Metals; (USA), Vol. 41:12; ISSN 0148-6608
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
MATTER
INTERACTIONS
NEUTRONS
NUCLEAR POWER PLANTS
PRESSURE VESSELS
EMBRITTLEMENT
STEELS
PHYSICAL RADIATION EFFECTS
EVALUATION
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
SERVICE LIFE
WELDING
ALLOYS
BARYONS
CONTAINERS
ELEMENTARY PARTICLES
FABRICATION
FERMIONS
HADRONS
IRON ALLOYS
IRON BASE ALLOYS
JOINING
NUCLEAR FACILITIES
NUCLEONS
POWER PLANTS
RADIATION EFFECTS
REACTORS
SAFETY
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220200* - Nuclear Reactor Technology- Components & Accessories
360106 - Metals & Alloys- Radiation Effects
654003 - Radiation & Shielding Physics- Neutron Interactions with Matter