Radiation embrittlement of nuclear reactor pressure vessel steels
A critical issue in assuring the safety of nuclear power plants involves the integrity of the primary pressure vessel of light water reactors, which are the nuclear source of choice in most nations. Such integrity depends upon no serious degradation of the steel in the pressure vessel, which, in turn, depends upon the knowledge of neutron irradiation embrittlement and the means for minimizing such degradation of this key component. While research and operational surveillance of this phenomenon have been carried out for many years, it is essential that such efforts not stop until the authors have full assurance on an international basis that knowledge is adequate to provide the technical basis for preventing catastrophic vessel rupture. Further, in view of the Chernobyl accident, international collaboration in developing such knowledge should be condoned by all nations having or developing nuclear power.
- OSTI ID:
- 6834850
- Report Number(s):
- CONF-8705275-; ISBN: 0-8031-1187-8; TRN: 90-021650
- Resource Relation:
- Conference: Symposium on irradiation embrittlement and aging of reactor pressure vessels, Philadelphia, PA (USA), 27-29 May 1987; Related Information: STP 1011
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
REACTOR VESSELS
PHYSICAL RADIATION EFFECTS
STEELS
EMBRITTLEMENT
CHARPY TEST
DAMAGING NEUTRON FLUENCE
FRACTURE PROPERTIES
IRRADIATION
LEADING ABSTRACT
PRESSURE VESSELS
REACTOR SAFETY
ABSTRACTS
ALLOYS
CONTAINERS
DESTRUCTIVE TESTING
DOCUMENT TYPES
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
NEUTRON FLUENCE
RADIATION EFFECTS
SAFETY
TESTING
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories
360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties