Radiation embrittlement of nuclear reactor pressure vessel steels: An international review (Fourth Volume)

Conference · Wed Dec 01 04:00:00 EST 1993

OSTI ID:139987

Steele, L E ^[1]

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1. ed.

The technical content is highly focused on the title subject, which is crucial to the continued operating safety of commercial nuclear electric power generating plants, as it treats the phenomenon of neutron embrittlement of the primary containment vessel of the nuclear reactor power source. Integrity of this nuclear reactor component is a primary goal of all the specialists who have participated in this series of four international meetings. These international meetings and the publication arising from them offer a progressive series of volumes that provide a valuable technical resource to nuclear power plant operators, national regulatory specialists, and researchers in this area of nuclear safety. The progressive nature of these publications is particularly valuable in teaching scientific and technical developments on what has become one of the most critical elements in reactor safety analysis with the aging of nuclear power reactors. The progress of research and vessel surveillance for neutron embrittlement reflects the aging of nuclear power reactors and, therefore, the attendant interest in assuring safe life attainment for this crucial element of electric power generation, as the authors approach the close of the Twentieth century. Separate abstracts were prepared for 31 papers of this book.

• OSTI ID: 139987
• Report Number(s): CONF-9009544--; ISBN 0-8031-1478-8
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
EMBRITTLEMENT
FRACTURE PROPERTIES
IRRADIATION
LEADING ABSTRACT
MEETINGS
NEUTRONS
NONDESTRUCTIVE TESTING
NUCLEAR POWER PLANTS
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR SAFETY
RESEARCH PROGRAMS
STEELS
SURVEILLANCE