(Reactor materials embrittlement)
Technical Report
·
OSTI ID:6792390
The traveler served as a member of a delegation from the US Nuclear Regulatory Commission in an information exchange meeting on nuclear safety with the USSR in Moscow, USSR, June 25--29, 1990. The meetings were held within the framework of the US-USSR Joint Coordinating Committee on Civilian Nuclear Reactor Safety. The traveler participated in the meetings of Working Group 3 on Radiation Embrittlement of the Housing (Pressure Vessel) and Support Structures, and Annealing of the Housing. This was the second meeting for Working Group 3; the first was held in Washington, D.C., in June 1989 and the traveler has participated in both. The traveler presented results of research on the effects of irradiation on crack-arrest toughness of submerged-arc welds, fracture toughness of stainless steel cladding, and mechanisms of radiation embrittlement in pressure vessel steels. The meetings resulted in detailed exchange of technical progress between participants, identification of specific areas requiring continued research, agreements regarding exchange of additional information, agreements on exchange of reactor vessel materials, and US witnessing of a thermal annealing of a USSR-designed commercial light-water reactor vessel.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6792390
- Report Number(s):
- ORNL/FTR-3667; ON: DE90014311
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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36 MATERIALS SCIENCE
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ALLOYS
ANNEALING
ASIA
CONTAINERS
COOPERATION
CRACK PROPAGATION
CRACKS
EASTERN EUROPE
EMBRITTLEMENT
EUROPE
HEAT TREATMENTS
INTERNATIONAL COOPERATION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MEETINGS
NORTH AMERICA
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR MATERIALS
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THERMAL SHOCK
TRAVEL
USA
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WATER COOLED REACTORS
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Nonbreeding
Light-Water Moderated
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
ANNEALING
ASIA
CONTAINERS
COOPERATION
CRACK PROPAGATION
CRACKS
EASTERN EUROPE
EMBRITTLEMENT
EUROPE
HEAT TREATMENTS
INTERNATIONAL COOPERATION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MEETINGS
NORTH AMERICA
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
SAFETY
STEELS
THERMAL SHOCK
TRAVEL
USA
USSR
WATER COOLED REACTORS
WATER MODERATED REACTORS