Proceedings: second seminar on countermeasures for pipe cracking in BWRs. Volume 2. Remedy development
Conference
·
OSTI ID:6258379
The second seminar on countermeasures for BWR pipe cracking was held late in 1983 in Palo Alto, California. The results of nearly four years of R and D on pipe cracking, jointly sponsored by the BWR Owners Group and EPRI, were presented. Some 60 papers were delivered by organizations within the United States and overseas. The significance of this program to the utility is the development, qualification, and implementation of a large of a large number of countermeasures for the problems of pipe cracking in BWRs. Countermeasures are available for both operating plants and plants under construction. In particular, the Japanese papers demonstrated the success of the countermeasures with several years of crack-free operation in a number of BWRs. The report is published in three volumes corresponding to the three divisions of the seminar: Volume 1: Problem Resolution; Volume 2: Remedy Development; and Volume 3: Remedy Application. Volume 1 includes a list of authors of the written reports submitted and the agenda of the four-day meeting. The first seminar was held early in 1980. It was devoted to earlier work and the delineation of the program for the succeeding work, which is now reported. That seminar was reported in EPRI WS-79-174-LD, May 1980.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (USA)
- OSTI ID:
- 6258379
- Report Number(s):
- EPRI-NP-3684-SR-Vol.2; CONF-8311208-Vol.2; ON: TI85920099
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
COOLING SYSTEMS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
DOCUMENT TYPES
ENERGY SYSTEMS
INSPECTION
IRON ALLOYS
IRON BASE ALLOYS
LEADING ABSTRACT
MEASURING METHODS
MEETINGS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
STAINLESS STEELS
STEELS
STRESS CORROSION
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
COOLING SYSTEMS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
DOCUMENT TYPES
ENERGY SYSTEMS
INSPECTION
IRON ALLOYS
IRON BASE ALLOYS
LEADING ABSTRACT
MEASURING METHODS
MEETINGS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
STAINLESS STEELS
STEELS
STRESS CORROSION
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS