Published 1977 | Version v1
Miscellaneous Metadata-only

Nuclear pressure boundary materials research, problems and proposed solutions

Creators

  • 1. Electric Power Research Inst., Palo Alto, Calif. (USA)

Description

The complete test discusses several important materials problems facing LWR operation and some of the research programs that have been formulated at EPRI to address these problems. The problems include steam generator corrosion damage, BWR pipe cracking, BWR nozzle corner cracking, and radiation induced embrittlement. LWR materials problems are complex and will not easily yield to solution. However, the economic rewards for the solutions are great

Availability note (English)

MF available from INIS under the Report Number.

Additional details

Publishing Information

Imprint Pagination
G 1/9, 6 p.
Report number
INIS-mf--4506

Conference

Title
4. International conference on structural mechanics in reactor technology.
Dates
15 - 19 Aug 1977.
Place
San Francisco, Calif., USA.

INIS

Country of Publication
European Commission (EC), Brussels (Belgium)
Country of Input or Organization
European Commission (EC), Brussels (Belgium)
INIS RN
9414934
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CORROSION; CRACKS; EMBRITTLEMENT; FRACTURE PROPERTIES; NOZZLES; PHYSICAL RADIATION EFFECTS; PIPE FITTINGS; REACTOR COMPONENTS; STEAM GENERATORS; STEELS
Descriptors DEC
ALLOYS; BOILERS; CARBON ADDITIONS; CHEMICAL REACTIONS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; RADIATION EFFECTS; REACTORS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS