Published February 1987
| Version v1
Report
Radiation embrittlement correlation between power and test reactor data
Description
A large data base has been examined for evidence of a bias between test reactor and PWR pressure vessel Charpy embrittlement data, where the embrittlement is irradiation induced. The statistical evidence indicates that power reactor embrittlement predictions based on test reactor data will be non-conservative. The existence of the bias is more apparent for weld materials than for plate materials
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fourteenth water reactor safety information meeting. Volume 2. Research in nondestructive evaluation, environmental effects in primary system components, pressure vessel research, irradiation effects on RPV steels, degraded piping research
- Journal Page Range
- p. 349-355.
- Report number
- NUREG/CP--0082-Vol.2
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19002191
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHARPY TEST; COMPARATIVE EVALUATIONS; EMBRITTLEMENT; FRACTURE MECHANICS; IRRADIATION; MATHEMATICAL MODELS; NEUTRON FLUENCE; NICKEL; PHYSICAL RADIATION EFFECTS; PLATES; PRESSURE VESSELS; PWR TYPE REACTORS; QUANTITY RATIO; REACTOR SAFETY; RESEARCH AND TEST REACTORS; WELDED JOINTS
- Descriptors DEC
- CONTAINERS; DESTRUCTIVE TESTING; ELEMENTS; ENRICHED URANIUM REACTORS; EVALUATION; IMPACT TESTS; JOINTS; MATERIALS TESTING; MECHANICAL TESTS; MECHANICS; METALS; POWER REACTORS; RADIATION EFFECTS; REACTORS; SAFETY; TESTING; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS