Evaluation and prediction of neutron embrittlement in reactor pressure vessel materials. Final report. [PWR; BWR]

Technical Report · Wed Dec 01 00:00:00 EST 1982

OSTI ID:6636157

Hawthorne, J R; Menke, B H; Loss, F J; Watson, H E; Hiser, A L; Gray, R A

This study evaluates the effects of fast neutron irradiation on the mechanical properties of eight nuclear reactor vessel materials. The materials include submerged arc weldments, three plates, and one forging. The materials are in the unirradiated and irradiated conditions with regard to tensile, Charpy impact, and static and dynamic fracture toughness properties. Correlations between impact and fracture toughness parameters are developed from the experimental results. The observed shifts in transition temperature and the drop in upper-shelf energy are compared with predictions developed from the Regulatory Guide 1.99.1 trend curves.

• Research Organization: Naval Research Lab., Washington, DC (USA)
• OSTI ID: 6636157
• Report Number(s): EPRI-NP-2782; ON: DE83901107
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
BWR TYPE REACTORS
REACTOR MATERIALS
PWR TYPE REACTORS
FRACTURE PROPERTIES
PHYSICAL RADIATION EFFECTS
TENSILE PROPERTIES
STEEL-ASTM-A302
STEEL-ASTM-A508
STEEL-ASTM-A533
STEEL-ASTM-A533-B
CHARPY TEST
FAST NEUTRONS
PRESSURE VESSELS
ALLOYS
BARYONS
CARBON STEELS
CONTAINERS
DESTRUCTIVE TESTING
ELEMENTARY PARTICLES
FERMIONS
HADRONS
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
NEUTRONS
NUCLEONS
RADIATION EFFECTS
REACTORS
STEELS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
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Light-Water Moderated
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360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties