BEHAVIOR OF STRUCTURAL MATERIALS EXPOSED TO AN ORGANIC-MODERATED REACTOR ENVIRONMENT

Journal Article · Mon Jun 01 04:00:00 EDT 1959 · Nuclear Sci. and Eng.

OSTI ID:4237000

Gioseffi, N J; Kline, H E

The behavior of various structural materials in an organic-moderated and -cooled reactor was determined under realistic operating conditions. Tests were run in the OMRE operating at 6-Mwh. Two in-pile dummy fuel elements and an out- of-pile section of a bypass line were loaded with mechanical and corrosion test specimens. Tensile strength, yield strengths reduction in areas elongation, and impact were measured after exposure for specimens of 1020 carbon steels 4130 alloy steels 304 stainless steel, 304 stainless steel sensitized 2 hr at 1200 deg F, 410 stainless steel, aluminum, and magnesium. (W.D.M.)

• Research Organization: Atomics International Div., North American Aviation, Inc., Canoga Park, Calif.
• NSA Number: NSA-13-017334
• OSTI ID: 4237000
• Journal Information: Nuclear Sci. and Eng., Journal Name: Nuclear Sci. and Eng. Vol. Vol: 2, No. 1, Suppl.
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ALUMINUM
ANALOG SYSTEMS
BYPASS
CARBON STEELS
DEFORMATION
EXPANSION
FUEL ELEMENTS
HEAT TREATMENTS
MAGNESIUM
MATERIALS TESTING
MECHANICAL PROPERTIES
OMRE
OPERATION
ORGANIC COOLANT
ORGANIC MODERATOR
PERFORMANCE
QUANTITATIVE ANALYSIS
REACTORS
STAINLESS STEELS
TENSILE PROPERTIES
VOLUME s...................