EVALUATION OF REACTOR CORE MATERIALS FOR A GAS-COOLED REACTOR EXPERIMENT | Zendy

D.L. Keller | Zendy

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EVALUATION OF REACTOR CORE MATERIALS FOR A GAS-COOLED REACTOR EXPERIMENT

Author(s) -

D.L. Keller

Publication year - 1957

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/4174375

Subject(s) - materials science , metallurgy , thermal expansion , hydride , hydrogen , ultimate tensile strength , composite material , nuclear engineering , metal , chemistry , organic chemistry , engineering

An evaluation of core materials for a gas-cooled reactor is being made. Work on the ZrH/sub n/ moderator has been confined to the high-hydrogen or delta- phase material. Methods for preparing sound hydride bodies of the highhydrogen composition have been developed. Both solid hydride and hydride powder compacts are being clad by a pressure-bonding technique. The hot hardness, tensile strength, thermal conductivity, thermal-expansion coefficient, and dissociation pressure of the delta-phase material are being determined. Control-material development was directed at rare-earth-oxide dispersions in Ni-chrome V or Co alloys. The reference fuel element is dispersedUO/sub 2/ in stainless steel. Studies include work on fabrication techniques and irradiation damage, and physical- and mechanical-property determinations. Several alternate fuels are being investigated. Gas-coolant studies involve N-metal and NH/sub 4/-metal reactions. Several additives to retard nitriding are being investigated. An in- pile-loop facility for testing reference materials is being constructed for operation in the Battelle Research Reactor. (auth

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