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ON THE IMPROVEMENT OF METALLIC URANIUM FUEL. II. THERMAL CYCLING AND CORROSION TESTS OF EXTRUDED URANIUM RODS AND SOME URANIUM ALLOYS (in Japanese)

Journal Article · · Nippon Genshiryoku Gakkaishi (Japan)
OSTI ID:4647102

Uranium alloys were fabricated by a co-reduction process, and thermal cycling tests were carried out. Properties of gamma -extruded uranium rods were tested, and their merits were compared with those of alloying specimens. Corrosion tests of uranium and uranium alloys were undertaken in a temperature range of 300 to 800 deg C. Limitation of corrosion resistivity of uranium alloys is discussed. On gamma -extruded uranium rods, BETA -oil-quenched specimen showed the smallest growth, warp, and wrinkle after the thermal-cycling tests. After oil-quenching treatment, it was not necessary to follow with an alpha - annealing procedure. Requirements to reduce thermal-cycling growth by heat treatments were different in each specimen, so the appropriate heat treatments should be considered. Thermal-cycling growth was also large in extremely grain- refined specimens. Weight gain of uranium alloys in oxidation by CO/sub 2/ was larger than that of metallic uranium in the temperature range above 550 deg C. From the standpoints of grain refinement, workability, thermal cycling growth, corrosion resistivity, and neutron economics, U--Nb--Mo, U--Cr--Mo, and U-- Zr-- Mo ternary alloys are recommended as the uranium fuels. (auth)

Research Organization:
Mitsubishi Atomic Power Industries, Inc., Japan
NSA Number:
NSA-17-037471
OSTI ID:
4647102
Journal Information:
Nippon Genshiryoku Gakkaishi (Japan), Journal Name: Nippon Genshiryoku Gakkaishi (Japan) Vol. Vol: 5; ISSN NGEGA
Country of Publication:
Country unknown/Code not available
Language:
Japanese