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Title: Thermal properties of cesium molybdate

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:436843
;  [1]; ; ;  [2]
  1. Japan Atomic Energy Research Inst., Nakagun, Ibaraki-ken (Japan)
  2. Hokkaido Univ. (Japan)

Cesium is one of the most important fission products to aid in the understanding and prediction of the behavior of oxide nuclear fuels because of its high mobility, chemical reactivity, and large yield. In postirradiation examinations of the Phoenix reactor fuel pins, the accumulation of cesium and molybdenum between the fuel pellet and cladding was observed, though the chemical form was not determined. In the thermodynamic analyses of chemical states of fission products, Cs{sub 2}MoO{sub 4} was often predicted to exist as a stable compound in oxide fuels. The Cs{sub 2}MoO{sub 4} compound is thermodynamically stable under the conditions of light water reactors, fast breeder reactors, and high-temperature gas-cooled reactors. In the Cs-Mo-O system several phases have been found, and the structural and thermodynamic properties were studied. At room temperature, Cs{sub 2}MoO{sub 4} has an orthorhombic structure and a phase transition occurs at 841 K to a hexagonal structure. Both structures are expected to exist in the fuel, depending on the fuel temperature. However, no data has been available on the thermal properties of CS{sub 2}MoO{sub 4}. In the current work, the thermal expansion and thermal conductivity of Cs{sub 2}MoO{sub 4} were determined, which are the basic data needed to understand and predict the fuel/clad mechanical interaction and fuel temperature.

OSTI ID:
436843
Report Number(s):
CONF-9606116-; ISSN 0003-018X; TRN: 96:005275-0074
Journal Information:
Transactions of the American Nuclear Society, Vol. 74; Conference: Annual meeting of the American Nuclear Society (ANS), Reno, NV (United States), 16-20 Jun 1996; Other Information: PBD: 1996
Country of Publication:
United States
Language:
English