论文信息 - Fabrication of Uranium-Plutonium Mixed Nitride Fuel Pins for Irradiation Tests in JMTR

Fabrication of Uranium-Plutonium Mixed Nitride Fuel Pins for Irradiation Tests in JMTR

Abstract Pour He-bonded fuel pins containing uranium-plutonium mixed nitride pellets were fabricated for the irradiation tests in JMTR, aiming at understanding the irradiation behavior and demonstrating the feasibility of mixed nitride as an advanced fuel for FBRs. Mixed nitride pellets were prepared by carbothermic reduction of the oxides. One of the fuel pins was fitted with a set of W-Re thermocouples in order to trace the temperature change of pellet center during irradiation. Moreover, ferritic stainless steel was adopted as a cladding material in one fuel pin besides type 316 austenitic stainless steel. In this report, the design and characteristics of mixed nitride fuel pins are described.

[1] D. W. Stuteville,et al. Optimum Pin Diameter for LMFBR Carbide Fuels , 1975 .

[2] M. Nakazawa,et al. Fast Neutron Detector Using PIN-type Silicon Photodiode. , 1992 .

[3] Y. Arai,et al. Fabrication of (U, Pu)N fuel pellets , 1989 .

[4] Yasufumi Suzuki,et al. Vaporization behavior of uranium-plutonium mixed nitride , 1992 .

[5] T. Iwai,et al. Dependence of the thermal conductivity of (U, Pu) N on porosity and plutonium content , 1992 .

[6] H. Matzke,et al. Dense fuels in Europe , 1989 .

[7] T. Iwai,et al. Determination of nitrogen in UN, PuN and (U,Pu)N by oxidation in circulating oxygen and gas chromatographic measurement of the combustion gases , 1990 .

[8] Hj. Matzke,et al. Science of advanced LMFBR fuels , 1986 .

[9] E. S. Bomar,et al. Lattice Parameters of (U,Pu)N Solid Solutions , 1971 .

[10] G. Butterworth. Activation characteristics and waste management options for some candidate tritium breeders , 1991 .