Radiochemical and chemical characterization of fuel, salt, and deposit from the electrorefining of irradiated U-6 wt% Zr in hot cells

被引:3
作者
Sankar, Dwarapudi Bola [1 ,2 ]
Seshadri, Rajeswari [2 ]
Thirunavukkarasu, Kalaiyarasu [2 ]
Pakhui, Gurudas [1 ,2 ]
Rao, Jakkula Siva Brahmaji [2 ]
Bera, Suranjan [1 ,2 ]
Sreenivasulu, Balija [1 ,2 ]
Radhakrishnan, Kumaresan [1 ,2 ]
Manoravi, Periasamy [1 ,2 ]
Jayaraman, Venkataraman [1 ,2 ]
机构
[1] Homi BhabhaNat Inst, Indira Gandhi Ctr Atom Res, Kalpakkam 603102, India
[2] Indira Gandhi Ctr Atom Res, Mat Chem & Met Fuel Cycle Grp, Kalpakkam 603102, India
关键词
uranium; plutonium; electrorefining; cathode deposit; eutectic melt; fission products;
D O I
10.1515/ract-2023-0203
中图分类号
O61 [无机化学];
学科分类号
070301 ; 081704 ;
摘要
Metal fuels are considered as the promising candidates for future fast breeder reactors. Pyro-chemical reprocessing is the ideal method for reprocessing spent metallic fuels due to the inherent process advantages. Electrorefining run was demonstrated in a hot cell facility with irradiated U-6 wt% Zr alloy at 500 degrees C using LiCl-KCl eutectic melt. In order to understand the behavior of the actinides and various fission products during high-temperature electrolysis, various process streams, viz., irradiated metal alloy fuel, the eutectic salt, and the cathode deposit were analyzed for the uranium, plutonium, and other fission product contents. Various methods employed for characterizing the process streams and the behaviors of some of the fission products during the electrolysis process are highlighted. The major gamma emitting radionuclides present in the irradiated fuel were Ru-106, Sb-125, Cs-134, Cs-137, Ce-144, and Eu-154. During electrorefining, cesium, cerium and europium were oxidized and dissolved in the molten media, whereas ruthenium and antimony remained in the anode basket. A minor contamination of zirconium was found in the cathode deposit.
引用
收藏
页码:487 / 494
页数:8
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