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Synthesis of Molten Chloride Salt Fast Reactor Fuel Salt from Spent Nuclear Fuel

机译：废氯化盐快速反应器燃料燃料的合成从废核燃料中

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Mark A. Williamson; James Willit;
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年度 2019
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1. Treatment of molten salt wastes by phosphate precipitation: removal of fission product elements after pyrochemical reprocessing of spent nuclear fuels in chloride melts [J] . Volkovich VA., Griffiths TR., Thied RC. Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2003,第1期

机译：通过磷酸盐沉淀处理熔融盐废料：在氯化物熔体中对乏核燃料进行热化学处理后，除去裂变产物元素
2. Sensitivity/uncertainty analyses comparing LR-0 reactor experiments containing FLiBe salt with models for molten-salt-cooled and molten-salt-fueled reactors [J] . J.J. Powers, N.R. Brown, D.E. Mueller, Annals of nuclear energy . 2018,第octa期

机译：敏感性/不确定性分析，将含有FLiBe盐的LR-0反应堆实验与熔融盐冷却和熔融盐燃料反应堆的模型进行比较
3. DEVELOPMENT OF TREATMENT PROCESS FOR ANODE RESIDUE FROM MOLTEN SALT ELECTROREFINING OF SPENT METALLIC FAST REACTOR FUEL [J] . MASATOSHI IIZUKA, MASAAKIAKAGI, TAKASHI OMORI Nuclear Technology . 2013,第3期

机译：速成金属快速反应釜熔融盐电解精制阳极残渣的处理工艺开发
4. CEMSO (Catalyst Enhanced Molten Salt Oxidation) for Complete and Continuous Pyrochemical Reprocessing of Spent Nuclear Fuel: An Overview of a Viable New Technology for Next Generation Nuclear Reactors [C] . T. R. Griffiths, V. A. Volkovich, W. R. Carper International Symposium on Molten Salts . 2007

机译：CEMO（催化剂增强的熔盐氧化）用于花费核燃料的完全和连续的猪肉再加工：概述下一代核反应堆的可行新技术
5. Electrochemical Monitoring of Corrosion Processes in Molten Salts Used for Pyroprocessing Spent Nuclear Fuel [D] . Horvath, David Christopher. 2019

机译：用于溶解核燃料的熔盐腐蚀过程的电化学监测
6. On the Use of a Molten Salt Fast Reactor to Apply an Idealized Transmutation Scenario for the Nuclear Phase Out [O] . Bruno Merk, Ulrich Rohde, Varvara Glivici-Cotruţă, -1

机译：关于使用熔融盐快堆为核淘汰应用理想化的S变方案
7. Design of construction materials for fast neutron molten salt reactors with closed nuclear fuel cycle [O] . Абрамов, А. В., Abramov, A. V. 2013

机译：封闭核燃料循环的快速中子熔盐反应堆建筑材料设计
8. Fast Reactors Using Molten Chloride Salts as Fuel. [R] . Taube, M. 1978

机译：使用熔融氯盐作为燃料的快堆。

Synthesis of Molten Chloride Salt Fast Reactor Fuel Salt from Spent Nuclear Fuel

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