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Journal Articles

A Review of separation processes proposed for advanced fuel cycles based on technology readiness level assessments

Baron, P.*; Cornet, S. M.*; Collins, E. D.*; DeAngelis, G.*; Del Cul, G.*; Fedorov, Y.*; Glatz, J. P.*; Ignatiev, V.*; Inoue, Tadashi*; Khaperskaya, A.*; et al.

Progress in Nuclear Energy, 117, p.103091_1 - 103091_24, 2019/11

 Times Cited Count:17 Percentile:88.22(Nuclear Science & Technology)

The results of an international review of separation processes for spent nuclear fuel (SNF) recycling in future closed fuel cycles with the evaluation of Technology Readiness Level are reported. This study was made by the Expert Group on Fuel Recycling Chemistry (EGFRC) organised by the Nuclear Energy Agency (NEA) of the Organisation for Economic Co-operation and Development (OECD). A unique feature of this study was that processes were classified according to a hierarchy of separations aimed at different elements within spent fuel (uranium; uranium-plutonium co-recovery; minor actinides; high heat generating radionuclides) and also the Head-end processes, used to prepare the SNF for chemical separation, were included. Separation processes covered both wet (hydrometallurgical) and dry (pyro-chemical) processes.

Journal Articles

Summary of OECD/NEA/NSC expert group on integral experiments for minor actinide management

Okajima, Shigeaki; Fougeras, P.*; Gil, C.-S.*; Glinatsis, G.*; Gulliford, J.*; Iwamoto, Osamu; Jacqmin, R.*; Khomyakov, Y.*; Kochetkov, A.*; Kormilitsyn, M. V.*; et al.

NEA/NSC/DOC(2013)3, p.265 - 278, 2013/04

The Expert Group on Integral Experiments for Minor Actinide Management (EG on IEMAM) was established under OECD/NEA/NSC. The objectives are to review integral experiments for validating MA nuclear data, to recommend additional integral experiments and to propose an international framework to facilitate them from view points of the MA management. The paper summarized the discussion results in the EG on IEMAM as follows: (1) Requirement of nuclear data for MA management, (2) Reviewing existing integral data and identifying specification of missing experimental work to be required, (3) Identifying the bottlenecks and considering possible solutions to them and (4) Proposal of action program for international cooperation.

Journal Articles

Electro-deposition behavior of minor actinides with liquid cadmium cathodes

Kofuji, Hirohide; Fukushima, Mineo; Kitawaki, Shinichi; Myochin, Munetaka; Kormilitsyn, M. V.*; Terai, Takayuki*

IOP Conference Series; Materials Science and Engineering, 9, p.012010_1 - 012010_8, 2010/05

 Times Cited Count:0 Percentile:1.02

Journal Articles

MOX Co-deposition tests at RIAR for SF reprocessing optimization

Kofuji, Hirohide; Sato, Fuminori; Myochin, Munetaka; Nakanishi, Shigeyuki*; Kormilitsyn, M. V.*; Ishunin, V.*; Bychkov, A. V.*

Journal of Nuclear Science and Technology, 44(3), p.349 - 353, 2007/03

 Times Cited Count:5 Percentile:39.35(Nuclear Science & Technology)

The Oxide Electrowinning method has being studied as one of the candidate dry reprocessing concepts of future fuel cycle system. On the MOX co-deposition process, main process of that method, some fundamental experiments have been performed to confirm its feasibility. In the experiments, several parameters were set to study the suitable electrolysis condition to obtain desired granule of MOX. The concentrations of uranium, plutonium, FP simulators, and CP simulators were adopted as the parameters. The blowing gas composition during the electrolysis was also set as the variable condition. Through these experiments, it was clarified that the partial pressure of chlorine gas during electrolysis was important to obtain MOX granule with high Pu concentration without generating bottom precipitation in melt. Finally, adequacy of process control method for MOX co-electrolysis was confirmed through the test using spent FR fuel.

Journal Articles

Study of minor actinide recovery prosece for the oxide pyro-process

Myochin, Munetaka; Mizuguchi, Koji; Kormilitsyn, M. V.*; Ossipenko, A.*

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 4 Pages, 2005/10

In the Oxide Pyro-process, oxides of U, Np and Pu can be co-deposited as MOX from their oxide ions in the melt. Due to the difference of their deposition potential, neither Am nor Cm will co-deposit in the MOX. An additional process must be developed to recover them without FP especially the lanthanides. Various processes were reviewed based on existing experimental data and thermodynamic considerations. As the result, the liquid metal extraction seems to be most promising. Based on the measured separation factor of Am against Nd in the LiCl-KCl/Bi system, MA recovery rate can be higher than 95% with DF equals 10. The number of steps can be reduced if there is any other liquid metal such as Al and Ga with higher separation factor. As for the carbonate precipitation, some subsequent separation process will be needed. A new process named MAPLE is proposed for it; where Li is applied to reduce only MA oxide into metal in LiCl melt while keeping lanthanides as their oxide. If it works as expected, it will have high recovery rate such as 99% without lowering the DF.

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