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Journal Articles

Recent progress of JAEA-CRIEPI joint study for metal pyroreprocessing at CPF

Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo; Koizumi, Tsutomu; Kurata, Masaki*; Yahagi, Noboru*

Proceedings of International Conference on Advanced Nuclear Fuel Cycle; Sustainable Options & Industrial Perspectives (Global 2009) (CD-ROM), p.1269 - 1273, 2009/09

JAEA is developing the pyroreprocessing by collaboration with CRIEPI. The test using U began in 2002, and the test using PuO$$_{2}$$ and unirradiated MOX were ended in 2008. The reduction of UO$$_{2}$$ pellets by using Li-reduction method, the electrowinning using reduced pellets, the separation of adhered salt with deposit by distillation, and the ingot formation of deposit were performed. As a result, 99% of the loaded U is recovered as metal ingot. The tests similar to U tests were performed by using PuO$$_{2}$$. As a result, Pu was successfully recovered with U metal. In the MOX test, the mass balance of Pu was maintained at $$sim$$100% with respect to the initial amount. We try to form the U-Pu-Zr alloy by using reduced MOX. After 2009, the process development that uses the alloy will be continued.

Journal Articles

Recovery of U-Pu alloy from MOX using a pyroprocess series

Kitawaki, Shinichi; Shinozaki, Tadahiro; Fukushima, Mineo; Usami, Tsuyoshi*; Yahagi, Noboru*; Kurata, Masaki*

Nuclear Technology, 162(2), p.118 - 123, 2008/05

 Times Cited Count:17 Percentile:75.01(Nuclear Science & Technology)

A series test of pyro-process was carried out to recover U-Pu alloy from MONJU MOX pellets. In the Li-reduction step, the reduction behavior of MOX was similar to that of UO$$_{2}$$. In the electrorefining step, the separation factor between U and Pu was 5.7 for the combination of reduced MOX anode and liquid cadmium cathode, which is almost comparable to the value in the previous studies. For the material balance, approximately 98% of U and 103% of Pu were detected in the electrodes or molten salt after the electrolysis with respect to the initial amounts in the anode or molten salt. Considering the analytical error of ICP-AES, these values are reasonable. The remained amount of U in the anode was slightly larger than that of Pu due to the re-oxidation. The U-Pu alloy ingot was successfully formed by distillation of Cd.

Journal Articles

Ingot formation using uranium dendrites recovered by electrolysis in LiCl-KCl-PuCl$$_{3}$$-UCl$$_{3}$$ melt

Fukushima, Mineo; Nakayoshi, Akira; Kitawaki, Shinichi; Kurata, Masaki*; Yahagi, Noboru*

Proceedings of 3rd International ATALANTE Conference (ATALANTE 2008) (CD-ROM), 4 Pages, 2008/05

Products on solid cathodes recovered from metal pyrochemical processing were processed to obtain uranium ingot. Studies on process conditions for uranium forming, assay recovered uranium products and by-products and evaluation of mass balance were carried out. In this tests, it is confirmed that uranium ingots can be obtained with heating the products up to more than melting temperature of metal uranium under normal pressure because adhered salt cover the uranium not to oxidize it during uranium cohering. Volatilization of americium is very small under the condition of high temperature.

Journal Articles

Basic knowledge on treating various wastes generated from practical operation of metal pyro-reprocessing

Nakayoshi, Akira; Kitawaki, Shinichi; Fukushima, Mineo; Kurata, Masaki*; Yahagi, Noboru*

Proceedings of International Symposium on EcoTopia Science 2007 (ISETS '07) (CD-ROM), p.1062 - 1066, 2007/11

Pyro-reprocessing is one of the promising reprocessing methods for recycling spent nuclear fuels generated from fast reactors. Comparing to the conventional aqueous-processes, following benefits are expected when introducing the pyro-reprocessing, such as reduction of environmental burden, enhancement of proliferation-resistant, enhancement of economical potential, efficient utilization of nuclear resources. The pyro-reprocessing will therefore become more attractive not only in developed countries regarding nuclear energy, but also in developing countries. As for reducing environmental burden, the most important subject is establishment of the nuclear fuel cycle, in which actinide elements are closed. Various kinds of intermediate waste which contains actinide elements are formed in the practical operation not only from the main steps of the pyro-reprocessing but also from related sub-streams.

Oral presentation

Demonstration test with plutonium for electrometallurgical pyroprocess at CPF, 12; Electrorefining test with reduced MOX

Kitawaki, Shinichi; Shinozaki, Tadahiro; Fukushima, Mineo; Usami, Tsuyoshi*; Yahagi, Noboru*; Kurata, Masaki*

no journal, , 

no abstracts in English

Oral presentation

Demonstration test with plutonium for electrometallurgical pyroprocess at CPF, 11; Lithium reduction behavior of MOX pellet

Usami, Tsuyoshi*; Kurata, Masaki*; Yahagi, Noboru*; Kitawaki, Shinichi; Shinozaki, Tadahiro; Fukushima, Mineo

no journal, , 

no abstracts in English

Oral presentation

Demonstration test with plutonium for electrometallurgical pyroprocess at CPF, 13; Cd-distillation of cathode and formation of U-Pu alloy

Yahagi, Noboru*; Usami, Tsuyoshi*; Kurata, Masaki*; Kitawaki, Shinichi; Fukushima, Mineo; Shinozaki, Tadahiro

no journal, , 

no abstracts in English

Oral presentation

Demonstration test with plutonium for electrometallurgical pyroprocess at CPF, 14; Re-treatment of anode residue generated from electrorefining of reduced MOX

Kurata, Masaki*; Usami, Tsuyoshi*; Yahagi, Noboru*; Kitawaki, Shinichi; Fukushima, Mineo; Shinozaki, Tadahiro

no journal, , 

no abstracts in English

Oral presentation

Series process test including "re-work" of various residues generated from metal pyro-processing

Kurata, Masaki*; Yahagi, Noboru*; Kitawaki, Shinichi; Fukushima, Mineo

no journal, , 

no abstracts in English

Oral presentation

Development of pyrometallurgical reprocessing; Mass balance of electrorefining process

Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo; Yahagi, Noboru*; Kurata, Masaki*

no journal, , 

no abstracts in English

Oral presentation

Development of a fabrication technology of TRU alloy fuel and fuel design for TRU transmutation I, 2; Construction of thermodynamic database for actinide alloy

Kurata, Masaki*; Nakamura, Kinya*; Yahagi, Noboru*; Nakajima, Kunihisa; Arai, Yasuo; Arita, Yuji*

no journal, , 

no abstracts in English

Oral presentation

Development of metal pyro-processing, 2; Sequential process test for electro-chemical reduction of MOX pellet

Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo; Kurata, Masaki*; Yahagi, Noboru*

no journal, , 

no abstracts in English

Oral presentation

Sequential process tests for metal pyro-reprocessing

Kurata, Masaki*; Yahagi, Noboru*; Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo

no journal, , 

To demonstrate the real process of metal pyro-reprocessing of nuclear spent fuels, sequential tests of major step were performed, such as electro-chemical reduction of MOX pellets and electro-chemical recovery of U metal and U-Pu alloy, in 1/1000 scale w.r.t. the real process. Variation in various operation parameters, product composition, and actinide distribution were investigated in the sequential tests.

Oral presentation

Development of pyro-metallurgical reprocessing, 3; Sequential test for electro-refining using U-Pu alloy

Kurata, Masaki*; Yahagi, Noboru*; Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo

no journal, , 

Sequential test for electro-refining using U-Pu alloy that was obtained by reduction of MOX pellets was performed. The test was consisted of four electrolysis using three solid cathodes and a liquid cadmium cathode. Test results shows that (1) material balance of nuclear materials were satisfactorily closed in whole process, (2) concentration of Pu and Am in uranium products were less than 1 ppm respectively, (3) U metal reacted with oxygen impurities in media as an oxygen getter.

Oral presentation

Sequential process test for metal pyro-processing using U, Pu, and Am

Kurata, Masaki*; Yahagi, Noboru*; Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo

no journal, , 

CRIEPI and JAEA are continuing a collaboration study for metal pyro-processing, in which sequential process tests have been performed under practical conditions using 1kg of molten salt baths. Recent results on two kinds of sequential process test are reported. The former is the electro-chemical reduction test of MOX pellet in order to form U-Pu alloy ingots. The latter is the electrolysis test using a combination of U-Pu alloy anode and solid or liquid cadmium cathode to recover U-product or U-Pu-Am alloy product, respectively. Variation in electrode potentials, current efficiency, molten salt composition, Pu- or Am-impurity in the U-product, U/Pu or Am/Pu separation factor in the U-Pu alloy product, and etc. were measured. These tests reproduced practical operating conditions at a scale of 1/1000 that of the actual process.

Oral presentation

The Research of practical operation for metal pyro-reprocessing using MOX pellets

Nakayoshi, Akira; Kitawaki, Shinichi; Fukushima, Mineo; Kurata, Masaki*; Yahagi, Noboru*

no journal, , 

no abstracts in English

Oral presentation

Development of metal pyro-processing, 4; Reaction between molten salt of electrorefiner and Li$$_{2}$$O or LiOH

Kitawaki, Shinichi; Tanaka, Hitoshi*; Kurata, Masaki*; Yahagi, Noboru*

no journal, , 

no abstracts in English

Oral presentation

Development of pyrometallurgical reprocessing, 5; Study on ICP-AES analysis for U/Pu/Am co-existence system in metal pyro-processing

Kitawaki, Shinichi; Nakayoshi, Akira; Tanaka, Hitoshi*; Yahagi, Noboru*; Kurata, Masaki*

no journal, , 

no abstracts in English

Oral presentation

Development of a fabrication technology of TRU alloy fuel and fuel design for TRU transmutation I, 7; Analysis for miscibility of Np and Am in TRU alloy fuel

Kurata, Masaki*; Nakamura, Kinya*; Yahagi, Noboru*; Nakajima, Kunihisa; Arita, Yuji*

no journal, , 

no abstracts in English

Oral presentation

Development of pyro-metallurgical reprocessing; Electrochmical reduction of MOX pellets & Sequential test for electro-refining using reduced MOX pellets

Kurata, Masaki*; Yahagi, Noboru*; Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo

no journal, , 

CRIEPI and JAEA are continuing a collaboration study for metal pyro-processing, in which sequential process tests have been performed under practical conditions. Recent results on two kinds of sequential process test are reported. The former is the electro-chemical reduction test of MOX pellet. The latter is the electrolysis test using a combination of U-Pu alloy anode and solid or liquid cadmium cathode. Variation in electrode potentials, current efficiency, molten salt composition, Pu- or Am-impurity in the U-product, and etc. were measured.

Oral presentation

Development of metal pyro-processing. 6; Back-extraction of U, Pu, Am from liquid cadmium into LiCl-KCl molten salt

Kurata, Masaki*; Murakami, Tsuyoshi*; Yahagi, Noboru*; Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo

no journal, , 

Back-extraction of U, Pu, Am from liquid cadmium into LiCl-KCl molten salt. Liquid cadomium that was processed in the past electro-refining test was soaked into LiCl-KCl eutectic and CdCl$$_{2}$$ was used as a oxidizing agent. Reaction rate and mass balance were measured.

21 (Records 1-20 displayed on this page)