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Journal Articles

Phase analysis of simulated nuclear fuel debris synthesized using UO$$_{2}$$, Zr, and stainless steel and leaching behavior of the fission products and matrix elements

Tonna, Ryutaro*; Sasaki, Takayuki*; Kodama, Yuji*; Kobayashi, Taishi*; Akiyama, Daisuke*; Kirishima, Akira*; Sato, Nobuaki*; Kumagai, Yuta; Kusaka, Ryoji; Watanabe, Masayuki

Nuclear Engineering and Technology, 55(4), p.1300 - 1309, 2023/04

 Times Cited Count:0 Percentile:75.85(Nuclear Science & Technology)

Simulated debris was synthesized using UO$$_{2}$$, Zr, and stainless steel and a heat treatment method under inert or oxidizing conditions. The primary U solid phase of the debris synthesized at 1473 K under inert conditions was UO$$_{2}$$, whereas a (U,Zr)O$$_{2}$$ solid solution formed at 1873 K. Under oxidizing conditions, a mixture of U$$_{3}$$O$$_{8}$$ and (Fe,Cr)UO$$_{4}$$ phases formed at 1473 K whereas a (U,Zr)O$$_{2+x}$$ solid solution formed at 1873 K. The leaching behavior of the fission products from the simulated debris was evaluated using two methods: the irradiation method, for which fission products were produced via neutron irradiation, and the doping method, for which trace amounts of non-radioactive elements were doped into the debris. The dissolution behavior of U depended on the properties of the debris and aqueous medium the debris was immersed in. Cs, Sr, and Ba leached out regardless of the primary solid phases. The leaching of high-valence Eu and Ru ions was suppressed, possibly owing to their solid-solution reaction with or incorporation into the uranium compounds of the simulated debris.

Journal Articles

Progress report of Japanese simulation research projects using the high-performance computer system Helios in the International Fusion Energy Research Centre

Ishizawa, Akihiro*; Idomura, Yasuhiro; Imadera, Kenji*; Kasuya, Naohiro*; Kanno, Ryutaro*; Satake, Shinsuke*; Tatsuno, Tomoya*; Nakata, Motoki*; Nunami, Masanori*; Maeyama, Shinya*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 92(3), p.157 - 210, 2016/03

The high-performance computer system Helios which is located at The Computational Simulation Centre (CSC) in The International Fusion Energy Research Centre (IFERC) started its operation in January 2012 under the Broader Approach (BA) agreement between Japan and the EU. The Helios system has been used for magnetised fusion related simulation studies in the EU and Japan and has kept high average usage rate. As a result, the Helios system has contributed to many research products in a wide range of research areas from core plasma physics to reactor material and reactor engineering. This project review gives a short catalogue of domestic simulation research projects. First, we outline the IFERC-CSC project. After that, shown are objectives of the research projects, numerical schemes used in simulation codes, obtained results and necessary computations in future.

Journal Articles

Parallel computing with Particle and Heavy Ion Transport code System (PHITS)

Furuta, Takuya; Sato, Tatsuhiko; Ogawa, Tatsuhiko; Niita, Koji*; Ishikawa, Kenichi*; Noda, Shigeho*; Takagi, Shu*; Maeyama, Takuya*; Fukunishi, Nobuhisa*; Fukasaku, Kazuaki*; et al.

Proceedings of Joint International Conference on Mathematics and Computation, Supercomputing in Nuclear Applications and the Monte Carlo Method (M&C + SNA + MC 2015) (CD-ROM), 9 Pages, 2015/04

In Particle and Heavy Ion Transport code System PHITS, two parallel computing functions are prepared to reduce the computational time. One is the distributed-memory parallelization using message passing interface (MPI) and the other is the shared-memory parallelization using OpenMP directives. Each function has advantages and disadvantages, and thus, by adopting both functions in PHITS, it is possible to conduct parallel computing suited for needs of users. It is also possible to conduct the hybrid parallelization by the intra-node OpenMP parallelization and the inter-node MPI parallelization in supercomputer systems. Each parallelization functions were explained together with some application results obtained using a workstation and a supercomputer system, K computer at RIKEN.

Journal Articles

Formation process of perovskite-type hydride LiNiH$$_{3}$$; ${it In situ}$ synchrotron radiation X-ray diffraction study

Sato, Ryutaro*; Saito, Hiroyuki; Endo, Naruki; Takagi, Shigeyuki*; Matsuo, Motoaki*; Aoki, Katsutoshi; Orimo, Shinichi*

Applied Physics Letters, 102(9), p.091901_1 - 091901_4, 2013/03

 Times Cited Count:23 Percentile:73.58(Physics, Applied)

Journal Articles

Density-functional study of perovskite-type hydride LiNiH$$_{3}$$ and its synthesis; Mechanism for formation of metallic perovskite

Takagi, Shigeyuki*; Saito, Hiroyuki; Endo, Naruki; Sato, Ryutaro*; Ikeshoji, Tamio*; Matsuo, Motoaki*; Miwa, Kazutoshi*; Aoki, Katsutoshi; Orimo, Shinichi*

Physical Review B, 87(12), p.125134_1 - 125134_6, 2013/03

 Times Cited Count:12 Percentile:53.67(Materials Science, Multidisciplinary)

Journal Articles

Formation of an Fe-H complex anion in YFe$$_{2}$$; Adjustment of imbalanced charge by additional Li as an electron donor

Matsuo, Motoaki*; Saito, Hiroyuki; Machida, Akihiko; Sato, Ryutaro*; Takagi, Shigeyuki*; Miwa, Kazutoshi*; Watanuki, Tetsu; Katayama, Yoshinori; Aoki, Katsutoshi; Orimo, Shinichi*

RSC Advances (Internet), 3(4), p.1013 - 1016, 2013/01

 Times Cited Count:16 Percentile:52.39(Chemistry, Multidisciplinary)

Journal Articles

Conceptual study of ECH/ECCD system for fusion DEMO plant

Sakamoto, Keishi; Takahashi, Koji; Kasugai, Atsushi; Minami, Ryutaro; Kobayashi, Noriyuki*; Nishio, Satoshi; Sato, Masayasu; Tobita, Kenji

Fusion Engineering and Design, 81(8-14), p.1263 - 1270, 2006/02

 Times Cited Count:5 Percentile:36.44(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal tests on B$$_{4}$$C-overlaid carbon fibre reinforced composites under disruption heat load conditioned

Nakamura, Kazuyuki; Akiba, Masato; Araki, Masanori; Dairaku, Masayuki; Sato, Kazuyoshi; ; ; Ando, Toshiro; *; Saido, Masahiro; et al.

Fusion Engineering and Design, 30, p.291 - 298, 1995/00

 Times Cited Count:2 Percentile:28.65(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Feasibility tests on B$$_{4}$$C-converted carbon with various film thicknesses for JT-60U application

Nakamura, Kazuyuki; Ando, Toshiro; Akiba, Masato; Araki, Masanori; ; Sato, Kazuyoshi; ; Dairaku, Masayuki; Saido, Masahiro; *

Fusion Engineering and Design, 24, p.431 - 435, 1994/00

 Times Cited Count:0 Percentile:0.49(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

*; *

PNC TJ2222 93-001, 88 Pages, 1993/03

PNC-TJ2222-93-001.pdf:3.54MB

None

JAEA Reports

None

*; *; *

PNC TJ2222 92-002, 131 Pages, 1992/03

PNC-TJ2222-92-002.pdf:4.91MB

None

JAEA Reports

None

*; *; *

PNC TJ2222 92-001, 145 Pages, 1992/03

PNC-TJ2222-92-001.pdf:4.74MB

None

Oral presentation

Leaching behavior of simulated fuel debris in the UO$$_{2}$$-SUS system prepared by irradiation or tracer doping method

Sasaki, Takayuki*; Tonna, Ryutaro*; Kobayashi, Taishi*; Akiyama, Daisuke*; Kirishima, Akira*; Sato, Nobuaki*; Kumagai, Yuta; Kusaka, Ryoji; Watanabe, Masayuki

no journal, , 

Oral presentation

Leaching behavior of fission products from simulated fuel debris in the UO$$_{2}$$-SS system

Sasaki, Takayuki*; Kodama, Yuji*; Tonna, Ryutaro*; Kobayashi, Taishi*; Kumagai, Yuta; Kusaka, Ryoji; Watanabe, Masayuki; Akiyama, Daisuke*; Kirishima, Akira*; Sato, Nobuaki*; et al.

no journal, , 

no abstracts in English

Oral presentation

Research on the stability of fuel debris consisting of oxides and alloys, 10; Leaching behavior of nuclides from simulated fuel debris in the UO$$_{2}$$-Zr-SS system; Irradiation or addition method

Sasaki, Takayuki*; Tonna, Ryutaro*; Kobayashi, Taishi*; Akiyama, Daisuke*; Kirishima, Akira*; Sato, Nobuaki*; Watanabe, Masayuki; Kumagai, Yuta; Kusaka, Ryoji

no journal, , 

We synthesized simulated fuel debris which containing stainless steel and zirconium. The fission of Uranium by the irradiation of thermal neutron or non-radioactive elements was fed in the simulated fuel debris as fission products (FP), and the sample was immersed in pure water or artificial sea water. In this presentation, we would report the behavior of the solubility of the FP and the interpretation of its results.

Oral presentation

Research on the stability of fuel debris consisting of oxides and alloys, 13; Leaching behavior of FPs from the simulated debris

Sasaki, Takayuki*; Tonna, Ryutaro*; Kobayashi, Taishi*; Akiyama, Daisuke*; Kirishima, Akira*; Sato, Nobuaki*; Watanabe, Masayuki; Kumagai, Yuta; Kusaka, Ryoji

no journal, , 

Fuel debris containing alloy phases is expected to be formed in the Fukushima Daiichi Nuclear Power Plant. In this study, two series of simulated debris samples comprising uranium-zirconium-stainless steel were synthesized. One series of the samples was prepared by the irradiation method, where the samples were irradiated by thermal neutron for fission generation. The other was prepared by the doping method, where stable isotopes of FPs were added during the synthesis. We performed leaching tests as an aging treatment, and then measured structural changes in the samples and the elution rates of U and FPs contained in the samples. Moreover, in order to evaluate the colloid formation of these elements, particle size distribution was analyzed by an ICP-MS method combined with filtration using different pore-size filters or size exclusion chromatography. Based on the results, the chemical stability of the simulated debris and the speciation of the eluted nuclides were discussed.

Oral presentation

Dissolution behavior of iron-uranium oxide

Tonna, Ryutaro*; Sasaki, Takayuki*; Okamoto, Yoshihiro; Kobayashi, Taishi*; Akiyama, Daisuke*; Kirishima, Akira*; Sato, Nobuaki*

no journal, , 

Since fuel debris recovered from the Fukushima Daiichi Nuclear Power Plant may be directly disposed of in deep geological strata, knowledge of dissolution reactions of fuel debris in water and chemical states of dissolved nuclides is essential for safety assessment of disposals. The chemical composition and physical properties of fuel debris depend on the atmosphere and temperature, but the formation of FeUO$$_4$$ has been suggested at conditions under which air enters the reactor from outside. Uranium in FeUO$$_4$$ is reported to be pentavalent, but no dissolution reaction in water has been investigated. In this study, FeUO$$_4$$ was synthesized by heating at a predetermined temperature and oxygen pressure, immersed in nitric acid to remove unreacted uranium oxides, and then immersed in a solution of pH2-8. After the prescribed period, pH and Eh values were measured, and dissolved iron and uranium concentrations were measured by ICP-MS. X-ray absorption fine structure (XAFS) and powder X-ray diffraction (XRD) were used to evaluate the solid state before and after immersion. From these results, it was interpreted that the dissolution of FeUO$$_4$$ was accompanied by a redox reaction between Fe(III)/Fe(II) and U(V)/U(VI) during dissolution.

17 (Records 1-17 displayed on this page)
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