Research Group for High Temperature Science on Fuel Materials
Location : JAEA > Nucl. Sci. and Eng. > Fuels and Mater. Eng. > High Temperature Sci. on Fuel Materials

Profile

[Research Activities]

High-level radioactive liquid waste (HLLW) produced in a reprocessing plant contains minor actinides (MA; Np, Am, Cm) besides numerous fission products. It is well known that most of MA nuclides are alpha-emitters with the long half-lives and/or large decay heat. From the viewpoint of mitigating the long-term toxicity of radioactive waste and the burden of final disposal of radioactive waste, an advanced fuel cycle with partitioning and transmutation (PT), in which MA are partitioned from HLLW and burnt in a transmutation system such as a fast reactor (FR) or accelerator driven system (ADS), has been investigated.

Our group has been carrying out the R&D on the preparation of transuranium (TRU) compounds such as the oxide, nitride, chloride and alloy, the measurement of thermal properties, the fuel fabrication technology, the evaluation of irradiation behavior, and the pyrochemical process for spent fuel treatment in order to support the development of an advanced fuel cycle with PT.

Furthermore, basic properties on the TRU compounds have been measured by use of Moesbauer spectroscopy, nuclear magnetic resonance (NMR), X-ray absorption fine structure (XAFS) and so on under collaboration with domestic partners.

Research activities related to MA-recycling Research activities related to MA-recycling

Publication

Journals, Proceedings, Technical Reports

-2015-
H.Hayashi, M.Akabori, K.Minato
5th Asia-Pacific Symposium on Radiochemistry (APSORC '13)
-2014-
F.Fuel Debris Conditioning Technology Development Group, .Fuel Debris Analysis Technology Development Group,Fukushima Project Team
H.Hayashi, T.Sato, H.Shibata, M.Kurata, T.Iwai, Y.Arai
H.Shibata, H.Hayashi, M.Akabori, Y.Arai, M.Kurata
K.Nishihara, H.Akie, N.Shirasu, T.Iwamura
K.Sakamoto, H.Shibata, K.Une, A.Ouchi, M.Aomi, M.Kurata
2014 Water Reactor Fuel Performance Meeting/ Top Fuel / LWR Fuel Performance Meeting (WRFPM 2014)
Proceedings of 2014 Water Reactor Fuel Performance Meeting/ Top Fuel / LWR Fuel Performance Meeting (WRFPM 2014) (USB Flash Drive)
M.Pukari, M.Takano
M.Pukari, M.Takano, T.Nishi
M.Takano, H.Hayashi, K.Minato
M.Takano, T.Nishi, N.Shirasu
T.Nishi, Y.Arai, M.Takano, M.Kurata
-2013-
A.Nakayoshi, S.Kitawaki, M.Fukushima, T.Murakami, M.Kurata
C.Suzuki, T.Nishi, M.Nakada, T.Tsuru, M.Akabori, M.Hirata, Y.Kaji
H.Akie, I.Sato, M.Suzuki, H.Serizawa, Y.Arai
H.Hayashi, H.Hagiya, S.Kim, Y.Morita, M.Akabori, K.Minato
H.Hayashi, M.Takano, H.Otobe, T.Koyama
H.Otobe
Nuclear Materials Conference 2012 (NuMat 2012)
M.Kurata
Conference on Molten Salts in Nuclear Technology (CMSNT 2013)
Proceedings of Conference on Molten Salts in Nuclear Technology (CMSNT 2013)
M.Kurata, N.Shirasu, T.Ogawa
M.Takano
Nuclear Materials Conference 2012 (NuMat 2012)
M.Takano, T.Nishi
Nuclear Materials Conference 2012 (NuMat 2012)
M.Takano, T.Nishi, H.Hayashi, K.Nakajima, H.Otobe
9th International Conference on the Chemistry and Physics of the Actinide Elements (ACTINIDES 2013)
T.Nishi, M.Takano, M.Akabori, Y.Arai
T.Nishi, M.Takano, M.Akabori, Y.Arai
Nuclear Materials Conference 2012 (NuMat 2012)
T.Nishi, M.Takano, Y.Arai, M.Kurata
第34回日本熱物性シンポジウム
Dai-34-Kai Nippon Netsu Bussei Shimpojiumu Koen Rombunshu
T.Sato, K.Nishihara, M.Takano
International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011)
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM)
-2012-
C.Suzuki, T.Nishi, M.Nakada, M.Akabori, M.Hirata, Y.Kaji
H.Shibata, H.Hayashi, T.Koyama
4th Asian Conference on Molten Salt Chemistry and Technology \& 44th Symposium on Molten Salt Chemistry, Japan
Proceedings of 4th Asian Conference on Molten Salt Chemistry and Technology \& 44th Symposium on Molten Salt Chemistry, Japan
H.Shibata, T.Tsuru, T.Nishi, M.Hirata, Y.Kaji
K.Nakamura, T.Kato, T.Ogata, K.Nakajima, T.Iwai, Y.Arai
International Conference on Fast Reactors and Related Fuel Cycles (FR 2009)
M.Takano, T.Nishi, M.Kurata, M.Amaya, F.Nagase
5th European Review Meeting on Severe Accident Research (ERMSAR 2012)
Y.Arai
Y.Arai
4th International ATALANTE Conference on Nuclear Chemistry for Sustainable Fuel Cycles (ATALANTE 2012)
Y.Haga, Y.Homma, D.Aoki, K.Nakajima, Y.Arai, T.Matsuda, S.Ikeda, H.Sakai, E.Yamamoto, A.Nakamura, N.Tateiwa, Y.Onuki, Z.Fisk
International Workshop on Heavy Fermions (TOKIMEKI 2011)
Y.Tokunaga, H.Sakai, S.Kambe, H.Chudo, M.Osaka, S.Miwa, T.Nishi, M.Nakada, A.Ito, Y.Homma
Materials Research Society 2012 Spring Meeting
 2011 | 2010 | 2009 | 2008 | 2007 | 2006 

∗This list is automatically generated from the database of JAEA Originated Papers Searching System(JOPSS).

Cooperation

Joint Research

2013—2014
Central Research Institute of Electric Power Industry (CRIEPI)
過酷事故における炉内物質の挙動評価と処理に関する基盤研究
2006—2013
CRIEPI
Fundamental research on recycling of transuranium elements by pyrochemical process:Phase II,III,IV

Competitive Research Funding

2010—2012
Ministry of Education, Culture, Sports, Science and Technology (MEXT)
Development of numerical simulation technology of microstructure for nuclear fuels
2010—2011
MEXT
Development of the reprocessing of spent nitride fuel by chemical dissolution in molten salt
2010—2013
MEXT
Engineering development of MA-alloy fuel fabrication for irradiation test
2009—2011
MEXT
Research and development of flexible technology realization for smooth transition to FBR
MEXT
Development of metal fuel cycle technology for closing FBR fuel cycle
2008—2010
MEXT
Basic actinide chemistry and physics research in close cooperation with hot laboratories
2007—2009
MEXT
Development of common and fundamental technologies on the evaluation of fuel behavior for realizing MA recycling
2006—2008
MEXT
Development of a fabrication technology of TRU alloy fuel and fuel design for TRU transmutation
MEXT
Development of fabrication technique for the MA-containing nitride fuel dispersed in TiN inert matrix
MEXT
Application of electrochemical reduction to pyrochemical reprocessing for oxide nuclear fue
MEXT
Research and development of flexible fuel cycle for the smooth introduction of FBR
2005—2007
MEXT
Development of high-efficiency separation and recovery technology of minor actinides using liquid gallium
2002—2006
MEXT
Technological development of a fuel cycle based on nitride fuel and pyrochemical reprocessing

Member

Group Leader

倉田 正輝
KURATA Masaki

Deputy Leaders

林 博和
HAYASHI Hirokazu
高野 公秀
TAKANO Masahide

Staffs

白数 訓子
SHIRASU Noriko
音部 治幹
OTOBE Haruyoshi
小野澤 淳
ONOZAWA Atsushi
柴田 裕樹
SHIBATA Hiroki
佐藤 匠
SATO Takumi
須藤 彩子
SUDO Ayako
徳島 ニ之
TOKUSHIMA Kazuyuki
千葉 力也
CHIBA Rikiya
荒井 康夫
ARAI Yasuo
岩井 孝
IWAI Takashi
菊地 啓修
KIKUCHI Hironobu
中村 勤也
NAKAMURA Kinya
徳島 ニ之
TOKUSHIMA Kazuyuki
重藤 房子
SHIGETO Fusako

Collabolators

中島 邦久
NAKAJIMA Kunihisa
赤堀 光雄
AKABORI Mitsuo
中田 正美
NAKATA Masami
芹澤 弘幸
SERIZAWA Hiroyuki
田上 進
TAGAMI Susumu

Contact Infomation

Japan Atomic Energy Agency
Nuclear Science & Engineering Center
Fuels and Material Engineering Division
Research Group for High Temperature Science on Fuel Materials

1st Laboratory building-120, Nuclear Science and Engineering Institute

2-4 Shirane Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan

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