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Journal Articles

Characterization of the VULCANO test products for fuel debris removal from the Fukushima Daiichi Nuclear Power Plant

Kitagaki, Toru; Ikeuchi, Hirotomo; Yano, Kimihiko; Ogino, Hideki; Haquet, J.-F.*; Brissonneau, L.*; Tormos, B.*; Piluso, P.*; Washiya, Tadahiro

Progress in Nuclear Science and Technology (Internet), 5, p.217 - 220, 2018/11

Journal Articles

Thermodynamic evaluation of the solidification phase of molten core-concrete under estimated Fukushima Daiichi Nuclear Power Plant accident conditions

Kitagaki, Toru; Yano, Kimihiko; Ogino, Hideki; Washiya, Tadahiro

Journal of Nuclear Materials, 486, p.206 - 215, 2017/04

AA2016-0278.pdf:0.74MB

 Times Cited Count:14 Percentile:86.92(Materials Science, Multidisciplinary)

Journal Articles

FaCT Phase-I evaluation on the advanced aqueous reprocessing process, 4; Solvent extraction simplified for FBR fuel reprocessing

Koma, Yoshikazu; Ogino, Hideki; Sakamoto, Atsushi; Nakabayashi, Hiroki; Shibata, Atsuhiro; Nakahara, Masaumi; Washiya, Tadahiro

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 6 Pages, 2011/12

Journal Articles

Study on cleaing solvents using activated alumina in PUREX process

Arai, Yoichi; Ogino, Hideki; Takeuchi, Masayuki; Kase, Takeshi; Nakajima, Yasuo

Proceedings in Radiochemistry, 1(1), p.71 - 74, 2011/09

Solvent cleanup method using activated alumina was discussed in this study. This method was one of candidate to remove TBP/$$n$$-dodecane degradation products. The degradation sample of 30% TBP/$$n$$-dodecane was prepared by irradiation (1.6 MGy) using $$^{60}$$Co $$gamma$$-source. The absorbed dose for sample was almost 1.6 MGy. The degradation products were qualitatively analyzed by gas chromatography-mass spectrometer (GC-MS). After the irradiation, solvent cleanup was performed by activated alumina and the cleanup using alumina was examined by phase separation test with 3M HNO$$_{3}$$. As the result, it was found that hexane and long-chain alcohols were mainly generated as the n-dodecane degradation products by irradiation, and almost 70% of the TBP/$$n$$-dodecane degradation products were removed and the phase separation performance were improved by the cleanup using activated alumina.

Journal Articles

Extraction and stripping tests of engineering-scale centrifugal contactors cascade system for spent nuclear fuel reprocessing

Takeuchi, Masayuki; Ogino, Hideki; Nakabayashi, Hiroki; Arai, Yoichi; Washiya, Tadahiro; Kase, Takeshi; Nakajima, Yasuo

Journal of Nuclear Science and Technology, 46(3), p.217 - 225, 2009/03

 Times Cited Count:8 Percentile:53.11(Nuclear Science & Technology)

Journal Articles

Development of centrifugal contactor with high reliability

Okamura, Nobuo; Takeuchi, Masayuki; Ogino, Hideki; Kase, Takeshi; Koizumi, Tsutomu

Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), p.1070 - 1075, 2007/09

no abstracts in English

Journal Articles

Development of centrifugal contactor system in JNC

Washiya, Tadahiro; Takeuchi, Masayuki; Ogino, Hideki; Aose, Shinichi

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10

Japan Nuclear Cycle Development Institute (JNC) has been developing centrifugal contactors which are compact and high performance for solvent extraction process in industrial reprocessing plant. Centrifugal contactor has some advantages which are more compact, smaller holdup volume and higher separation performance than conventional contactor such as mixer-settler or pulse column and contributes to economic advantage and reduction of solvent waste. In addition, the compact contactor is easy to manage the critical safety, and the operation ratio for fuel treatment can be improved because of short start-up and shut-down time. Since 1985, JNC stared the development of centrifugal contactor and then fundamental design was established for engineering scale hot test plant (RETF). The life time was evaluated by the result of endurance test, and system performance of multi-stages contactor on engineering scale was demonstrated. [1] In addition, several types of advanced contactors have been developing. This paper introduces the development of centrifugal contactor in JNC

Journal Articles

Conceptual Design Study on Advanced Aqueous Reprocessing System for Fast Reactor Fuel Cycle

Takata, Takeshi; Koma, Yoshikazu; Sato, Koji; Kamiya, Masayoshi; Shibata, Atsuhiro; Nomura, Kazunori; Ogino, Hideki; Koyama, Tomozo; Aose, Shinichi

Journal of Nuclear Science and Technology, 41(3), 307 Pages, 2004/00

 Times Cited Count:27 Percentile:85.48(Nuclear Science & Technology)

The design study of aqueous reprocessing system has been progressed for the feasibility study on commercialized fast reactor cycle systems. Based on the PUREX process,an aqueous reprocessing process with the addition of a uranium crystallization step and

Journal Articles

None

Washiya, Tadahiro; Ogino, Hideki; Takeuchi, Masayuki; Suganuma, T.; Aose, Shinichi

Saikuru Kiko Giho, (21), p.23 - 32, 2003/00

None

Oral presentation

Study of secondary solvent cleanup using activated alumina in PUREX reprocessing processes, 2; Result of solvent cleanup examination with activated alumina

Arai, Yoichi; Ogino, Hideki; Takeuchi, Masayuki; Kase, Takeshi; Koizumi, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Study of secondary solvent cleanup using activated alumina in PUREX reprocessing processes, 1; Influence of n-dodecane degradation products on phase-separation time

Ogino, Hideki; Arai, Yoichi; Takeuchi, Masayuki; Kase, Takeshi; Koizumi, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Research on radiation resistance of grease, etc. for reprocessing cell equipment

Okamura, Nobuo; Ogino, Hideki; Arai, Yoichi; Kase, Takeshi; Koizumi, Tsutomu; Idesaki, Akira; Morishita, Norio; Oshima, Takeshi; Kojima, Takuji

no journal, , 

no abstracts in English

Oral presentation

Development of centrifugal contactor; Fluidic performance evaluation and Advanced Centrifugal Contactor Test System(ACT) test results

Ogino, Hideki; Takeuchi, Masayuki; Arai, Yoichi; Okamura, Nobuo; Washiya, Tadahiro; Kase, Takeshi; Koizumi, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Engineering scale demonstration test of centrifugal contactor system, 6; Flushout test

Arai, Yoichi; Ogino, Hideki; Onose, Tsutomu*; Koizumi, Satoshi*; Fujisaku, Kazuhiko*; Yokoyama, Yoshitomo*

no journal, , 

no abstracts in English

Oral presentation

Development of centrifugal contactor with magnetic bearing system, 5; Results of 5000 hours operation

Ogino, Hideki; Okamura, Nobuo; Kase, Takeshi; Nakajima, Yasuo; Fujisaku, Kazuhiko*

no journal, , 

no abstracts in English

Oral presentation

Engineering scale demonstration test of centrifugal contactor system, 7; Examination on operating conditions for solvent flushout

Arai, Yoichi; Ogino, Hideki; Onose, Tsutomu*; Kase, Takeshi; Nakajima, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Development of the solvent extraction technique for U-Pu-Np co-recovery in the NEXT process

Sano, Yuichi; Ogino, Hideki; Washiya, Tadahiro; Myochin, Munetaka

no journal, , 

In the FaCT Project, JAEA has been working on the improvement of solvent extraction for U-Pu-Np co-recovery as a part of the advanced aqueous reprocessing process (NEXT process) development. In the process development, the appropriate flowsheet condition was indicated for the efficient Np co-extraction with U and Pu, and their sufficient co-stripping. On the experiments with the engineering-scale centrifugal contactors, excellent extraction and stripping performances were obtained. In addition, the high durability of the centrifugal contactor using the magnetic bearing was confirmed.

Oral presentation

Investigation of condition for solvent flushout on centrifugal contactor

Arai, Yoichi; Ogino, Hideki; Onose, Tsutomu*; Hoshino, Takanori; Kase, Takeshi; Nakajima, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Design of centrifugal contactor, 1; Fluidic performance of miniature centrifugal contactor

Hoshino, Takanori; Ogino, Hideki; Arai, Yoichi; Kase, Takeshi; Nakajima, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Design of centrifugal contactor, 2; Operable zone of 200tHM/year-scale centrifugal contactor

Ogino, Hideki; Nakajima, Yasuo; Kase, Takeshi; Koizumi, Satoshi*; Ishii, Hideyuki*

no journal, , 

no abstracts in English

49 (Records 1-20 displayed on this page)