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Journal Articles

Estimation of creep behavior of thick rubber bearings from 47 years observation in an actual building

Masaki, Nobuo*; Kato, Koji*; Yamamoto, Tomohiko; Miyagawa, Takayuki*; Fujita, Satoshi*; Okamura, Shigeki*

Nihon Kenchiku Gakkai Gijutsu Hokokushu, 28(68), p.81 - 84, 2022/02

no abstracts in English

Journal Articles

Study on gamma-ray-degradation of adsorbent for low pressure-loss extraction chromatography

Miyazaki, Yasunori; Sano, Yuichi; Okamura, Nobuo; Watanabe, Masayuki; Koka, Masashi*

QST-M-29; QST Takasaki Annual Report 2019, P. 72, 2021/03

no abstracts in English

Journal Articles

Prediction of the drying behavior of debris in Fukushima Daiichi Nuclear Power Station for dry storage

Nakayoshi, Akira; Suzuki, Seiya; Okamura, Nobuo; Watanabe, Masayuki; Koizumi, Kenji

Journal of Nuclear Science and Technology, 55(10), p.1119 - 1129, 2018/10

 Times Cited Count:1 Percentile:17.98(Nuclear Science & Technology)

Journal Articles

Mechanical properties of cubic (U,Zr)O$$_{2}$$

Kitagaki, Toru; Hoshino, Takanori; Yano, Kimihiko; Okamura, Nobuo; Ohara, Hiroshi*; Fukasawa, Tetsuo*; Koizumi, Kenji

Journal of Nuclear Engineering and Radiation Science, 4(3), p.031011_1 - 031011_7, 2018/07

Journal Articles

Development on rubber bearings for sodium-cooled fast reactor, 3; Ultimate properties of a half scale thick rubber bearings based on breaking test

Fukasawa, Tsuyoshi*; Okamura, Shigeki*; Yamamoto, Tomohiko; Kawasaki, Nobuchika; Hirotani, Tsutomu*; Moriizumi, Eriko*; Sakurai, Yu*; Masaki, Nobuo*

Proceedings of 2016 ASME Pressure Vessels and Piping Conference (PVP 2016) (Internet), 10 Pages, 2016/07

Half-scale thick rubber bearing to investigate ultimate properties application for a Sodium-cooled-Fast-Reactor. The fundamental restoring-force characteristics of the thick rubber bearings has been already cleared through the static loading tests using a half-scale thick rubber bearing, 800 mm in diameter. However, variations of the restoring force characteristics and ultimate properties have not been obtained yet. The purpose of this paper is to indicate the variation of the stiffness and damping ratio concerning restoring force characteristics and the breaking strain or stress as ultimate properties through static loading tests using the half-scale thick rubber bearings.

Journal Articles

Development on rubber bearings for sodium-cooled fast reactor, 1; Examination plan

Yamamoto, Tomohiko; Kawasaki, Nobuchika; Fukasawa, Tsuyoshi*; Okamura, Shigeki*; Somaki, Takahiro*; Samejima, Yusuke*; Masaki, Nobuo*

Proceedings of 2015 ASME Pressure Vessels and Piping Conference (PVP 2015) (Internet), 7 Pages, 2015/07

Since a SFR (Sodium-cooled Fast Reactor) has thin-walled component structures, a seismic isolation system is employed to mitigate the seismic force. Seismic isolation system for applying the SFR consists of the laminated rubber bearing considering characteristics of SFR structures. This paper describes a basic mechanical characteristic examination with a 1/8 scale model and a characterization examination plan of half-scale laminated rubber.

Journal Articles

Development on rubber bearings for sodium-cooled fast reactor, 2; Fundamental characteristics of half-scale rubber bearings based on static test

Fukasawa, Tsuyoshi*; Okamura, Shigeki*; Yamamoto, Tomohiko; Kawasaki, Nobuchika; Somaki, Takahiro*; Sakurai, Yu*; Masaki, Nobuo*

Proceedings of 2015 ASME Pressure Vessels and Piping Conference (PVP 2015) (Internet), 10 Pages, 2015/07

This paper described the results of static loading tests using a half-scale rubber bearing model to investigate the fundamental characteristics such as restoring force of a rubber bearing applied to a Sodium-Cooled-Fast-Reactor (SFR). Since the SFR has thin-walled structures, a seismic isolation system is employed to mitigate the seismic force. The static loading tests were performed using the half-scale rubber bearing with a diameter of 800 mm in the range which exceeds a linear limit of horizontal direction and a yield stress of vertical direction to investigate the horizontal and vertical of each stiffness and damping ratio. The fundamental characteristic of rubber bearing employed to the SFR and the validity of a design formula became clear through the static tests.

Journal Articles

Mechanical properties of fuel debris for defueling toward decommissioning

Hoshino, Takanori; Kitagaki, Toru; Yano, Kimihiko; Okamura, Nobuo; Ohara, Hiroshi*; Fukasawa, Tetsuo*; Koizumi, Kenji

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6 Pages, 2015/05

Journal Articles

Sludge behavior in centrifugal contactor operation for nuclear fuel reprocessing

Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Okamura, Nobuo; Koizumi, Kenji

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 5 Pages, 2015/05

Journal Articles

Effect of pulse electrolysis on morphology of co-deposited MOX granules

Kofuji, Hirohide; Okamura, Nobuo; Mizuguchi, Koji*; Myochin, Munetaka

Journal of Nuclear Science and Technology, 45(9), p.942 - 950, 2008/09

 Times Cited Count:1 Percentile:10.92(Nuclear Science & Technology)

In the oxide electrowinning method of nuclear fuel recycling, the applicability of the pulse electrolysis method to the MOX co-deposition process was evaluated. Several experiments were conducted involving uranium, plutonium, and elements simulating fission product (FP) or corrosion product (CP). Through study of the results of these experiments, the influences of the impurities and the effect of the waveform of electrolysis pulses on the electro-deposit were clarified. As a result, pulse electrolysis conditions which could restrain Pu enrichment of the deposited MOX were confirmed. Furthermore, it was found that the element distribution in the MOX granule obtained by the pulse electrolysis was homogenized, which is well suited for nuclear fuel fabrication. Finally, a qualitative model of the pulse electrolysis reaction near the field of cathode surface is proposed.

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

Design of Electrodes in Geometrical Control Type Electrolyzer for Oxide Electrowinning Process

Okamura, Nobuo; Koizumi, Kenji; Washiya, Tadahiro; Aose, Shinichi

Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13) (CD-ROM), 0 Pages, 2005/05

In Japan Nuclear Cycle Development Institute (JNC), a commercial scale electrolyzer, whose capacity is 25tHM/y, is been developing to be used in an oxide electrowinning process, a kind of non-aqueous reprocessing process. It has some significant subjects that must be solved before introduced in a commercial reprocessing plant. It developed in JNC has some innovative characteristics, such as cold crucible induction melting (CCIM), to cope with those subjects. But these characteristics make it difficult to arrange the internal components because of a narrow and deep shape of a crucible. So two kinds of analysis systems with computer were constructed to help a design of the internal constitution. One of them is to evaluate the temperature distribution in the crucible and another is to evaluate the shape of deposits. In this study, the internal constitution in the commercial scale electrolyzer was designed by using them finally.

Journal Articles

Development of the for the materials transfer capability evaluation system in a Pyrochemical Reprocessing Plant

Okamura, Nobuo; Tozawa, Katsuhiro; Sato, Koji

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 0 Pages, 2003/00

None

Journal Articles

None

Okamura, Nobuo; Sato, Koji

Saikuru Kiko Giho, 14(2001), 1 Pages, 

None

Oral presentation

Electrolytic recovery of UO$$_{2}$$ from spent fuel with LiCl-KCl; Preliminary experiment by simulated spent fuel consisted of UO$$_{2}$$ and noble metals

Okamura, Nobuo; Koizumi, Tsutomu; Fukushima, Mineo; Kurata, Masaki; Sakamura, Yoshiharu*

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

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

Durability of centrifugal contactors under sludge inclusion condition, 1; Effect of operation conditions on sludge accumulation

Arai, Yoichi; Takeuchi, Masayuki; Sakamoto, Atsushi; Ohata, Fumikazu; Okamura, Nobuo; Ogino, Hideki; Koizumi, Kenji

no journal, , 

no abstracts in English

Oral presentation

Durability of centrifugal contactors under sludge inclusion condition, 2; Effect of scale-up on sludge accumulation

Okamura, Nobuo; Sakamoto, Atsushi; Takeuchi, Masayuki; Koizumi, Kenji; Sakamoto, Yukio*

no journal, , 

no abstracts in English

40 (Records 1-20 displayed on this page)