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Ohgama, Kazuya; Aliberti, G.*; Stauff, N. E.*; Oki, Shigeo; Kim, T. K.*
Mechanical Engineering Journal (Internet), 4(3), p.16-00592_1 - 16-00592_9, 2017/06
Ohgama, Kazuya; Aliberti, G.*; Stauff, N. E.*; Oki, Shigeo; Kim, T. K.*
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 8 Pages, 2017/04
Ohgama, Kazuya; Aliberti, G.*; Stauff, N. E.*; Oki, Shigeo; Kim, T. K.*
Proceedings of 24th International Conference on Nuclear Engineering (ICONE-24) (DVD-ROM), 6 Pages, 2016/06
Under the cooperative effort of the Civil Nuclear Energy R&D Working Group within the framework of the U.S.-Japan bilateral, Argonne National Laboratory (ANL) and Japan Atomic Energy Agency (JAEA) have been performing benchmark study using Japan Sodium-cooled Fast Reactor (JSFR) design with metal fuel. In this benchmark study, core characteristic parameters at the beginning of cycle were evaluated by the best estimate deterministic and stochastic methodologies of ANL and JAEA. The results obtained by both institutions are agreed well with less than 200 pcm of discrepancy on the neutron multiplication factor, and less than 3% of discrepancy on the sodium void reactivity, Doppler reactivity, and control rod worth. The results by the stochastic and deterministic were compared in each party to investigate impacts of the deterministic approximation and to understand potential variations in the results due to different calculation methodologies employed. Impacts of the nuclear data libraries were also investigated using a sensitivity analysis methodology.
Takeda, Hayato*; Onuma, Kenji*; Tamada, Masao; Kasai, Noboru; Katakai, Akio; Hasegawa, Shin; Seko, Noriaki; Kawabata, Yukiya*; Sugo, Takanobu
JAERI-Tech 2001-062, 66 Pages, 2001/10
Real sea experiment for the recovery of significant metals such as uranium and vanadium has been carried out at the offing of Mutsu establishment to evaluate the adsorption performance of adsorbent synthesized by radiation-induced graft-polymerization. After elution of uranium and vanadium from the adsorbent, their metals were adsorbed onto the conventional chelate resin. This chelate resin in a plastic column was further put in a cylindrical stainless transport container. The container was transported to the facility for separation and purification by a truck for the exclusive loading. The maximum concentration is 60 Bq/g when the uranium is adsorbed on the chelate resin. Transportation of recovered metals can be treated as general substance since these amount and concentration are out of legal control. However, the recovered metals were transported in conformity to L type transportation as a voluntary regulation. The strength analysis of the container was equal to the safety level of IP-2 type which is higher transportation grade than L type .
*; Nakajima, Hideo; Nunoya, Yoshihiko; Miura, Yushi; Kawasaki, T.*; Tsuji, Hiroshi
Advances in Cryogenic Engineering Materials, 44, p.73 - 80, 1998/00
no abstracts in English
Nakamura, Hisashi; Hirabayashi, Takakuni
Nihon Kikai Gakkai Dai-6-Kai Doryoku, Enerugi Gijutsu Shimpojiumu '98 Koen Rombunshu, p.371 - 376, 1998/00
no abstracts in English
Nakamura, Hisashi; Shindo, Hideaki
Proc. of 3rd European Technical Seminar on Melting and Recycling of Metallic waste Materials, p.79 - 91, 1997/00
no abstracts in English
Hishinuma, Akimichi; Fukai, Katsumaro; Sawai, Tomotsugu; *
Intermet., 4, p.179 - 184, 1996/00
no abstracts in English
Maeta, Hiroshi; Yamakawa, Koiji*; *; Haruna, K.*; Kato, Teruo; Ono, Fumihisa*
Nuclear Instruments and Methods in Physics Research B, 97, p.491 - 494, 1995/00
Times Cited Count：0 Percentile：0.01(Instruments & Instrumentation)no abstracts in English
Naramoto, Hiroshi
Isotope News, (474), p.28 - 29, 1993/12
no abstracts in English
Sawa, Kazuhiro; Shiozawa, Shusaku; Fukuda, Kosaku;
Journal of Nuclear Science and Technology, 29(9), p.842 - 850, 1992/09
no abstracts in English
; Konishi, Satoshi; Naruse, Yuji
Nucl.Technol./Fusion, 3, p.471 - 484, 1983/00
no abstracts in English
Otani, Kyohei; Tsukada, Takashi; Ueno, Fumiyoshi; Kato, Chiaki
no journal, ,
Corrosion tests of carbon steel was carried out in air-solution alternating condition in previous study. It has been reported that the corrosion rate of carbon steel exposed in air-solution alternating condition was accelerated compare with the steel exposed in solution. In this study, it was investigated that the effect of concentration of model sea water on corrosion rate of carbon steel in air-solution alternating condition. The mass measurement in corrosion tests clarified that the corrosion rate of carbon steel in the 200 times diluted model sea water is fastest during various model sea water. Cross-sectional analysis of iron rust layer formed on carbon steel after corrosion tests indicated that the corrosion rate of carbon steel in model sea water is decreased by precipitation of metal cations containing in model sea water.
Otani, Kyohei
no journal, ,
This is a comprehensive paper of the corrosion of carbon steel in air/solution alternating condition. From cross-sectional observation and analysis of the iron rust layer formed on the surface of carbon steel in the alternating condition, it was found that a multilayered iron rust layer composed of red rust layer, rust crust layer, inner crystal, and inner rust layer was formed on carbon steel. The multi-layered iron rust layer would accelerate the cathodic oxygen reduction reaction, and the reason why the corrosion rate of the carbon steel in the alternating condition was accelerated. The effect of artificial seawater (ASW) composition on the corrosion rate of carbon steel in air/solution alternating condition was investigated. It was found that the corrosion rate increased with increasing concentration from pure water to 200 times diluted ASW, and decreased with increasing concentration from 20 times diluted ASW to no diluted ASW. The Mg and Ca ions in ASW precipitated on the reaction interface and formed a metal cation layer, which inhibited the oxygen reduction reaction, and thus the corrosion of carbon steel was inhibited in the highly concentrated ASW. This is a commemorative lecture for the awarding of the Progress Award by the Japan Society of Corrosion Engineering.
