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Zaima, Naoki; Nakashima, Shinichi; Kaneda, Koji; Kado, Kazumi
no journal, ,
We developed uranium mass assay systems for 200-litter wastes drums applied neutron and 
measurements by NDA method. In this intermediate report we will describe measurement systems and trial data. The systems are composed of the 16 pieces of helium-3 proportional counters for neutron detection and a large sized NaI(Tl) scintillation detector for -ray detection. The extensive testing trials using the calibrated uranium sources with different enrichment and some kinds of matrices in drums were performed. Through the one year testing the useful experiences of this system concerning neutron and -ray measurements for uranium mass were obtained. Almost all instruments and software were so good performance as is designed. As the next step we are going to schedule to try measurements for actual wastes that are stored in the Uranium Refining and Conversion Plant at Ningyo-toge, and put practical uses near future. Our research was accomplished with the support of Los Alamos National Laboratory.
Katayama, Masaharu*; Takamatsu, Kuniyoshi; Sawa, Kazuhiro; Takagi, Naoyuki*; Ooka, Yasunori*; Yamasaki, Masatoshi*
no journal, ,
As collaborative research project by Japan Atomic Energy Agency, Toyota Tsusho Corporation and Nuclear Fuel Industries, Ltd., new utilizations of HTGR and new R&D of a cooperative relationship between car industries and HTGR are presented. Specifically, we showed the results of feasibility study on material creation and new-type fuel utilization by using HTTR.
Kurosaki, Ken*; Sugawara, Toru*; Yusuf, A.*; Oishi, Yuji*; Muta, Hiroaki*; Yamanaka, Shinsuke*; Morita, Yasuji
no journal, ,
As solidification method for insoluble residue appeared in spent nuclear fuel dissolution, the composite materials of Mo-Ru-Rh-Pd alloys and oxide ceramics were prepared by spark plasma sintering method and the characterization of the solidified materials was performed by examining their microstructure and phase state. Aluminum oxide, 
-Al
O
, was used as oxide ceramics. Mixed phases of -AlO and Mo-Ru-Rh-Pd alloys were observed in the solidified materials.
Ota, Masakazu; Nagai, Haruyasu
no journal, ,
no abstracts in English
Sekine, Takashi; Kitamura, Ryoichi; Maeda, Yukimoto; Chatani, Keiji
no journal, ,
Since in-vessel observation for a sodium fast reactor has to be conducted under severe conditions that include high temperatures (approximately 200
C) and high radiation doses (approximately 200 Gy/h). In addition, since the primary sodium coolant has to be always kept in the reactor vessel to remove the decay heat of fuel subassemblies. Therefore an in-vessel observation equipment has to be designed to not only stand the severe conditions but also be capable of being inserted into the sealed reactor vessel through the holes built into the rotating-plug. In Joyo, in-vessel inspections and repair technologies are developed and applied to observe the upper core structure and bent irradiation test subassembly. The detail design of the Joyo restoration work is now pushed forward based on the in-vessel observation results.
Tachi, Yukio; Yotsuji, Kenji; Seida, Yoshimi*
no journal, ,
Diffusion and sorption behaviors of Cs+, I- and HTO in samples of the Wakkanai Formation from Horonobe URL were investigated as a function of salinity of synthetic groundwater by through-diffusion and batch sorption experiments. The Kd values for Cs determined by through-diffusion and batch experiments were in good agreement and decreased with salinity as a result of competitive ion exchange. The De values showed cation excess and anion exclusion effects, which were strongly dependent on IS; De for Cs+ decreased as salinity increased, De for I- showed the opposite dependency and De for HTO showed no dependence. Sorption and diffusion behaviors were interpreted based on the clay-based modeling approach in assuming the clay components of illite and smectite control diffusion and sorption mechanisms. The model predicted the De and Kd trends obtained by the series of experiments reasonably well, implying the key contribution of the clay particle and nano-size pore for ionic migration.
Kitamura, Akira; Fujiwara, Kenso; Mihara, Morihiro; Cowper, M.*; Kamei, Gento
no journal, ,
Solubility of thorium and americium in cement porewater was measured. Effect of super plasticizer on solubility was investigated. Applicability of thermodynamic calculations using JAEA-TDB was verified.
Takeuchi, Shinji; Kunimaru, Takanori; Ota, Kunio
no journal, ,
Hydraulic packer test (HT) has been carried out in the deep borehole investigations in the URL programs. Obtained results (transmissivity and flow model etc.) are used for the groundwater modeling/simulations etc. Therefore, quality of HT data is crucial for ensuring reliability of the modeling/simulation results. Thus quality management system for the HT from data acquisition has been established. The established system has been applied to the recent borehole investigations in the URL program and confirmed it's appropriateness.
Inoue, Toshihiko; Ogawa, Ryuichiro; Inoue, Masaki; Yoshitake, Tsunemitsu; Nishinoiri, Kenji
no journal, ,
no abstracts in English
Kaito, Yasuaki; Ashida, Takashi; Miyamoto, Kazuyuki; Ito, Hideaki
no journal, ,
no abstracts in English
Yamamoto, Tomohiko; Negishi, Kazuo*; Hara, Hiroyuki*
no journal, ,
The JSFR adopts SCCV for the improvement of quality and economic efficiency. For commercialization of JSFR, we have carried out the research and development of not only the study on SCCV structure and construction term at the site but also the material strength test and analysis. These series presentation show the results. In this presentation, the results of study on construction methods are shown.
Kato, Atsushi; Chikazawa, Yoshitaka; Obata, Hiroyuki*
no journal, ,
Japan Sodium-cooled Fast Reactor have been adopted a new concept of the fuel handling machine which enables a compact reactor vessel compared with a conventional one. This fuel handling machine have been developing in the FaCT project. This time, a seismic analysis at the design base seismic condition have been conducted. As a result, the fuel handling machine would not interfere the equipments around them at its seismic condition.
Itagaki, Wataru; Soga, Tomonori; Aoyama, Takafumi; Ogata, Takanari*; Nakamura, Kinya*
no journal, ,
no abstracts in English
Tanaka, Yoshio; Morimoto, Yasuyuki; Tokuyasu, Takashi; Takahashi, Nobuo; Sugitsue, Noritake
no journal, ,
In Ningyo-toge environmental engineering center started the decommissioning project of commercial-scale nuclear fuel facility in 2008. We worked on dismantling/removal of equipments in the radiation controlled area, and about 80 % were finished. Therefore, we arranged it systematically for dismantling work in work elements to need for the decommissioning project. The man-hour ratio of 3 work division was preparation 29 % and dismantlement 59 %, post-processing 12 %. The breakdown of each work division is preparations 14 processes and dismantlement 32, post-processing 11. At least 57 processes classifications are necessary for dismantling work. In addition, a man-hour ratio to need for post-processing was almost a constant in every result. On the other hand, the man-hour ratios of preparations and dismantling were classified in 3 groups.
Kushida, Noriyuki; Fujibayashi, Kenichi; Kureta, Masatoshi; Segawa, Mariko; Shinohara, Takenao; Takemiya, Hiroshi
no journal, ,
Center for Computational Science and E-systems of Japan Atomic Energy Agency has been developing elemental technologies for high-speed data analysis in order to achieve "On Site" data analysis. Recent huge experimental facilities provide tremendous amount of data, which is beyond traditional computers capability. Therefore we developed and applied novel parallel computing techniques. As a result, we achieved around 100 times speed-up in computation, and 10 times speed-up in data storage access than traditional computers.
Okano, Masanori; Goto, Yuichi; Jitsukata, Shu*; Nemoto, Hirokazu*; Kuno, Takehiko; Yamada, Keiji
no journal, ,
no abstracts in English
Kato, Masato
no journal, ,
no abstracts in English
Yamamoto, Masaya; Kawahara, Hirotaka; Terakado, Tsuguo; Aoyama, Takafumi; Sato, Ikken; Ohshima, Hiroyuki
no journal, ,
CDF caused by ATWS (Anticipated Transient Without Scram) event and PLOHS (Protected Loss of Heat Sink) event are majority of CDF in probabilistic safety study at Joyo. Evaluation of these values by reactor dynamic characteristics analysis and natural convection analysis are conducted with a detailed success standard. It was found from evaluation result that CDF are quite low and a dominant core damage accident is UTOP (Unprotected Transient Over Power) event.
Sasaki, Shinji; Maeda, Koji; Nagamine, Tsuyoshi; Asaka, Takeo
no journal, ,
no abstracts in English
Seki, Masayuki; Kihara, Yoshiyuki; Hirako, Kazuhito*; Motoki, Kazuhiko*; Tsukada, Tatsuya*
no journal, ,
no abstracts in English