Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Tasaka, Masayuki; Washiya, Tadahiro; Kobayashi, Tsuguyuki*
no journal, ,
From previous reports, the powdered fuel was considered to be suitable for the preparation of high concentrated solution efficiently. And the short stroke shearing technology is expected to make the powdered fuel rationally. In this study, the short stroke shearing tests with simulated fuel pin bundle has been carried out at engineering scale. From these tests, fundamental data of the short stroke shearing characteristics were obtained.
Nogami, Masanobu*; Kawasaki, Takeshi*; Takao, Koichiro*; Noda, Kyoko*; Sugiyama, Yuichi*; Harada, Masayuki*; Ikeda, Yasuhisa*; Morita, Yasuji; Chikazawa, Takahiro*; Kikuchi, Toshiaki*; et al.
no journal, ,
A reprocessing system for spent FBR fuels based on the two precipitation processes has been proposed. In this system, first only U(VI) species are precipitated using pyrrolidone derivatives (NRP) with low hydrophobicity and donicity, and secondly residual U(VI) and Pu(IV, VI) are precipitated simultaneously using pyrrolidone derivative with high precipitation ability. In order to develop such a reprocessing method, behavior of uranyl ions in HNO
has been studied using various novel NRP. In this presentation, recent advances on precipitation behavior and of uranyl ions and calcination of U(VI)-NRP will be introduced.
Kim, S.-Y.; Kawata, Yoshihisa; Morita, Yasuji; Nogami, Masanobu*; Harada, Masayuki*; Ikeda, Yasuhisa*; Kikuchi, Toshiaki*; Nishimura, Kenji*
no journal, ,
A reprocessing system for spent FBR fuels based on the two precipitation processes has been proposed. In this system, first only U(VI) species are precipitated using pyrrolidone derivatives (NRP) with low hydrophobicity and donicity, and secondly residual U(VI) and Pu(IV, VI) are precipitated simultaneously using pyrrolidone derivative with high precipitation ability. It is important to control precipitation of Pu(IV), and recent advances on precipitation behavior of Pu(IV, VI) by using novel pyrrolidone derivatives will be introduced in this presentation. Precipitation tests using mixed solutions of U(VI) and Pu(IV) showed that N-n-butyl-2-pyrrolidone (NBP) is the most appropriate precipitant for the first precipitation step and N-neopenthyl-2-pyrrolidone (NNpP) is the most appropriate precipitant for the second step.
Kaji, Naoya; Nomura, Kazunori; Sano, Yuichi; Koizumi, Tsutomu
no journal, ,
Advanced aqueous reprocessing is the technology that JAEA is developing as a part of Fast Reactor Cycle Technology Development Project (FaCT). Radioactive liquid waste polarization is one of the concepts introduced to the advanced aqueous reprocessing. In this concept, waste solutions are to be concentrated enough to just be divided to two categories of high level and very low level. It will be achieved by decreasing amount of sodium salt waste drastically and decomposing excess nitric acid. One of the main sources of sodium salt waste in the conventional PUREX is the solvent washing process with sodium carbonate. Salt-free technology brings alternative solvent washing method that does not produce the sodium salt waste. The outline and the current status of the development of this technology will be reported.
Koizumi, Tsutomu; Kitajima, Takafumi; Nomura, Kazunori; Kitawaki, Shinichi
no journal, ,
Chemical Processing Facility (CPF) is the facility for the hot experiment. This facility has the cells where irradiated fast reactor fuel can be treated and globeboxes and foods where plutonium and uranium can be treated. The demonstration experiments of the conventional PUREX reprocessing process with fast reactor fuel there from 1982. After that, renovation of CPF was carried out until 2002. From then, the development of the advanced aqueous reprocessing process such as dissolution with high HM concentration, crystallization of U, MA separation and direct extraction using supercritical fluid has been carried out. the development of metal electrorefining process has been carried out, too. The outcomes of the development is used as the fundamental data for fact reactor cycle technology development project (FaCT).
Sasa, Toshinobu; Nishihara, Kenji; Sugawara, Takanori; Oigawa, Hiroyuki
no journal, ,
The managements of recycled actinides and radiological wastes are important issues for sustainable energy production by nuclear power. To solve these problems, the impact and effectiveness of partitioning and transmutation technologies becomes more obvious through the latest studies at JAEA. By the introduction of dedicated minor actinide burnup cycle to power reactor fuel cycle, enhancement of waste disposal capacity and improvement of power reactor economics can be achieved concurrently. At the presentation, current status for waste disposal scenario study using accelerator-driven systems, future plan of J-PARC Transmutation Experimental Facility, and activities at Asian ADS Network initiative will be described.
Matsumura, Tatsuro; Inaba, Yusuke*; Takeshita, Kenji*; Mori, Atsunori*
no journal, ,
no abstracts in English
Surugaya, Naoki; Kitagawa, Osamu; Kurosawa, Akira; Hiyama, Toshiaki
no journal, ,
Analytical activities handling radioactive materials involve quite tedious procedures, and require highly skilled operators for obtaining reliable results with a high degree of accuracy. Therefore, analytical performance depend much on human ability. In order to maintain human resources at higher level, education and personnel training should be conducted by proper measures based on a system. At TRP, skill test in a laboratory authorization system was established for the engineers of the analytical laboratory, and has been implemented for several years. According to the levels of the required skill, the engineers are trained and educated to obtain the license in the system. Persons who desire to acquire more practical techniques or skills by carrying out on-the-job training are examined in the system. This experience has been confirmed by exercises done in the currently operating TRP. This paper presents our analytical activities and training program we have applied over recent years.
Morita, Yasuji; Asakura, Toshihide; Sasaki, Yuji; Kitatsuji, Yoshihiro; Kimura, Takaumi
no journal, ,
A counter-current extraction test with TDdDGA, N,N,N',N'-tetradodecyl-diglycolamide, was performed using a mixer-settler equipment for the development of the separation process for transuranium elements. TDdDGA has a high extraction capacity and suppresses to form the third phase with extracted elements. In this experiment, the feed solution as simulated HLLW contained four elements, Sr, Pd, Zr and Nd. The results of the counter-current test showed that Nd was extracted in a high yield of more than 99.96% and the extracted Nd was recovered from the solvent by 0.2 M nitric acid also in a high yield. Other three elements were not extracted and therefore separated from Nd. The ratio of Pd and Sr found in Nd fraction was 0.4% and less than 0.07%, respectively.
Miura, Yasushi; Fukuhara, Junichi
no journal, ,
Kitagaki, Toru; Tasaka, Masayuki; Washiya, Tadahiro; Kobayashi, Tsuguyuki
no journal, ,
JAEA has been developing a reliable disassembly system for FBR fuel reprocessing as a part of Fast Reactor Cycle Technology Development (FaCT). We fabricated a testing machine of disassembly system. In this poster, we described design of this device.
Tayama, Toshimitsu; Nakamura, Kazuhito; Washiya, Tadahiro; Yano, Kimihiko; Shibata, Atsuhiro; Nomura, Kazunori; Chikazawa, Takahiro*; Kikuchi, Toshiaki*
no journal, ,
no abstracts in English
Momose, Takumaro; Endo, Kuniaki; Ito, Yasuhisa; Yamashita, Tomoyuki; Namiki, Atsushi; Sanada, Yukihisa; Akiyama, Kiyomitsu; Takeishi, Minoru; Tago, Itaru; Furuta, Sadaaki
no journal, ,
The first reprocessing pilot plant in Japan (Tokai Reprocessing Plant; TRP) has been operated since 1977 at Nuclear Fuel Cycle Engineering Laboratories, JAEA. General radiation protection in TRP is performed with continuous monitoring and sampling methods. The continuous monitors measuring 
-ray, neutron, particulate alpha and beta nuclides in the air are installed in the radiation controlled area as a central monitoring system to prevent from unnecessary exposure. Air and water effluents from the TRP are also monitored by continuous monitors or sampling methods to comply with regulations. In addition to this, environmental monitoring has been carried out to assess influences on public and environment by the plant operation. A feature of radiation protection and its recent relevant researches at TRP will be introduced in this presentation.
Watanabe, So; Sano, Yuichi; Goto, Ichiro; Koma, Yoshikazu
no journal, ,
no abstracts in English