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Shibata, Yuichi
Genshiryoku eye, 57(6), p.60 - 63, 2011/06
Plutonium-contaminated solid wastes have been generated during MOX fuel fabrication in the Japan Atomic Energy Agency (JAEA). Chlorine contained solid wastes such as PVC bags and chloroprene rubber gloves have been steadily generated because MOX fuel fabrication equipments are installed in glove boxes. Incinerations of chlorinated wastes cause the problems such as corrosion of the equipments and dust load against the exhaust system. The JAEA had designed and manufactured a new type incineration system for chlorine contained wastes and combustible wastes based on past experience gained by the operation of the Plutonium contaminated Waste Treatment Facility (PWTF) to solve the problems.
Takashima, Hideki; Takasaki, Koji; Shimizu, Takehiko; Kurihara, Ryoichi
Genshiryoku eye, 57(5), p.72 - 76, 2011/05
no abstracts in English
Natsume, Tomohiro*; Nakano, Makoto*; Harada, Akio; Yamanaka, Atsushi; Kurihara, Ryoichi
Genshiryoku eye, 57(4), p.72 - 76, 2011/04
no abstracts in English
Oigawa, Hiroyuki
Genshiryoku eye, 57(3), p.52 - 56, 2011/03
As one of the options for nuclear transmutation technology aiming at the reduction of the burden for disposal of high-level radioactive waste, research and development on Accelerator Driven System (ADS) is being vigorously promoted in Europe. From 2005 to 2010, wide range of research and development including design study, physics experiment, fuel, material and nuclear data were conducted in the EUROTRANS project, and a design of an experimental ADS was proposed. In accordance with this movement, the MYRRHA project, which is an experimental ADS in Belgium, is under way aiming for the start of construction in 2016. In Japan, there is a plan to build a Transmutation Experimental Facility (TEF) as Phase-2 of the J-PARC project. It is of importance to promote the collaboration between MYRRHA and TEF and to lead the world-wide research and development to realize the ADS for nuclear transmutation.
Kurihara, Ryoichi; Nakano, Junichi; Abe, Sadayoshi
Genshiryoku eye, 57(3), p.71 - 76, 2011/03
no abstracts in English
Deshimaru, Takehide
Genshiryoku eye, 57(3), p.30 - 35, 2011/03
The prototype fast breeder reactor (FBR) MONJU resumed the system startup test (SST) on May 6th 2010 after five months and fourteen years shutdown since the sodium leakage of the secondary heat transport system on December 1995. Core confirmation test (CCT) is the first step of SST which consists of three steps, and finished on July 22nd after 78 days test. CCT is composed 20 test items including confirmation of the safety criteria and measurement of several core performance data. Through CCT, were demonstrated the stable operation and the accuracy of the prediction on the core performance after long-term shutdown and refueling. The several core physics characteristic data especially by accumulated minor actinide americium-241 will be contributed to the research and development of FBR. And the operation and maintenance experiences gained in CCT are also very variable to development next FBR power plant.
Tanimura, Yoshihiko
Genshiryoku eye, 57(2), p.37 - 40, 2011/02
Ten mono-energetic neutron irradiation fields have been developed at the Facility of Radiation Standards in Nuclear Science Research Institute. In these fields, mono-energetic neutrons can be stably generated over a wide energy range with five digits from 8 keV to 19 MeV using an accelerator and they are used for the performance test of the neutron detectors.
Sasaki, Satoru; Suzuki, Soju; Nakano, Junichi; Takamatsu, Misao; Matoba, Ichiyo*; Nakano, Makoto*; Oketani, Koichiro*; Natsume, Tomohiro*
Genshiryoku eye, 57(2), p.66 - 75, 2011/02
no abstracts in English
Tsukada, Takashi
Genshiryoku eye, 57(1), p.13 - 16, 2011/01
no abstracts in English
Uchida, Shunsuke
Genshiryoku eye, 57(1), p.5 - 8, 2011/01
no abstracts in English
Sasaki, Satoru; Suto, Toshiyuki; Harada, Akio; Kurihara, Ryoichi; Yamamoto, Kazuyoshi; Tsuchida, Noboru; Shimizu, Isamu; Nomura, Toshibumi
Genshiryoku eye, 57(1), p.66 - 75, 2011/01
no abstracts in English
Sasaki, Satoru; Suto, Toshiyuki; Yamamoto, Kazuyoshi
Genshiryoku eye, 56(12), p.66 - 73, 2010/12
no abstracts in English
Koyama, Shinichi
Genshiryoku eye, 56(10), p.16 - 18, 2010/10
Current status for utilization technology of separated nuclides from a spent fuel is described. Firstly, utilization of middle life fission product (Cs, Sr) as a heat source separated by nano absorber is introduced. Secondary, platinum group metals are separated from spent fuel by electrochemical method, and then development of hydrogen production technique by using its electrode is introduced.
Ozawa, Masaki
Genshiryoku eye, 56(10), p.7 - 11, 2010/10
On the Advanced ORIENT Cycle research, fundamental properties of nuclear rare metals are described as an incentive of the study, and R&D strategies and tactics are summarized for realizing the concept.
Yamanaka, Atsushi
Genshiryoku eye, 56(9), p.66 - 67, 2010/09
no abstracts in English
Nagura, Fuminori; Ichimiya, Masakazu; Sagayama, Yutaka
Genshiryoku eye, 56(6), p.20 - 23, 2010/06
As for Japan because it is energy security guaranty and the like, Japan continued the research and development of FBR ("Joyo", "Monju") and fuel cycle. In recent years, there are a growing interest in the long-term energy security and terrestrial environmental problem. And FBR cycle has again been observed, by the development of young country and the like. This year, reactor operation was reopened after about 14 years, "Monju" is the only prototype FBR reactor which it works as the Western Worlds, and the result of these research and developments is expected even worldwide. JAEA is carrying on international cooperation of "JAEA-CEA", "JAEA-DOE", GIF, IAEA, for the points of view "The efficient development", "Decrease of development risk", "Establishment of worldwide standard technology", "Monju" establishes to the position as base of international research and development, and JAEA makes the best endeavors to "Monju" carrying out worldwide contribution.
Kuno, Yusuke
Genshiryoku eye, 56(5), p.72 - 76, 2010/05
Nuclear proliferation measures to be considered for future nuclear fuel cycle should include 3 key components, Safeguards, nuclear security, and physical protection. However, internationalization of nuclear fuel cycle, as the fourth component, would be the ultimate measure. This paper discuss the relation among those 4 elements and future direction of effective nuclear non-proliferation measure.
Naoi, Yosuke; Kobayashi, Naoki*; Wakabayashi, Shuji; Tazaki, Makiko
Genshiryoku eye, 56(4), p.50 - 53, 2010/04
Japanese Government proposed "IAEA Standby Arrangements System (INFCIRC/683)" for assurance of nuclear fuel supply (AOS). We studied on main issues in AOS system and on the solutions which could work practically.
Sato, Koji
Genshiryoku eye, 56(3), p.20 - 25, 2010/03
International Conference on "Fast Reactors and Related Fuel Cycles; Challenges and Opportunities" (FR09) organized by the IAEA and hosted by the JAEA was held on December 2009 in Kyoto and Tsuruga. The conference is summarized in this report.
Naoi, Yosuke; Kobayashi, Naoki*; Wakabayashi, Shuji; Tazaki, Makiko
Genshiryoku eye, 56(3), p.33 - 37, 2010/03
Japanese Government proposed "IAEA Standby Arrangements System (INFCIRC/683)" for assurance of nuclear fuel supply (AOS). We focused and based our study on Japan's proposal. We have been able to show feasibility of AOS system more specifically by supposing additional costs and the required period necessary for AOS and present a system which could work practically.
