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Cappia, F.*; Tanaka, Kosuke; Kato, Masato; McClellan, K.*; Harp, J.*
Journal of Nuclear Materials, 533, p.152076_1 - 152076_14, 2020/05
Times Cited Count：6 Percentile：60.71(Materials Science, Multidisciplinary)Kato, Masato; McClellan, K.*
Transactions of the American Nuclear Society, 113(1), p.613 - 614, 2015/10
A joint study on advanced oxide fuels is being carried out under the Civil Nuclear Energy Working Group (CNWG) bilateral collaboration between the U.S. Department of Energy and the Japan Atomic Energy Agency. The main goal of this study is to support development and validation of a science-based fuel analysis code for minor actinide (MA) bearing MOX fuel. In analysis and evaluation of fuel performance, it is essential to understand the physical properties of the advanced oxide fuels. Therefore, we are investigating physical properties of (U,Pu)O
, (U,Ce,)O, PuO, CeO and other related compounds to prepare a physical property database and to construct an integrated mechanistic physical property model. In this paper, we describe the derivation of a model to represent heat capacity and thermal conductivity of (U,Pu)O
that is based on the experimental database.
Yui, Mikazu; Ishikawa, Hirohisa; Watanabe, Atsuo*; Yoshino, Kyoji*; Umeki, Hiroyuki; Hioki, Kazumasa; Naito, Morimasa; Seo, Toshihiro; Makino, Hitoshi; Oda, Chie; et al.
JAEA-Research 2010-015, 106 Pages, 2010/05
JAEA-Research-2010-015.pdf:13.58MB
This report summarizes the activity of Phase I of Waste Management Working Group of the United States - Japan Joint Nuclear Energy Action Plan started in 2007. The working group focused on consolidation of the existing technical basis between the U.S. and Japan and the joint development of a plan for future collaborative activities. Firstly, the political/regulatory frameworks related to nuclear fuel cycles in both countries were reviewed. The various advanced fuel cycle scenarios in both countries were surveyed and summarized. Secondly, the waste management/disposal system optimization was discussed. Repository system concepts for the various classifications of nuclear waste were reviewed and summarized, then disposal system optimization processes and techniques were reviewed, and factors to consider in future repository design optimization activities were also discussed. Finally the potential collaboration areas and activities related to the optimization problem were extracted.
Sumi, Mika; Kageyama, Tomio; Suzuki, Toru; Manson, P.*; Neuhoff, J.*
Proceedings of INMM 47th Annual Meeting (CD-ROM), 7 Pages, 2006/00
All accountancy analyses at the Plutonium Fuel Development Center (PFDC) of JAEA are performed by isotope dilution mass spectrometry (IDMS) with well-characterized standard materials, which prepared at PFDC itself from Pu and U reference materials. Currently, Pu reference materials must be obtained from foreign suppliers because there are no facilities in Japan with the capability for preparation and supply of Pu reference materials, and, importing those Pu reference materials is gradually becoming more difficult. Therefore, JAEA has started collaborative work with NBL for the preparation of Pu reference materials and associated Large Size Dried (LSD) spike. MOX powder which has been stored in JAEA was dissolved and ion-exchange was performed to obtain purified Pu solution at JAEA. Several aliquots had taken from the solution, dried, and sent to NBL for analysis. Pu samples were shipped and have arrived to NBL. After certification analysis on NBL, the Pu nitrate solution will be mixed with a U nitrate solution which prepared from CRMs. The uncertainty of the purified Pu solution and prepared LSD spikes will be evaluated by GUM method. This paper presents the present status and future plans for the collaboration work.
Sink, C.*; Sakaba, Nariaki; Yvon, P.*; Shin, Y.-J.*; Dominguez, M. T.*; Suppiah, S.*
no journal, ,
On going R&D of hydrogen production project for the very high-temperature reactors at the Generation IV international forum is described.
Hori, Keiichiro; Heinberg, C.; Conner, J.*; Browne, M.*; Colin, C.*
no journal, ,
At the time of accident, about 270 tons of fuel were in Units 1- 3 at Fukushima Daiichi Nuclear Power Station. Up to that time, material accountancy was implemented as an item facility for adequate material control and for the International Atomic Energy Agency's safeguards verification. Fuel debris contains nuclear fuel materials, fission products and structural materials, etc. Fuel debris will need to be controlled adequately after removal from the reactors, but material accountancy measures as an item facility no longer can be applied because of meltdown of the fuel. Development of measurement technologies for fuel debris may be required for adequate material control and accountancy of special nuclear material in the fuel debris at Fukushima Daiichi. Japan Atomic Energy Agency (JAEA) and United States Department of Energy/National Nuclear Security Administration (DOE/NNSA) have agreed to collaborate to investigate past experience on material control at severe accidents involving reactor core fuels and potential measurement technologies for fuel debris measurement. Besides DOE/NNSA and JAEA, Japanese Government, Tokyo Electric Power Company (TEPCO), Central Research Institute of Electric Power Industry (CRIEPI) and the U.S. National Laboratories have been collaborating in this effort. This paper describes the purpose, objectives, structure and process of this collaboration.
O meltsSakamura, Yoshiharu*; Iizuka, Masatoshi*; Kofuji, Hirohide
no journal, ,
no abstracts in English
Sugita, Yutaka; Ono, Hirokazu; Beese, S.*; Pan, P.*; Kim, M.*; Lee, C.*; Jove-Colon, C.*; M Lopez, C.*; Liang, S.-Y.*
no journal, ,
This paper presents the results of analytical simulations of in-situ test of engineered barriers system conducted at the Horonobe Underground Research Laboratory. This results is one of the tasks of the current phase "DECOVALEX-2023" of the international joint project DECOVALEX in which JAEA participates. Research teams from 6 countries or region, including JAEA, are participating in this task, Different analytical approaches and their effects on the analytical results are introduced, as well as the factors that affect the evaluation of coupled phenomena in engineered barrier system obtained through the task.
