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Journal Articles

Concepts and basic designs of various nuclear fuels, 5; Fuels for high temperature gas-cooled reactor and molten salt reactor

Ueta, Shohei; Sasaki, Koei; Arita, Yuji*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 63(8), p.615 - 620, 2021/08

no abstracts in English

Journal Articles

Four-point-bend tests on high-burnup advanced fuel cladding tubes after exposure to simulated LOCA conditions

Narukawa, Takafumi; Amaya, Masaki

Journal of Nuclear Science and Technology, 57(7), p.782 - 791, 2020/07

 Times Cited Count:2 Percentile:62.87(Nuclear Science & Technology)

Journal Articles

Fracture limit of high-burnup advanced fuel cladding tubes under loss-of-coolant accident conditions

Narukawa, Takafumi; Amaya, Masaki

Journal of Nuclear Science and Technology, 57(1), p.68 - 78, 2020/01

 Times Cited Count:1 Percentile:23.13(Nuclear Science & Technology)

Journal Articles

Behavior of high-burnup advanced LWR fuel cladding tubes under LOCA conditions

Narukawa, Takafumi; Amaya, Masaki

Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.912 - 921, 2019/09

Journal Articles

Oxidation behavior of high-burnup advanced fuel cladding tubes in high-temperature steam

Narukawa, Takafumi; Amaya, Masaki

Journal of Nuclear Science and Technology, 56(7), p.650 - 660, 2019/07

 Times Cited Count:6 Percentile:81.33(Nuclear Science & Technology)

Journal Articles

Behavior of high-burnup advanced LWR fuels under design-basis accident conditions

Amaya, Masaki; Udagawa, Yutaka; Narukawa, Takafumi; Mihara, Takeshi; Taniguchi, Yoshinori

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09

Journal Articles

Physical property model for advanced oxide fuels

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$$_{2}$$, (U,Ce,)O$$_{2}$$, PuO$$_{2}$$, CeO$$_{2}$$ 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$$_{2-x}$$ that is based on the experimental database.

Journal Articles

Current status of thermal/hydraulic feasibility project for reduced-moderation water reactor, 2; Development of two-phase flow simulation code with advanced interface tracking method

Yoshida, Hiroyuki; Tamai, Hidesada; Onuki, Akira; Takase, Kazuyuki; Akimoto, Hajime

Nuclear Engineering and Technology, 38(2), p.119 - 128, 2006/04

The reduced-moderation water reactor core adopts a hexagonal tight-lattice arrangement. In the core, there is no sufficient information about the effects of the gap spacing and grid spacer configuration on the flow characteristics. Thus, we start to develop a predictable technology for thermal-hydraulic performance of the core using an advanced numerical simulation technology. As a part of this technology development, we are developing a two-phase flow simulation code TPFIT with an advanced interface tracking method. The vector and parallelization of the code was conducted to fit the large-scale simulations. The numerical results applied to large-scale water-vapor two-phase flow in tight lattice rod bundles are shown and compared with experimental results. In the results, a tendency of the predicted void fraction distribution in horizontal plane agreed with the measured values including the bridge formation of the liquid at the position of adjacent fuel rods where an interval is the narrowest.

Journal Articles

Large-scale direct simulation of two-phase flow structure around a spacer in a tight-lattice nuclear fuel bundle

Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Akimoto, Hajime

Computational Fluid Dynamics 2004, p.649 - 654, 2006/00

no abstracts in English

Journal Articles

Accomplishment of 10-year research in NUCEF and future development; Process safety and development research

Morita, Yasuji; Asakura, Toshihide; Mineo, Hideaki; Hotoku, Shinobu; Uchiyama, Gunzo

JAERI-Conf 2005-007, p.25 - 30, 2005/08

Researches on process safety of reprocessing, development of an advanced reprocessing and partitioning of high-level liquid waste(HLLW) have been conducted in NUCEF - BECKY (Back-end Fuel Cycle Key Elements Research Facility), which has alpha-gamma concrete cells and many glove-boxes. This paper presents 10 year accomplishment of the above researches and future activities to be conducted in the field of separation process development.

Journal Articles

Predicted two-phase flow structure in a fuel bundle of an advanced light-water reactor

Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Tamai, Hidesada

Proceedings of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations and Safety (NUTHOS-6) (CD-ROM), 14 Pages, 2004/10

no abstracts in English

JAEA Reports

Nuclear Energy System Department annual report

Department of Nuclear Energy System

JAERI-Review 2003-004, 236 Pages, 2003/03

JAERI-Review-2003-004.pdf:16.34MB

This report summarizes the research and development activities in the Department of Nuclear Energy System during the fiscal year of 2001 (April 1, 2001 - March 31, 2002). The Department has been organized from April 1998. The main research activity is aimed to build the basis of the development of future nuclear energy systems. The research activities of the Department cover basic nuclear data evaluation, conceptual design of a reduced-moderation water reactor, reactor physics experiments and development of the reactor analysis codes, experiment and analysis of thermal-hydrodynamics, energy system analysis and assessment, development of advanced materials for a reactor, lifetime reliability assessment on structural material, development of advanced nuclear fuel, design of a marine reactor and the research for a nuclear ship system. The maintenance and operation of reactor engineering facilities belonging to the Department are undertaken. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report.

JAEA Reports

Nuclear Energy System Department annual report; April 1, 2000 - March 31, 2001

Department of Nuclear Energy System

JAERI-Review 2002-005, 280 Pages, 2002/03

JAERI-Review-2002-005.pdf:18.05MB

no abstracts in English

JAEA Reports

Study on high-performance fuel cladding materials; Joint research report in FY 1999-2000 (Phase 1) (Joint research)

Kiuchi, Kiyoshi; Ioka, Ikuo; Tachibana, Katsumi; Suzuki, Tomio; Fukaya, Kiyoshi*; Inohara, Yasuto*; Kambara, Shozo; Kuroda, Yuji*; Miyamoto, Satoshi*; Ogura, Kazutomo*

JAERI-Research 2002-008, 63 Pages, 2002/03

JAERI-Research-2002-008.pdf:7.85MB

no abstracts in English

JAEA Reports

Nuclear Energy System Department annual report; April 1, 1999 - March 31, 2000

Department of Nuclear Energy System

JAERI-Review 2001-010, 322 Pages, 2001/03

JAERI-Review-2001-010.pdf:27.21MB

no abstracts in English

JAEA Reports

Nuclear Energy System Department annual report; April 1, 1998 - March 31, 1999

Department of Nuclear Energy System

JAERI-Review 99-031, p.320 - 0, 2000/01

JAERI-Review-99-031.pdf:16.21MB

no abstracts in English

JAEA Reports

Outline of research proposals selected in the Nuclear Energy Research Initiative (NERI) program

Iwamura, Takamichi; Okubo, Tsutomu; Usui, Shuji*; Shimada, Shoichiro*; Nabeshima, Kunihiko; *; Kakuta, Tsunemi; Ishikawa, Nobuyuki; Suzudo, Tomoaki; Nakatsuka, Toru; et al.

JAERI-Review 99-017, 60 Pages, 1999/08

JAERI-Review-99-017.pdf:2.94MB

no abstracts in English

JAEA Reports

Journal Articles

Current status of the NUCEF project

Takeshita, Isao

Genshiryoku Shisutemu Nyusu, 7(4), p.30 - 36, 1997/03

no abstracts in English

29 (Records 1-20 displayed on this page)