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Marufuji, Takato; Sato, Takumi; Ito, Hideaki; Suzuki, Hisashi; Fujishima, Tadatsune; Nakano, Tomoyuki
JAEA-Technology 2019-006, 22 Pages, 2019/05
JAEA-Technology-2019-006.pdf:2.84MB
Radioactive contamination incident occurred at Plutonium Fuel Research Facility (PFRF) in Oarai Research and Development Institute, Japan Atomic Energy Agency on June 6, 2017. During inspection work of storage container containing nuclear fuel materials, the PVC bag packaging in the storage container ruptured when a worker opened the lid in the hood, and a part of contents was spattered over the room. The cause of the increase of internal pressure of the storage container was gas generation by alpha radiolysis of the epoxy resin mixed with nuclear fuel materials. Opening inspection of about 70 similar containers stored in PFRF has been planned to confirm the condition of the contents and to stabilize the stored materials containing organic compounds. For safe and reliable open inspection of the storage containers with high internal pressure in the glove box, it is necessary to develop a pressure-resistant chamber in which the storage containers are opened and the contents are inspected under gastight condition. This report summarizes the concerns and countermeasures of the chamber design and the design results of the chamber.
Kasahara, Seiji; Imai, Yoshiyuki; Suzuki, Koichi*; Iwatsuki, Jin; Terada, Atsuhiko; Yan, X.
Nuclear Engineering and Design, 329, p.213 - 222, 2018/04
Times Cited Count：21 Percentile：90.78(Nuclear Science & Technology)A conceptual design of a practical large scale plant of the thermochemical water splitting iodine-sulfur (IS) process flowsheet was carried out as a heat application of JAEA's commercial high temperature gas cooled reactor GTHTR300C plant design. Innovative techniques proposed by JAEA were applied for improvement of hydrogen production thermal efficiency; depressurized flash concentration H
SO
using waste heat from Bunsen reaction, prevention of HSO vaporization from a distillation column by introduction of HSO solution from a flash bottom, and I condensation heat recovery in an HI distillation column. Hydrogen of about 31,900 Nm
/h would be produced by 170 MW heat from the GTHTR300C. A thermal efficiency of 50.2% would be achievable with incorporation of the innovative techniques and high performance HI concentration and decomposition components and heat exchangers expected in future R&D.
Adachi, Junichi*; Kaminaga, Masanori; Sasaki, Shinobu; Haga, Katsuhiro; Aso, Tomokazu; Kinoshita, Hidetaka; Hino, Ryutaro
JAERI-Tech 2001-093, 108 Pages, 2002/01
JAERI-Tech-2001-093.pdf:7.49MB
In designing of the neutron scattering facility, a spent target vessel should be replaced with remote handling devices in order to protect radioactive exposure, since it would be highly. In the storage of the spent target vessel, it is necessary to consider decay heat of the target vessel and mercury contamination caused by vaporization of the residual mercury in the vessel. A conceptual design has been carried out to establish basic concept and to clarify its specification of main equipments on a handling and storage system for the spent target vessel. This report presents the basic concept and a system plot plan based on latest design works of remote handling devices, which aim at reasonability and simplification.
Kaminaga, Masanori; Haga, Katsuhiro; Aso, Tomokazu; Kinoshita, Hidetaka; Kogawa, Hiroyuki; Ishikura, Shuichi*; Terada, Atsuhiko*; Kobayashi, Kaoru*; Adachi, Junichi*; Teraoku, Takuji*; et al.
Proceedings of American Nuclear Society Conference "Nuclear Applications in the New Millennium" (AccApp-ADTTA '01) (CD-ROM), 9 Pages, 2002/00
no abstracts in English
Enoeda, Mikio; Ohara, Yoshihiro; Akiba, Masato; Sato, Satoshi; Hatano, Toshihisa; Kosaku, Yasuo; Kuroda, Toshimasa*; Kikuchi, Shigeto*; Yanagi, Yoshihiko*; Konishi, Satoshi; et al.
JAERI-Tech 2001-078, 120 Pages, 2001/12
This report is a summary of the design works, which was discussed in the design workshop held in 2000 for the demonstration (DEMO) blanket aimed to strengthen the commercial competitiveness and technical feasibility simultaneously. The DEMO blanket must supply the feasibility and experience of the total design of the power plant and the materials. This conceptual design study was performed to determine the updated strategy and goal of the R&D of the DEMO blanket which applies the supercritical water cooling proposed in A-SSTR, taking into account the recent progress of the plasma research and reactor engineering technology.
Kusunoki, Tsuyoshi; Takahashi, Teruo*; Nishimura, Hajime*; Tokunaga, Sango*; Odano, Naoteru; Yoritsune, Tsutomu; Ishida, Toshihisa
JAERI-Tech 2001-045, 68 Pages, 2001/07
JAERI-Tech-2001-045.pdf:5.33MB
A concept of a submersible research vessel navigating in 600 m depth and a compact nuclear reactor were carried out for the expansion of the nuclear power utilization. The mission of the vessel is the research of mechanism of the climate change. Through conditions of the Arctic Ocean and the sea at high latitude have significant impacts on the global environmental change, it is difficult to investigate those areas by ordinary ships because of thick ice or storm. By taking account of the research mission, the basic specifications of the vessel are decided; the total weight is 500 t, the submersible depth is 600 m, the maximum speed is 12 knots (22.2km/h), and the number of crews is 16. Nuclear power has an advantage in supplying large power of electricity in the sea for long period. Based on the requirements, it has been decided that two sets of compact nuclear reactor, SCR, which is light-weighted and of enhanced safety characteristics to supply the total electricity of 500 kW.
Kugo, Teruhiko
Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications, p.821 - 826, 2001/00
no abstracts in English
Minehara, Eisuke; Sawamura, Masaru; Nagai, Ryoji; Kikuzawa, Nobuhiro; Sugimoto, Masayoshi; Hajima, Ryoichi; Shizuma, Toshiyuki; Yamauchi, Toshihiko; Nishimori, Nobuyuki
Nuclear Instruments and Methods in Physics Research A, 445(1-3), p.183 - 186, 2000/05
Times Cited Count：18 Percentile：73.64(Instruments & Instrumentation)no abstracts in English
Kugo, Teruhiko; Tsuchihashi, Keiichiro*; Nakakawa, Masayuki; Ido, Masaru*
JAERI-Data/Code 2000-011, p.138 - 0, 2000/02
JAERI-Data-Code-2000-011.pdf:7.41MB
no abstracts in English
Murao, Yoshio; Ochiai, Masaaki
Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 2, p.1075 - 1085, 1997/00
no abstracts in English
Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Enginering (ICONE), Vol. 2, 0, p.723 - 728, 1995/00
no abstracts in English
Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke
Transactions of the American Nuclear Society, 71, p.527 - 529, 1995/00
no abstracts in English
Kugo, Teruhiko; Nakakawa, Masayuki
Transactions of the American Nuclear Society, 73, p.207 - 208, 1995/00
no abstracts in English
Kugo, Teruhiko; Fujii, Sadao*; Nakakawa, Masayuki
JAERI-Data/Code 94-001, 187 Pages, 1994/08
JAERI-Data-Code-94-001.pdf:7.51MB
no abstracts in English
Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke
10th Proc. of Nuclear Thermal Hydraulics, 0, p.3 - 12, 1994/00
no abstracts in English
Uchiyama, Gunzo; Maeda, Mitsuru; Fujine, Sachio; *; *
JAERI-M 93-213, 204 Pages, 1993/10
no abstracts in English
JAERI-M 90-090, 94 Pages, 1990/06
no abstracts in English
JAERI-M 89-208, 322 Pages, 1989/12
no abstracts in English
Yamamoto, Shin; Ohara, Yoshihiro; Tani, Keiji; Nishio, Satoshi; Okumura, Yoshikazu; Araki, Masanori; Azumi, Masafumi; R.S.Devoto*; Fujisawa, Noboru; Hitoki, Shigehisa*; et al.
JAERI-M 88-086, 183 Pages, 1988/05
no abstracts in English
Nakajima, Kunihiko*; *; *
JAERI-M 87-154, 106 Pages, 1987/09
no abstracts in English
; Tone, Tatsuzo; *; *
JAERI-M 87-021, 272 Pages, 1987/02
no abstracts in English
