Japan
Construction of the HTTR and its testing programme for advanced HTGR development
Tanaka, T.; Baba, O.; Shiozawa, S.; Okubo, M.; Kunitomi, K. (Japan Atomic Energy
Research Inst., Ibaraki (Japan). Dept. of HTTR Project)
IAEA-TECDOC--899, pp:15-23
Overview of HTGR utilization system developments at JAERI
Miyamoto, Y.; Shiozawa, S.; Inagaki, Y. (Japan Atomic Energy Research Inst., Oarai, Higashi, Ibaraki (Japan)) (and others)
IAEA-TECDOC--988, pp:47-58
Permanent cessation of Tokai power plant's operation
Satoh, T. (Japan Atomic Power Co., Tokyo (Japan))
IAEA-TECDOC--1043, pp:55-69
Recent activities on the HTGR for its commercialization in the 21st century
Minatsuki, I.; Uchida, S.; Nomura, S.; Yamada, S. (Mitsubishi Heavy Industries Ltd, Tokyo (Japan))
IAEA-TECDOC--988, pp:73-90
Conceptual design of helium gas turbine for MHTGR-GT
Matsuo, E.; Tsutsumi, M.; Ogata, K. (Mitsubishi Heavy Industries Ltd., Nagasaki (Japan). Nagasaki Research and Development Center); Nomura, S. (Mitsubishi Heavy Industries Ltd., Nagasaki (Japan). Nagasaki Shipyard and Machinery Works)
IAEA-TECDOC--899, pp:95-109
An introduction to our activities supporting HTGR developments in Japan
An, S.; Hayashi, T.; Tsuchie, Y. (Tokai Univ., Tokyo (Japan))
IAEA-TECDOC--988, pp:101-116
Results of assembly test of HTTR reactor internals
Maruyama, S.; Saikusa, A.; Shiozawa, S. (Japan Atomic Energy Research Inst., Ibaraki (Japan)); Tsuji, N.; Miki, T. (Fuji Electric Co. Ltd., Kawasaki, Kanagawa (Japan))
IAEA-TECDOC--901, pp:105-116
HTGR gas turbine-module demonstration test - A proposal
Takada, E.; Ohashi, K.; Hayakawa, H.; Kawata, O.; Kobayashi, O. (Fuji Electric Co.
Ltd., Kawasaki, Kanagawa (Japan))
IAEA-TECDOC--899, pp:121-127
A study of silver behavior in gas-turbine high temperature gas-cooled reactor
Sawa, K.; Shiozawa, S.; Kunitomi, K.; Tanaka, T. (Japan Atomic Energy Research Inst.,
Ibaraki (Japan). Dept. of HTTR Project)
IAEA-TECDOC--899, pp:131-143
Development of compact heat exchanger with diffusion welding
Kunitomi, K.; Takeda, T. (Japan Atomic Research Inst., Ibaraki (Japan). Dept. of HTTR
Project); Horie, T.; Iwata, K. (Sumitomo Precision Products Co., Ltd., Hyogo (Japan). Heat Exchangers Div.)
IAEA-TECDOC--899, pp:165-176
Study on storage and reprocessing concept of the high
temperature engineering test reactor (HTTR) fuel
Sawa, K.; Yoshimuta, S.; Shiozawa, S.;
Fujikawa, F.; Tanaka, T. (Japan Atomic
Energy Research Inst. (Japan)); Watarumi, K.;
Deushi, K.; Koya, F. (Nuclear Fuel Industries
Ltd, Ibaraki (Japan))
IAEA-TECDOC--1043, pp:177-189
Status of the research and development at JAERI on the C/C composite control rod for HTGR
Eto, M.; Ishiyama, S.; Ugachi, H. (Japan Atomic Energy Research Inst., Ibaraki (Japan))
IAEA-TECDOC--901, pp:205-214
Influence of air oxidation on thermal shock resistances of nuclear carbon materials
Kurumada, A.; Oku, T. (Ibaraki Univ., Hitachi (Japan). Faculty of Engineering); Harada,
K. (Japan Atomic Energy Research Inst., Ibaraki (Japan)); Kawamata, K. (Ibaraki Univ., Ibaraki (Japan). Faculty Engineering); Sato, S. (Iwaki Meisei Univ., Fukushima (Japan)); Hiraoka, T. (Tokyo Tanso Co. Ltd., Kagawa (Japan)); McEnaney, B. (Bath Univ. (United Kingdom). School of Materials Science)
IAEA-TECDOC--901, pp:215-224
An analytical study on porosity changes of nuclear graphites under high temperature irradiations
Arai, T. (Japan Atomic Energy Research Inst.,
Ibaraki (Japan). Dept. of High Temperature
Engineering)
IAEA-TECDOC--901, pp:225-237
Acceptance test for graphite components and construction status of HTTR
Iyoku, T.; Ishihara, M.; Maruyama, S.; Shiozawa, S. (Japan Atomic Energy Research Inst., Ibaraki (Japan)); Tsuji, N.; Miki, T. (Fuji Electric Co. Ltd., Kawasaki, Kanagawa (Japan))
IAEA-TECDOC--901, pp:239-249
Calculation of neutron fluxes and radioactivities in and
around the Tokai-1 reactor pressure vessel
Currie, I.D.; Smith, P.N. (NNC Ltd,
Knutsford (United Kingdom)); Shirakawa, M.
(Fuji Electric Co., Ltd, Tokyo (Japan));
Yamamoto, T. (Japan Atomic Power Co. (Japan))
IAEA-TECDOC--1043, pp:239-256
Effect of compressive prestress on the Young's modulus and strength of isotropic graphite
Oku, T.; Ota, S. (Ibaraki Univ., Hitachi (Japan).
Faculty of Engineering); Shiraishi, M. (National
Inst. for Pollution and Resources, Ibaraki (Japan));
Eto, M. (Japan Atomic Energy Research Inst.,
Ibaraki (Japan)); Gotoh, Y. (Hitachi Research
Lab., Hitachi (Japan))
IAEA-TECDOC--901, pp:275-285
Preliminary study on application of eddy current testing as monitoring technique for graphite components
in HTTR
Ishihara, M.; Iyoku, T. (Japan Atomic Energy
Research Inst., Oarai, Ibaraki (Japan). Oarai
Research Establishment)
IAEA-TECDOC--901, pp:287-298
Material and fabrication of the HTTR reactor pressure vessel
Tachibana, Y.; Kunitomi, K.; Shiozawa, S. (Japan Atomic Energy Research Isnt., Oarai, Ibaraki (Japan)); Asami, T.; Yamaguchi, S. (Babcock-Hitachi K.K., Hiroshima (Japan))
IAEA-TECDOC--988, pp:305-318
Characteristics of HTTR's startup physics tests
Nojiri, N.; Nakano, M.; Takeuchi, M.; Pohl, P.; Yamashita, K. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan))
IAEA-TECDOC--988, pp:333-343
Study of a high temperature gas cooled reactor heat utilization plant
Ide, A.; Hayakawa, H.; Yasuno, T. (HTR Heat Utilization Core Group, FAPIG, The First Power Industry Group (Japan)) (and others)
IAEA-TECDOC--988, pp:345-357
Test programmes of HTTR for future generation HTGRs
Kunitomi, K.; Tachibana, Y.; Takeda, T.; Saikusa, A.; Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan))
IAEA-TECDOC--988, pp:359-371
Present status of initial core fuel fabrication for the HTTR
Kitamura, N.; Watarumi, K.; Sato, K. (Nuclear Fuel Industries Ltd, Naka, Ibaraki (Japan));
Sawa, K.; Shiozawa, S.; Tanaka, T. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan)
IAEA-TECDOC--988, pp:373-383
Preliminary study on the development of an in-service inspection technique for graphite components in the HTTR
Ishihara, M.; Hanawa, S.; Furusawa, T.; Aihara, J.; Tachibana, Y. (Japan Atomic Energy
Research Inst., Oarai, Ibaraki (Japan))
IAEA-TECDOC--988, pp:443-452
Post-irradiation heating tests of ZrC coated fuel particles
Minato, K.; Ogawa, T.; Fukuda, K.; Sekino, H.; Takahashi, I. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan))
IAEA-TECDOC--988, pp:453-463
GTHTR300 System Design Features and Performance
X. Yan, K. Kunitomi, T. Nakata and S. Shiozawa, Japan Atomic Energy research Institute, Japan
HTR-2002, pp:1-7
Present Status Of HTTR Project
N. Fujimoto, S.Fujikawa, H. Hayashi, T. Nakazawa, T. Iyoku and K. Kawasaki, Dept. of HTTR Project, Japan Atomic Energy Research Institute, Ibaraki, JAPAN
HTR-2004, pp:1-8
GTHTR300C For Hydrogen Cogeneration, Kazuhiko KUNITOMI
Kazuhiko Kunitomi, Xing Yan, Shusaku Shiozawa, Nozomu Fujimoto, Dept. of Advanced Nuclear Heat Technology, JAERI, Ibaraki-ken, JAPAN
HTR-2004, pp:1-11
Present status of the HTTR project at JAERI
Saito, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Dept. of HTTR
Project)
IAEA-TECDOC--761, pp:11-19
Overview of current research and development programmes for
fuel in Japan
Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai,
Ibaraki (Japan). Oarai Research Establishment)
IWGGCR--25, pp:19-21
Experimental study on structural integrity of oxidized support post for HTTR
Ishihara, M.; Iyoku, T.; Shiozawa, S. (Japan Atomic Energy Research Inst., Tokai, Ibaraki
(Japan). Tokai Research Establishment); Miki, T. (Fuji Electric Co. Ltd., Tokyo (Japan)); Takikawa, N. (Kawasaki Heavy Industries Ltd, Tokyo (Japan))
IAEA-TECDOC--784, pp:25-31
A proposal to develop a high temperature structural design guideline for HTGR components
Hada, K. (Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). HTTR
Designing Lab.)
IWGGCR--18, pp:27-33
Safety requirements and research and development on HTTR
fuel
Saito, S.; Shiozawa, S. (Japan Atomic Energy Research Inst.,
Oarai Research Establishment, Oarai, Ibaraki (Japan). Dept. of
HTTR Project); Fukuda, K.; Kondo, T. (Japan Atomic Energy
Research Inst., Tokai Research Establishment, Tokai, Ibaraki
(Japan). Dept. of Fuels and Materials Research)
IWGGCR--25, pp:31-36
Production process and quality control for the HTTR fuel.
Yoshimuta, S.; Suzuki, N.; Kaneko, M. (Nuclear Fuel
Industries, Ltd, Tokai, Ibaraki (Japan)); Fukuda, K. (Japan
Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai
Research Establishment)
IWGGCR--25, pp:37-42
Present activity of the feasibility study of HTGR-GT system
Y. MUTO, Y. MIYAMOTO and S. SHIOZAWA (Department of Advanced Nuclear Heat Technology, Oarai Research Establishment, JAERI)
IAEA-TECDOC--1210, pp:39-51
Depressurization accident analysis for the HTTR by the TAC-NC
Kunitomi, K.; Nishiguchi, I.; Wada, H.; Takeda, T.; Hishida, M.; Sudo, Y.; Tanaka, T.; Saito, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)
IAEA-TC--389.26, pp:41-55
Research on in-pile release of fission products from coated
particle fuels
Fukuda, K.; Iwamoto, K. (Department of Fuels
and Materials Research, Japan Atomic Energy
Research Institute, Tokai-mura, Ibaraki-ken
(Japan))
IWGGCR--13, pp:41-56
Structural integrity evaluation of a helically-coiled He/He intermediate heat exchanger
Okubo, M.; Hada, K.; Baba, O. (Japan Atomic Energy Research Inst., Naka,
Ibaraki (Japan). HTTR Designing Lab.)
IWGGCR--18, pp:41-48
F.P. plate-out study using in-pile loop OGL-1
Baba, O. (Japan Atomic Energy Research Inst., Oarai, Ibaraki. Oarai Research Establishment)
IWGGCR--2, pp:44-49
Study on the seismic load against the HTTR building. Seismicity
and wave propagation features of the HTTR site.
Suzuki, T. (Hazama-Gumi Ltd, Tokyo (Japan). Building
Construction Div.); Yamagishi, Y. (Japan Atomic Energy
Research Inst., Tokai, Ibaraki (Japan). Construction Div.);
Tokita, K. (Tokyo Electric Power Services Company Ltd,
Tokyo (Japan). Seismic Engineering Dept.)
IWGGCR--22, pp:45-52
Determination of the temperature coefficients and the kinetic
parameters for the HTTR safety analysis.
Tokuhara, K. (Fuji Electric Co. Ltd., Tokyo (Japan)); Nakata,
T. (Kawasi Heavy Industries Ltd, Tokyo (Japan)); Murata, I.;
Yamashita, K.; Shindo, R. (Japan Atomic Energy Research
Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)
IWGGCR--24, pp:45-53
A preliminary study on co-generation systems with the modular HTGR for Japanese conditions
Yamada, M. (Fuji Electric Co. Ltd., Tokyo (Japan)); Sato, S. (Tokyo Electric Power Co.,
Inc. (Japan)); Mitsui, H. (Saitama Inst. of Technology, Okabe, Saitama (Japan)); Fujimoto, N. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan))
IAEA-TECDOC--761, pp:46-54
Soil-structure interaction analysis of HTTR building by a
simplified model.
Yagishita, F. (Tokyo Electric Power Services Company Ltd,
Tokyo (Japan). Seismic Engineering Dept.); Suzuki, H.;
Yamagishi, Y. (Japan Atomic Energy Research Inst., Tokai,
Ibaraki (Japan). Construction Div.)
IWGGCR--22, pp:52-59
Calculational methods of power distribution in the HTTR and
verifications
Nakata, T. (Kawasaki Heavy Industries Ltd, Tokyo (Japan));
Tokuhara, K. (Fuji Electric Co. Ltd., Tokyo (Japan)); Murata,
I.; Yamashita, K.; Shindo, R. (Japan Atomic Energy Research
Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)
IWGGCR--24, pp:53-59
Outlook on heat utilization and H2 production potential of HTR in Japan
Ide, A. (Fuji Electric Co. Ltd., Tokyo (Japan)); Tasaka, K. (Nagoya Univ. (Japan))
IAEA-TECDOC--761, pp:55-59
Analytical method of fractional release of fission products from
fuel elements of HTTR.
Sawa, K.; Shiozawa, S. (Japan Atomic Energy Research Inst.,
Oarai Research Establishment, Oarai, Ibaraki (Japan). Dept. of
HTTR Project); Fukuda, K. (Japan Atomic Energy Research
Inst., Tokai Research Establishment, Tokai, Ibaraki (Japan).
Dept. of Fuels and Materials Research); Ichihashi, Y. (Japan
Atomic Energy Research Inst., Oarai Research Establishment,
Oarai, Ibaraki (Japan). Dept. of JMTR Project)
IWGGCR--25, pp:55-61
Selection of JAERI’s HTGR-GT Concept
Y. Muto, S. Ishizama and S. Shiozawa, JAERI, Oarai-machi, Ibaraki-ken, Japan
IAEA-TECDOC--1238, pp:57-66
Structural design of reactor core and support graphite components for the experimental VHTR
Arai, T.; Mogi, H.; Iyoku, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment); Ide, A.; Takikawa,N.
IWGGCR--11, pp:58-62
The plant dynamics analysis code ASURA for the High
Temperature Engineering Test Reactor (HTTR)
Shimakawa, Y.; Tanji, M. (Mitsubishi Atomic Power Industries,
Inc., Tokyo (Japan)); Nakagawa, S.; Fujimoto, N. (Japan
Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai
Research Establishment)
IWGGCR--24, pp:59-66
Soil-structure interaction analysis of HTTR building by a finite
element model.
Yamagishi, Y.; Suzuki, H. (Japan Atomic Energy Research
Inst., Tokai, Ibaraki (Japan). Construction Div.); Yagishita, F.
(Tokyo Electric Power Services Company Ltd, Tokyo (Japan).
Seismic Engineering Dept.)
IWGGCR--22, pp:60-66
Release behavior of metallic fission products from fuel for HTTR.
Hayashi, K.; Fukuda, K. (Japan Atomic Energy Research Inst.,
Tokai Research Establishment, Tokai, Ibaraki (Japan). Dept. of
Fuels and Materials Research); Shiozawa, S. (Japan Atomic
Energy Research Inst., Oarai Research Establishment, Oarai,
Ibaraki (Japan). Dept. of HTTR Project)
IWGGCR--25, pp:61-67
Activities of RAHP and problems to be cleared towards commercialization
S. AN (Chairman, RAHP; Professor Emeritus, Univ. of Tokyo),Y. TSUCHIE (Rep. Secretary, RAHP; The Japan Atomic Power Co.)
IAEA-TECDOC--1210, pp:67-73
Statistical considerations of graphite strength for assessing design allowable stresses
Ishihara, M.; Mogi, H.; Ioka, I.; Arai, T.; Oku, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)
IWGGCR--11, pp:69-74
Evaluations of the fracture mechanical properties of fuel compacts for the HTTR, with emphasis on
thermal shock resistances and neutron irradiation effects
Sato, S.; Kurumada, A.; Kawamata, K. (Ibaraki Univ., Hitachi (Japan). Faculty of
Engineering); Suzuki, N.; Kaneko, M. (Nuclear Fuels Industries, Ltd, Tokai (Japan). Tokai Works); Fukuda, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)
IAEA-TECDOC--690, pp:70-78
Evaluating on graphite oxidation during an air ingress accident in HTTR
Iyoku, T.; Maruyama, S.; Ishihara, M.; Shiozawa, S. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment); Ohashi, K.; Okamoto, F.; Hayakawa, H. (Fuji Electric Co. Ltd., Tokyo (Japan))
IAEA-TECDOC--784, pp:72-78
Fracture criterion of reactor graphite under multiaxial stresses
Sato, S.; Kawamata, K.; Kurumada, A. (Ibaraki Univ., Hitachi (Japan). Faculty of Engineering); Awaji, H.; Oku, T
IWGGCR--11, pp:75-89
Current status of studies on high temperature metallic materials for HTGR applications in JAERI
Tsuji, H.; Nakajima, H.; Kondo, T. (Japan Atomic Energy Research Inst., Naka,
Ibaraki (Japan). Dept. of Fuels and Materials Research)
IWGGCR--18, pp:76-85
Diffusion modeling of fission product release during
depressurized core conduction cooldown conditions.
Martin, R.C. (Oak Ridge National Lab., TN (United States))
IWGGCR--25, pp:77-84
Design, construction and operation experience of the He-He intermediate heat exchanger
Itoh, M. (Ishikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan))
IWGHTR--6, pp:77-86
Safety evaluation during a depressurization accident of the SFHTR
S. Nakagawa, A. Saikusa and K. Kunitomi (Department of HTTR Project, JAERI, Japan)
IAEA-TECDOC--1210, pp:77-84
Methanol synthesis from recycled carbon dioxide and hydrogen from high temperature steam electrolysis
with the nuclear heat of an HTGR
Miyamoto, Y. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)); Omoto, A.;
Aoki, Y. (Tokyo Electric Power Co., Inc. (Japan)); Murakami, T.; Uchida, S.; Shirakawa, S.; Murakami, N.; Yamauchi, Y. (Mitsubishi Heavy Industries Ltd, Nagasaki (Japan)); Fukuda, S.; Kamishima, Y. (Mitsubishi Atomic Power Industries, Inc., Tokyo (Japan))
IAEA-TECDOC--761, pp:79-85
Uncertainties in calculations of nuclear design code system for
the high temperature engineering test reactor (HTTR).
Shindo, R.; Yamashita, K.; Murata, I. (Japan Atomic Energy
Research Inst., Orai, Ibaraki (Japan). Dept. of HTTR Project)
IWGGCR--24, pp:81-86
Recent research and development of intermediate heat exchanger for VHTR plant
Shimizu, Akira; Matsumura, Noboru; Nishikawa, Hidetsugu;
Yamada, Seiya (Nagasaki Shipyard and Engine Works,
Mitsubishi Heavy Industries, Ltd., Nagasaki (Japan))
IWGGCR--9, pp:82-93
Technical development of graphite waste treatment in NUPEC
S. Saishu, T. Inoue
TCM-Manchester99, pp:85-91
Safety analysis and considerations for HTTR steam reforming hydrogen/methanol co-production system
Fujimoto, N.; Saikusa, A.; Hada, K.; Sudo, Y. (Japan Atomic Energy Research Inst.,
Oarai, Ibaraki (Japan).
IAEA-TECDOC--761, pp:86-91
Thermodynamic analysis of behaviour of HTGR fuel and fission products under accidental air or water ingress conditions
Minato, K.; Fukuda, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan).
Tokai Research Establishment)
IAEA-TECDOC--784, pp:86-91
High temperature low-cycle fatigue strength of Hastelloy-XR
Nagato, K.; Murakami, T.; Hashimoto, T. (Kawasaki Heavy Industries Ltd,
Tokyo (Japan). Nuclear Systems Div.)
IWGGCR--18, pp:86-90
Bending fatigue behavior of nuclear-grade graphite under impact loading
Futakawa, M.; Kikuchi, K.; Muto, Y. (Japan Atomic Energy Research Inst., Tokai,
Ibaraki (Japan). Dept. of High Temperature Engineering); Shibata, H. (Tokyo Univ. (Japan). Inst. of Industrial Science)
IAEA-TECDOC--690, pp:87-95
Seismic response analysis for HTTR core using the
SONATINA-2V code.
Iyoku, T.; Shiozawa, S.; Nishiguchi, I.; Hayashi, K. (Japan
Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of
HTTR Project); Watanabe, Y. (Toshiba Corp., Kawasaki
(Japan). Nuclear Engineering Lab.); Tsuji, N. (Fuji Electric
Company Ltd, Kawasaki (Japan). Engineering Dept.)
IWGGCR--22, pp:89-94
Structural assessment of prismatic blocks for pin-in-block fuel element
Takikawa, N.; Koike, H.; Tanaka, M. (Kawasaki Heavy Industries Ltd., Tokyo (Japan)); Arai, T.; Iyoku, T.; Ide, A
IWGGCR--11, pp:90-98
Helium-heated steam reformer
Meguro, T. (Research and Development Centre, Chiyoda Chemical Eng. and Construction Co. Ltd., Moriya/Cho, Japan)
IWGHTR--6, pp:94-101
Reliability analysis of VHTR reserve shutdown system
Araki, T.; Sugawara, M.; Ikeda, T. (Toshiba Corp., Japan Atomic Energy
Research Inst., Tokyo); Miyamoto, Y. (Japan Atomic Energy Research Inst.,
Tokyo)
IAEA-TECDOC--358, pp:95-103
Component test of the core support post of the HTTR
Ishihara, M.; Iyoku, T.; Takikawa, N.; Shiozawa, S. (Japan Atomic Energy Research Inst.,
Oarai, Ibaraki (Japan). Oarai Research Establishment); Jinza, K.; Tsuji, N.; Miki, T. (Fuji Electric Co. Ltd., Kawasaki, Kanagawa (Japan))
IAEA-TECDOC--690, pp:95-105
High temperature heat storage and temperature upgrading by use of CaO/H2O and CaO/CO2 reactions
Ogura, H.; Kanamori, M.; Matsuda, H.; Hasatani, M. (Nagoya Univ., Nagoya (Japan).
Dept. of Chemical Engineering)
IAEA-TECDOC--761, pp:95-102
Analytical and experimental investigations of the passive heat transport in HTRs under severe
accident conditions
Rehm, W.; Barthels, H.; Jahn, W. (Forschungszentrum Juelich GmbH
(Germany)); Cleveland, J. (Oak Ridge National Lab., TN (United States));
Ishihara, M. (Japan Atomic Energy Research Inst., Ibaraki (Japan))
IAEA-TECDOC--757, pp:95-103
Seismic response of HTTR core bottom structures
yoku, T.; Inagaki, Y.; Nishiguchi, I. (Japan Atomic Energy
Research Inst., Tokai, Ibaraki (Japan). Dept. of HTTR Project);
Futakawa, M. (Japan Atomic Energy Research Inst., Tokai,
Ibaraki (Japan). Dept. of High Temperature Engineering); Miki,
T.; Jinza, K.; Tomizuka, T. (Fuji Electric Company Ltd,
Kawasaki (Japan). Engineering Dept.)
IWGGCR--22, pp:95-104
Strength and fatigue properties of near-isotropic graphites
Oku, T.; Eto, M.; Arai, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)
IWGHTR--3, pp:96-102
Evaluation of graphite oxidation during water ingress accidents in HTTR
Maruyama, S.; Saikusa, A.; Ikoku, T.; Kunitomi, K.; Shiozawa, S. (Japan Atomic Energy
Research Inst., Tokai, Ibaraki (Japan)); Ohashi, K.; Hayakawa, H. (Fuji Electric Co. Ltd., Tokyo (Japan))
IAEA-TECDOC--784, pp:97-103
Experimental and theoretical evaluation of core alignment structures against a seismic load
Ide, A.; Miki, T. (Fuji Electric Co. Ltd., Tokyo (Japan)); Matsumura, M.; Mogi, H.; Ishihara, M.; Koike, H
IWGGCR--11, pp:99-107
Application of chemical heat pipe using SO2/SO3 reversible thermo chemical reaction to the transportation
of high temperature thermal energy
Zeng Weiping; Matsuda, H.; Hasatani, M. (Nagoya Univ., Nagoya (Japan). Dept. of
Chemical Engineering)
IAEA-TECDOC--761, pp:102-107
Design considerations and improvements of the high temperature
engineering test reactor (HTTR) for a reactor outlet coolant
temperature of 950 deg. C
Sudo, Y.; Saito, S. (Japan Atomic Energy Research Inst., Tokai,
Ibaraki (Japan)); Yamada, M. (Fuji Electric Co. Ltd., Tokyo
(Japan)); Uno, M. (Kawasaki Heavy Industries, Ltd., Tokyo
(Japan)); Ohno, T. (Mitsubishi Atomic Power Industries, Inc.,
Tokyo (Japan))
IWGGCR--19, pp:104-112
Assessment of the load capacity of the dowel and socket system in the HTTR hexagonal block
Takikawa, N.; Ishihara, M.; Iyoku, T.; Shiozawa, S. (Japan Atomic Energy Research Inst.,
Oarai, Ibaraki (Japan). Oarai Research Establishment); Tokumitsu, M.; Koe, S.; Uno, M. (Kawasaki Heavy Industries (Japan))
IAEA-TECDOC--690, pp:105-112
Analytical method and result of off-site exposure during normal operation of high-temperature engineering test reactor (HTTR)
Sawa, K.; Mikami, H.; Saito, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)
IAEA-TC--389.26, pp:105-124
Seismic scrammability of HTTR control rods.
Nishiguchi, I.; Iyoku, T.; Ito, N. (Japan Atomic Energy
Research Inst., Tokai, Ibaraki (Japan). Dept. of HTTR Project);
Watanabe, Y. (Toshiba Corp., Kawasaki (Japan). Nuclear
Engineering Lab.); Araki, T. (Toshiba Corp., Yokohama
(Japan). Nuclear Energy Group); Katagiri, S. (Toshiba Corp.,
Yokohoma (Japan). Keihin Product Operations)
IWGGCR--22, pp:105-111
Study on efficient methods for removal and treatment of graphite blocks in a gas cooled reactor
S. Fujii, M. Shirakawa, T. Murakami
TCM-Manchester99, pp:105-113
R&D and the application of metal hydride super heat pump for nuclear plant and H2 plant
Ishiyama, S.; Ugachi, H.; Eto, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki
(Japan))
IAEA-TECDOC--761, pp:108-114
Structural strength of core graphite bars
Kikuchi, K.; Futakawa, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)
IWGGCR--11, pp:108-112
Fatigue properties of nickel-base high temperature alloys for HTGRs
Tsuji, H.; Nakajima, H. (Japan Atomic Energy Research Inst., Naka, Ibaraki
(Japan). Dept. of Fuels and Materials Research)
IWGGCR--18, pp:110-123
The vibrational characteristics of the keyed graphite components in the HTTR
Futakawa, M.; Iyoku, T.; Shiozawa, S.; Takada, S. (Japan Atomic Energy Research Inst.,
Tokai, Ibaraki (Japan). Tokai Research Establishment); Shirai, H. (CSK Co., Tokyo (Japan))
IAEA-TECDOC--690, pp:113-120
A progress report on bench scale studies of the iodine-sulfur process for thermo chemical hydrogen
production
Shimizu, S.; Nakajima, H.; Onuki, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki
(Japan))
IAEA-TECDOC--761, pp:114-119
Study of Fission Product Release, Plate-out and Maintenance in Helium Turbomachinery
Y. Muto, S.Ishtyama, S.Shiozawa, Japan Atomic Energy Research Institute, Oarai-machi, Ibaraki-ken, Japan
IAEA-TECDOC--1238, pp:114-137
Analytical method and result of fission product release from core
during a depressurization accident of HTTR
Sawa, K.; Tazawa, Y.; Shiozawa, S. (Japan Atomic Energy
Research Inst., Oarai, Ibaraki (Japan). Dept. of HTTR Project);
Mikami, H. (Fuji Electric Co., Ltd, Tokyo (Japan). HTR
Project Dept.)
IWGGCR--25, pp:117-123
Hydrogen production by high-temperature electrolysis of steam
Hino, R.; Miyamoto, Y. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan))
IAEA-TECDOC--761, pp:119-124
Measurements of temperature coefficient of reactivity of the
VHTRC-1 core by the criticality method.
Yasuda, H.; Akino, F.; Yamane, T.; Kaneko, Y. (Japan Atomic
Energy Research Inst., Tokai (Japan))
IWGGCR--24, pp:119-124
Construction and performance tests of a secondary hydrogen gas cooling system
Sanokawa, K.; Hishida, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)
IWGHTR--6, pp:119-133
Seismic response analysis of prismatic block cores of the experimental VHTR
Iyoku, T.; Motoki, Y.; Arai, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment); Miki, T.; Ide, A
IWGGCR--11, pp:120-127
Application study of the heat pipe to the passive decay heat removal system of the modular HTR
K. OHASHI, F. OKAMOTO, H. HAYAKAWA (Fuji Electric Co., Ltd.,Japan),T. HAYASHI (Tokai University, Japan)
IAEA-TECDOC--1210, pp:121-131
Design of steam reforming hydrogen and methanol co-production system to be connected to the HTTR
Hada, K.; Fujimoto, N.; Sudo, Y. (Japan Atomic Energy Research Inst., Oarai, Ibaraki
(Japan). Dept. of HTTR Project)
IAEA-TECDOC--761, pp:124-134
Heat transfer in the upper part of the HTTR pressure vessel during loss of forced cooling
Shiina, Y.; Hishida, M. (Japan Atomic Energy Research Inst., Ibaraki (Japan))
IAEA-TECDOC--757, pp:125-130
Life time test of a partial model of HTGR helium-helium heat exchanger
Kitagawa, Masaki; Hattori, Hiroshi; Ohtomo, Akira; Teramae,
Tetsuo; Hamanaka, Junichi; Itoh, Mitsuyoshi; Urabe, Shigemi
(Ishikawajima-Harima Heavy Industries Co., Ltd., Tokyo
(Japan))
IWGGCR--9, pp:127-138
Design study of He gas-cooled fast breeder reactor
Mochizuki, H.; Izaki, T.; Takitani, K.; Koike, H.; Kobayashi, Y.; Matsuki, Y.; Ooka, T.; Tanaka, R.;
Watanabe, T.; Kobayashi, T. (Kawasaki Heavy Industries Ltd., Tokyo (Japan))
IAEA-TECDOC--154, pp:133-164
High temperature Young's modulus of IG-110 graphite
Konishi, T.; Eto, M.; Oku, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)
IWGGCR--11, pp:133-137
Core seismic study on experimental VHTR
Miyamoto, Y. (JAERI, Tokai, Japan); Ikushima, T.; Tamura, K.; Honma, T
IWGGCR--6, pp:133-145
Effects of high temperature neutron irradiation on the physical, chemical and mechanical properties of fine-grained isotropic graphite
Matsuo, H.; Nomura, S.; Imai, H.; Oku, T.; Eto, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research
Establishment)
IWGGCR--11, pp:138-143
Mechanical properties and thermal shock resistances of recently developed high performance graphites
Sato, S.; Kawamata, K.; Kurumada, A.; Chiba, A. (Ibaraki Univ., Hitachi (Japan). Faculty
of Engineering)
IAEA-TECDOC--690, pp:140-146
Recent research and development of bearings for helium circulator
Taniguchi, S.; Ezaki, Z.; Kawaguchi, K.; Matsumura, N.; Kozima, M. (Mitsubishi Heavy Industries Ltd, Nagasaki (Japan))
IWGGCR--17, pp:141-148
Degradations of thermal shock resistance and the fracture toughness of reactor graphite subjected to neutron irradiation
Sato, S.; Kawamata, K.; Kurumada, A.; Ugachi, H. (Ibaraki Univ., Hitachi (Japan). Faculty of Engineering); Awaji, H
IWGGCR--11, pp:144-157
Test apparatus of cooling panel system for MHTGR
Takada, S.; Suzuki, K.; Inagaki, Y.; Miyamoto, Y. (Japan Atomic Energy
Research Inst., Tokai, Ibaraki (Japan). Dept. of High Temperature Engineering)
IAEA-TECDOC--757, pp:147-151
Operating experience of gas bearing helium circulators in HTGR development facility
Shimomura, H.; Kawaji, S.; Fujisaki, K.; Ihizuka, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)
IWGGCR--17, pp:148-156
Behavior of gas desorption and gas permeability of carbon materials
Okada, M.; Sogabe, T. (Toyo Tanso Co., Ltd, Mitoyo, Kagawa (Japan))
IAEA-TECDOC--690, pp:149-158
Design of a nuclear desalination facility for Bushehr, Iran
Shiota, Y. (Sasakura Engineering Company Ltd., Osaka (Japan))
IAEA-TECDOC--1056, pp:149-154
A study on cost reduction effect due to changes of safety grade of HTGR
S. UCHIDA(Advanced Reactor Technology Co., Ltd.,Japan), I. MINATSUKI, M. TANIHIRA, S. YAMADA (Mitsubishi Heavy Industries Co., Ltd.,Japan)
IAEA-TECDOC--1210, pp:155-166
Relation between gasification rates and gas desorption behavior with metallic impurities of carbon and
graphite materials for the HTTR
Nomura, S.; Fujii, K.; Shindo, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki,
(Japan). Dept. of Fuels and Materials Research); Imai, H. (Research Association for Nuclear Facilities Decommissioning, Tokai, Ibaraki (Japan))
IAEA-TECDOC--690, pp:159-168
Application of ISRM testing methods to fracture toughness testing of graphite
Hashida, T.; Fukasawa, T.; Takahashi, H. (Tohoku Univ., Sendai (Japan)); Ishiyama, S.; Oku, T
IWGGCR--11, pp:159-162
Notch sensitivity of graphite materials for VHTR
Kawakami, Haruo (Fuji Electric Corp. Research and Development Ltd., Yokosuka, Kanagawa (Japan))
IWGGCR--11, pp:163-168
Characteristics of DC electrical braking method of the gas circulator to limit the temperature rise at the heat transfer pipes in the HTTR
K. KAWASAKI, K. SAITO and T. IYOKU(JAERI, Department of HTTR Project, Japan)
IAEA-TECDOC--1210, pp:167-179
Corrosion behavior of sintered pellet of graphite and boron carbide in helium containing water vapor
Fujii, K.; Nomura, S.; Shindo, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki
(Japan). Dept. of Fuels and Materials Research); Imai, H. (Research Association for Nuclear Facilities Decommissioning, Tokai, Ibaraki (Japan))
IAEA-TECDOC--690, pp:169-176
Nondestructive testing of HTGR graphites
Maruyama, T. (Tokyo Inst. of Tech. (Japan). Research Lab. of Nuclear Reactor); Uragaki, H.; Fujii, M.; Ooka, K.; Sakashita, T.;
Suzuki, H.; Oku, T
IWGGCR--11, pp:169-175
Investigation of morphology and impurity of nuclear-grade graphite, and leaching mechanism of carbon-14
R. Takahashi, M. Toyahara, S. Maruki, H. Ueda, T. Yamamoto
TCM-Manchester99, pp:176-190
Effect of atmosphere on the bend strength of nuclear graphite
Maruyama, T. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki
(Japan). Oarai Engineering Center)
IAEA-TECDOC--690, pp:177-182
Japanese HTTR programme for demonstration of high temperature applications of nuclear energy
Nishihara, T.; Hada, K.; Shiozawa, S. (Japan Atomic Energy Research Inst.,
Oarai, Ibaraki (Japan). Oarai Research Establishment)
IAEA-TECDOC--923, pp:179-186
Fabrication of HTTR first loading fuel
S. KATO, S. YOSHIMUTA, T. HASUMI, K. SATO (Nuclear Fuel Industries, Ltd., Japan),K. SAWA, S. SUZUKI, H. MOGI, S. SHIOZAWA, T. TANAKA (Japan Atomic Energy Research Institute, Japan)
IAEA-TECDOC--1210, pp:187-199
Estimation of graphite materials corrosion with water-vapor in coolant of the VHTR and oxidation effect on the materials properties
Eto, M.; Kurosawa, T.; Imai, H.; Nomura, S.; Oku, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research
Establishment)
IWGGCR--11, pp:189-194
Overview of HTGR heat utilization system development at JAERI
Miyamoto, Y.; Shiozawa, S.; Ogawa, M.; Akino, N.; Shimizu, S.; Hada, K.; Inagaki, Y.;
Onuki, K.; Takeda, T.; Nishihara, T. (Japan Atomic Energy Research Institute, Ibaraki (Japan))
IAEA-TECDOC--1056, pp:191-200
Seismic analysis of a helical coil type heat exchanger
Nishiguchi, I.; Baba, O. (Japan Atomic Energy Research
Institute, Ibaraki-ken (Japan)); Yatabe, H. (Babcock Hitachi
K.K. (Japan))
IWGGCR--9, pp:192-203
Engineering thermomechanics of nuclear graphites under neutron irradiation, oxidation and transient
heat up: A review
Arai, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research
Establishment)
IAEA-TECDOC--690, pp:195-199
A graphite corrosion rate equation under high concentration water-vapor in helium and an estimation of the VHTR support post corrosion and strength
Nomura, S.; Kurosawa, T.; Imai, H.; Eto, M.; Oku, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research
Establishment)
IWGGCR--11, pp:195-200
The reactor safety study of experimental multi-purpose VHTR design
Yasuno, T.; Mitake, S.; Ezaki, M.; Suzuki, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)
IWGGCR--1, pp:198-207
Research on irradiation behavior of VHTR fuel
Ikawa, K.; Fukuda, K.; Iwamoto, K. (Department of Fuels
and Materials Research, Japan Atomic Energy Research
Institute, Tokai-mura, Naka-gun, Ibaraki-ken (Japan))
IWGGCR--8, pp:201-211
The study of metallic fission product release from the VHTR core under power operating
condition
Okamoto, F.; Mikami, H. (Nuclear Promotion Div., Fuji Electric Co., Ltd.,
Tokyo (Japan)); Mitake, S.; Suzuki, K. (Department of Power Reactor
Projects, Japan Atomic Energy Research Inst., Tokai, Ibaraki)
IAEA-TECDOC--358, pp:203-212
Numerical analysis of the release of metallic fission product in
high temperature gas-cooled reactor
Fujii, S.; Tsubosaka, A.; Niguma, Y. (Kawasaki
Heavy Industries Ltd. (Japan)); Hirano, M.;
Suzuki, K. (Japan Atomic Energy Research
Institute (Japan))
IWGGCR--13, pp:208-220
Irradiation behavior of boronated graphite for the HTTR
Matsuo, H. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research
Establishment); Kobayashi, F.; Sawa, K. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)
IAEA-TECDOC--690, pp:210-219
Irradiation dimensional stability of graphite containing green coke filler
Kalyagina, I.P.; Virgiliev, Yu.S
IWGGCR--11, pp:213-216
Development programme on hydrogen production in HTTR
Y.INAGAKI, T.NISHIHARA, T.TAKEDA, K.HADA, M.OGAWA, S.SHIOZAWA, Y.MIYAMOTO (JAERI, Japan)
IAEA-TECDOC--1210, pp:213-221
Elastic-plastic fracture toughness of HTGR graphites
Oku, T.; Ishiyama, S.; Eto, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment); Inagaki, M.;
Hashida, T.; Takahashi, H
IWGGCR--11, pp:217-221
Capsule design, fabrication and irradiation for tensile creep test on HTGR graphites at 1200 deg. C in the
JMTR
Saito, T. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research
Establishment); Kikuchi, T.; Arai, T.; Ugachi, H. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)
IAEA-TECDOC--690, pp:219-225
Fatigue behavior of fine-grained isotropic graphite for HTGRs
Ishiyama, S.; Eto, M.; Oku, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)
IWGGCR--11, pp:222-226
Acoustic emission from polycrystalline graphites
Ioka, I.; Yoda, S.; Oku, T.; Miyamoto, Y. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)
IWGGCR--11, pp:227-232
Experience obtained from construction and preliminary test of in-core structure test section (T-2)
Kunitomi, K.; Inagaki, Y.; Ioka, I.; Kondo, Y.; Miyamoto, Y.; Shimomura, H. (Japan Atomic Energy Research Inst., Tokai, Ibaraki.
Tokai Research Establishment); Akisada, T.; Yamaguchi, S
IWGGCR--11, pp:233-238
Cumulative fatigue damage on HTGR graphite
Ishiyama, S.; Eto, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept.
of High Temperature Engineering)
IAEA-TECDOC--690, pp:248-255
Analysis of cooling capability of reactor vessel cooling system of the experimental VHTR
Suzuki, K.; Sumimoto, H.; Hirano, M. (Department of Power Reactor Projects,
Japan Atomic Energy Research Inst., Tokai, Ibaraki); Asami, T. (Babcock
Hitachi K.K., Tokyo (Japan))
IAEA-TECDOC--358, pp:251-259
Fission product release characteristics of the experimental VHTR core
Mitake, S.; Okada, T.; Suzuki, K. (Japan Atomic Energy
Research Institute, Toka-mura, Naka-gun, Ibaraki-ken
(Japan))
IWGGCR--8, pp:255-263
Fracture behavior of nuclear graphites under compressive impact loading
Ugachi, H.; Ishihara, M.; Ishiyama, S.; Eto, M. (Japan Atomic Energy Research Inst.,
Tokai, Ibaraki (Japan). Dept. of High Temperature Engineering)
IAEA-TECDOC--690, pp:256-261
Thermal and hydraulic behaviours during start-up of emergency reactor cooling system for the
experimental VHTR
Asami, T.; Kudo, A. (Babcock Hitachi K.K., Tokyo (Japan)); Hirano, M.;
Suzuki, K. (Department of Power Reactor Projects, Japan Atomic Energy
Research Inst., Tokai, Ibaraki)
IAEA-TECDOC--358, pp:263-271
Summary of experience and practice in Japanese nuclear desalination plants at the interface between
nuclear and desalination systems
Shiota, Y. (Sasakura Engineering, Osaka (Japan)); Minato, A. (CRIEPI, Tokyo (Japan))
IAEA-TECDOC--1056, pp:271-277
Non-destructive testing and acceptance test for HTTR graphite components
Takikawa, N.; Iyoku, T.; Shiozawa, S.; Ooka, N. (Japan Atomic Energy Research Inst.,
Oarai, Ibaraki (Japan). Oarai Research Establishment); Kambe, M.; Ide, A. (Fuji Electric Co. Ltd., Kawasaki, Kanagawa (Japan))
IAEA-TECDOC--690, pp:281-288
Non-destructive test of HTGR graphite components
Ishihara, M.; Ishii, T.; Ishiyama, S.; Eto, M. (Japan Atomic Energy Research Inst., Tokai,
Ibaraki (Japan). Dept. of High Temperature Engineering)
IAEA-TECDOC--690, pp:291-298
The correlation of hardness with Young's modulus and strengths of nuclear carbon materials
Oku, T.; Ohta, S. (Ibaraki Univ., Hitachi, Ibaraki (Japan). Dept. of Mechanical
Engineering); Eto, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)
IAEA-TECDOC--690, pp:299-303
Quantitative analysis of trace amounts of impurities contaminating pure graphite with ICP-MS and metal
atomizer FLAAS
Miyatani, T.; Suzuki, H.; Yoshimoto, O. (Toyo Tanso Co., Ltd, Mitoyo, Kagawa (Japan))
IAEA-TECDOC--690, pp:304-308
Analysis of core flow deviation caused by the large gaps between horizontal block interfaces
Suzuki Kunihiko; Suzuki Katsuo; Mogi, H.; Fumizawa, M.; Iyoku, T.; Sawa, K.
(Department of Power Reactor Projects, Japan Atomic Energy Research Inst.,
Tokai, Ibaraki)
IAEA-TECDOC--358, pp:313-323
Process study on advanced graphite-burn method for head-end step of HTR fuel reprocessing
Maeda, M.; Tsujino, T.; Iwamoto, K. (Department of Fuels
and Materials Research, Japan Atomic Energy Research
Institute, Toka-mura, Naka-gun, Ibaraki-ken (Japan))
IWGGCR--8, pp:345-356
Monitoring experiment of gaseous fission products in the
primary coolant helium of OGL-1
Terada, H.; Saruta, T.; Suzuki, K.; Wakayama,
N.; Aoyama, I. (Japan Atomic Energy Research
Institute, Tokai-mura, Naka-gun, Ibaraki-ken
(Japan))
IWGGCR--13, pp:351-362
Fission product plate-out measurement of Oarai helium gas loop
OGL-1
Tsuyuzaki, N.; Sasajima, H.; Endo, Y.; Itami, H.
(Department of JMTR Project, Japan Atomic
Energy Research Institute, Oarai Research
Establishment (Japan)); Matsumoto, M. (Nuclear
Engineering Co., Omika-cho, Hitachi-shi (Japan))
IWGGCR--13, pp:363-370
Design and safety consideration in the high-temperature engineering test reactor (HTTR)
Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)
IAEA-TC--389.26, pp:368-388
Two layers thermal insulations tests for designing of hot gas ducts
Nakase, T.; Midoriyama, S.; Roko, K.; Yoshizaki, A.
(Kawasaki Heavy Industries, Ltd., Tokyo (Japan))
IWGGCR--9, pp:401-412
Construction and performance tests of Helium Engineering Demonstration Loop (HENDEL) for VHTR
Hishida, M.; Tanaka, T.; Shimomura, H.; Sanokawa, K.
(Department of High Temperature Engineering, Japan Atomic
Energy Research Institute, Ibaraki-ken (Japan))
IWGGCR--9, pp:477-488
Research and Development programs for HTGRs in JAERI
Nishiguchi, Isoharu; Saito, Sinzo (Department of HTTR Project, Japan Atomic Energy Research Institute (Japan))
IAEA-TC--389.26, pp:562-594
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