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Journal Articles

Conceptual design of the iodine-sulfur process flowsheet with more than 50% thermal efficiency for hydrogen production

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:91.03(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$$_{2}$$SO$$_{4}$$ using waste heat from Bunsen reaction, prevention of H$$_{2}$$SO$$_{4}$$ vaporization from a distillation column by introduction of H$$_{2}$$SO$$_{4}$$ solution from a flash bottom, and I$$_{2}$$ condensation heat recovery in an HI distillation column. Hydrogen of about 31,900 Nm$$^{3}$$/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.

JAEA Reports

Concept of a nuclear powered submersible research vessel and a compact reactor

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.

Journal Articles

Conceptual designing of a reduced moderation pressurized water reactor by use of MVP and MVP-BURN

Kugo, Teruhiko

Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications, p.821 - 826, 2001/00

no abstracts in English

Journal Articles

Advantage of modified JAERI passive safety reactor (JPSR-II)

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

Journal Articles

Concept of passive safety light water reactor system (JPSR)

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

Journal Articles

Conceptual design of the JAERI passive safety reactor and its thermal-hydraulic characteristics

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke

Transactions of the American Nuclear Society, 71, p.527 - 529, 1995/00

no abstracts in English

Journal Articles

Conceptual design of JAERI passive safety reactor (JPSR) and its thermal-hydraulic characteristics

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke

10th Proc. of Nuclear Thermal Hydraulics, 0, p.3 - 12, 1994/00

no abstracts in English

JAEA Reports

Conceptual design of SPWR, a PWR with enbanced passive safety

JAERI-M 89-208, 322 Pages, 1989/12

JAERI-M-89-208.pdf:8.66MB

no abstracts in English

JAEA Reports

Development of Tokamak Reactor Systems Analysis Code "TORSAC"

; Tone, Tatsuzo; *; *

JAERI-M 87-021, 272 Pages, 1987/02

JAERI-M-87-021.pdf:4.66MB

no abstracts in English

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