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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.

Journal Articles

Design of HTTR-GT/H$$_{2}$$ test plant

Yan, X.; Sato, Hiroyuki; Sumita, Junya; Nomoto, Yasunobu*; Horii, Shoichi*; Imai, Yoshiyuki; Kasahara, Seiji; Suzuki, Koichi*; Iwatsuki, Jin; Terada, Atsuhiko; et al.

Nuclear Engineering and Design, 329, p.223 - 233, 2018/04

 Times Cited Count:20 Percentile:90.27(Nuclear Science & Technology)

The pre-licensing design of an HTGR cogeneration test plant to be coupled to JAEA's existing test reactor HTTR is presented. The plant is designed to demonstrate the system of JAEA commercial plant design GTHTR300C. With construction planned to be completed around 2025, the test plant is expected to be the first-of-a-kind nuclear system operating on two of the advanced energy conversion systems attractive for the HTGR closed cycle helium gas turbine for power generation and thermochemical iodine-sulfur water-splitting process for hydrogen production.

Journal Articles

Conceptual design of 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.

Proceedings of 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016) (CD-ROM), p.491 - 500, 2016/11

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 Japan Atomic Energy Agency's commercial Gas Turbine High Temperature Reactor Cogeneration (GTHTR300C) plant design. Innovative techniques proposed by JAEA were applied for improvement of hydrogen production thermal efficiency; flash concentration of 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, and I$$_{2}$$ condensation heat recovery by direct contact heat exchange in the HI distillation column. A simulation of material and heat balance showed hydrogen of about 31,900 Nm$$^{3}$$/h was produced by 170 MW heat from the GTHTR300C. A process thermal efficiency of 50.2% was achievable with incorporation of the innovative techniques and several high performance components expected in future R&D.

Journal Articles

HTTR-GT/H$$_{2}$$ test plant; System design

Yan, X.; Sato, Hiroyuki; Sumita, Junya; Nomoto, Yasunobu; Horii, Shoichi; Imai, Yoshiyuki; Kasahara, Seiji; Suzuki, Koichi*; Iwatsuki, Jin; Terada, Atsuhiko; et al.

Proceedings of 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016) (CD-ROM), p.827 - 836, 2016/11

Pre-licensing basic design for a cogenerating HTGR test plant system is presented. The plant to be coupled to existing 30 MWt 950$$^{circ}$$C test reactor HTTR is intended as a system technology demonstrator for GTHTR300C plant design. More specifically the test plant of HTTR-GT/H$$_{2}$$ aims to (1)demonstrate the licensability of the GTHTR300C for electricity production by gas turbine and hydrogen cogeneration by thermochemical process and (2) confirm the operation control and safety of such cogeneration system. With construction and operation completion by 2025, the test plant is expected to be the first of a kind HTGR-powered cogeneration plant operating on the two advanced energy conversion systems of closed cycle helium gas turbine for power generation and thermochemical iodine-sulfur water-splitting process for hydrogen production.

JAEA Reports

Study of HTGR contribution to Japan's CO$$_{2}$$ emission reduction goal in 2050

Kamiji, Yu; Suzuki, Koichi*; Yan, X.

JAEA-Technology 2016-010, 24 Pages, 2016/07

JAEA-Technology-2016-010.pdf:1.05MB

Japanese government has set the goal of reducing CO$$_{2}$$ emission by 26% in 2030 below the 2013 level, in longer term, by 80% below the 1990 level. To achieve the goals, various measures should be taken. The GTHTR300, a commercial High Temperature Gas-cooled Reactor (HTGR) design being developed by JAEA offers spectrum of heat applications by using its high temperature heat up to 950$$^{circ}$$C. The potential contribution of CO$$_{2}$$ emission reduction by HTGR is estimated considering domestic and overseas deployment of the GTHTR300. The best estimate for domestic CO$$_{2}$$ reduction is 2.07$$times$$10$$^{8}$$ ton- CO$$_{2}$$/yr and that from oversea is 2.25$$times$$10$$^{8}$$ ton- CO$$_{2}$$/yr. The sum of these is about 47% of 9.13$$times$$10$$^{8}$$ ton- CO$$_{2}$$/yr which is CO$$_{2}$$ reduction target in 2050, for which deployment of 52 plants in Japan and 113 plants abroad, with each plant containing four 600 MWt reactor units, is required.

Journal Articles

Breeding new varieties of miniature ${it Cymbidium}$ using ion beam irradiation

Yuki, Shunji*; Araki, Satoshi*; Suzuki, Takanori*; Osuga, Toshio*; Katayama, Koichi*; Hase, Yoshihiro; Yokota, Yuichiro

JAEA-Review 2007-060, JAEA Takasaki Annual Report 2006, P. 85, 2008/03

no abstracts in English

Journal Articles

Development of a magnetic focusing device for pulsed neutrons

Suzuki, Junichi; Oku, Takayuki; Adachi, Tomohiro*; Shimizu, Hirohiko; Kiyanagi, Yoshiaki*; Kamiyama, Takashi*; Hiraga, Fujio*; Iwasa, Hirokatsu*; Sato, Koichi*; Furusaka, Michihiro*

Nuclear Instruments and Methods in Physics Research A, 529(1-3), p.120 - 124, 2004/08

 Times Cited Count:11 Percentile:58.51(Instruments & Instrumentation)

no abstracts in English

Journal Articles

High performance computing at Japan Atomic Energy Research Institute

; Higuchi, Kenji; ; Harada, Hiro; ; *; *

High Performance computing 1995; Grand Challenges in Computer Simulation, 0, p.9 - 15, 1995/00

no abstracts in English

JAEA Reports

Parallelization of MCNP 4, a Monte Carlo neutron and photon transport code system, in highly parallel distributed memory type computer

Masukawa, Fumihiro; ; Naito, Yoshitaka; *; *; *; *

JAERI-M 93-210, 40 Pages, 1993/11

JAERI-M-93-210.pdf:1.24MB

no abstracts in English

JAEA Reports

Vectorization and improvement of nuclear codes; MEUDAS4, FORCE, STREAM V2.6, HEATING7-VP, SCDAP/RELAP5/MOD2.5, NBI3DGFN

*; *; *; *; *; Yokokawa, Mitsuo

JAERI-M 92-142, 117 Pages, 1992/09

JAERI-M-92-142.pdf:2.45MB

no abstracts in English

JAEA Reports

Installation of a new FORTRAN compiler and effective programming method on the vector supercomputer

*; *; Watanabe, Kenji*; *; *; *; Harada, Hiro; Yokokawa, Mitsuo

JAERI-M 92-105, 209 Pages, 1992/07

JAERI-M-92-105.pdf:5.23MB

no abstracts in English

Journal Articles

Parallelization of Monte Carlo shielding code MCACE and Monte Carlo criticality code KENO-IV

; Masukawa, Fumihiro; Komuro, Yuichi; Naito, Yoshitaka; *; *; *; *

Nihon Genshiryoku Gakkai-Shi, 34(6), p.533 - 543, 1992/06

 Times Cited Count:1 Percentile:17.26(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Parallel processing for the direct simulation Monte Carlo method

Watanabe, Kenji*; *; Yokokawa, Mitsuo; ;

Joho Shori Gakkai Kenkyu Hokoku, 91(61), p.17 - 24, 1991/07

no abstracts in English

Journal Articles

Drug diffusion and necrose effect from the anticancer-polymer composites for cotrolled release

Kaetsu, Isao; ; Asano, Masaharu; *; *; *; *; *; *; *; et al.

Jinko Zoki, 15(1), p.210 - 213, 1986/00

no abstracts in English

Journal Articles

Effect of nonbiodegradable vinyl copolymer formulations with controlled slow release of anticancer drugs on the necrosis of braintumor

Kaetsu, Isao; ; Asano, Masaharu; *; *; *; *; *; *; *

Jinko Zoki, 15(1), p.214 - 217, 1986/00

no abstracts in English

Oral presentation

Development of a pulsed sextupole electromagnet for pulsed neutron focusing

Shinohara, Takenao; Suzuki, Junichi; Oku, Takayuki; Iwashita, Hidenori*; Kamiyama, Takashi*; Iwasa, Hirokatsu*; Hiraga, Fujio*; Kiyanagi, Yoshiaki*; Sato, Koichi*; Shimizu, Hirohiko*

no journal, , 

no abstracts in English

Oral presentation

Neutron beam focusing by a pulsed sextupole electromagnet

Shinohara, Takenao; Suzuki, Junichi; Oku, Takayuki; Iwashita, Hidenori*; Kamiyama, Takashi*; Iwasa, Hirokatsu*; Hiraga, Fujio*; Kiyanagi, Yoshiaki*; Sato, Koichi*; Shimizu, Hirohiko*

no journal, , 

no abstracts in English

Oral presentation

Development of $$^{3}$$He polarized neutron spin filters and its present status, 2

Kira, Hiroshi; Sakaguchi, Yoshifumi; Oku, Takayuki; Suzuki, Junichi; Nakamura, Mitsutaka; Arai, Masatoshi; Endo, Yasuo; Kakurai, Kazuhisa; Arimoto, Yasushi*; Ino, Takashi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of polarization measurement devices for polarized $$^{3}$$He gas neutron spin filters

Kira, Hiroshi; Sakaguchi, Yoshifumi; Oku, Takayuki; Suzuki, Junichi; Nakamura, Mitsutaka; Arai, Masatoshi; Endo, Yasuo; Arimoto, Yasushi*; Ino, Takashi*; Shimizu, Hirohiko*; et al.

no journal, , 

no abstracts in English

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