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Journal Articles

Reduction on high level radioactive waste volume and geological repository footprint with high burn-up and high thermal efficiency of HTGR

Fukaya, Yuji; Nishihara, Tetsuo

Nuclear Engineering and Design, 307, p.188 - 196, 2016/10

AA2015-0894.pdf:0.58MB

 Times Cited Count:1 Percentile:79.42(Nuclear Science & Technology)

Reduction of High Level Waste (HLW) and footprint in a geological repository due to high burn-up and high thermal efficiency of High Temperature Gas-cooled Reactor (HTGR) has been investigated. A helium-cooled and graphite-moderated commercial HTGR was designed as a Gas Turbine High Temperature Reactor (GTHTR300), and the features are significantly high burn-up of approximately 120 GWd/t, high thermal efficiency around 50%, and pin-in-block type fuel. The pin-in-block type fuel was employed to reduce processed graphite volume in reprocessing, and effective waste loading method for direct disposal is proposed by applying the feature in this study. As a result, it is found that the number of canisters and its repository footprint per electricity generation can be reduced by 60% compared with LWR representative case for direct disposal because of the higher burn-up, higher thermal efficiency, less TRU generation, and effective waste loading proposed in this study for HTGR. For disposal with reprocessing, the number of canisters and its repository footprint per electricity generation can be reduced by 30% compared with LWR because of the 30% higher thermal efficiency of HTGR.

Journal Articles

Gas turbine high temperature reactor

Kunitomi, Kazuhiko; Katanishi, Shoji; Shiozawa, Shusaku

Nippon Genshiryoku Gakkai-Shi, 43(11), p.1085 - 1099, 2001/11

no abstracts in English

Journal Articles

High temperature gas-cooled reactor

Muto, Yasushi; Kunitomi, Kazuhiko

Karyoku Genshiryoku Hatsuden, 52(10), p.1279 - 1286, 2001/10

no abstracts in English

Journal Articles

Improvement in the design of helium turbine for the HTGR-GT power plant

Muto, Yasushi; Ishiyama, Shintaro; Inomata, Asako*; Kishibe, Tadaharu*; Minatsuki, Isao*; Matsumoto, Iwao*; Levet, F.*

Proceedings of ASME Turbo Expo 2001 (CD-ROM), 8 Pages, 2001/00

no abstracts in English

Journal Articles

Technical issues and their solutions in HTGR gas turbine system

Muto, Yasushi; Ishiyama, Shintaro

Nippon Genshiryoku Gakkai-Shi, 42(10), p.1020 - 1027, 2000/10

 Times Cited Count:1 Percentile:86.57(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

A Design study of high electric power for fast reactor cooled by super critical light water

Koshizuka, Seiichi*

JNC-TJ9400 2000-011, 102 Pages, 2000/03

JNC-TJ9400-2000-011.pdf:2.71MB

In order to evaluate the possibility to achieve high electric power by a fast reactor with supercritical light water, the design study was carried out on a large fast reactor core with high coolant outlet temperature (SCFR-H). Since the reactor coolant circuit uses once-through direct cycle where all feedwater flows through the core to the turbine at supercritical pressure, it is possible to design much simpler and more compact reactor systems and to achieve higher thermal efficiency than those of current light water reactors. The once-through direct cycle system is employed in current fossil-fired power plants. In the present study, three types of core were designed. The first is SCFR-H with blankets cooled by ascending flow, the second is SCFR-H with blankets cooled by descending flow and the third is SCFR-H with high thermal power. Every core was designed to achieve the thermal efficiency over 43%, positive coolant density reactivity coefficient and electric power over 1600MW. Core characteristics of SCFR-Hs were compared with those of SCLWR-H (electric power: 1212MW), which is a thermal neutron spectrum reactor cooled and moderated by supercritical light water, with the same diameter of the reactor pressure vessel. It was shown that SCFR-H could increase the electric power about l.7 times maximally. From the standpoint of the increase of a reactor thermal power, a fast reactor has advantages as compared with a thermal neutron reactor, because it can increase the power density by adopting tight fuel lattices and eliminating the moderator region. Thus, it was concluded that a reactor cooled by supercritical light water could further improve the cost competitiveness by using a fast neutron spectrum and achieving a higher thermal power.

Journal Articles

Feasibility design study of compact heat exchanger for HTGR gas turbine systems

Ishiyama, Shintaro; Muto, Yasushi; Kasaba, Michihiro*; Kaneta, Takayoshi*

Nippon Genshiryoku Gakkai-Shi, 42(3), p.196 - 203, 2000/03

 Times Cited Count:1 Percentile:86.57(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Study on treatment of miscellaneous solid waste by plasmas melting; Melting characteristics of plasma heating method

Fukui, Toshiki; Nakashio, Nobuyuki; Isobe, Motoyasu; Otake, Atsushi*; Wakui, Takuji*; Nakashima, Mikio; Hirabayashi, Takakuni*

Dai-7-Kai Doryoku Enerugi Gijutsu Shimpojiumu Koen Rombunshu (00-11), p.356 - 359, 2000/00

no abstracts in English

Journal Articles

Design study of helium turbine for the 300MW HTGR-GT power plant

Muto, Yasushi; Ishiyama, Shintaro; Fukuyama, Yoshitaka*; Okumoto, Junji*; Kishibe, Tadaharu*; Yamada, Seiya*

Proceedings of 45th ASME International Gas Turbine & Aeroengine Technical Congress, Exposition and Users Symposium (CD-ROM), 8 Pages, 2000/00

no abstracts in English

Journal Articles

Development of HTGR-GT power generation system, 1; Development status in Japan

; Miyamoto, Yoshiaki; Tanaka, Toshiyuki

Karyoku Genshiryoku Hatsuden, 50(9), p.1123 - 1130, 1999/09

no abstracts in English

Journal Articles

Preliminary design of 600MWt HTGR-gas turbine plant

; Miyamoto, Yoshiaki; Shiozawa, Shusaku

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

Journal Articles

Design study of helium turbine for the 600MWt HTGR-GT power plant

Muto, Yasushi; Ishiyama, Shintaro; *; Kishibe, Tadaharu*; Matsumoto, Iwao*

Proceedings of International Gas Turbine Congress 1999 Kobe, I, p.313 - 320, 1999/00

no abstracts in English

Journal Articles

Steady-state tokamak reactor:SSTR and A-SSTR

Kikuchi, Mitsuru

Purazuma, Kaku Yugo Gakkai-Shi, 74(9), p.944 - 946, 1998/09

no abstracts in English

Journal Articles

Recent design features of tokamak fusion reactors and issues in reactor plasma research

Kikuchi, Mitsuru

Purazuma, Kaku Yugo Gakkai-Shi, 74(8), p.787 - 794, 1998/08

no abstracts in English

Journal Articles

Nuclear power cogeneration systems using gas turbine

Fumizawa, Motoo; *; Yamada, Seiya*

Enerugi, Shigen, 18(5), p.73 - 78, 1997/09

no abstracts in English

Journal Articles

Technical evaluation of UT-3 thermochemical hydrogen production process for an industrial scale plant

; Kajiyama, Takeyoshi; *; *; *; *

International Journal of Hydrogen Energy, 22(1), p.49 - 56, 1997/00

no abstracts in English

JAEA Reports

Design of intermediate heat exchanger for the HTGR-closed cycle gas turbine power generation system

; Hada, Kazuhiko; Koikegami, Hajime*; Kisamori, Hiroyuki*

JAERI-Tech 96-042, 41 Pages, 1996/10

JAERI-Tech-96-042.pdf:1.35MB

no abstracts in English

JAEA Reports

JAEA Reports

Stationary analysis program code STEDFAST for space, terrestrial and deep sea fast reactor $$cdot$$ gas turbine power generation system (User's manual)

; Sekiguchi, Nobutada

PNC-TN9520 95-002, 66 Pages, 1995/02

PNC-TN9520-95-002.pdf:2.55MB

This analysis program code STEDFAST; Space, TErrestrial and Deep sea FAST reactor $$cdot$$ gas tubine system; is used to get the adequate values of system parameters on fast reactor $$cdot$$ gas turbine power generation systems used as power sources for deep sea, space and terrestrial cogeneration. Characteristics of the code are as follows. $$cdot$$ Objective systems of the code are a deep sea, a space and a terrestrial reactors. $$cdot$$ Primary coolants of the systems are NaK, Na, Pb and Li. Secondary coolant is the mixture gas of He and Xe. The ratio of He and Xe is arbitrary. $$cdot$$ Modeling of components in the systems was performed so that detailed modeling might be capable in future and that a transient analytical code could be easily made by using the code. $$cdot$$ A progra㎜ing language is MAC-FORTRAN. The code can be easily used in a personal computer. The code made possible instant calculation of various state values in a Brayton cycle, understanding the effects of many parameters on thermal efficiency and finding the most adequate values of the parameters. From now on, detailed modeling of the components will be performed. After that, the transient program code will be made.

Journal Articles

Evaporation of metal impregnated in porous material by electron beam heating; Measurement of surface temperature profile using a CCD camera

Oba, Hironori; Shibata, Takemasa

Nippon Kikai Gakkai Netsu Kogaku Koenkai Koen Rombunshu, 0, p.202 - 204, 1995/00

no abstracts in English

28 (Records 1-20 displayed on this page)