Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 37

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

A Numerical simulation method for core internals behavior in severe accident conditions; Chemical reaction analyses in core structures by JUPITER

Yamashita, Susumu; Kino, Chiaki*; Yoshida, Hiroyuki

Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 7 Pages, 2020/08

In order to contribute the improvement of estimation accuracy for severe accident code such as SAMPSON, we have developed the chemical reaction model such as eutectic reaction and oxidation in micro scale, e.g., B$$_{4}$$C-SUS in the control rod blade and UO$$_{2}$$-Zry in fuel rods, and implemented them to the computational fluid dynamics code named JUPITER. And we try to develop the coupled analysis frame work using SAMPSON and JUPITER to decrease uncertainty due to micro scale phenomena which cannot be calculate by severe accident analysis codes. From the preliminary analysis in fuel rod heating analysis by JUPITER using SAMPSON output data, it was revealed that the implemented chemical reaction models work stably and obtain reasonable results.

Journal Articles

Status of the JENDL project

Iwamoto, Osamu; Shibata, Keiichi; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Ichihara, Akira; Nakayama, Shinsuke

EPJ Web of Conferences, 146, p.02005_1 - 02005_6, 2017/09

 Times Cited Count:0 Percentile:0.08

Journal Articles

Experimental study on U-Pu cocrystallization reprocessing process

Shibata, Atsuhiro; Oyama, Koichi; Yano, Kimihiko; Nomura, Kazunori; Koyama, Tomozo; Nakamura, Kazuhito; Kikuchi, Toshiaki*; Homma, Shunji*

Journal of Nuclear Science and Technology, 46(2), p.204 - 209, 2009/02

 Times Cited Count:6 Percentile:44.02(Nuclear Science & Technology)

A new reprocessing system with 2-stage crystallization process has been developed. In the first stage of the system, U and Pu are recovered from dissolver solution by U-Pu co-crystallization. Laboratory scale experiments were carried out with U and Pu mixed solution and irradiated fuel dissolver solution to obtain fundamental data on U-Pu co-crystallization process. Pu co-crystallized with U, but crystallization yields of Pu were lower than those of U. FPs were separated from U and Pu by co-crystallization, and decontamination factors of Cs and Eu to U in crystal were over 100.

JAEA Reports

Research and development on reduced-moderation light water reactor with passive safety features (Contract research)

Iwamura, Takamichi; Okubo, Tsutomu; Akie, Hiroshi; Kugo, Teruhiko; Yonomoto, Taisuke; Kureta, Masatoshi; Ishikawa, Nobuyuki; Nagaya, Yasunobu; Araya, Fumimasa; Okajima, Shigeaki; et al.

JAERI-Research 2004-008, 383 Pages, 2004/06

JAERI-Research-2004-008.pdf:21.49MB

The present report contains the achievement of "Research and Development on Reduced-Moderation Light Water Reactor with Passive Safety Features", which was performed by Japan Atomic Energy Research Institute (JAERI), Hitachi Ltd., Japan Atomic Power Company and Tokyo Institute of Technology in FY2000-2002 as the innovative and viable nuclear energy technology (IVNET) development project operated by the Institute of Applied Energy (IAE). In the present project, the reduced-moderation water reactor (RMWR) has been developed to ensure sustainable energy supply and to solve the recent problems of nuclear power and nuclear fuel cycle, such as economical competitiveness, effective use of plutonium and reduction of spent fuel storage. The RMWR can attain the favorable characteristics such as high burnup, long operation cycle, multiple recycling of plutonium (Pu) and effective utilization of uranium resources based on accumulated LWR technologies.

Journal Articles

Design of small reduced-moderation water reactor

Okubo, Tsutomu; Iwamura, Takamichi; Takeda, Renzo*; Moriya, Kumiaki*; Yamauchi, Toyoaki*; Aritomi, Masanori*

Nihon Kikai Gakkai 2003-Nendo Nenji Taikai Koen Rombunshu, Vol.3, p.245 - 246, 2003/08

A design study on a 300MWe class small Reduced-Moderation Water Reactor (RMWR) has been performed, based on the experienced LWR technology. The core can be cooled by the natural circulation and can achieve a conversion ratio of 1.01, a negative void reactivity coefficient, a core average burn-up of 65 GWd/t and a cycle length of 25 months. The system has been simplified as much as possible by introducing the passive safety components, in order to reduce the construction cost per electric power output overcoming “the scale demerit" for a small reactor comparing with the large one. The results show a 1.35 times higher cost than for the ABWR case, but suggest the possible lower cost when the effects such as the mass production are taken into account.

JAEA Reports

None

JNC TJ1420 2002-008, 166 Pages, 2003/02

JNC-TJ1420-2002-008.pdf:8.02MB

no abstracts in English

Journal Articles

Design of small Reduced-Moderation Water Reactor (RMWR) with natural circulation cooling

Okubo, Tsutomu; Suzuki, Motoe; Iwamura, Takamichi; Takeda, Renzo*; Moriya, Kumiaki*; Kanno, Minoru*

Proceedings of International Conference on the New Frontiers of Nuclear Technology; Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002) (CD-ROM), 10 Pages, 2002/10

A small scale around 300 MWe reduced-moderation water reactor (RMWR) concept has been developed. For the core, a BWR type core concept with the tight-lattice fuel rod arrangement and the high void fraction is adopted to attain a high conversion ratio over 1.0. The negative void reactivity coefficients are also required, and the very flat short core concept is adopted to make the natural circulation cooling (NC) possible. The core burn-up of 60 GWd/t and the operation cycle of 24 months are also attained. For the system, simplification of the system with the passive safety features is a basic approach to overcome the scale demerit as well as the NC. For example, the HPCF system is replaced with the passive accumulator system resulting in the expensive emergency DGs reduction. The cost evaluation for concerned NSSS components gives about 20% reduction. Since MOX fuels in the RMWR contains Pu around 30 wt% and is irradiated to a high burn-up, the fuel safety evaluation has been performed and the acceptable results have been obtained from the thermal feasibility point of view.

Journal Articles

Activities of design studies on innovative small and medium LWRs in JAERI

Iwamura, Takamichi; Ochiai, Masaaki

Proceedings of 1st Asian Specialist Meeting of Future Small-Sized LWR Development, p.7_1 - 7_9, 2001/00

JAERI has developed two types of small and medium size Light Water Reactors to meet the goals of innovative nuclear reactors such as sustainability and diversification of energy utilization. One is the Reduced-Moderation light Water Reactor (RMWR) with passive safety features. The reactor core consists of MOX fuel assemblies with tight lattice arrangement to increase the conversion ratio by reducing the moderation of neutron energy. The core design of 330MWe output with the operational cycle of 26 months was accomplished. A breeding ratio of 1.01, negative void coefficient and natural circulation cooling of the core were realized under the discharged burn-up of 60GWd/t. The other is the Passive Safe small Reactor for Distributed energy systems (PSRD) to diversify the nuclear energy utilization. An innovative advanced marine reactor (MRX) is used to supply the small grid electricity or electricity and heat co-supply by installing it on a barge. A small integral LWR for underground deployment is also studied for exclusive use of heat supply to household or office.

JAEA Reports

None

*; ; *; *

JNC TJ1420 2000-007, 241 Pages, 2000/03

JNC-TJ1420-2000-007.pdf:11.05MB

no abstracts in English

JAEA Reports

None

*; ; *; *

JNC TJ1420 2000-006, 132 Pages, 1999/11

JNC-TJ1420-2000-006.pdf:5.71MB

no abstracts in English

JAEA Reports

None

Takeuchi, Shinji

JNC TJ7440 99-019, 334 Pages, 1999/04

JNC-TJ7440-99-019.pdf:17.5MB

no abstracts in English

JAEA Reports

None

*; ; *; *

JNC TJ1400 99-024, 213 Pages, 1999/01

JNC-TJ1400-99-024.pdf:8.03MB

None

JAEA Reports

None

; Tsuchida, Toru*

PNC TJ1521 96-001, 141 Pages, 1996/02

PNC-TJ1521-96-001.pdf:5.31MB

None

JAEA Reports

Geological disposal concepts of Japan, II

Murano, Toru*; Tsuchida, Toru*; Hatano, Yuko*

JNC TJ1400 2005-027, 149 Pages, 1995/03

JNC-TJ1400-2005-027.pdf:5.09MB

JAEA Reports

None

PNC TJ1521 94-001, 152 Pages, 1994/03

PNC-TJ1521-94-001.pdf:4.89MB

None

JAEA Reports

None

PNC TJ1521 93-002, 97 Pages, 1993/02

PNC-TJ1521-93-002.pdf:3.32MB

None

JAEA Reports

None

PNC TJ1521 93-001, 138 Pages, 1993/02

PNC-TJ1521-93-001.pdf:4.11MB

None

JAEA Reports

Geological disposal concepts of Japan (IV)

Murano, Toru*; Sato, Tomio*

PNC TJ1521 92-001, 215 Pages, 1992/02

PNC-TJ1521-92-001.pdf:6.78MB

None

JAEA Reports

None

PNC TJ1521 92-002, 96 Pages, 1991/12

PNC-TJ1521-92-002.pdf:3.2MB

None

JAEA Reports

None

PNC TJ1521 91-001, 128 Pages, 1991/05

PNC-TJ1521-91-001.pdf:4.24MB

no abstracts in English

37 (Records 1-20 displayed on this page)