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Journal Articles

Development of granulation system for simplified MOX pellet fabrication process

Ishii, Katsunori; Segawa, Tomoomi; Kawaguchi, Koichi; Suzuki, Masahiro

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 5 Pages, 2019/05

Japan Atomic Energy Agency (JAEA) is developing a simplified pelletizing process for MOX fuel fabrication. In this process, the flowability of MOX powder produced by de-nitration conversion based on microwave heating, calcination, and reduction is improved using the wet granulation method. In a previous paper, to produce MOX granules of appropriate sizes for pelletizing them effectively, we proposed a granulation system composed of a wet granulator and a sizing machine. In the present work, we modernized the wet granulator, completed the granulation system by adding auxiliary equipment, and conducted performance tests of the granulation system with WO$$_{3}$$ powder. The results of a performance test indicated that it is possible to convert raw powder into granules characterized by appropriate size and excellent flowability. The time required to process 5 kg of WO$$_{3}$$ powder was about 70 min, which almost satisfies the target time.

JAEA Reports

Studies on sodium cooled fast breeder reactor

Nibe, Nobuaki; Shimakawa, Yoshio; ; ; ; ;

JNC-TN9400 2000-074, 388 Pages, 2000/06

JNC-TN9400-2000-074.pdf:13.32MB

Large sized sodium-cooled fast breeder reactors of large-size are being studied and have been operated in Japan and many countries. ln this feasibility study, evaluation was made on technical feasibinty for design concepts or 1 loop type and 3 pool types, specially from the viewpoint of improvement of economical competence. The design concepts include the ideas of cost reduction measures such as large-scaled components, reduction of loop number and integration of components on the basic of utilization of sodium characteristics. From the results of the evaluation, it may be possible for all the concepts to attain the economical target of 200 thousands yen per kilowatt, though further confirmation should be made for technical feasibility of those concepts. ln addition, the following items were listed up as further cost-reduction measures. (1)Higher temperature cooling system and steam cycle efficiency (2)Shortening of construction term (3)Reduction of safety systems by using measuring instruments with high performmce (4)Adoption of SG-ACS

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.

JAEA Reports

None

; Ojima, Hisao

PNC-TN8410 97-220, 33 Pages, 1997/12

PNC-TN8410-97-220.pdf:1.63MB

None

Journal Articles

Development of a power divider in the $$H$$ plane using posts in a rectangular waveguide for the next generation lower hybrid current drive antenna

Seki, Masami; Maebara, Sunao; ; Ikeda, Yoshitaka; Imai, Tsuyoshi; Hirokawa, Jiro*; Arai, Hiroyuki*

Fusion Engineering and Design, 36(2-3), p.281 - 287, 1997/05

 Times Cited Count:0 Percentile:100

no abstracts in English

JAEA Reports

None

Hirata, Yoichi*; *; *

PNC-TJ7439 96-002, 88 Pages, 1996/03

PNC-TJ7439-96-002.pdf:2.7MB

no abstracts in English

Journal Articles

Analysis of E-plane multi-junctional power divider for LHCD plasma heating

Ueda, Hiroyuki*; Takizawa, Yasuhiro*; Arai, Hiroyuki*; Seki, Masami; Maebara, Sunao;

Proceedings of 1996 Asia-Pacific Microwave Conference (APMC '96), 4 Pages, 1996/00

no abstracts in English

Journal Articles

High reflection LH experiments with the JT-60U launcher with oversized waveguides

Tuccillo, A. A.*; S.Podda*; Seki, Masami; Asakura, Nobuyuki; Ide, Shunsuke; Ikeda, Yoshitaka; Kimura, Haruyuki; Kondoh, Takashi; Naito, Osamu; Ushigusa, Kenkichi; et al.

AIP Conference Proceedings 355, p.114 - 117, 1995/00

no abstracts in English

Journal Articles

Conceptual design of integrated reactor with inherent safery

Asahi, Yoshiro; *; *

Nuclear Technology, 91, p.28 - 50, 1990/07

 Times Cited Count:2 Percentile:67.17(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Study on the condition of MOX granules suitable for constant die filling in MOX fuel pellet production

Akashi, Masatoshi; Nishina, Masahiro; Morimoto, Kyoichi; Kato, Yoshiyuki; Kato, Masato

no journal, , 

A die filling experiment was carried out using granulated MOX powder to investigate the condition of MOX granules suitable for constant die filling. It was found that the mean particle diameter and the Hausner ratio gave an indication of the die filling for the granulated MOX powder.

Oral presentation

Development of flowability improvement technology for MOX powder by wet granulation; Performance evaluation of granulator

Ishii, Katsunori; Segawa, Tomoomi; Kawaguchi, Koichi; Suzuki, Masahiro

no journal, , 

To develop flowability improvement technology for the simplified pelletizing process, a simple granulator with little powder adhesion, was experimentally produced. To know the performance of the granulator, granulation experiments was conducted by using dummy powder.

Oral presentation

Development of flowability improvement technology for MOX powder by wet granulation; Experiments on size distribution control of granulated powder

Ishii, Katsunori; Kawaguchi, Koichi; Segawa, Tomoomi; Suzuki, Masahiro

no journal, , 

JAEA is developing the simplified pelletizing process as advanced MOX fuel fabrication technology in the future. The standardizer could eliminate coarse particles from granules produced by wet granulator without degradation of flowability.

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