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Journal Articles

The Integral experiment on beryllium with D-T neutrons for verification of tritium breeding

Verzilov, Y. M.; Sato, Satoshi; Ochiai, Kentaro; Wada, Masayuki*; Klix, A.*; Nishitani, Takeo

Fusion Engineering and Design, 82(1), p.1 - 9, 2007/01

 Times Cited Count:4 Percentile:63.42(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Neutronics design of the low aspect ratio tokamak reactor, VECTOR

Nishitani, Takeo; Yamauchi, Michinori*; Nishio, Satoshi; Wada, Masayuki*

Fusion Engineering and Design, 81(8-14), p.1245 - 1249, 2006/02

 Times Cited Count:12 Percentile:29.48(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Neutron shielding and blanket neutronics study on low aspect ratio tokamak reactor

Yamauchi, Michinori*; Nishitani, Takeo; Nishio, Satoshi

Denki Gakkai Rombunshi, A, 125(11), p.943 - 946, 2005/11

Considering the geometrical characteristics of tokamak reactors with low aspect ratio, a basic neutronics strategy was derived to construct the inboard structure mainly for neutron shielding and produce enough tritium in the outboard blanket. The designs for optimal inboard shield were surveyed and necessary thickness was estimated to make the neutron flux low enough on the super-conducting magnet. In addition, the outer blanket designs were studied to attain the tritium breeding ratio (TBR) large enough for a self-sustaining fusion reactor on the basis of the advanced fusion reactor materials.

Journal Articles

Investigation on Innovative Water Reactor for Flexible Fuel Cycle (FLWR), 2; Recycle characteristics

Okubo, Tsutomu; Uchikawa, Sadao; Kugo, Teruhiko; Akie, Hiroshi; Takeda, Renzo*

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10

In order to ensure sustainable energy supply in the future based on the commercialized LWR technologies, a concept of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) has been investigated in JAERI. Results on the FLWR recycling characteristics under possible various reprocessing schemes are presented in the present paper. The results show the recycling is possible a few times at most as long as the fissile Pu content stays over 60%, even in the high conversion type core with the conversion ratio around 0.9, under the simplified PUREX reprocessing, with relatively high average decontamination factor. For breeding core, the results have indicated that even under the reprocessing with relatively low DFs and with whole MA, the recycling is also feasible, suggesting all MAs from the core can be possibly recycled itself, although the core performances are a little degraded depending on MA and FP contents.

Journal Articles

Investigation on Innovative Water Reactor for Flexible Fuel Cycle (FLWR), 1; Conceptual design

Uchikawa, Sadao; Okubo, Tsutomu; Kugo, Teruhiko; Akie, Hiroshi; Nakano, Yoshihiro; Onuki, Akira; Iwamura, Takamichi

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10

no abstracts in English

Journal Articles

Research for thermal-hydraulic performance in tight-lattice fuel assembly, 1; Outline of research program

Akimoto, Hajime; Tamai, Hidesada; Onuki, Akira; Takase, Kazuyuki

Nippon Konsoryu Gakkai Nenkai Koenkai 2005 Koen Rombunshu, p.229 - 230, 2005/08

A thermal-hydraulic research program for Reduced-Moderation Water Reactor (RMWR) has been performed since 2002. The RMWR has a tight-lattice core to attain the breeding of nuclear fuel for the effective use of Plutonium in a light-water reactor system. In this R&D program, large-scale thermal-hydraulic tests, several model experiments and development of advanced numerical analysis codes are being carried out to confirm the cooling performance in tight-lattice fuel assembly of the RMWR. In this paper, outline of the research program is described as well as the latest results of critical power measurement in the large-scale thermal-hydraulic tests and model experiments, which simulates the tight-lattice core of the RMWR.

Journal Articles

Methods for tritium production rate measurement in design-oriented blanket experiments

Verzilov, Y. M.; Ochiai, Kentaro; Nishitani, Takeo

Fusion Science and Technology, 48(1), p.650 - 653, 2005/07

 Times Cited Count:6 Percentile:53.71(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Concept of Innovative Water Reactor for Flexible Fuel Cycle (FLWR)

Iwamura, Takamichi; Uchikawa, Sadao; Okubo, Tsutomu; Kugo, Teruhiko; Akie, Hiroshi; Nakatsuka, Toru

Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13) (CD-ROM), 8 Pages, 2005/05

In order to ensure sustainable energy supply in the future based on the matured Light Water Reactor (LWR) and coming LWR-Mixed Oxide (MOX) technologies, a concept of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) has been investigated in Japan Atomic Energy Research Institute (JAERI). The concept consists of two parts in the chronological sequence. The first part realizes a high conversion type core concept, which is basically intended to keep the smooth technical continuity from current LWR without significant gaps in technical point of view. The second part represents the Reduced-Moderation Water Reactor (RMWR) core concept, which realizes a high conversion ratio over 1.0 being useful for the long-term sustainable energy supply through plutonium multiple recycling based on the well-experienced LWR technologies. The key point is that the two core concepts utilize the compatible and the same size fuel assemblies, and hence, the former concept can proceed to the latter in the same reactor system, based flexibly on the fuel cycle circumstances.

Journal Articles

Preliminary evaluation of reduction of prediction error in breeding light water reactor core performance

Kugo, Teruhiko; Kojima, Kensuke; Ando, Masaki; Okajima, Shigeaki; Mori, Takamasa; Takeda, Toshikazu*; Kitada, Takanori*; Matsuoka, Shogo*

Proceedings of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP '05) (CD-ROM), 10 Pages, 2005/05

We have preliminarily evaluated the reduction of prediction errors of the core characteristics of the breeding light water reactor core based on the bias factor method by utilizing the FCA critical experiments carried out for MOX fueled tight lattice light water reactor cores. The prediction uncertainty of k$$_{eff}$$ is reduced from 0.62% to 0.39% by utilizing the FCA-XV-2 (65V) result. As for the reaction rate ratio of $$^{238}$$U capture and $$^{239}$$Pu fission, it is found that the FCA XXII-1 (95V) and XV (95V) results are suitable for the upper core and the upper blanket of the real core and the FCA XXII-1 (65V) and XV-2 (65V) results are suitable for the lower core and the internal blanket.

Journal Articles

Characteristics of severe accidents of Reduced-Moderation Water Reactor (RMWR)

Yonomoto, Taisuke; Akie, Hiroshi; Kobayashi, Noboru; Okubo, Tsutomu; Uchikawa, Sadao; Iwamura, Takamichi

Proceedings of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations and Safety (NUTHOS-6) (CD-ROM), 11 Pages, 2004/10

Reduced-Moderation Water Reactor (RMWR) is a light-water cooled high-conversion reactor that is being developed by JAERI with collaboration from the Japanese industries. Since RMWR utilizes the highly enriched plutonium, the safety concern for RMWR includes the possibility of recriticality during severe accidents as is the case with the liquid metal cooled fast breeder reactor. In order to clarify this concern, characteristics of severe accidents of RMWR are analyzed in this study. The results obtained so far indicate that (1) the mechanical impact of recriticality in the core, if occurs, is supposed to be insignificant due to the absence of water, (2) the mixture of the fuel and cladding debris in the lower plenum does not cause recriticality when they are well mixed and distributed flatly, and (3) if requires, the installation of neutron-absorption material with realistic geometry can effectively prevent recriticality in the lower plenum even for the conservatively-assumed spherical accumulation of core debris.

Journal Articles

Non-destructive analysis of impurities in beryllium, affecting evaluation of the tritium breeding ratio

Verzilov, Y. M.; Ochiai, Kentaro; Klix, A.; Sato, Satoshi; Wada, Masayuki*; Yamauchi, Michinori*; Nishitani, Takeo

Journal of Nuclear Materials, 329-333(Part2), p.1337 - 1341, 2004/08

 Times Cited Count:3 Percentile:73(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Analysis of impurities in beryllium, affecting evaluation of the tritium breeding ratio

Verzilov, Y. M.; Ochiai, Kentaro; Sato, Satoshi; Wada, Masayuki*; Yamauchi, Michinori*; Nishitani, Takeo

JAERI-Research 2004-005, 30 Pages, 2004/03

JAERI-Research-2004-005.pdf:1.93MB

no abstracts in English

JAEA Reports

Summary of the 2nd Workshop on Ion Beam-applied Biology; November 21, 2003, JAERI, Takasaki

Shikazono, Naoya; Hase, Yoshihiro; Sakamoto, Ayako; Ono, Yutaka; Tanaka, Atsushi

JAERI-Conf 2004-001, 72 Pages, 2004/03

JAERI-Conf-2004-001.pdf:4.88MB

Induction of novel plant resources by ion beam-irradiation has been investigated in JAERI. To share the knowledge of the present status of the field, and to find out future plans, 1st Workshop on ion beam-applied biology was held last year by Department of Ion-beam-Applied Biology. To further improve the research cooperation and to exchange useful information in the field, researchers inside JAERI and also with researchers outside, such as those from Universities, Research institutes, agricultural experiment stations, and companies, met each other at the 2nd workshop on ion beam-applied biology. This workshop was held by Department of Ion-beam-Applied Biology on November 21, 2003 under the joint auspices of Kanto $$cdot$$ Kouetsu branch of Atomic Energy Society of Japan, Breeding Science Society of Japan, and Genetics Society of Japan, and 134 people participated. Highly qualified presentations were given on studies with new irradiation techniques, on novel varieties, and on future plans. Many more new plant resources are now expected to be produced by ion beam irradiation.

Journal Articles

Development of supercritical pressure water cooled solid breeder blanket in JAERI

Akiba, Masato; Ishitsuka, Etsuo; Enoeda, Mikio; Nishitani, Takeo; Konishi, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 79(9), p.929 - 934, 2003/09

no abstracts in English

Journal Articles

Present research status on divertor and plasma facing components for fusion power plants

Suzuki, Satoshi; Ueda, Yoshio*; Tokunaga, Kazutoshi*; Sato, Kazuyoshi; Akiba, Masato

Fusion Science and Technology, 44(1), p.41 - 48, 2003/07

 Times Cited Count:14 Percentile:25.64(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Nuclear, thermo-mechanical and tritium release analysis of ITER breeding blanket

Kosaku, Yasuo; Kuroda, Toshimasa*; Enoeda, Mikio; Hatano, Toshihisa; Sato, Satoshi; Sato, Shinichi*; Osaki, Toshio*; Miki, Nobuharu*; Akiba, Masato

JAERI-Tech 2003-058, 69 Pages, 2003/06

JAERI-Tech-2003-058.pdf:5.86MB

The design of the breeding blanket in ITER applies pebble bed breeder in tube (BIT) surrounded by multiplier pebble bed. It is assumed to use the same module support mechanism and coolant manifolds and coolant system as the shielding blankets. This work focuses on the verification of the design of the breeding blanket, from the viewpoints which is especially unique to the pebble bed type breeding blanket, such as, tritium breeding performance, tritium inventory and release behavior and thermo-mechanical performance of the ITER breeding blanket.

JAEA Reports

Report of the 2nd Joint Research Committee for Fusion Reactor and Materials; July 12, 2002, Tokyo, Japan

Research Committee for Fusion Reactor; Research Committee for Fusion Materials

JAERI-Review 2003-015, 123 Pages, 2003/05

JAERI-Review-2003-015.pdf:24.89MB

no abstracts in English

Journal Articles

Wide variety of flower-color and -shape mutants regenerated from leaf cultures irradiated with ion beams

Okamura, Masachika*; Yasuno, Noriko*; Otsuka, Masako*; Tanaka, Atsushi; Shikazono, Naoya; Hase, Yoshihiro

Nuclear Instruments and Methods in Physics Research B, 206, p.574 - 578, 2003/05

 Times Cited Count:64 Percentile:2.49

Resent studies indicate that the ion beams have higher mutation frequency than low-LET radiations in plants but the difference in mutation spectrum still remains to be characterized. We investigated the efficiency of ion-beam irradiation combined with tissue culture in obtaining floral mutants. Leaves collected from carnation plants, cultivar Vital (cherry pink flowers with frilly petals), were irradiated with carbon ions or X-rays. They were cultured till the shoots regenerated. Sixteen mutants were obtained from 705 regenerated plants by carbon-ion irradiation. Those mutants were rich in variety, i.e., pink, dark pink, light pink, salmon, red, complex- and striped-color, and round and Dianthus-type petals were obtained. In contrast, 7 mutants obtained from 556 regenerated plants by X-rays were only pink, light pink and red. These results indicate that the ion beams could induce wider variety of flower-color and shape mutant than X-rays, and also indicate that the combined method of ion-beam irradiation with tissue culture is useful to obtain commercial varieties in a short time.

JAEA Reports

Experimental study of material activation of reduced activation ferritic steel F82H by D-T neutron irradiation

Terada, Yasuaki*; Ochiai, Kentaro; Sato, Satoshi; Wada, Masayuki*; Klix, A.; Yamauchi, Michinori*; Hori, Junichi; Nishitani, Takeo

JAERI-Research 2002-019, 70 Pages, 2002/10

JAERI-Research-2002-019.pdf:8.47MB

D-T neutron irradiation experiments have been carried out with a F82H-containing breeding blanket mock-up of a fusion in order to investigate the activation characteristics of F82H low activation stainless steel. We have measured reaction rates producing 54Mn, 56Mn, 51Cr and 187W in foils of F82H, chromium and tungsten. MCNP calculations were done with evaluated nuclear data from the JENDL-3.2 and the FENDL/E-2.0 files and the results were compared with the measured values. The comparison shows that by using the current data files the reaction rates obtained from the calculations will be overestimated by up to 10-20% for 54Mn, 56Mn and 51Cr, up to 30-40% for 187W, respectively. The calculated values for tungsten are different with the evaluated nuclear data library, which shows that the neutron capture cross sections of tungsten have discrepancy in the resonance region for each nuclear data libraries.

JAEA Reports

Thermal cycle test of elemental mockups of ITER breeding blanket

Yanagi, Yoshihiko*; Kosaku, Yasuo; Hatano, Toshihisa; Kuroda, Toshimasa*; Enoeda, Mikio; Akiba, Masato

JAERI-Tech 2002-046, 45 Pages, 2002/05

JAERI-Tech-2002-046.pdf:2.61MB

no abstracts in English

51 (Records 1-20 displayed on this page)