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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:10 Percentile:57.51(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:13 Percentile:65.10(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

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:7 Percentile:44.40(Nuclear Science & Technology)

no abstracts in English

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:4 Percentile:28.95(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

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

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

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

JAEA Reports

Report of Joint Research Committee for Fusion Reactor and Materials; July 16, 2001, Tokyo, Japan

Research Committee for Fusion Reactor; Research Committee for Fusion Materials

JAERI-Review 2002-008, 79 Pages, 2002/03

JAERI-Review-2002-008.pdf:9.92MB

Joint research committee for fusion reactor and materials was held in Tokyo on July 16, 2001. In the committee, a review of the development programs and the present status on the blanket technology, materials and IFMIF(International Fusion Materials Irradiation Facility) in JAERI and Japanese Universities was reported, and the direction of these R&D was discussed. Moreover, the progress of the collaboration between JAERI and Japanese Universities was discussed. This report consists of the summaries of the presentations and the viewgraphs which were used at the committee.

JAEA Reports

Conceptual design of solid breeder blanket system cooled by supercritical water

Enoeda, Mikio; Ohara, Yoshihiro; Akiba, Masato; Sato, Satoshi; Hatano, Toshihisa; Kosaku, Yasuo; Kuroda, Toshimasa*; Kikuchi, Shigeto*; Yanagi, Yoshihiko*; Konishi, Satoshi; et al.

JAERI-Tech 2001-078, 120 Pages, 2001/12

JAERI-Tech-2001-078.pdf:8.3MB

This report is a summary of the design works, which was discussed in the design workshop held in 2000 for the demonstration (DEMO) blanket aimed to strengthen the commercial competitiveness and technical feasibility simultaneously. The DEMO blanket must supply the feasibility and experience of the total design of the power plant and the materials. This conceptual design study was performed to determine the updated strategy and goal of the R&D of the DEMO blanket which applies the supercritical water cooling proposed in A-SSTR, taking into account the recent progress of the plasma research and reactor engineering technology.

Journal Articles

Experimental study on beryllium-7 production via sequential reactions in lithium-containing compounds irradiated by 14-MeV neutrons

Maekawa, Fujio; Verzilov, Y.M.*; Smith, D. L.*; Ikeda, Yujiro

Journal of Nuclear Materials, 283-287(Part.2), p.1448 - 1452, 2000/12

 Times Cited Count:6 Percentile:42.14(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Neutronic design of pulse operation simulating device for in-pile functional test of fusion blanket by MCNP

Nagao, Yoshiharu; Nakamichi, Masaru; Kawamura, Hiroshi

Journal of Nuclear Science and Technology, 37(Suppl.1), p.423 - 426, 2000/03

no abstracts in English

Journal Articles

Development of ceramic breeder blankets in Japan

Takatsu, Hideyuki; Kawamura, Hiroshi; Tanaka, Satoru*

Fusion Engineering and Design, 39-40, p.645 - 650, 1998/09

 Times Cited Count:17 Percentile:77.51(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Design of test blanket system for ITER module testing

Miura, H.*; Sato, Satoshi; Enoeda, Mikio; Kuroda, Toshimasa*; Takatsu, Hideyuki; Kawamura, Yoshinori; Tanaka, Satoru*

JAERI-Tech 97-051, 51 Pages, 1997/10

JAERI-Tech-97-051.pdf:1.91MB

no abstracts in English

Journal Articles

Design development of breeding blanket based on pebble bed concept for fusion experimental reactor

Miura, H.*; ; ; Takatsu, Hideyuki; Kuroda, Toshimasa*; Sato, Satoshi; Furuya, Kazuyuki; Hatano, Toshihisa; Kurasawa, Toshimasa; ; et al.

Fusion Technology 1996, 0, p.1339 - 1342, 1997/00

no abstracts in English

JAEA Reports

Phase III experiments of the JAERI/USDOE collaborative program on fusion blanket neutronics - Line source and annular blanket experiments, Volume I; Experiment

Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; Maekawa, Fujio; Kosako, Kazuaki*; Nakamura, Tomoo; Maekawa, Hiroshi; M.Z.Youssef*; A.Kumar*; M.A.Abdou*; et al.

JAERI-M 94-015, 193 Pages, 1994/02

JAERI-M-94-015.pdf:6.62MB

no abstracts in English

Journal Articles

JAERI/USDOE collaborative experiments on fusion blanket neutronics

Oyama, Yukio

NCC Nyusu, 0(18), p.17 - 23, 1994/00

no abstracts in English

24 (Records 1-20 displayed on this page)