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Journal Articles

Designs of contraction nozzle and concave back-wall for IFMIF target

Ida, Mizuho*; Nakamura, Hideo; Nakamura, Hiroo; Takeuchi, Hiroshi

Fusion Engineering and Design, 70(2), p.95 - 106, 2004/02

 Times Cited Count:18 Percentile:73.97(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of in-vessel neutron monitor using micro-fission chambers for ITER

Yamauchi, Michinori*; Nishitani, Takeo; Ochiai, Kentaro; Morimoto, Yuichi*; Hori, Junichi; Ebisawa, Katsuyuki*; Kasai, Satoshi; Walker, C.*

Review of Scientific Instruments, 74(3), p.1730 - 1734, 2003/03

 Times Cited Count:22 Percentile:70.86(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Neutronics experiment of $$^{6}$$Li-enriched breeding blanket with Li$$_{2}$$TiO$$_{3}$$/Be/F82H assembly using D-T neutrons

Ochiai, Kentaro; Klix, A.; Hori, Junichi; Morimoto, Yuichi*; Wada, Masayuki*; Nishitani, Takeo

Journal of Nuclear Science and Technology, 39(Suppl.2), p.1147 - 1150, 2002/08

Thermal blanket type as one of conceptual designs for DEMO-fusion blanket is proposed. We have irradiated the trial blanket assembly which was stratified 95-% enriched Li2TiO3,F82H and beryllium block using Fusion Neutron Source (FNS) and verified the accuracy of these parameters by measurements of tritium and gamma-ray emitted from samples of95-% enriched Li2TiO3 and F82H. We have used the liquid scintillated counter as the method of tritium measurement. Activation foils, NE213, Si-SBD and Fission chamber have usedto measure neutron fluence. Moreover, we have concurrently measured the gamma rays of 56Mn, 54Mn, 187W and 51Cr was produced by 56Fe(n,p), 54Fe(n,p), 186W(n,g), 52Cr(n,2n) and 50Cr(n,g) in F82H. We have used the JENDL Fusion File library and MCNP to verify the accuracy tritium-production rate and 56Mn, 54Mn, 187W and 51Cr. From the results of above experiments, MCNP that uses the JENDL-FF nuclear data library can predict the nuclear parameters such as TPR, Nb, 56Mn, In and 54Mn in the test assemblies within an accuracy of 10%.

Journal Articles

Tritium measurements for $$^{6}$$Li-enriched Li$$_{2}$$TiO$$_{3}$$ breeding blanket experiments with D-T neutrons

Klix, A.; Ochiai, Kentaro; Terada, Yasuaki; Morimoto, Yuichi*; Yamauchi, Michinori*; Hori, Junichi; Nishitani, Takeo

Fusion Science and Technology, 41(3, Part2), p.1040 - 1043, 2002/05

$$^{6}$$Li-enriched Li$$_{2}$$TiO$$_{3}$$ is one of the candidate materials for the breeding blanket of the fusion DEMO reactor. Therefore, it is necessary to measure the tritium production performance and estimate the accuracy of the measurement method. The JAERI Fusion Neutronics Source (FNS) group has carried out experiments with breeding blanket mock-ups composed of layers of beryllium, ferritic steel F82H and enriched Li$$_{2}$$TiO$$_{3}$$. Pellets of enriched Li$$_{2}$$TiO$$_{3}$$ with a diameter of 12mm and a thickness of 2mm were used as detectors inside the tritium breeding layer. After irradiation, the pellets were dissolved and the tritium activity in the sample solution was measured by liquid scintillation counting. The experimentally obtained tritium production profile in the lithium titanate layer agreed well with MCNP calculations within the estimated error of the measured values (10%). The calculation-experiment ratio was close to one for all samples. Tritium loss from the pellet during storage time (a few days) was experimentally found to be negligible.

Journal Articles

JENDL Fusion File 99

Chiba, Satoshi; Fukahori, Tokio; Shibata, Keiichi; Yu, B.*; Kosako, Kazuaki*; Yamamuro, Nobuhiro*

Journal of Nuclear Science and Technology, 39(2), p.187 - 194, 2002/02

 Times Cited Count:16 Percentile:69.75(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Fusion reactor technology; Challenge to future energy

Seki, Masahiro; Hishinuma, Akimichi; Kurihara, Kenichi; Akiba, Masato; Abe, Tetsuya; Ishitsuka, Etsuo; Imai, Tsuyoshi; Enoeda, Mikio; Ohira, Shigeru; Okumura, Yoshikazu; et al.

Kaku Yugoro Kogaku Gairon; Mirai Enerugi Eno Chosen, 246 Pages, 2001/09

no abstracts in English

Journal Articles

Journal Articles

Activity report of Japanese Nuclear Data Committee in period of April 1995 to March 1997

Japanese Nuclear Data Committee

Nihon Genshiryoku Gakkai-Shi, 39(12), p.1019 - 1027, 1997/00

no abstracts in English

Journal Articles

Direct nuclear heating measurements and analyses for structural materials induced by deuterium-tritium neutrons

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

Fusion Technology, 28(1), p.156 - 172, 1995/08

no abstracts in English

Journal Articles

Experiment and analysis of induced radioactivity in large SS-316 stainless steel shielding material bombarded with 14MeV neutrons

Ikeda, Yujiro; Konno, Chikara; Maekawa, Fujio; Uno, Yoshitomo; Oyama, Yukio; Kosako, Kazuaki*; Maekawa, Hiroshi

Fusion Engineering and Design, 28, p.449 - 456, 1995/00

no abstracts in English

Journal Articles

First in situ measurement of electrical resistivity of ceramic insulator during irradiation with neutrons of energy 14MeV

Noda, Kenji; ; Oyama, Yukio; Maekawa, Hiroshi; *; Kinoshita, Chiken*

Fusion Engineering and Design, 29, p.448 - 454, 1995/00

 Times Cited Count:10 Percentile:69.2(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Scaling of Thermonuclear Fusion Neutron Yield on Doublet III Tokamak

*; ; ; *; ; ; ; T.Angel*; F.Blau*; R.Chase*; et al.

JAERI-M 87-038, 25 Pages, 1987/03

JAERI-M-87-038.pdf:0.8MB

no abstracts in English

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