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Kondo, Keitaro; Takagi, Satoshi*; Murata, Isao*; Miyamaru, Hiroyuki*; Takahashi, Akito*; Kubota, Naoyoshi; Ochiai, Kentaro; Nishitani, Takeo
Fusion Engineering and Design, 81(8-14), p.1527 - 1533, 2006/02
Times Cited Count：14 Percentile：68.12(Nuclear Science & Technology)In a fusion reactor development, double-differential charged-particle emission cross sections(DDXc) are necessary to estimate nuclear heating and material damages of candidate materials irradiated with neutrons. Especially in light nuclei such as Be, Li, and C, nuclear reactions are complicated and difficult to estimate energy spectra of emitted particles based only on theoretical calculations Therefore development of a new technique for precise measurements of DDXc is quite important. Recently we successfully developed a new spectrometer for measurement of DDXc using a pencil-beam DT neutron source of FNS in JAERI. In the present study we carried out measurements of DDXc of 
Be, 
C, 
F, and 
Al using the spectrometer. The present technique was valid from the result of measurement for the Al(n,x
) reactions. Slight differences appeared between measured data and evaluation or previous experimental values for Be(n,x) reactions at backward scattering angle and in lower energy region.
Sato, Satoshi; Verzilov, Y. M.; Ochiai, Kentaro; Nakao, Makoto*; Wada, Masayuki*; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori*; Nishitani, Takeo
Fusion Engineering and Design, 81(8-14), p.1183 - 1193, 2006/02
Times Cited Count：19 Percentile：77.5(Nuclear Science & Technology)no abstracts in English
Ikeda, Yujiro; Konno, Chikara; Kosako, Kazuaki*; Oyama, Yukio; Maekawa, Fujio; Maekawa, Hiroshi; A.Kumar*; M.Z.Youssef*; M.A.Abdou*
Fusion Technology, 21(3), p.2190 - 2196, 1992/05
no abstracts in English
JAERI-M 92-025, 171 Pages, 1992/02
no abstracts in English
JAERI-M 89-074, 109 Pages, 1989/06
no abstracts in English
Kwon, Saerom; Ota, Masayuki; Ochiai, Kentaro; Sato, Satoshi; Konno, Chikara
no journal, ,
A benchmark experiment on copper with DT neutron source was performed 20 years ago at JAEA/FNS. However, the calculated results tended to underestimate the measured data related to lower energy neutrons below a few keV in the experiment, which suggested that the measured data might be affected by neutrons scattered in the concrete wall of the experiment room or other surroundings. Therefore, we have carried out an additional integral experiment on copper, where a copper assembly was covered with Li
O blocks to reduce neutrons scattered in the concrete wall. We used the Monte Carlo neutron transport code, MCNP5-1.40 and the recent nuclear data libraries, ENDF/B-VII.1, JEFF-3.2, JENDL-4.0 and FENDL-3.0 (ENDF/B-VII.0) for the experiment analysis. JENDL/D-99 was used as dosimetry cross section data. The calculated reaction rates of the 
Au(n,
)
Au reaction with all the nuclear data libraries still underestimate the measured data, although the underestimation was improved compared to the previous result with JENDL-4.0 in particular. We found out that the nuclear data of copper caused this underestimation problem.
Ochiai, Kentaro
no journal, ,
It was presented the comprehensive tritium recovery experiment of blanket mock-up assemblies irradiated DT neutron source of JAEA/FNS facility. Especially, the both dependencies of temperature and time response was reported. In addition, based on past result, It was suggested it about simulating blanket irradiation experiment plan by A-FNS which JAEA is planning to construct as next intense neutron source for DEMO reactor and ITER test blanket module.
