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Journal Articles

Shutdown dose evaluation experiment for ITER

Morimoto, Yuichi*; Ochiai, Kentaro; Sato, Satoshi; Hori, Junichi; Yamauchi, Michinori*; Nishitani, Takeo

Fusion Engineering and Design, 69(1-4), p.643 - 648, 2003/09

 Times Cited Count:4 Percentile:31.64(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Histrory of benchmark experiment analysis with Monte Carlo mehtod for nuclear data reliability evaluation

Sakurai, Kiyoshi; Ueki, Kotaro*

Nihon Genshiryoku Gakkai-Shi, 43(4), p.351 - 352, 2001/04

no abstracts in English

Journal Articles

Benchmark experiment on LiAlO$$_{2}$$, Li$$_{2}$$TiO$$_{3}$$ and Li$$_{2}$$ZrO$$_{3}$$ assemblies with D-T neutrons; Leakage neutron spectrum measurement

Murata, Isao*; Nishio, T.*; Kokooo*; Kondo, T.*; Takagi, H.*; Nakano, D.*; Takahashi, Akito*; Maekawa, Fujio; Ikeda, Yujiro; Takeuchi, Hiroshi

Fusion Engineering and Design, 51-52(Part.B), p.821 - 827, 2000/11

 Times Cited Count:8 Percentile:50.62(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Benchmark experiment on vanadium assembly with D-T Neutrons; Leakage neutron spectrum measurement

Kokooo*; Murata, Isao*; Nakano, D.*; Takahashi, Akito*; Maekawa, Fujio; Ikeda, Yujiro

Fusion Technology, 34(3), p.980 - 984, 1998/11

no abstracts in English

Journal Articles

Benchmark experiment on vanadium-alloy assembly with D-T neutrons; In-situ measurement

Maekawa, Fujio; Kasugai, Yoshimi; Konno, Chikara; Wada, Masayuki*; Oyama, Yukio; Ikeda, Yujiro; R.Johnson*; E.T.Cheng*; M.Pillon*; Murata, Isao*; et al.

Fusion Technology, 34(3), p.1018 - 1022, 1998/11

no abstracts in English

Journal Articles

Some comments for cross section data of iron around 15 MeV

Konno, Chikara; Maekawa, Fujio; Wada, Masayuki*; Kosako, Kazuaki*

Fusion Technology, 34(3), p.1013 - 1017, 1998/11

no abstracts in English

Journal Articles

Benchmark experiments of effective delayed neutron fraction $$beta$$$$_{eff}$$ in JAERI-FCA

Sakurai, Takeshi; Okajima, Shigeaki; ; Osugi, Toshitaka; M.Martini*; P.Chaussonnet*; H.Philibert*; I.P.Matveenko*; S.P.Belov*; V.A.Doulin*; et al.

Proc. of Int. Conf. on Physics of Nucl. Science and Technol., 1, p.182 - 189, 1998/00

no abstracts in English

Journal Articles

Status of international benchmark experiment for effective delayed neutron fraction ($$beta$$$$_{eff}$$)

Okajima, Shigeaki; Sakurai, Takeshi; Mukaiyama, Takehiko

JAERI-Conf 97-005, 00(00), p.71 - 76, 1997/00

no abstracts in English

Journal Articles

Pre-evaluation of fusion shielding benchmark experiment

*; *; Konno, Chikara; Maekawa, Fujio; Maekawa, Hiroshi; *; *; *

Fusion Engineering and Design, 28, p.525 - 533, 1995/00

no abstracts in English

JAEA Reports

Oral presentation

A New benchmark experiment on copper with DT neutron source at JAEA/FNS

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$$_{2}$$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 $$^{197}$$Au(n,$$gamma$$)$$^{198}$$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.

Oral presentation

Problems on ENDF/B-VIII.0 and JEFF-3.3 copper nuclear data above a few MeV

Kwon, Saerom*; Konno, Chikara; Ota, Masayuki*; Sato, Satoshi*

no journal, , 

Our analyses of JAEA/FNS copper benchmark experiment with ENDF/B-VIII.0 and JEFF-3.3 pointed out that the calculation with ENDF/B-VIII.0 underestimated and that with JEFF-3.3 overestimated the measured reaction rate of the $$^{93}$$Nb(n,2n)$$^{rm 92m}$$Nb sensitive to neutrons above 10 MeV. As a result of our detailed study, we specified that this issue was due to the (n,np) and (n,n') reaction data above a few MeV, etc.

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