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Journal Articles

Analysis of fission with selective channel scission model

Ota, Masayuki; Nakamura, Shoji

JAEA-Conf 2006-009, p.145 - 150, 2006/11

no abstracts in English

Journal Articles

Analysis of fission with selective channel scission model

Ota, Masayuki; Nakamura, Shoji

JAEA-Conf 2006-009, p.145 - 150, 2006/11

no abstracts in English

Journal Articles

Measurement of neutron capture cross sections

Nakamura, Shoji; Laptev, A.; Ota, Masayuki; Harada, Hideo; Fujii, Toshiyuki*; Yamana, Hajimu*

JAEA-Conf 2006-009, P. 65, 2006/11

no abstracts in English

Journal Articles

Photoneutron cross section measurement for $$^{94}$$Zr using laser inverse Compton $${gamma}$$ rays

Hohara, Shinya*; Goko, Shinji*; Makinaga, Ayano*; Kaihori, Takeshi*; Toyokawa, Hiroyuki*; Utsunomiya, Hiroaki*; Hara, Kaoru; Kitatani, Fumito; Harada, Hideo; Matsumoto, Tetsuro*; et al.

JAEA-Conf 2006-009, p.66 - 69, 2006/11

no abstracts in English

Journal Articles

Integral comparison of library performance

Mori, Takamasa

JAEA-Conf 2006-009, p.52 - 57, 2006/11

The 2003-2004 activities of Reactor Integral Test WG under Subcommittee on Reactor Constants of Japanese Nuclear Data Committee are presented. During this period, the WG carried out integral tests of JENDL-3.3, ENDF/B-VI and JEF 2.2 (JEFF-3.0) for reactor applications. Some results of integral tests for other latest libraries, JEFF-3.1 and ENDF/B-VII are also presented.

Journal Articles

Measurement of neutron production spectra at the forward direction from thick graphite, aluminum, iron and lead targets bombarded by 250 MeV protons

Iwamoto, Yosuke; Taniguchi, Shingo*; Nakao, Noriaki*; Itoga, Toshio*; Nakamura, Takashi*; Nakane, Yoshihiro; Nakashima, Hiroshi; Satoh, Daiki; Yashima, Hiroshi*; Yamakawa, Hiroshi*; et al.

JAEA-Conf 2006-009, p.118 - 123, 2006/11

Neutron energy spectra produced at the forward direction from thick graphite, aluminum, iron and lead targets bombarded by 250 MeV protons were measured by the TOF method at RCNP of Osaka University. The experimental data were compared with the calculated results of the PHITS, MCNPX codes. All calculations give lower neutron energy spectra than the experimental ones for all targets above 20 MeV and must be improved for neutron production at 0-degree. These experimental data will be useful as benchmark data for investigating the accuracy of the Monte Carlo simulation and for the shielding design of accelerator facilities.

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