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Yokoyama, Kenji; Yamamoto, Akio*; Kitada, Takanori*
Journal of Nuclear Science and Technology, 55(3), p.319 - 334, 2018/03
Times Cited Count：8 Percentile：62.29(Nuclear Science & Technology)A new formulation of the cross-section adjustment methodology with the dimensionality reduction technique has been derived. This new formulation is proposed as the dimension reduced cross-section adjustment method (DRCA). Since the derivation of DRCA is based on the minimum variance unbiased estimation (MVUE), an assumption of normal distribution is not required. The result of DRCA depends on a user-defined matrix that determines the dimension reduced feature subspace. We have examine three variations of DRCA, namely DRCA1, DRCA2, and DRCA3. Mathematical investigation and numerical verification have revealed that DRCA2 is equivalent to the currently widely used cross-section adjustment method. Moreover, DRCA3 is found to be identical to the cross-section adjustment method based on MVUE, which has been proposed in the previous study.
Kunieda, Satoshi; Ichihara, Akira
JAERI-Data/Code 2005-005, 33 Pages, 2005/09
JAERI-Data-Code-2005-005.pdf:1.5MB
The computer code, POD-P, was developed to calculate energy spectra and angular distributions of emitted particles for the neutron-induced preequiliblium nuclear reactions. The energy-differential cross sections are computed with the classical one-component exciton model for the nucleon and composite-particle emissions. Along with this, the semi-empirical exciton models are also used for the composite-particle emissions. The double-differential cross sections are derived from those model calculations plus the angular-distribution systematics. The computational method and explanation of input parameters are given with some output examples.
Ueshima, Yutaka
PSE Book, p.69 - 82, 2005/03
no abstracts in English
Shibata, Keiichi
Journal of Nuclear Science and Technology, 39(10), p.1065 - 1071, 2002/10
Times Cited Count：6 Percentile：39.48(Nuclear Science & Technology)Neutron nuclear data of 
Na have been evaluated in the neutron energy region up to 20 MeV. Evaluated are the elastic and inelastic scattering, capture, (n,2n), (n,p), (n,
), (n,np), (n,n) reaction and 
-ray production cross sections, and the angular and energy distributions of neutrons and -rays. The evaluation is mainly based on nuclear model calculations. The pre-equilibrium and direct-reaction processes were taken into account in addition to the compound process. The evaluated data have been compiled into the latest version of JENDL, JENDL-3.3.
Iwamoto, Osamu; Rong, J.; Fukahori, Tokio; Chiba, Satoshi
Journal of Nuclear Science and Technology, 39(Suppl.2), p.128 - 131, 2002/08
The nucleon induced fission cross section and the fragment distribution are calculated using the Quantum Molecular Dynamics (QMD) plus Statistical Decay Model (SDM) in the nucleon energy range 10 MeV to 10 GeV. The fission cross section is calculated for 
Au, 
Bi and 
U and compared with experiments. The calculation predicts fairly well the experimental values. The mass and charge distribution is calculated for 
Pb and 
Th at 1.6-GeV and 190-MeV proton incident energy, respectively.
Shibata, Keiichi; Oh, S.*
JAERI-Research 2000-007, p.57 - 0, 2000/02
JAERI-Research-2000-007.pdf:1.23MB
no abstracts in English
Matsuda, Katsuyuki*; Takemiya, Hiroshi*
JAERI-Data/Code 2000-014, p.121 - 0, 2000/02
JAERI-Data-Code-2000-014.pdf:6.36MB
no abstracts in English
B, 
B, 
Mn, 
Pu and 
Pu neutron nuclear data in JENDL-3.2Shibata, Keiichi; *; Murata, Toru*
JAERI-Research 98-045, 48 Pages, 1998/08
JAERI-Research-98-045.pdf:1.64MB
no abstracts in English
Komuro, Yuichi; Suzaki, Takenori; *; Sakurai, Kiyoshi; Horiki, Oichiro*
JAERI-Research 97-088, 19 Pages, 1997/11
JAERI-Research-97-088.pdf:0.86MB
no abstracts in English
Suzuki, Mitsuhiro; Nakamura, Hideo; Yonomoto, Taisuke; Kumamaru, Hiroshige; Anoda, Yoshinari; Murata, Hideo
JAERI-M 91-103, 156 Pages, 1991/07
no abstracts in English
; *;
JAERI-M 8757, 41 Pages, 1980/03
no abstracts in English
Nagai, Haruyasu; Terada, Hiroaki; Tsuzuki, Katsunori; Ota, Masakazu; Furuno, Akiko; Akari, Shusaku; Katata, Genki
no journal, ,
In order to assess the radiological dose to the public resulting from the Fukushima Daiichi Nuclear Power Station accident in Japan, the spatial and temporal distribution of radioactive materials in the environment are reconstructed by computer simulations. In this study, by refining the source term of radioactive materials discharged into the atmosphere and modifying the atmospheric dispersion model, the atmospheric dispersion simulation of radioactive materials is improved. Then, a database of spatiotemporal distribution of radioactive materials in the air and on the ground surface is developed from the output of the simulation, and is used for the dose assessment by coupling with the behavioral pattern of evacuees from the nuclear accident. In this year, (1) investigation of the source term, (2) improvement of atmospheric dispersion simulation, and (3) acquisition and organization of measured data have been conducted.
