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Zukeran, Atsushi*; Nakagawa, Tsuneo; Shibata, Keiichi; Ishikawa, Makoto*; Hino, Tetsushi*
JAERI-Research 2004-026, 102 Pages, 2005/02
Reactivity uncertainties such as effective multiplication factor can be estimated by the sensitivity coefficients of the infinitely diluted cross section and resonance self-shielding factor to the changes of resonance parameters of interest. In the present work, the uncertainties of the resolved resonance parameters for the evaluated nuclear data file JENDL-3.2 were estimated on the basis of Breit-Wigner Multi-level formula. The resonance self-shielding factor based on NR-approximation is analytically described. Reactivity uncertainty evaluation method for the effective multiplication factor k
, temperature coefficient
, and Doppler reactivity worth
is developed by means of the sensitivity coefficient against the resonance parameter. Final uncertainties are estimated by means of error propagation law using the level-wise uncertainties. Preliminary uncertainty of Doppler reactivity worth results about 4% at the temperature 728 K for large sodium-cooled FBR.
U Doppler Effect using various samples in FCA XVII-1Ando, Masaki; Okajima, Shigeaki; Oigawa, Hiroyuki
JAERI-Research 2001-017, 20 Pages, 2001/03
U Doppler effect measurements were carried out using 6 uranium samples with various composition or diameter varying self-shielding factors of
U. Calculation accuracy of the standard analysis method for fast reactor cores at FCA was investigated.The Doppler effect were measured by the sample-heated and reactivity worth measurement method up to 800 degree in the FCA XVII-1 assembly, which simulated Na-cooled MOX fueled FBR. In the analysis, the Doppler effect was calculated using the effective cross sections obtained by the PEACO-X code. The calculated values based on the diffusion theory agreed well with the experiment for the U-metal and UO
samples. The calculation underestimated the experiment from 10% to 30% for the UO
samples containing BeO. This underestimation was improved by the use of the transport calculation. The calculation, however, underestimated about 20% for the sample whose background cross section is greater than 300 barns.
U at FCA, I; Reactivity worth measurement with a small heated sample up to 1500
COkajima, Shigeaki; Oigawa, Hiroyuki; Mukaiyama, Takehiko; Ando, Masaki
Journal of Nuclear Science and Technology, 33(3), p.202 - 210, 1996/03
Times Cited Count:3 Percentile:31.89(Nuclear Science & Technology)no abstracts in English
C in the fast critical facility FCAOkajima, Shigeaki; Oigawa, Hiroyuki; Ando, Masaki; Mukaiyama, Takehiko
Proc. of 9th Int. Symp. on Reactor Dosimetry, 0, p.172 - 179, 1996/00
no abstracts in English
Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke
Journal of Nuclear Science and Technology, 32(9), p.855 - 867, 1995/09
Times Cited Count:4 Percentile:42.22(Nuclear Science & Technology)no abstracts in English
Okajima, Shigeaki; Oigawa, Hiroyuki; Mukaiyama, Takehiko
Journal of Nuclear Science and Technology, 31(10), p.1097 - 1104, 1994/10
Times Cited Count:10 Percentile:62.25(Nuclear Science & Technology)no abstracts in English
C at FCAOkajima, Shigeaki; Oigawa, Hiroyuki; Mukaiyama, Takehiko; ; Kasahara, Y.*;
Transactions of the American Nuclear Society, 66, p.523 - 524, 1992/11
no abstracts in English
Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Nakagawa, Shigeaki; Nakata, Tetsuo*;
JAERI-M 90-008, 49 Pages, 1990/02
no abstracts in English
Kaneko, Yoshihiko; ; Akino, Fujiyoshi;
JAERI-M 8846, 21 Pages, 1980/05
no abstracts in English
Kaneko, Yoshihiko; ;
JAERI-M 8311, 58 Pages, 1979/07
no abstracts in English