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JAEA Reports

Criticality and doppler reactivity worth uncertainty due to resolved resonance parameter errors; Formula for sensitivity analysis

Zukeran, Atsushi*; Nakagawa, Tsuneo; Shibata, Keiichi; Ishikawa, Makoto*; Hino, Tetsushi*

JAERI-Research 2004-026, 102 Pages, 2005/02

JAERI-Research-2004-026.pdf:7.68MB

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$$_{eff}$$, temperature coefficient $$alpha$$, and Doppler reactivity worth $$rho$$ 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.

JAEA Reports

Measurement of $$^{238}$$U Doppler Effect using various samples in FCA XVII-1

Ando, Masaki; Okajima, Shigeaki; Oigawa, Hiroyuki

JAERI-Research 2001-017, 20 Pages, 2001/03

JAERI-Research-2001-017.pdf:0.82MB

$$^{238}$$U Doppler effect measurements were carried out using 6 uranium samples with various composition or diameter varying self-shielding factors of $$^{238}$$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$$_{2}$$ samples. The calculation underestimated the experiment from 10% to 30% for the UO$$_{2}$$ 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.

Journal Articles

High temperature Doppler effect experiment for $$^{238}$$U at FCA, I; Reactivity worth measurement with a small heated sample up to 1500$$^{circ}$$C

Okajima, 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

Journal Articles

Doppler effect measurement up to 2,000$$^{circ}$$C in the fast critical facility FCA

Okajima, 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

Journal Articles

A Concept of passive safety pressurized water reactor system with inherent matching nature of core heat generation and heat removal

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

Journal Articles

Resonance interaction effect between hot sample and cold core in analysis of Doppler effect measurement

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

Journal Articles

Measurement of Doppler effect up to 2000$$^{circ}$$C at FCA

Okajima, Shigeaki; Oigawa, Hiroyuki; Mukaiyama, Takehiko; ; Kasahara, Y.*;

Transactions of the American Nuclear Society, 66, p.523 - 524, 1992/11

no abstracts in English

JAEA Reports

Evaluation of reactivity coefficients for High Temperature Engineering Test reactor(HTTR)

Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Nakagawa, Shigeaki; Nakata, Tetsuo*;

JAERI-M 90-008, 49 Pages, 1990/02

JAERI-M-90-008.pdf:1.17MB

no abstracts in English

JAEA Reports

Measurement of Reactivity Change with Temperature of Single Rod Using Coated Particles

Kaneko, Yoshihiko; ; Akino, Fujiyoshi;

JAERI-M 8846, 21 Pages, 1980/05

JAERI-M-8846.pdf:0.75MB

no abstracts in English

JAEA Reports

Herting Apparatns for a Single Fuel Rod Experiment

Kaneko, Yoshihiko; ;

JAERI-M 8311, 58 Pages, 1979/07

JAERI-M-8311.pdf:2.11MB

no abstracts in English

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