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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

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

Computation on fuel particle size capable of being regarded as homogeneous in nuclear criticality safety analysis

Okuno, Hiroshi; Naito, Yoshitaka; *

Journal of Nuclear Science and Technology, 31(9), p.986 - 995, 1994/09

 Times Cited Count:2 Percentile:28.77(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

JAEA Reports

Measurement of Doppler effect up to 2000$$^{circ}$$C at FCA, 3; Development of a cell code, PEACO-X, with ultra-fine group structure

Okajima, Shigeaki; Oigawa, Hiroyuki; Mukaiyama, Takehiko

JAERI-M 92-185, 42 Pages, 1992/11

JAERI-M-92-185.pdf:1.02MB

no abstracts in English

JAEA Reports

DELIGHT-7; One dimensional fuel cell burnup analysis code for High Temperature Gas-Cooled Reactors (HTGR)

Shindo, Ryuichi; Yamashita, Kiyonobu; Murata, Isao

JAERI-M 90-048, 225 Pages, 1990/03

JAERI-M-90-048.pdf:5.06MB

no abstracts in English

JAEA Reports

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