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JAEA Reports

Acceleration of criticality analysis solution convergence by matrix eigenvector for a system with weak neutron interaction

Nomura, Yasushi; Takada, Tomoyuki; Kadotani, Hiroyuki*; Kuroishi, Takeshi

JAERI-Tech 2003-020, 88 Pages, 2003/03

JAERI-Tech-2003-020.pdf:4.31MB

no abstracts in English

Journal Articles

Present status of nuclear criticality safety research; Highlights of ICNC'95, the 5th International Conference on Nuclear Criticality Safety

Nishina, Kojiro*; *; Miyoshi, Yoshinori; Suzaki, Takenori; Okuno, Hiroshi; Nomura, Yasushi; Mitake, Susumu*; ; Tonoike, Kotaro; *; et al.

Nihon Genshiryoku Gakkai-Shi, 38(4), p.262 - 271, 1996/00

no abstracts in English

JAEA Reports

Journal Articles

Present status of nuclear criticality safety research; highlights of International Conference on Nuclear Criticality Safety(ICNC-91)

Nishina, Kojiro*; Yamane, Yoshihiro*; Kobayashi, Iwao; Tachimori, Shoichi; ; Miyoshi, Yoshinori; Okuno, Hiroshi; Nakajima, Ken; Mitake, Susumu*; *; et al.

Nihon Genshiryoku Gakkai-Shi, 34(4), p.311 - 319, 1992/04

 Times Cited Count:0 Percentile:0.49(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Analytical Study of Criticality Experiments of Organic and Light Water Moderated Mixed Oxide Fuel Pin Arrays

*; Fukumura, Nobuo*; *; Koyama, Tomozo; M.J.Hai*

PNC TN9410 87-072, 25 Pages, 1987/05

PNC-TN9410-87-072.pdf:0.57MB

As part of a joint criticality data development between the power peactor and Nuclear Fuel Development Corporation (PNC) of Japan and the United State Department of Energy (USDOE), critical experiments have been conducted with organic moderated Fast Test Reactor (FTR) mixed oxide fuel pin arrays. The neutronic characteristics of an organic moderator can be examined by comparing the results of these experiments with the results of the same type of experiments performed with light water moderated system. In recent experiments performed at the Battelle Pacific Northwest Laboratories Critical Mass Laboratory, five distances of the lattice pitches were utilized which span from soft to hard neutron energy spectra. Results obtained by benchmark analyses of these experiments are discussed in this paper. The benchmark analysis was performed using the coupled WIMS-CITATION computer code whose accuracy has been demonstrated by applying them to heavy water reactor (ATR) with cluster type fuel. The scattering kernel used in the calculation for hydrogen atoms in light water was based on Nelkin's model. This same scattering kernel was used for hydrogen atoms in the organic moderator. The agreement between calculation and experiment (k-eff=1) for the light water moderated cores are fairly good (less than 0.2% $$Delta$$k/k). On the other hand, k-eff's for the organic moderated core show a tendency to diverge from k-eff=1 gradually, as the lattice pitches become larger; the approximation used to calculate the scattering kernels for the organic moderator becomes less accurate. It is theorized that small difference in chemical bonding between light water and organic moderator account for the increasing deviation from k-eff=1 for the organic moderators, the larger the fuel pin lattice pitch. Future work would be necessary to establish a more accurate scattering kernel model of the organic moderator to precisely calculate critical conditions for organic moderated fuel pin ...

JAEA Reports

Development of radiation dose calculation code for nuclear power plant; QAD-Fugen

*; *; *

PNC TN341 83-10, 10 Pages, 1983/05

PNC-TN341-83-10.pdf:0.33MB

A radiation dose calculation code,QAD-FUGEN,hasbeen developed for a prototype heavy water reactor FUGEN. The code is designed to calculate the radiation dose frommany radiation sources at a time. It is a $$gamma$$ ray shielding calculation code which utilizes the point-kernelmethod as its analytical procedure,and is developedby modifying the QAD code substantially. Main characteristics of the QAD-FUGEN code are asfollows:(1) The cylindrical sources can be set at any positionand direction in space. The mutual shielding of sourceregions can be treated in the code. (2) The geometry ofshielding structure should be composed of pipes,tanks andrectangular parallelepipeds,and they can be also set at anyposition and direction. There is no limit in number ofsources and shieldings. (3) The geometry of radiationsources and shieldings,obtained with a digitizer which isused to measure the distances on the drawings can be fedto QAD-FUGEN. (4) The check routines are prepared to drawthe geometries on two dime

JAEA Reports

Vectorization of Diffusion Code VENTURE Using CRAY-1 and FACOM230-75APU

*; *; Harada, Hiro

JAERI-M 82-019, 61 Pages, 1982/03

JAERI-M-82-019.pdf:1.73MB

no abstracts in English

JAEA Reports

Bibliography for Thermal Neutron Scattering; Sixth Edition, 1979

; ; *; *; ; ; *;

JAERI-M 8417, 360 Pages, 1979/09

JAERI-M-8417.pdf:16.03MB

no abstracts in English

JAEA Reports

Bibliography for thermal neutron scattering; Fifth edition, 1976

; ; ; *; *;

JAERI-M 6857, 287 Pages, 1976/12

JAERI-M-6857.pdf:13.27MB

no abstracts in English

JAEA Reports

Oral presentation

Refurbishment and restart of JMTR, 11; Technology development for attractive irradiation tests, 5; Re-evaluation of thermal scattering law for neutron dosimetry

Imaizumi, Tomomi; Kadotani, Hiroyuki*; Okumura, Keisuke; Katakura, Junichi; Nagao, Yoshiharu

no journal, , 

no abstracts in English

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