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JAEA Reports

None

*; *; *; *

JNC TJ1420 2000-003, 1020 Pages, 1999/03

JNC-TJ1420-2000-003.pdf:110.99MB

no abstracts in English

JAEA Reports

None

*; ; ; *

JNC TJ1400 99-026, 217 Pages, 1999/02

JNC-TJ1400-99-026.pdf:8.64MB

no abstracts in English

Journal Articles

None

; ; Ishikawa, Hirohisa; ; Tsubota, Koji;

Donen Giho, (100), p.235 - 253, 1996/12

None

JAEA Reports

None

Kawamura, Kazuhiro; ;

PNC TN8600 93-003, 269 Pages, 1993/02

PNC-TN8600-93-003.pdf:8.79MB

no abstracts in English

JAEA Reports

Review of the presented papers for the 7th International Conference on Radiation Shielding

Sasamoto, Nobuo; *; *; *; *; *; Kinno, Masaharu*; Sakamoto, Yukio; Sakurai, Kiyoshi; *; et al.

JAERI-M 89-122, 74 Pages, 1989/09

JAERI-M-89-122.pdf:2.52MB

no abstracts in English

JAEA Reports

Radiation shielding analysis of the Fugen nuclear power station

*; *; ; 2 of others*

PNC TN3410 88-025, 11 Pages, 1988/09

PNC-TN3410-88-025.pdf:0.38MB

The radiation shielding analysis of pressure tube type heavy water reactors was performed using the discrete ordinate transport code, dot 3.5. The present paper describes the analytical methods developed to calculate the dose rates after shutdown in various regions such as pressure tubes, outside the primary shield and penetrations through the primary shield and calandria tank. The calculation methods were applied to analyze the dose rates in Fugen measured by neutron and $$gamma$$-ray detectors. These calculated results are in good agreement with the measured values within a factor of approximately 3.

JAEA Reports

Gamma Dose Rates in the Pressure Tubes of Fugen Nuclear Power Station

*; *;

PNC TN341 84-16, 13 Pages, 1984/11

PNC-TN341-84-16.pdf:0.38MB

Evaluation of gamma dose rates in the pressure tube and the streaming through the lower radiation shield of pressure-tube-type heavy water reactor, Fugen, is necessary for design and maintenance of this type of reactor. Calculations of these values using computer programs were made and compared with the experimental results; doser ates in a pressure tube surrounded with fuels and without fuels in adjacent tubes were calculated and the results were in good agreement with the experimental on es.

JAEA Reports

None

*

PNC TN352 84-02, 37 Pages, 1984/05

PNC-TN352-84-02.pdf:0.73MB

no abstracts in English

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

None

Miura, Makoto; *; *; *; Tanaka, Yasumasa;

PNC TN841 78-25, 375 Pages, 1978/03

PNC-TN841-78-25.pdf:29.15MB

no abstracts in English

JAEA Reports

None

Miura, Makoto; *; Tanaka, Yasumasa; *; *

PNC TN841 78-02, 142 Pages, 1978/01

PNC-TN841-78-02.pdf:8.25MB

no abstracts in English

JAEA Reports

None

Miura, Makoto; Tsunoda, Naomi; *; *; *; *; Tanaka, Yasumasa; *

PNC TN841 77-34, 69 Pages, 1977/06

PNC-TN841-77-34.pdf:3.67MB

no abstracts in English

JAEA Reports

None

Miura, Makoto; *; ; *; *; Tanaka, Yasumasa

PNC TN841 77-15, 125 Pages, 1977/04

PNC-TN841-77-15.pdf:8.29MB

no abstracts in English

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