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Journal Articles

Nuclear decay data used in radiation protection

Endo, Akira

Hoken Butsuri, 38(4), p.308 - 317, 2003/12

no abstracts in English

Journal Articles

Nuclear decay data used in radiation protection and medical application

Endo, Akira

Nihon Genshiryoku Gakkai-Shi, 43(12), p.1191 - 1194, 2001/12

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Nuclear decay data, a set of data on half-life and energies and intensities of radiations emitted by nuclear transformation, are required in calculating external and internal doses by emissions from radionuclides. A nuclear decay database, which has been the most widely used for dose calculation in radiation protection, is Publication 38 (ICRP38) of the International Commission on Radiological Protection. The paper describes overview of ICRP38 and a future plan of its revision.

Journal Articles

Nuclear data used in radiation protection

Yamaguchi, Yasuhiro

Nihon Genshiryoku Gakkai-Shi, 43(7), p.664 - 665, 2001/07

no abstracts in English

JAEA Reports

Report of radiation exposure control on the 12th periodic inspection at experimental fast reactor JOYO

; Kano, Yutaka; ; Shindo, Katsutoshi

JNC TN9410 2000-001, 20 Pages, 1999/12

JNC-TN9410-2000-001.pdf:1.84MB

The 12th periodic inspection had been executed at the experimental fast reactor JOYO from February 24,1998 to June 28,1999. This inspection had been extended about three months because it was addtion to the work for the safety countermeasure. The result of collective dose equivalent was 263.92 man*mSv, whereas, the expected collective dose equivalent was about 407 man*mSv in the whole period of this inspection. It was confirmed that this inspection was carried out with the suitable radiation protection programmes. In this report, provided in 12th periodic inspection, were described with taking the results of the past periodic inspections into consideration.

Journal Articles

Extermal dose calculation using mathematical phantom

Yamaguchi, Yasuhiro

Radioisotopes, 45(3), p.223 - 224, 1996/00

no abstracts in English

JAEA Reports

Visualization of atmospheric diffusion with Mathematica

Shinohara, Kunihiko

PNC TN9410 92-339, 47 Pages, 1992/11

PNC-TN9410-92-339.pdf:18.25MB

The calculation of atmospheric concentrations of radionuclides discharged from nuclear facilities is the first step for environmental dose assessment. Gaussian diffusion equation is usually used for the calculation. Computer programs such as ANDOSE and ORION-II have been developed by using of the equation and applied with meteorological data to evaluuate dose equivalents in the environment. results are shown numerically by the computer codes. However, if the results are shown in visualized form, it may be very useful to understand the diffusion phenomena and will also be helpful for beginners of the environmental dose assessment In the report, atmospheric diffusions and depositions by Gaussian equation have been visualized with mathematica. Almost text and graphics in the report are the direct print of mathematica's Note Book.

JAEA Reports

None

*; Kishimoto, Yoichiro; Shinohara, Kunihiko*

PNC TN841 78-01, 67 Pages, 1978/01

PNC-TN841-78-01.pdf:1.56MB

no abstracts in English

Oral presentation

Feasibility study of technology for Pu solution monitoring including FP, 4; Comparison between dose rate measurement result and simulation result

Matsuki, Takuya; Nishida, Naoki; Horigome, Kazushi; Sekine, Megumi; Kitao, Takahiko; Nakamura, Hironobu

no journal, , 

To inquest the measurement point of the detector which can conduct the Pu monitoring in the high active liquid waste at Tokai reprocessing plant, we have made the simulation model which can calculate the radiation distribution in the cell storing HALW. Comparing the dose rate distribution between calculation result and actual measurement result, we evaluated the validity of the current simulation model.

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