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Journal Articles

Centralized radioactivity measurement system for radiation control in Tokai research establishment of JAERI

Kawasaki, Katsuya

Hoken Butsuri, 40(1), p.56 - 60, 2005/03

The centralized radioactivity measurement system has been used to carry out intensively measurements of a large number and variety of samples that are necessary for the control of radioactivity in the facilities of the JAERI Tokai Establishment and its environment. The operation of the system started in 1981, and presently the system processes more than 20,000 samples a year. However, the computers of the system have aged so much that the manufacturer's support and stable operation are no longer sure. Therefore, we renewed and restructured the computer system in 2003. A client-server system was adopted in the new system. The information of samples can be registered through the intranet. The clients can also confirm the progress of processing of their samples and browse the analytical results from their own computers. The renewed system can provide some convenience functions to the clients. This report is introduced about the centralized radioactivity measurement system.

JAEA Reports

Renewal of centralized radioactivity measurement system for radiation control

Kawasaki, Katsuya; Mochizuki, Kaoru*; Suzuki, Takehiko; Kinouchi, Nobuyuki

JAERI-Tech 2004-070, 50 Pages, 2004/12

JAERI-Tech-2004-070.pdf:18.19MB

The centralized radioactivity measurement system has been used to carry out intensively measurements of a large number and variety of samples that are necessary for the control of radioactivity in the facilities of the JAERI Tokai Establishment and its environment. The operation of the system started in 1981, and presently the system processes more than 20,000 samples a year. However, the computers of the system have aged so much that the manufacturer's support and stable operation are no longer sure. Therefore, we renewed and restructured the computer system in 2003. A client-server system was adopted in the new system. The information of samples can be registered through the intranet. The clients can also confirm the progress of processing of their samples and browse the analytical results from their own computers. The renewed system can provide some convenience functions to the clients.

Journal Articles

Design of an anti-compton spectrometer for low-level radioactive wastes using Monte Carlo techniques

Tsutsumi, Masahiro; Oishi, Tetsuya; Kinouchi, Nobuyuki; Sakamoto, Ryuichi; Yoshida, Makoto

Journal of Nuclear Science and Technology, 39(9), p.957 - 963, 2002/09

 Times Cited Count:3 Percentile:24.2(Nuclear Science & Technology)

An anti-Compton spectrometer with semi-2$$pi$$ Compton suppression is designed to identify the photons emitted from low-level radioactive wastes from radioisotope usage and nuclear research laboratory. Since the objective sample is massive and large, the system has a full opening towards the sample position. The characteristics and features of the system concerning Compton suppression and reduction of the background component due to natural radioactive source are estimated by the Monte Carlo simulations. The anti-Compton technique is shown to be quite advantageous for the reduction of the surrounding natural background radiation, as well as the suppression of the background for the higher energy photons.

Journal Articles

Simulation of the background for $$gamma$$ detection system in the indoor environments of concrete buildings

Tsutsumi, Masahiro; Oishi, Tetsuya; Kinouchi, Nobuyuki; Sakamoto, Ryuichi; Yoshida, Makoto

Journal of Nuclear Science and Technology, 38(12), p.1109 - 1114, 2001/12

In order to predict the indoor background spectra to gamma detection systems, the gamma radiation field in a concrete building is studied by the Monte Carlo simulations. The parameters of wall thickness, room shape and dimensions were considered in the modeling. The indoor source geometry was simulated by a spherical layer model with the intention of easy and effective calculations. The model was applied to an unshielded germanium detector and the detection system with a more complex shielding configuration. As the results, we found that the indoor radiation field in concrete buildings can be predicted well with the source geometry of a spherical concrete layer of 25cm thickness and with the source of the natural major three components of the $$^{238}$$U series, $$^{232}$$Th series and $$^{40}$$K that are homogeneously distributed. The simulation model is useful for designing and optimizing gamma detection systems or shielding assemblies.

Journal Articles

Determination of detection efficiency curve for a gas monitor with a built-in germanium detector

Oishi, Tetsuya; Yoshida, Makoto; Saegusa, Jun; Honda, Tetsutaro*; Takahashi, Koji*; Kuwabara, H.*

Journal of Nuclear Science and Technology, 38(3), p.203 - 208, 2001/03

no abstracts in English

Journal Articles

A Calibration technique for radioactive gas monitor with a built-in germanium detector

Yoshida, Makoto; Oishi, Tetsuya; Saegusa, Jun; Honda, Tetsutaro*; Takahashi, Koji*; Kuwabara, H.*

Proceedings of 10th International Congress of the International Radiation Protection Association (IRPA-10) (CD-ROM), 6 Pages, 2000/05

no abstracts in English

Journal Articles

Evaluation of peak-to-total ratio for germanium detectors

*; Oi, Yoshihiro; Taki, Mitsumasa; Kawasaki, Katsuya; Yoshida, Makoto

Applied Radiation and Isotopes, 50(6), p.1057 - 1061, 1999/00

 Times Cited Count:6 Percentile:46.15(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Measurement of peak efficiency and peak-to-total ratio of coaxial-type HP Ge detector

Tanaka, Susumu; Imamura, Mineo*

Genshikaku Kenkyu, 41(3), p.13 - 20, 1996/06

no abstracts in English

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