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Oral presentation

applied example MCNP5 on skyshine of nuclear facility

Zaima, Naoki; Naganuma, Masaki; Sakao, Ryota; Tokizawa, Takayuki

no journal, , 

In the field of safety analysis on nuclear fuel facility, conventional calculation code (QAD/G33 etc.) had been used. However some confines of codes had lead overestimation. At the chance of trial for shielding or skyshine calculation, Monte Carlo transport calculation code MCNP5 was applied. The comparison between both, error estimations, model designs, several artifices will be introduced.

Oral presentation

Analysis of the risk index of radiation health using Disability-Adjusted Life Years (DALY)

Shimada, Kazumasa; Kai, Michiaki*

no journal, , 

In this study, we proposed that Disability-Adjusted Life Year (DALY) to estimate radiation cancer risk in Japanese residents. Lifetime cancer mortality, incidence rate, and lives lost have been the previous indices of health risk associated with radiation protection. ICRP defined the detriment in Publication 60 by considering non-fatal cancers and the number of lives lost due to the difference in latent times. However, the detriment has the disadvantage that it can neither be appropriately interpreted nor used. Therefore, the common index is required to discuss health risk of radiation and the others. As a risk measure of both common health and environmental health, there is a disability-adjusted life year (DALY) that is developed from concepts of life lost. DALY was developed by Harvard University in 1990 and was further adopted to establish an order of priority for health issues by the World Health Organization (WHO). In this study, we calculated DALY to estimate radiation cancer risk and compared this with the radiation detriment to discuss the effectiveness of DALY.

Oral presentation

Design of a D$$_{2}$$O-moderated $$^{241}$$Am-Li neutron calibration field

Hoshi, Katsuya; Yoshida, Tadayoshi; Tsujimura, Norio; Okada, Kazuhiko

no journal, , 

no abstracts in English

Oral presentation

Study of method of measurement of the $$beta$$-ray 3mm dose equivalent and protection measures of the lens of eyes, 2; TL dosimeter

Yamazaki, Takumi; Takimoto, Misaki; Suga, Takumi; Hoshi, Katsuya; Yoshida, Tadayoshi; Takada, Chie; Tsujimura, Norio; Okada, Kazuhiko; Ishikawa, Hisashi

no journal, , 

no abstracts in English

Oral presentation

Study of method of measurement of the $$beta$$-ray 3mm dose equivalent and protection measures of the lens of eyes, 1; Ionization chamber

Takimoto, Misaki; Yamazaki, Takumi; Imahashi, Atsushi; Hoshi, Katsuya; Kawasaki, Takashi; Yoshida, Tadayoshi; Takada, Chie; Tsujimura, Norio; Okada, Kazuhiko; Ishikawa, Hisashi

no journal, , 

no abstracts in English

Oral presentation

Investigation of electronic personal dosemeters response in the $$gamma$$-ray field with low dose rate

Kojima, Naomi; Nakagawa, Takahiro; Yamazaki, Takumi; Takimoto, Misaki; Takada, Chie

no journal, , 

In late years, Electronic Personal Dosemeter (EPD) has been widely used because of its useful specifications: indicating measurement values on site, lower detect limits than glass badge. However, an investigation of its response characteristic is difficult to perform using actual low dose rate $$gamma$$-ray. The investigation needs sheildings of a entire irradiation room for reducing natural radiation. In this study, at the compact irradiation system with low dose rate which National Institute of Advanced Industrial Science and technology developed, $$gamma$$-ray of $$^{137}$$Cs below 0.1$$mu$$Sv/h were irradiated to two models of EPD with recording function. Integrated dose and standard deviation for EPD were analyzed to investigate response characteristics for low dose rate radiation.

Oral presentation

Shield effect of the respirator and estimated dose to the lens of the eye for the worker in the cell

Torii, Yosuke; Yamasoto, Kotaro; Kato, Takuya; Yoshitomi, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

Development of emergency monitoring system which detects radionuclide emitting $$alpha$$ ray in air

Hokama, Tomonori; Fujita, Hiroki

no journal, , 

no abstracts in English

Oral presentation

Evaluation of the tube-voltage dependence of organ doses in X-ray CT scans using Monte-Carlo calculation

Koba, Yusuke*; Matsumoto, Shinnosuke*; Nakada, Yoshihiro*; Kasahara, Tetsuji*; Akahane, Keiichi*; Okuda, Yasuo*; Sato, Kaoru; Takahashi, Fumiaki; Yoshitake, Takayasu*; Hasegawa, Takayuki*; et al.

no journal, , 

Many of the CT devices are in Japan. It is guessed that exposure doses of Japanese derived from CT scans are higher than others. Thus, it is needed to properly manage scan conditions and exposure doses of individual patients. JAEA developed WAZA-ARI under the collaboration research project with the National Institute of Radiological Sciences (NIRS) and the Oita University of Nursing and Health Sciences. Practical use of new version WAZA-ARI named WAZA-ARIv2 began on January 30, 2015 at the web server in NIRS. In WAZA-ARIv2, users can calculate patients doses by using only standard condition (120 kV) of X-tube voltage. In recent years, CT scans at low tube voltage against pediatric patients with high radiosensitivity are increasing. In this study, spectrum of X-ray derived from CT scan at low tube voltage was examined, and was defined in "usrsors.f" file of PHITS. We reported the characteristics of X-ray and organ doses derived from CT scan at low tube voltage (80 kV).

Oral presentation

Calculating dose distribution from diagnostic CT depending on age and physique size of patients; Development of dose assessment web - system WAZA-ARI

Ono, Koji*; Koba, Yusuke*; Matsumoto, Shinnosuke*; Nakada, Yoshihiro*; Okuda, Yasuo*; Akahane, Keiichi*; Sato, Kaoru; Takahashi, Fumiaki; Yoshitake, Takayasu*; Hasegawa, Takayuki*; et al.

no journal, , 

In medical treatment, CT scan is useful diagnostic method. On the other hand, exposure doses derived from CT scans are dependent on body sizes of patients. Therefore, consideration of body sizes is essential for accurate dose assessment of individual patients. JAEA developed the CT dose calculator, WAZA-ARIv2 under the collaboration research project with the National Institute of Radiological Sciences and the Oita University of Nursing and Health Sciences. WAZA-ARIv2 enable users to accurately calculate exposure doses of patients with sexes, ages (0y, 1y, 5y, 10y, 15y and adult) and fatness (small, large and extra-large body sizes). In the future, we will be plans to add the dose calculation functions corresponding to the scan conditions at low tube voltage and multi-detector row (more 80) CT devices to WAZA-ARIv2. We reported the system and future plans of WAZA-ARIv2 corresponding to dose calculation of patients with various body sizes.

Oral presentation

Latest situation and future targets of radiation countermeasures around water and woods environments in a priority investigation area on radioactive materials contamination

Iimoto, Takeshi*; Maedera, Ikuhiko*; Nunokawa, Jun*; Matsuzawa, Hajime*; Kurokawa, Sumihiko*; Yanagawa, Yukihide*; Someya, Seiichi*; Hashimoto, Makoto; Seya, Natsumi; Okawa, Yasuhisa; et al.

no journal, , 

no abstracts in English

Oral presentation

Study of absorption of radon through skin

Sakoda, Akihiro; Ishimori, Yuu; Tschiersch, J.*

no journal, , 

In general, the deposition of inhaled radon progeny on lung gives the largest dose when the dose evaluation is made for the so-called radon exposure. In this case, the dose from inhalation of radon itself is much lower than that from its progeny. Also, very little studies of the absorption of radon via skin have not been done so far. However, specific environments such as radon hot springs have the characteristics that radon concentration in water is significantly higher by a few orders than that in air. In the present study, a biokinetic model of radon into which its skin-absorption process was incorporated was developed to discuss the change in radon concentrations in tissues during and after bathing in thermal water.

Oral presentation

Variation due to precipitation in $$gamma$$-ray dose rate in the northern part of Okayama Prefecture

Ishimori, Yuu; Tanaka, Hiroshi; Ando, Masaki; Sakoda, Akihiro

no journal, , 

It is well known that environmental $$gamma$$-ray dose rates can be increased by radon progeny in rain, and commonly decreased down to usual levels about three hours after the termination of precipitation. In the present study, the variation of environmental dose rates due to precipitation was discussed based on the measurement results of radon progeny concentrations in rain or snow. Heavy snow is the property of the northern part of Okayama Prefecture.

Oral presentation

Radon concentration in water around Ningyo-toge

Ishimori, Yuu

no journal, , 

Ningyo-toge environmental engineering center of Japan Atomic Energy Agency has monitored radon concentrations in water and air around Ningyo-toge. This presentation shows the data on radon in water.

14 (Records 1-14 displayed on this page)
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