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Journal Articles

Development of nuclear decay data for radiation dosimetry calculation

Endo, Akira; Eckerman, K. F.*

JAEA-Conf 2007-002, p.76 - 85, 2007/02

no abstracts in English

Journal Articles

Simulation analysis of radiation fields inside phantoms for neutron irradiation

Satoh, Daiki; Takahashi, Fumiaki; Endo, Akira; Omachi, Yasushi*; Miyahara, Nobuyuki*

JAEA-Conf 2007-002, p.59 - 65, 2007/02

The present study intends to analyze internal radiation field of a typical mouse with voxel phantom and radiation transport code. A mouse was imaged by using the dedicated small-animal CT scanner, in which slice pitch was set at 0.1 mm. Each image with the resolution of 0.02 mm was segmented to construct a voxel phantom by using computer tools, which have been applied to process human-head images for 3-dimensional dosimetry in BNCT treatment at the Japan Atomic Energy Agency. Input files for particle and heavy ion transport code system were prepared from the constructed 3-dimensional voxel-based image data. Absorbed dose distributions and LET spectra in the mouse body were calculated by PHITS on the segmented images.

Journal Articles

Bystander effect studies using heavy-ion microbeam

Kobayashi, Yasuhiko; Funayama, Tomoo; Sakashita, Tetsuya; Furusawa, Yoshiya*; Wada, Seiichi*; Yokota, Yuichiro; Kakizaki, Takehiko; Hamada, Nobuyuki*; Hara, Takamitsu*; Fukamoto, Kana; et al.

JAEA-Conf 2007-002, p.28 - 35, 2007/02

no abstracts in English

Journal Articles

Discussion on concepts for radiological dosimetric quantities in the Japan Health Physics Society

Takahashi, Fumiaki; Oda, Keiji*

JAEA-Conf 2007-002, p.171 - 176, 2007/02

no abstracts in English

Journal Articles

Application of the PHITS code in high-energy particle dosimetry

Sato, Tatsuhiko; Endo, Akira; Niita, Koji*

JAEA-Conf 2007-002, p.86 - 93, 2007/02

Estimation of radiation dose from high energy particles is indispensable for the design study of accelerator shielding, radiation therapy, long-term space mission and so on. Particle transport simulation codes can play an important role in the estimation, since some dosimetric quantities such as fluence to dose conversion coefficients cannot be evaluated experimentally. We are therefore developing a general-purpose Monte Carlo code PHITS, which can deal with the transports of all kinds of hadrons and heavy ions with energies up to 200 GeV/n. The detailed features of the PHITS code will be given in the presentation, together with the calculated results of the dose conversion coefficients and their applications.

Journal Articles

Development of Japanese voxel models and their application to organ dose calculation

Sato, Kaoru; Endo, Akira; Saito, Kimiaki

JAEA-Conf 2007-002, p.94 - 101, 2007/02

The dose conversion coefficients have been calculated using radiation transport codes in conjunction with computational human phantoms. At Japan Atomic Energy Agency (JAEA), a series of Japanese voxel phantoms have been developed to provide a set of basic data for radiation protection for Asian. So far, five adult phantoms for three males (Otoko, JM, and JM2) and two females (Onago and JF) have been completed. The JM and JF phantoms are the male and female phantoms, respectively, whose voxel size is about 1 mm$$^{3}$$. The small voxel enable us to model realistically the shapes of small or thin organs and tissues. The JM2 phantom was constructed from CT data taken in upright posture of the same subject for employed in the construction with JM. Comparison between JM and JM2 shows the differences in organ doses due to postures.

Oral presentation

Study on the estimation of probabilistic effective dose; Committed effective dose from intake of marine products using oceanic general circulation model

Nakano, Masanao

no journal, , 

The worldwide environmental protection is required by the public. A long-term environmental assessment from nuclear fuel cycle facilities to the aquatic environment also becomes more important to utilize nuclear energy more efficiently. Evaluation of long-term risk including not only in Japan but also in neighboring countries is considered to be necessary in order to develop the number of site location and to operate facilities. The author is challenging to calculate probabilistic effective dose suggested by ICRP from intake of marine products due to atmospheric nuclear tests using the Monte Carlo method in the other part of LAMER. Depending on the deviation of each parameter, the 95 percentile of the probabilistic effective dose was calculated about half of the 95 percentile of the deterministic effective dose in proforma calculation. It means that probabilistic assessment has an advantage for the dose assessment of a nuclear fuel cycle facility.

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