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March 31, 2005Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; Radiation Control Division, Oarai; Safety Division, Kansai; Operation Safety Administration Division, Mutsu
JAERI-Review 2005-028, 232 Pages, 2005/08
JAERI-Review-2005-028.pdf:13.23MB
no abstracts in English
March 31, 2004Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; Radiation Control Division, Oarai; Safety Division, Kansai; Operation Safety Administration Division, Mutsu
JAERI-Review 2004-024, 209 Pages, 2004/11
JAERI-Review-2004-024.pdf:26.17MB
no abstracts in English
Yamamoto, Kazuyoshi; Kumada, Hiroaki; Nakai, Kei*; Endo, Kiyoshi*; Yamamoto, Tetsuya*; Matsumura, Akira*
Proceedings of 11th World Congress on Neutron Capture Therapy (ISNCT-11) (CD-ROM), 14 Pages, 2004/10
A dose distribution considered the tumor cell density distribution is required on the radiation therapy. We propose a novel method of determining target region considering the tumor cell concentration as a new function for the next generation Boron Neutron Capture Therapy (BNCT) dosimetry system. It has not been able to sufficiently define the degree of microscopic diffuse invasion of the tumor cells peripheral to a tumor bulk in malignant glioma using current medical imaging. Referring to treatment protocol of BNCT, the target region surrounding the tumor bulk has been set as the region which expands at the optional distance with usual 2cm margin from the region enhanced on T1 weighted gadolinium Magnetic Resonance Imaging (MRI). In this research, the cell concentration of the region boundary of the target was discussed by using tumor cell diffusion model in the sphere spatio-temporal system. The survival tumor cell density distribution after the BNCT irradiation was predicted by the two regions diffusion model for a virtual brain phantom.
Yoshizawa, Michio; Endo, Akira
JAERI-Conf 2003-002, 166 Pages, 2003/03
JAERI-Conf-2003-002.pdf:9.79MB
The present report is Proceedings of the Third Workshop on Dosimetry for External Radiations, held at the Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), in November 28-29, 2002. The proceedings comprises 16 papers and a summary of general discussion. The Third Workshop, subtitled "On an opportunity of the completion of the facility of calibration standards for neutron at JAERI", focused on neutron dosimetry and included presentations on the status of international neutron standards, the development of calibration techniques of neutron dosimeters using accelerator neutron sources, and dosimetry for high-energy neutrons. The workshop identified the directions for the future research and development in this field.
Shibata, Taiju; Kikuchi, Takayuki; Shimakawa, Satoshi
Reactor Dosimetry in the 21st Century, p.211 - 218, 2003/00
The High Temperature Engineering Test Reactor (HTTR) is the first HTGR in Japan with a maximum power of 30 MW. The construction of it was completed successfully in March 2002. The HTTR aims to perform irradiation studies at its very wide irradiation spaces at high temperatures. Although the creep behavior of materials is measured by the large standard size specimens at out-of-pile, small size ones are generally used for in-pile creep tests because of the irradiation capability of reactors. The I-I type irradiation equipment, the first rig for the HTTR, is to be used for the in-pile creep test on a stainless steel with the standard specimens. The rig can give big tensile loads of about 9.8 kN on them. The temperatures of 550 and 600
C and the fast neutron fluence of 1.2
10
n/m
are the targets of the test. Prior to the in-pile creep test, the in-core irradiation properties at the irradiation region are to be obtained by the rig as the first irradiation test. This paper describes the dosimetry plan at the first irradiation test and the subsequent data assessment procedure.
Shibata, Taiju; Kikuchi, Takayuki; Miyamoto, Satoshi*; Ogura, Kazutomo*
JAERI-Tech 2002-097, 19 Pages, 2002/12
The HTTR aims to establish and upgrade the technological basis for the HTGRs and to perform the innovative basic research on high temperature engineering. The HTTR is planned to be used to perform various tests such as, the safety demonstration test, high temperature test operation and irradiation test with large irradiation fields at high temperatures. This paper describes the design of the I-I type irradiation equipment, developed as the first rig for the HTTR, and does the planned dosimetry method at the first irradiation test. It was developed to perform in-pile creep test on a stainless steel with large standard size specimens. It can give great loads on the specimens stably and can control the irradiation temperature precisely. The in-core data are measured by differential transformers, thermocouples, SPNDs and neutron fluence monitors. The obtained data at the first test can be contributed to upgrade the technological basis for the HTGRs, since it is the first direct measurement of the in-core irradiation environments.
Matsushita, Akira*; Yamamoto, Tetsuya*; Matsumura, Akira*; Nose, Tadao*; Yamamoto, Kazuyoshi; Kumada, Hiroaki; Torii, Yoshiya; Kashimura, Takanori*; Otake, Shinichi*
Research and Development in Neutron Capture Therapy, p.141 - 143, 2002/09
A thermal-epithermal mixed beam "Thermal Neutron Beam Mode I" was used in the eleven sessions of boron neutron capture therapy which have been performed at JRR-4 from 1998. We are planning to use an epithermal beam for the treatment of deeper tumors in the next trial of the intraoperative BNCT. In this study, "Epi-12" which was made by putting up a cadmium shutter of "Thermal Neutron Beam Mode I" was investigated for the clinical benefits and safety by epithermal beams. Decrease of fast neutron contamination ratio in Epi-12 mode is the advantage for BNCT, particular in the intraoperative BNCT. Because fast neutron on the brain surface is one of the critical factors in the intraoperative BNCT in which the plain beam directly interacts the normal structures. Furthermore a mixture of mode Epi-12 and Th-12 will provide various dose distribution designs. It may be used as a new method to control the best distribution for individual tumors.
Endo, Kiyoshi*; Matsumura, Akira*; Yamamoto, Tetsuya*; Nose, Tadao*; Yamamoto, Kazuyoshi; Kumada, Hiroaki; Kishi, Toshiaki; Torii, Yoshiya; Kashimura, Takanori*; Otake, Shinichi*
Research and Development in Neutron Capture Therapy, p.425 - 430, 2002/09
Using the Rapid Prototyping Technique, we produced a realistic phantom as a formative model of a patient head. This realistic phantom will contribute to verification of our planning system. However, cross-correlation among the calculations using the JAERI Computational Dosimetry System (JCDS), the realistic phantom, and the in vivo measurements were not fully completed because of the difficulty involved in modeling a post-surgical brain and a thermal neutron shield. The experimental simulation technique using the realistic phantom is a useful tool for more reliable dose planning for the intraoperative BNCT.
Nagao, Yoshiharu
JAERI-Conf 2000-018, p.156 - 167, 2001/01
no abstracts in English
Kojima, Takuji; Sunaga, Hiromi; Tachibana, Hiroyuki; Takizawa, Haruki; Tanaka, Ryuichi
IAEA-TECDOC-156, p.91 - 98, 2000/06
no abstracts in English
Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; Radiation Control Division, Oarai; Utilities and Safety Division, Kansai; Operation Safety Administration Division, Mutsu
JAERI-Review 2000-001, p.225 - 0, 2000/03
JAERI-Review-2000-001.pdf:9.42MB
no abstracts in English
Co 
-ray calibration laboratory for radiation processingTachibana, Hiroyuki; Kojima, Takuji; ; ; Yotsumoto, Keiichi; Tanaka, Ryuichi
Radioisotopes, 48(4), p.247 - 256, 1999/04
no abstracts in English
Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; ; ; Operation Safety Administration Division, Mutsu
JAERI-Review 98-015, 239 Pages, 1998/12
no abstracts in English
Kojima, Takuji; Tanaka, Ryuichi
Nihon Yakkyokuho Ni Junkyoshita Mekkinho Oyobi Biseibutsu Satsumetsuho, p.74 - 82, 1997/00
no abstracts in English
Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; ;
JAERI-Review 96-014, 236 Pages, 1996/10
JAERI-Review-96-014.pdf:7.25MB
no abstracts in English
Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; ; Operation Safety Administration Division, Mutsu;
JAERI-Review 95-020, 264 Pages, 1995/11
JAERI-Review-95-020.pdf:8.68MB
no abstracts in English
December 2, 1994, Tokai, JapanMurakami, Hiroyuki; Takahashi, Fumiaki
JAERI-Conf 95-014, 160 Pages, 1995/06
no abstracts in English
Kashiwazaki, Shigeru*; ; ; ; Kojima, Takuji
JAERI-Conf 95-003, 0, p.270 - 274, 1995/03
no abstracts in English
Kojima, Takuji; Sunaga, Hiromi; Takizawa, Haruki; Tachibana, Hiroyuki
JAERI TIARA Annual Report 1994, p.71 - 73, 1995/00
no abstracts in English
Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; ; Operation Safety Administration Division, Mutsu;
JAERI-Review 94-007, 262 Pages, 1994/11
JAERI-Review-94-007.pdf:7.85MB
no abstracts in English
