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Fujita, Hiroki
Journal of Nuclear Science and Technology, 45(Suppl.5), p.147 - 150, 2008/06
Times Cited Count：1 Percentile：10.05(Nuclear Science & Technology)To develop retrospective dosimetry of unexpected radiation accident, the basic studies on violet thermoluminescence (VTL) phenomena were conducted using natural quartz grains. All VTL glowcurves of as-received samples exhibited no peaks below 250 
C, although there remained VTL peaks in the temperature region below 250 C for artificially irradiated quartz samples. Therefore, accident doses could be estimated without interference of naturally accumulated doses by VTL measurement from natural quartz. The mean lives of VTL were evaluated by the various heating rates method and then the range of values was between some days and ten thousands of years depending on each peak. Furthermore, the lower detection limit was calculated to be tens of mGy from the response curve. This value was lower than that of other methods such as ESR dosimetry. From these results, VTL dosimetry would be preferable for accidental evaluation.
Nakano, Masanao
Journal of Nuclear Science and Technology, 45(Suppl.5), p.598 - 601, 2008/06
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)The public generally requires worldwide environmental protection. A long-term environmental assessment from nuclear fuel cycle facilities to the aquatic environment also becomes more important to utilize nuclear energy globally. Evaluation of long-term risk including not only in Japan but also in neighboring countries is considered to be necessary in order to develop nuclear power industry. In advance of a multinational assessment of nuclear fuel cycle facilities, a worldwide estimation of probabilistic effective dose due to the atmospheric nuclear tests was carried out as an example. The author successfully simulated the distribution of radionuclides, which was produced by the atmospheric nuclear tests, in seawater and seabed sediment using LAMER (Long-term Assessment ModEl for Radioactivity in the oceans). A part of the LAMER calculated the advection-diffusion-scavenging processes for radionuclides in the oceans in cooperate with an oceanic general circulation model and was already validated for 
Cs and 
Pu. The author is challenging to calculate probabilistic effective dose, which is suggested by the International Commission on Radiological Protection, from intake of marine products due to atmospheric nuclear tests using the Monte Carlo method in the other part of LAMER. Although it depended on the deviation of each parameter, the 95th percentile of the probabilistic effective dose was calculated about half of the 95th percentile of the deterministic effective dose in proforma calculation. The probabilistic assessment gives realistic value for the dose assessment of a nuclear fuel cycle facility.
Sanada, Yukihisa; Tsujimura, Norio; Shimizu, Yoshio; Izaki, Kenji; Furuta, Sadaaki
Journal of Nuclear Science and Technology, 45(Suppl.5), p.74 - 77, 2008/06
Times Cited Count：1 Percentile：10.05(Nuclear Science & Technology)The purpose of this study is the establishment of the determination procedures for the placements of CAAS detectors in PCDF. The dose of detection point was evaluated the simple equation which was formulated in calculated factors by MCNP and ANISN. When the alarm trip point was 2.0 mGy/h, the detection area was covered 30 m distances from the equipment to the CAD and 100 cm concrete shielding. This result will be reflected in the determination of the CAD placements and three CADs were placed in PCDF.
Takahara, Shogo; Kimura, Masanori; Matsubara, Takeshi*; Homma, Toshimitsu
Journal of Nuclear Science and Technology, 45(Suppl.5), p.714 - 717, 2008/06
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)It is recognized that good preparedness and arrangement in advance of an emergency can improve the emergency response to a nuclear and radiological emergency. In the preparedness, comprehensive threat assessment is very important to provide technical guidance for developing the protective actions. Probabilistic safety assessment method is useful for assessing accident consequences comprehensively and quantitatively. In this study, an accident consequence assessment code OSCAAR, which was developed at the Japan Atomic Energy Agency, is used to provide the information for the guideline of intervention and return criteria for relocation on the long-term emergency situation.
Shikaze, Yoshiaki; Tanimura, Yoshihiko; Saegusa, Jun; Tsutsumi, Masahiro; Shimizu, Shigeru; Yoshizawa, Michio; Yamaguchi, Yasuhiro
Journal of Nuclear Science and Technology, 45(Suppl.5), p.209 - 212, 2008/06
Times Cited Count：8 Percentile：49.01(Nuclear Science & Technology)The neutron calibration fields is necessary to evaluate the energy response of the neutron monitors and dosimeters used in the facility such as J-PARC. The neutron calibration fields using accelerators, for the purpose, have been developed at the Facility of Radiation Standards (FRS) of JAEA-Tokai for neutrons below 20MeV and at Takasaki Ion Accelerators for Advanced Radiation Application (TIARA) of JAEA-Takasaki for those over 20 MeV. At FRS, a 4 MV Van-de-Graaff (Pelletron) accelerator is used. Up until the present, developments of the 8, 144, 250, 565 keV, 5.0 and 14.8 MeV fields have been completed. At TIARA, an AVF cyclotron is used, and three neutron fields of 45, 60 and 75 MeV are planned to be established. For the development, evaluation of the characteristics of the field have been in process.
(10) and H(0.07) measurable electronic pocket dosimeter for 
- and 
-raysTakahashi, Masa; Sekiguchi, Masato; Miyauchi, Hideaki; Tachibana, Haruo; Yoshizawa, Michio; Kato, Toru*; Yamaguchi, Akihito*
Journal of Nuclear Science and Technology, 45(Suppl.5), p.225 - 228, 2008/06
Times Cited Count：6 Percentile：40.09(Nuclear Science & Technology)
O moderated 
Cf source at JAEA and KAERIKowatari, Munehiko; Fujii, Katsutoshi; Tsutsumi, Masahiro; Kim, B.-H.*; Lee, K.-C.*; Yoshizawa, Michio; Yamaguchi, Yasuhiro
Journal of Nuclear Science and Technology, 45(Suppl.5), p.217 - 220, 2008/06
Times Cited Count：1 Percentile：10.05(Nuclear Science & Technology)no abstracts in English
Okuyama, Shinichi; Torii, Tatsuo; Suzuki, Akihiko*; Shibuya, Masanori*; Miyazaki, Nobuyuki*
Journal of Nuclear Science and Technology, 45(Suppl.5), p.414 - 416, 2008/06
Times Cited Count：27 Percentile：84.4(Nuclear Science & Technology)In case of a nuclear emergency when a large amount of radioactive substances and/or radiation is released from a nuclear facility, emergency radiation monitoring is carried out from the sea and air as well as from the ground adjacent to the facility to evaluate the influence of the radiation on the surrounding environment. As a means of radiation monitoring from the air, aerial monitoring using a manned helicopter is conducted. Although a manned helicopter can monitor a large area during a short time, flight at an altitude of 300 m or lower is prohibited by the Aviation Law in Japan. Therefore, it is difficult for a manned helicopter to measure the radiation profile near the ground and to measure the radiation level in a complicated terrain. In recent years, technologies for autonomous flying of industrial unmanned helicopters have been developed and applied to natural disasters. In expectation of the application of unmanned helicopters to aerial radiation monitoring during a nuclear emergency, we have developed a remote radiation monitoring system and investigated its possibilities.
Koarashi, Jun; Mikami, Satoshi; Nakada, Akira; Akiyama, Kiyomitsu; Kobayashi, Hirohide; Fujita, Hiroki; Takeishi, Minoru
Journal of Nuclear Science and Technology, 45(Suppl.5), p.462 - 465, 2008/06
Times Cited Count：7 Percentile：44.56(Nuclear Science & Technology)Tokai reprocessing plant (TRP) has released radionuclides such as 
H, 
C, 
Kr and 
I into the atmosphere since the start of operation in 1977. We have established the monitoring methodologies for these nuclides, to realize an appropriate and continuous radioactive discharge control. The methodologies having various special technical considerations for matching the monitoring of reprocessing off-gas, were summarized in this paper. Briefly, H was collected by a cold-trap technique and the concentration was evaluated being independent of the water collection efficiency; C was collected by a monoethanolamine bubbler and then measured by liquid scintillation counting without any interferences from H and Kr; Kr was continuously measured by combination of two kinds of detectors to cover very wide range of the concentration; and I was collected by a charcoal filter and a charcoal cartridge in series with a relatively high collecting performance.
Kinase, Sakae; Takahashi, Masa; Saito, Kimiaki
Journal of Nuclear Science and Technology, 45(Suppl.5), p.268 - 270, 2008/06
Times Cited Count：6 Percentile：40.09(Nuclear Science & Technology)Matsuda, Norihiro; Iwamoto, Yosuke; Hirao, Yoshihiro; Sakamoto, Yukio; Niita, Koji*
Journal of Nuclear Science and Technology, 45(Suppl.5), p.97 - 100, 2008/06
Times Cited Count：1 Percentile：10.05(Nuclear Science & Technology)Particle and Heavy Ion Transport code System (PHITS) supports a broad range of research activities: radiation shielding and dosimetry, radiotherapy and space science as well as the high-energy physics. In this paper, various benchmark calculations based on high-energy collision experiments are carried out using PHITS code: particle production (positive and negative pion) on thin or thick targets (hydrogen, carbon and aluminum), and energy deposition in target (copper) or peripheral equipment (inner and outer absorber). On the whole, the good agreement between PHITS calculations and experimental data is shown for many cases.
