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Miyauchi, Hideaki; Yoshitomi, Hiroshi; Sato, Yoshitaka; Takahashi, Fumiaki; Tachibana, Haruo; Kobayashi, Ikuo*; Suzuki, Akifumi*
Nihon Hoshasen Anzen Kanri Gakkai-Shi, 12(1), p.41 - 45, 2013/07
In the Japan Atomic Energy Agency (JAEA), exposures to fingertips can be significant in radiological decontamination at the facilities with mixture fields of beta and (X) rays. The radiation doses to fingertips have been measured by ring type dosemeters equipped with thermoluminescence dosemeters (TLD) in JAEA. We applied small Optically Stimulated Luminescence (OSL) elements to the ring type dosemeter, which has the advantages in the use for long term and repeating in dose measurements comparing to the TLDs. In this report, we introduce the outline and the dose evaluation method of the new ring type dosimeter which we applied.
Kawase, Keigo; Kando, Masaki; Hayakawa, Takehito; Daito, Izuru; Kondo, Shuji; Homma, Takayuki; Kameshima, Takashi; Kotaki, Hideyuki; Chen, L.*; Fukuda, Yuji; et al.
Nuclear Physics Review, 26(Suppl.), p.94 - 99, 2009/07
We constructed MeV- and sub-MeV-photon sources by means of Compton backscattering with a laser light and an electron beam at SPring-8 and KPSI-JAEA. MeV-photon source consists of a continuous-wave optically-pumped far infrared laser and an 8-GeV stored electron beam. Sub-MeV-photon source consists of a Nd:YAG pulse-laser and an 150-MeV electron beam accelerated by a microtron. Both source have been succeeded backscattered photon generation. In this talk, I will present characteristics and future prospects of these photon sources.
Kawase, Keigo; Arimoto, Yasushi*; Fujiwara, Mamoru; Okajima, Shigeki*; Shoji, Masazumi*; Suzuki, Shinsuke*; Tamura, Kazuhiro*; Yorita, Tetsuhiko*; Okuma, Haruo*
Nuclear Instruments and Methods in Physics Research A, 592(3), p.154 - 161, 2008/07
Times Cited Count:20 Percentile:77.66(Instruments & Instrumentation)A test experimental line at SPring-8 has been constructed for the generation of backward Compton scattered (BCS) -ray by head-on collision between an 8 GeV electron beam and a far-infrared (FIR) laser. For the FIR laser, we use a continuous-wave methanol laser optically pumped by a carbon dioxide () laser. The FIR laser output power achieved is 1.6 W at maximum for 118.8 m lasing; this value is the highest in the case of this type of laser. As a result of the direct measurement, the generated BCS -ray flux was found to be about photons/s. This value is consistent with the estimation calculated by taking into account the input laser power and the transmittance of the laser transport system.
Shimomura, Koichiro*; Kadono, Ryosuke*; Nishiyama, Kusuo*; Watanabe, Isao*; Suzuki, Takao*; Pratt, F.*; Oishi, Kazuki; Mizuta, Masashi*; Saito, Mineo*; Chow, K. H.*; et al.
Physica B; Condensed Matter, 376-377, p.444 - 446, 2006/04
Times Cited Count:1 Percentile:6.64(Physics, Condensed Matter)Suzuki, Satoru; Tachi, Yukio; Sato, Haruo
Journal of Nuclear Science and Technology, 40(9), p.698 - 701, 2003/09
Times Cited Count:5 Percentile:36.81(Nuclear Science & Technology)None
Taniguchi, Naoki; Kawasaki, Manabu*; Kawakami, Susumu; Suzuki, Haruo*
JNC TN8400 2003-016, 89 Pages, 2003/03
In current repository concept of high-level radioactive disposal in soft rock system, concrete support will be emplaced around the buffer material, and groundwater pH will be increased by the contact with cement. In such condition, carbon steel overpack i
Taniguchi, Naoki; Kawasaki, Manabu*; Kawakami, Susumu; Suzuki, Haruo*
13th Asian Pacific Corrosion Control Conference (APCCC-13) (CD-ROM), H06, 8 Pages, 2003/00
None
Suzuki, Satoru; Sato, Haruo
JNC TN8400 2002-002, 46 Pages, 2002/05
For a better understanding of the relationship between groundwater salinity and diffusivity of radionuclides in compacted bentonite, salinity dependences of effective diffusion coefficients De for I, Sr and HDO were investigated using a through-diffusion method. A sodium-bentonite was purified from Kunipia F (Na-montmorillonite content 99 wt.%), in order to eliminate unknown influences of impurities (e.g. quartz and organic substances), MX80 bentonite also used included 25% of impurities. The powdered sample was compacted to a dry bulk density () of 0.9 Mg/m or 1.6 Mg/m for the purified bentonite and 1.8 Mg/m for MX80 bentonite. These samples were then soaked in NaCl solutions of 0.01 to 0.5 M. Effective diffusion coefficients for I and Sr and increased with increasing salinity as represented by the power law, while De for HDO was almost constant. A salinity dependence of De in compacted sodium-bentonite was well expressed by the power n that was practically independent of impurities or dry densities. The Power n was evaluated to be 0.5 to 0.7 for anions (I and Cl), about 1.5 for Sr and 0.0 to 0.1 for HDO. Deuterated water may migrate through both interstitial pore water and interlamellar water, whereas iodine (I) may prefer interstitial pore water as major diffusion pathways as interpreted by the anion exclusion effect. On the other hand, a positive salinity dependence of De for Sr conflicts with the previously reported tendency explained by the surface diffusion theory. Discrepancies can be considered to be due to the diffusion cell design on the basis of rock capacity factor and boundary conditions for Sr.
Suzuki, Satoru; Sato, Haruo; Ishidera, Takamitsu; Fujii, Naoki*; Kawamura, Katsuyuki*
JNC TN8400 2001-031, 44 Pages, 2002/05
In order to quantify effect of temperature on diffusivity of deuterated water (HDO) in compacted sodium-bentonite, through-diffusion experiments were conducted at elevated tempemture from 298 to 333 K. Kunipia F (Na-montmorillonite content 98 wt. %; Kunimine Industly Co.) was compacted to a dry density of 0.9 and l.35 Mg/m. Since smectite flakes were perpendicularly oriented to a direction of compaction, anisotropy of diffusivity was investigated parallel and normal to the preferred orientation of smectite. Effective diffusion coeficient D of HDO was larger for a diffusional direction parallel to the preferred orientation than normal to that for both dry densities. These results well agreed to the previously reported ones for tritiated water. Activation energies of D in compacted bentonite increased with increasing dry density in the range of 19 - 25 kJ/mol which was slightly larger than that in bulk water (18 kJ/mol). This relationship can be considered to be due to both the pore structure development and high activation energy of water (18-23 kJ/mol) in the vicinity of smectite surface (within 2 nm) on the basis of molecular dynamics simulations.
Kawamura, Katsuyuki*; Ichikawa, Yasuaki*; Suzuki, Satoru; Shibata, Masahiro; Sato, Haruo; Ueno, Kenichi
JNC TY8400 2002-015, 90 Pages, 2002/03
None
Suzuki, Satoru; Sato, Haruo
JNC TN8410 2001-028, 36 Pages, 2002/03
For a safety assessment of the high-level radioactive waste disposal, effective diffusion coefficients (D) of radionuclides in bentonite have been accumulated by the through-diffusion method. It has been found recently that experimental results on Ds for several cations (cesium and strontium) by the fairly standard experimental method in JNC differ from those previously reported in several papers. Discrepancy can be considered to be due to different design of diffusion cell and system. In order to confirm influences of the experimental design on cation diffusivities in bentonite, a flow-through diffusion system was developed and several diffusion experiments were conducted.As a result, magnitude of D and its salinity dependence were relatively different between the standard and flow-through diffusion system. Since the latter system can control boundary conditions of the experiment more strictly than the standard method, we can conclude that the flow-through diffusion system provide correct results. In addition, we apply this flow-through diffusion system to a modification of controlling boundary condition during the experiment and to the diffusion experiment under controlled temperature.
Sato, Haruo; Suzuki, Satoru
Special Workshop of Clay Microstructure and its Importance Soil Behaviour, p.87 - 96, 2002/00
None
Suzuki, Satoru; Fujishima, Atsushi; Ueno, Kenichi; Ichikawa, Yasuaki*; Kawamura, Katsuyuki*; Fujii, Naoki*; Shibata, Masahiro; Sato, Haruo; Kitayama, Kazumi*
Nendo Kagaku, 41(2), p.43 - 57, 2001/12
None
Suzuki, Satoru; Fujishima, Atsushi; Ueno, Kenichi; Ichikawa, Yasuaki*; Kawamura, Katsuyuki*; Fujii, Naoki*; Shibata, Masahiro; Sato, Haruo
JNC TY8400 2001-003, 66 Pages, 2001/05
no abstracts in English
Sato, Haruo; Kitamura, Akira; Suzuki, Satoru
JNC TN8200 2001-002, 43 Pages, 2001/03
None
Suzuki, Satoru; Sato, Haruo
Migration '01, 0 Pages, 2001/00
None
Suzuki, Satoru; ; Ueno, Kenichi; Shibata, Masahiro; Sato, Haruo
Migration '01, 0 Pages, 2001/00
None
Miyauchi, Hideaki; Yoshitomi, Hiroshi; Akazaki, Tomohiko; Tachibana, Haruo; Suzuki, Takashi
no journal, ,
In the Nuclear Science Research Institute in the Japan Atomic Energy Agency (JAEA), the registration management of exposure dose data for radiation workers has been carried out using the "Personal dose Management System" that is took over from the old Japan Atomic Energy Research Institute. In accordance with the result of the discussion which of unification of a radiation control system, or rationalization in JAEA, development of the server system for Personal Dose Management was gradually advanced from 2006, all functions were ready in 2010, and the server system started formal operation in 2011. By the development of the server system, work efficiency and the accuracy of data improved, and more precise management of exposure dose was enabled.
Suzuki, Takehiko; Murayama, Takashi; Miyauchi, Hideaki; Sato, Yoshitaka; Oi, Yoshihiro; Tachibana, Haruo; Yoshitomi, Hiroshi
no journal, ,
Nuclear Science Research Institute is assisting activities concerning the accident of the Fukushima No.1 Nuclear Power Station including the environmental monitoring and the resident's house decontamination, etc. In these assistance, we executing the personal monitoring to assistance staff, because there was fear of the external exposure and the internal exposure. We did by the measurement and the evaluation method of the personal monitoring in consideration of the rise of the environmental background level. We introduce the method of use to evaluate the exposed dose etc.