Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Yoshitomi, Hiroshi; Tanimura, Yoshihiko*; Tatebe, Yosuke; Tsutsumi, Masahiro; Kawasaki, Katsuya; Kowatari, Munehiko; Yoshizawa, Michio; Shimizu, Shigeru*; Kim, J.-S.*; Lee, J.-G.*; et al.
Proceedings of 4th Asian and Oceanic Congress on Radiation Protection (AOCRP-4) (CD-ROM), 4 Pages, 2015/07
Takahashi, Yoshikazu; Suwa, Tomone; Nabara, Yoshihiro; Ozeki, Hidemasa; Hemmi, Tsutomu; Nunoya, Yoshihiko; Isono, Takaaki; Matsui, Kunihiro; Kawano, Katsumi; Oshikiri, Masayuki; et al.
IEEE Transactions on Applied Superconductivity, 25(3), p.4200904_1 - 4200904_4, 2015/06
Times Cited Count：3 Percentile：20.23(Engineering, Electrical & Electronic)The Japan Atomic Energy Agency (JAEA) is responsible for procuring all amounts of Central Solenoid (CS) Conductors for ITER, including CS jacket sections. The conductor is cable-in-conduit conductor (CICC) with a central spiral. A total of 576 Nb
Sn strands and 288 copper strands are cabled around the central spiral. The maximum operating current is 40 kA at magnetic field of 13 T. CS jacket section is circular in square type tube made of JK2LB, which is high manganese stainless steel with boron added. Unit length of jacket sections is 7 m and 6,300 sections will be manufactured and inspected. Outer/inner dimension and weight are 51.3/35.3 mm and around 90 kg, respectively. Eddy Current Test (ECT) and Phased Array Ultrasonic Test (PAUT) were developed for non-destructive examination. The defects on inner and outer surfaces can be detected by ECT. The defects inside jacket section can be detected by PAUT. These technology and the inspected results are reported in this paper.
Tsuda, Shuichi; Yoshida, Tadayoshi; Tsutsumi, Masahiro; Saito, Kimiaki
Journal of Environmental Radioactivity, 139, p.260 - 265, 2015/01
Times Cited Count：42 Percentile：77.44(Environmental Sciences)The car-borne survey system, KURAMA-II, developed by the Kyoto University Research Reactor Institute has been used for air dose rate mapping after the Fukushima Daiichi Nuclear Power Plant accident. The KURAMA-II consists of a CsI(Tl) scintillation detector, a GPS device, and a control device for data processing. The dose rates monitored by the KURAMA-II are based on the G(E) function (spectrum-dose conversion operator), which can precisely calculate dose rate from the measured pulse-height distribution even if the energy spectrum changes significantly. The characteristics of the KURAMA-II have been investigated with particular consideration to the reliability of the calculated G(E) function, dose rate dependence, statistical fluctuation, angular dependence, and energy dependence. The results indicate that 100 units of KURAMA-II systems have acceptable quality for mass monitoring dose rates in the environment.
-ray field by ionisation chamber and build-up plateKowatari, Munehiko; Tanimura, Yoshihiko; Tsutsumi, Masahiro
Radiation Protection Dosimetry, 162(4), p.446 - 458, 2014/12
Times Cited Count：3 Percentile：23.92(Environmental Sciences)no abstracts in English
Tsutsumi, Tomoaki*; Adachi, Rika*; Takatsuki, Satoshi*; Nei, Daisuke*; Kameya, Hiromi*; Todoriki, Setsuko*; Kikuchi, Masahiro; Kobayashi, Yasuhiko; Matsuda, Rieko*; Teshima, Reiko*
Shokuhin Shosha, 49(1), p.9 - 15, 2014/12
no abstracts in English
Shinto, Katsuhiro; Ichikawa, Masahiro; Takahashi, Yasuyuki*; Kubo, Takashi*; Tsutsumi, Kazuyoshi; Kikuchi, Takayuki; Kasugai, Atsushi; Sugimoto, Masayoshi; Gobin, R.*; Girardot, P.*; et al.
Proceedings of 11th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.1009 - 1012, 2014/10
The prototype accelerator is being developed as an engineering validation for the International Fusion Materials Irradiation Facility (IFMIF) equipped with an accelerator-driven-type neutron source for developing fusion reactor materials. This prototype accelerator is a deuteron linear accelerator consisting of an injector, an RFQ, a superconducting linac and their auxiliaries. It aims to produce a CW D
beam with the energy and current of 9 MeV/125 mA. The injector test was completed at CEA/Saclay in 2012 for producing a CW H beam and a CW D beam with the energy and current of 100 keV/140 mA. After the beam test at CEA/Saclay, the injector was transported to the International Fusion Energy Research Centre (IFERC) located in Rokkasho, Aomori, Japan. In the end of 2013, installation of the injector was started at IFERC for the injector beam test beginning from summer 2014 in order to obtain better beam qualities to be satisfied with the injection and acceleration of the following accelerators. In this paper, some results of the injector beam test performed at CEA/Saclay and the status quo of the installation of the injector at IFERC are presented.
Li(p,n)Be reactionTanimura, Yoshihiko; Tsutsumi, Masahiro; Yoshizawa, Michio
Radiation Protection Dosimetry, 161(1-4), p.149 - 152, 2014/10
Times Cited Count：2 Percentile：16.44(Environmental Sciences)Mono-energetic neutron calibration fields have been established in the energy range from 8 keV to 19 MeV using an accelerator at FRS. In the 144, 250 and 565 keV fields, mono-energetic neutrons are produced by bombarding a LiF target with accelerated protons in order to cause Li(p,n)Be reactions. Photons mixed in these neutron fields, which are produced by other nuclear reactions, can affect the calibration results. These mixed photon dose should be evaluated. In this paper the photons produced by the nuclear reactions between neutrons and target, its supporting materials and the constructional materials of the irradiation room such as the walls, floor and ceiling. were calculated using the MCNP-ANT code. Then the ambient dose equivalent H*(10) of the photons were evaluated and compared with that of the mono-energetic neutrons.
Tanimura, Yoshihiko; Tsutsumi, Masahiro; Yoshizawa, Michio
Radiation Protection Dosimetry, 161(1-4), p.144 - 148, 2014/10
Times Cited Count：10 Percentile：60.98(Environmental Sciences)A Long Counter (LC) is the most appropriate detector to measure neutron fluence due to flat response over a wide neutron energy range. Therefore, it is usually employed as a neutron fluence monitor. The weight of the LC used at FRS is 50 kg. It is too heavy to transfer it from one room to another room. Then we developed a new portable long counter whose weight is 15 kg. The portable LC consists of a 
He or BF
counter and a cylindrical moderator. It was designed to have an almost flat response from a few eV to a few MeV. While typical LCs have air gaps in the front surface, which allow lower-energy neutrons to penetrate deeper into the moderator, the portable LC has little space to make such air gaps due to the small size. Then we employed a polystyrene (PS) moderator instead of a polyethylene (PE) one as a front part of the moderator. As the hydrogen density of PS is nearly half that of PE, lower-energy neutrons can penetrate the PS moderator deeper than the PE moderator.
Sn conductor for ITER central solenoidTakahashi, Yoshikazu; Nabara, Yoshihiro; Ozeki, Hidemasa; Hemmi, Tsutomu; Nunoya, Yoshihiko; Isono, Takaaki; Matsui, Kunihiro; Kawano, Katsumi; Oshikiri, Masayuki; Uno, Yasuhiro; et al.
IEEE Transactions on Applied Superconductivity, 24(3), p.4802404_1 - 4802404_4, 2014/06
Times Cited Count：25 Percentile：72.88(Engineering, Electrical & Electronic)Japan Atomic Energy Agency (JAEA) is procuring all amounts of NbSn conductors for Central Solenoid (CS) in the ITER project. Before start of mass-productions, the conductor should be tested to confirm superconducting performance in the SULTAN facility, Switzerland. The original design of cabling twist pitches is 45-85-145-250-450 mm, called normal twist pitch (NTP). The test results of the conductors with NTP was that current shearing temperature (Tcs) is decreasing due to electro-magnetic (EM) load cycles. On the other hand, the results of the conductors with short twist pitches (STP) of 25-45-80-150-450 mm show that the Tcs is stabilized during EM load cyclic tests. Because the conductors with STP have smaller void fraction, higher compaction ratio during cabling is required and possibility of damage on strands increases. The technology for the cables with STP was developed in Japanese cabling suppliers. The several key technologies will be described in this paper.
Ishii, Kenji; Fujita, Masaki*; Sasaki, Takanori*; Minola, M.*; Dellea, G.*; Mazzoli, C.*; Kummer, K.*; Ghiringhelli, G.*; Braicovich, L.*; Toyama, Takami*; et al.
Nature Communications (Internet), 5, p.3714_1 - 3714_8, 2014/04
Times Cited Count：89 Percentile：94.27(Multidisciplinary Sciences)Tanimura, Yoshihiko; Fujii, Katsutoshi; Tsutsumi, Masahiro; Yoshizawa, Michio
Progress in Nuclear Science and Technology (Internet), 4, p.388 - 391, 2014/04
Mono-energetic neutron calibration fields have been developed at Facility of Radiation Standards (FRS) using a 4 MV Pelletron accelerator. The neutron energies are available between 8 keV and 19 MeV for determining the energy responses of neutron dosemeters. The neutron energies are well adjusted to the energy points specified in the international standard (ISO 8529-1) and Japanese standard (JIS Z4521). Precise neutron fluence is the most important parameter for the calibration. In order to determine the fluence a Long Counter (hereinafter LC) is installed in the field for monitoring the neutron emission rate from the target. The fluence can be precisely determined using the output counts of the LC, the distance from the target, calibration coefficient of the LC and the air attenuation factor. This presentation describes the neutron monitors, outline of our monitoring system, determination of the air attenuation factor and procedure to determine the neutron fluence.
Tanimura, Yoshihiko; Tsutsumi, Masahiro; Yoshizawa, Michio
Progress in Nuclear Science and Technology (Internet), 4, p.392 - 395, 2014/04
1.2 and 2.5 MeV Mono-energetic neutron calibration fields have been developed at Facility of Radiation Standards (FRS) by using a 4MV Pelletron accelerator and employing H(p,n)He reaction. For the calibration, neutron fluence should be precisely evaluated. A silicon semiconductor detector with a polyethylene converter (hereinafter CH
-SSD) was developed to determine the neutron fluence. The detection efficiency of a common CH-SSD is not large enough to determine the neutron fluence. Then we developed a CH-SSD with high efficiency by using a large silicon semiconductor detector with 3,000 mm
sensitive area. This makes it possible to determine the neutron fluence with satisfactory accuracy. The detection efficiency of the CH-SSD was calculated with NRESP-ANT code and PHITS code. The maximum neutron fluence at 1 m from the target were evaluated to be about 1,000 and 2,000 cm
s
in the 1.2 and 2.5 MeV neutron fields, especially.
and reference compound ThCd; Studied by the de Haas-van Alphen effectHirose, Yusuke*; Miura, Yasunao*; Tsutsumi, Hiroki*; Yoshiuchi, Shingo*; Oya, Masahiro*; Sugiyama, Kiyohiro*; Takeuchi, Tetsuya*; Yamagami, Hiroshi*; Yamamoto, Etsuji; Haga, Yoshinori; et al.
Physica Status Solidi (B), 250(3), p.642 - 645, 2013/03
Times Cited Count：4 Percentile：20.56(Physics, Condensed Matter)-rayTsuda, Shuichi; Tsutsumi, Masahiro
Hoken Butsuri, 47(4), p.260 - 265, 2012/12
The spectrum-dose conversion operators (hereafter, G(E) function) for CsI(Tl) scintillation counters with various crystal sizes were calculated based on the response functions obtained by a Monte Carlo simulation code, MCNP5. The G(E) functions were determined in the cases of crystal sizes 5.5
5.55.5, 101010, 131320 and 383825 mm
for ambient dose, H*(10). It is found that the values of H
(10) deduced from the pulse-height spectra and the G(E) function agree with those of H(10) evaluated in the calibration field in JAEA within 2% in the case of irradiations by a 
Cs, 
Ra and a 
Co source, by the measurements using a scintillation counter whose crystal size is 131320 mm.
Okura, Takehisa; Oishi, Tetsuya; Taki, Mitsumasa; Shibanuma, Yukio; Kikuchi, Masamitsu; Akino, Hitoshi; Kikuta, Yasuaki; Kawasaki, Masatsugu; Saegusa, Jun; Tsutsumi, Masahiro; et al.
JAEA-Data/Code 2012-010, 37 Pages, 2012/05
JAEA-Data-Code-2012-010.pdf:2.28MB
Due to the accident at Fukushima Daiichi Nuclear Power Plant caused by the 2011 off the Pacific coast of Tohoku Earthquake occurred at 11th March 2011, the emergency environmental radiation monitoring was conducted at Nuclear Science Research Institute, Japan Atomic Energy Agency (JAEA). This report provides the monitoring results of ambient -ray dose rate and atmospheric radioactivity concentration until the beginning of June 2011. Some anthropogenic radionuclides such as Cs-134, Cs-137, I-131, I-132, Te-132, Xe-133 and others were detected from air samples. The atmospheric radioactivity concentrations varied with some peaks corresponded with that of ambient -ray dose rate after 15th March 2011. Composition of each peak showed various characteristic. Internal exposure caused by inhalation was estimated from the observed atmospheric radioactivity.
Satoyama, Tomonori; Kishimoto, Katsumi; Hoshi, Akiko; Takaizumi, Hirohide; Tsutsumi, Masahiro; Inanobe, Hiroshi; Yoshimori, Michiro
JAEA-Technology 2011-003, 53 Pages, 2011/03
JAEA-Technology-2011-003.pdf:1.6MB
In Nuclear Science Research Institute, clearance activities for extremely low-level radioactive concrete debris, which were generated from the modification activities of JRR-3 from FY 1985 to FY 1989 and now are stored in the waste storage facility NL, have been carried out in order to plan reasonable disposal and effectively reusing of concrete waste, moreover to secure storage capacity at the waste storage facilities. Method for measuring and evaluating of radioactivity concentration was applied for approval of Minister of MEXT on November 8, 2007, approved on July 25, 2008. After that the necessary equipments for clearance works were equipped and operational safety progress and manuals for clearance works were prepared. So clearance works were started in FY 2009. This report summarizes the method for measuring and evaluating of radioactivity concentration for concrete generated from modification activities of JRR-3.
Shikaze, Yoshiaki; Tanimura, Yoshihiko; Saegusa, Jun; Tsutsumi, Masahiro; Uchita, Yoshiaki; Yoshizawa, Michio
Progress in Nuclear Science and Technology (Internet), 1, p.166 - 169, 2011/02
For the reliable dose evaluation in high intensity proton accelerator facilities such as J-PARC, high energy neutron calibration fields above 20 MeV to evaluate energy response of both the monitors and the dosimeters used there, are required. Therefore, development of three neutron calibration fields of 45, 60 and 75 MeV has been in progress at TIARA of JAEA-Takasaki. Evaluation of the neutron fluence and establishment of the monitoring technique are important for the development of the calibration fields. Here, results of the fluence evaluation in the absolute measurement by using proton recoil counter telescope with high detection efficiency, a transmission type neutron fluence monitor newly developed to monitor neutron beam directly and its performance will be reported.
Shikaze, Yoshiaki; Tanimura, Yoshihiko; Saegusa, Jun; Tsutsumi, Masahiro; Uchida, Yoshiaki*; Yoshizawa, Michio; Harano, Hideki*; Matsumoto, Tetsuro*; Mizuhashi, Kiyoshi
JAEA-Review 2010-065, JAEA Takasaki Annual Report 2009, P. 158, 2011/01
no abstracts in English
Li(p,n)Be reactionTanimura, Yoshihiko; Tsutsumi, Masahiro; Saegusa, Jun; Shikaze, Yoshiaki; Yoshizawa, Michio
Radiation Measurements, 45(10), p.1163 - 1166, 2010/12
Times Cited Count：4 Percentile：30.63(Nuclear Science & Technology)Mono-energetic neutron calibration fields have been developed at the Facility of Radiation Standards of Japan Atomic Energy Agency using a 4MV Pelletron accelerator. The fields of 8, 27, 144, 250, 565 keV and 1.2, 2.5, 5.0, 14.8 MeV neutrons were established using scandium, lithium, deuterium and tritium targets. The nuclear reactions between the accelerated particles and the target materials produce not only the mono-energetic neutrons but also unwanted photons. As the photons can affect the readings of dosemeters, their effects should be evaluated. In this work the photons in the 144, 250 and 565 keV neutron fields from a lithium fluoride target were measured using a cylindrical NaI(Tl) detector with 7.62 cm both in diameter and in length. The ambient dose equivalent H*(10) for the photons was evaluated by applying the "G(E) function" to the measured pulse height spectrum.
) cross-sections of a nucleus in the range 0.008 
20 MeVSegawa, Mariko; Toh, Yosuke; Harada, Hideo; Kitatani, Fumito; Koizumi, Mitsuo; Hatsukawa, Yuichi; Fukahori, Tokio; Matsue, Hideaki; Oshima, Masumi; Tanimura, Yoshihiko; et al.
Nuclear Instruments and Methods in Physics Research A, 618(1-3), p.153 - 159, 2010/06
Times Cited Count：2 Percentile：22.16(Instruments & Instrumentation)A new measurement system to determine the neutron-capture cross section of a nucleus at 0.008 20 MeV has been installed at the 4 MV Pelletron accelerator laboratory at the facility of radiation standards at Japan Atomic Energy Agency. Pulsed neutrons are produced by bombarding a pulsed proton beam on 
Li (or 
H) or a deuteron beam on H. The performance of the new system was studied by measuring discrete rays from neutron capture by 
Pb and 
Pb to their low-lying states at several resonances at 10 110 keV using neutrons from Li(p,n)Be. The rays were detected with a good signal-to-noise ratio by means of a highly sensitive anti-Compton NaI(Tl) spectrometer combined with a time-of-flight method. The present study demonstrated good sensitivity of the new system to determine the neutron-capture cross section of a nucleus at keV neutron energy.
