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Ashikagaya, Yoshinobu; Kawasaki, Tomokatsu; Yoshino, Toshiaki; Ishida, Keiichi
JAERI-Tech 2005-010, 81 Pages, 2005/03
JAERI-Tech-2005-010.pdf:16.65MB
no abstracts in English
Nakamura, Takemi*; Tonoike, Kotaro; Miyoshi, Yoshinori
Radiation Protection Dosimetry, 110(1-4), p.483 - 486, 2004/09
Times Cited Count：2 Percentile：16.58(Environmental Sciences)Dose measurement and evaluation technique in criticality accident conditions with a thermo luminescence dosimeter (TLD) was studied at the Transient Experiment Critical Facility (TRACY) of Japan Atomic Energy Research Institute (JAERI). The tissue absorbed dose can be derived from the ambient dose equivalent given by measurement with a TLD using the conversion factor given by computation. Using this technique, the neutron dose around the SILENE reactor of the Institute for Radioprotection and Nuclear Safety (IRSN) of France was measured in the Accident Dosimetry Intercomparison Exercise (June 10-21, 2002) organized by OECD/NEA and IRSN. In this exercise, the 
dose was also measured with a TLD. In this report, measurements and evaluation results at TRACY and SILENE are presented.
Saegusa, Jun; Tanimura, Yoshihiko; Yoshizawa, Michio; Yoshida, Makoto
Radiation Protection Dosimetry, 110(1-4), p.91 - 95, 2004/09
Times Cited Count：4 Percentile：28.24(Environmental Sciences)For the accurate estimation of neutron dose equivalents, it is important to calibrate dosemeters in the field whose energy spectrum is similar to that in the workplace. For the purpose, studies are made toward the built of the spectrum changeable neutron calibration fields with the Van-de-Graff accelerator in the FRS in JAERI. The fields are produced by bombarding proton or deuteron beam from the accelerator to suitable targets surrounded by quasi-cylindrical moderators and absorbers of various materials. In the fields, neutron spectra with wide range energy index should be provided with sufficient fluence rate for the calibration of dosemeters. The objectives and conceptual design of the fields are discussed here, followed by the test simulation results of neutron spectra produced by various arrangements of a target and moderators.
Yoshizawa, Michio; Tanimura, Yoshihiko; Saegusa, Jun; Nemoto, Hisashi*; Yoshida, Makoto
Radiation Protection Dosimetry, 110(1-4), p.81 - 84, 2004/09
Times Cited Count：3 Percentile：22.47(Environmental Sciences)The facility of Radiation Standards (FRS) of JAERI has equipped with the concrete-moderated neutron calibration fields as simulated workplace neutron fields. The fields use an Am-Be (37GBq) neutron source placed in the narrow space surrounded by concrete wall and bricks to produce scattered neutrons. The neutron spectra of the fields were measured with Bonner multi-sphere spectrometer system (BMS), spherical recoil-proton proportional counters (RPCs), and a liquid scintillation counter (NE-213). The results were compared with each other, and the neutron spectra and the ambient dose equivalent rate, 
(10), were agreed well within the uncertainty. The angular distributions of neutron fluence were calculated by the MCNP-4B2 Monte Carlo code to obtain the reference personal dose equivalent rate, 
(10). The calculated results show that the scattered neutrons have a wide variety of incident angles. The reference (10) values considered the angular distribution were found to be 10-18% smaller than those without consideration.
Ueta, Shohei; Takada, Eiji*; Sumita, Junya; Shimizu, Atsushi; Ashikagaya, Yoshinobu; Umeda, Masayuki; Sawa, Kazuhiro
JAERI-Tech 2004-047, 87 Pages, 2004/06
JAERI-Tech-2004-047.pdf:6.24MB
In the radiation shielding design of the High Temperature Engineering Test Reactor (HTTR), strong attention is needed to avoid especially upward neutron streaming. Shielding performance test have been carried out in the Rise-to-power test up to full power operation of 30MW. The measured dose equivalent rates in unrestricted area were lower than the detection limit for neutron-ray, and background level for -ray. The neutron dose equivalent rate measured in the stand pipes room was about 120
Sv/h at full power operation, which was much lower than the shielding design (330 mSv/h) and the prediction (10 mSv/h).
Ashikagaya, Yoshinobu; Yoshino, Toshiaki; Yasu, Katsuji; Kurosawa, Yoshiaki; Sawa, Kazuhiro
JAERI-Tech 2002-094, 80 Pages, 2002/12
JAERI-Tech-2002-094.pdf:12.8MB
no abstracts in English
Sakamoto, Yukio
JAERI-Research 2002-025, 34 Pages, 2002/11
JAERI-Research-2002-025.pdf:1.91MB
no abstracts in English
Takada, Eiji*; Fujimoto, Nozomu; Nojiri, Naoki; Umeta, Masayuki; Kokusen, Shigeru; Ashikagaya, Yoshinobu
JAERI-Data/Code 2002-009, 83 Pages, 2002/05
JAERI-Data-Code-2002-009.pdf:3.51MB
Dose equivalent rate around the fuel handling machine, the control rod handling machine, stand pipe compartment, maintenance pit were measured during gamma ray measurements from HTTR fuel, which was called as “power distribution measurements". The power distribution measurement was the first time to handle the fuel blocks irradiated in the core. Dose equivalent rate measurement aiming the check of shielding performance of components, the check of unexpected streaming path. The radiation monitoring during operation was carried out. As the results, there was no problem on shielding. The measured data at operation condition were also obtained. The data will be useful to expect operation circumstance in the future.
Ito, Masashi; Shiraishi, Akemi; Murakami, Hiroyuki
JAERI-Tech 2001-048, 20 Pages, 2001/07
JAERI-Tech-2001-048.pdf:1.27MB
In Japan Atomic Energy Research Institute, a new type radiophotoluminescent(RPL) glass dosimeter is recently adopted replaced film badge for external personal monitoring. Some fundamental characteristics of this dosimeter, such as dose dependence linearity, energy dependence, dose evaluation accuracy against mixed irradiation condition,fading, etc.,were examined at the Facility of Radiation Standard(FRS),JAERI. The results have proved that the RPL glass dosimeter has sufficient characteristics in practical use as a personal dosimeter for all of the items examined.
JAERI-Tech 99-002, 50 Pages, 1999/01
no abstracts in English
Kimura, Hideo; Takano, Hideki; Muromura, Tadasumi
Journal of Nuclear Materials, 274(1-2), p.197 - 205, 1999/00
Times Cited Count：7 Percentile：48.76(Materials Science, Multidisciplinary)no abstracts in English
Saito, Kimiaki; N.Petoussi*; Zankl, M.*
Health Physics, 74(6), p.698 - 706, 1998/06
Times Cited Count：49 Percentile：94.65(Environmental Sciences)no abstracts in English
Li(p,n) reactionNakao, Noriaki*; Nakashima, Hiroshi; Nakao, Makoto*; Sakamoto, Yukio; Nakane, Yoshihiro; ; Tanaka, Shunichi; Nakamura, Takashi*
JAERI-Data/Code 98-013, 46 Pages, 1998/03
JAERI-Data-Code-98-013.pdf:2.14MB
no abstracts in English
Kimura, Hideo; Matsuzuru, Hideo; Takano, Hideki; Muromura, Tadasumi
JAERI-Research 97-049, 25 Pages, 1997/07
JAERI-Research-97-049.pdf:1.42MB
no abstracts in English
Li(p,n) reactionNakao, Noriaki*; Nakashima, Hiroshi; Sakamoto, Yukio; Nakane, Yoshihiro; Tanaka, Shunichi; ; Nakamura, Takashi*; Shin, Kazuo*;
JAERI-Data/Code 97-020, 46 Pages, 1997/06
JAERI-Data-Code-97-020.pdf:1.53MB
no abstracts in English
;
Dekomisshoningu Giho, 0(15), p.24 - 34, 1996/12
no abstracts in English
Homma, Toshimitsu; Togawa, Orihiko
JAERI-Data/Code 96-034, 47 Pages, 1996/11
JAERI-Data-Code-96-034.pdf:1.64MB
no abstracts in English
JAERI-Data/Code 96-020, 45 Pages, 1996/06
JAERI-Data-Code-96-020.pdf:1.1MB
no abstracts in English
Li(P,n) reaction; Nakao, Noriaki*; Tanaka, Shunichi; Nakamura, Takashi*; Shin, Kazuo*; Tanaka, Susumu; Meigo, Shinichiro; Nakane, Yoshihiro; Takada, Hiroshi; Sakamoto, Yukio; et al.
JAERI-Data/Code 96-005, 46 Pages, 1996/03
JAERI-Data-Code-96-005.pdf:1.54MB
no abstracts in English
; Sakamoto, Yukio; Tanaka, Shunichi
JAERI-Data/Code 95-004, 64 Pages, 1995/06
JAERI-Data-Code-95-004.pdf:1.55MB
no abstracts in English
