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Sono, Hiroki; Ono, Akio; Kojima, Takuji; Yamane, Yoshihiro*
Journal of Nuclear Science and Technology, 44(1), p.43 - 53, 2007/01
Times Cited Count：2 Percentile：18.73(Nuclear Science & Technology)A practical method is proposed for retrospective estimation of the spatial dose distribution and the number of fissions in a typical criticality accident. In this method, two kinds of low-fading and tissue-equivalent dosimeters are used as area dosimeters: an alanine dosimeter and a thermoluminescence dosimeter made of enriched lithium tetra borate. The procedure of the method consists of four parts: (1) dosimetry using area dosimeters (2) search for the center of the radiation source, (3) estimation of the spatial dose distribution, and (4) estimation of the number of fissions. Dosimetry of criticality accident situations simulated at the TRACY facility demonstrates the practicability of the method. Although a post-hoc analysis in principle, this method gives useful information on the magnitude and hazard level of the accident to determine the strategy of radiation emergency medicine and other post-accident measures if the area dosimeters are retrieved immediately after the accident.
Ando, Masaki; Iijima, Susumu*; Oigawa, Hiroyuki; Sakurai, Takeshi; Nemoto, Tatsuo*; Okajima, Shigeaki; Osugi, Toshitaka*; Ono, Akio; Hayasaka, Katsuhisa; Sodeyama, Hiroshi
JAEA-Data/Code 2006-006, 67 Pages, 2006/03
JAEA-Data-Code-2006-006.pdf:6.08MB
As a part of research and development of an advanced fueled fast reactor, we carried out benchmark experiments in the FCA-XVII-1 core with MOX simulating fuel to obtain reference data to be compared with those measured in the FCA-XVI-1 and XVI-2 cores simulating metallic fueled FBR. Following nuclear characteristics were measured in the experiments: Criticality, reaction rate ratio, sample reactivity worth, sodium void reactivity effect and 
U Doppler effect. Extra measurements were performed in modified FCA-XVII-1 cores to obtain experimental data for various reactor types: (1) Measurement of sodium void reactivity effect in various plutonium isotope compositions, (2) Measurement of sodium void reactivity effect in a core where axial blanket was replaced with a sodium layer and (3) Measurement of various nuclear characteristics in a nitride fuel region. This report describes methods and results of the above experiments and method of analysis.
Sono, Hiroki; Ono, Akio*; Kojima, Takuji; Takahashi, Fumiaki; Yamane, Yoshihiro*
Journal of Nuclear Science and Technology, 43(3), p.276 - 284, 2006/03
Times Cited Count：1 Percentile：9.98(Nuclear Science & Technology)For a study on the applicability of a personal dosimetry method to criticality accident dosimetry, an assessment of the human body surface and internal dose estimations was performed by experimental and computational simulations. The experimental simulation was carried out in a criticality accident situation at the TRACY facility. The neutron and 
-ray absorbed doses in muscle tissue were separately estimated by a dosimeter set of an alanine dosimeter and a thermoluminescence dosimeter made of enriched lithium tetra borate with a phantom. The computational simulation was conducted with a Monte Carlo code taking account of dose components of neutrons, prompt -rays and delayed -rays. The computational simulation was ascertained to be valid by comparison between the calculated dose distributions in the phantom and the measured ones. The assessment based on the experimental and computational simulations confirmed that the personal dosimetry using the dosimeter set provided a first estimation of the body surface and internal doses with precision.
-ray dose components in criticality accident situationsSono, Hiroki; Yanagisawa, Hiroshi*; Ono, Akio*; Kojima, Takuji; Soramasu, Noboru*
Journal of Nuclear Science and Technology, 42(8), p.678 - 687, 2005/08
Times Cited Count：4 Percentile：30.51(Nuclear Science & Technology)Component analysis of -ray doses in criticality accident situations is indispensable for further understanding on emission behavior of -rays and accurate evaluation of external exposure to human bodies. Such dose components were evaluated, categorizing -rays into four components: prompt, delayed, pseudo components in the period of criticality, and a residual component in the period after the termination of criticality. This evaluation was performed by the combination of dosimetry experiments at the TRACY facility using a thermoluminescent dosimeter (TLD) made of lithium tetra borate and computational analyses using a Monte Carlo code. The evaluation confirmed that the dose proportions of the above components varied with the distance from the TRACY core tank. This variation was due to the difference in attenuation of the individual components with the distance from the core tank. The evaluated dose proportions quantitatively clarified the contribution of the pseudo and the residual components to be excluded for accurate evaluation of -ray exposure.
Ono, Akio*
Kaku Busshitsu Kanri Senta Nyusu, 33(9), p.12 - 15, 2004/09
no abstracts in English
Onodera, Seiji; Sugawara, Susumu; Kobayashi, Heigo; Haga, Koichi; Fukushima, Susumu*; Shichiji,Isamu*; Ono, Akio
JAERI-Tech 2002-070, 77 Pages, 2002/09
JAERI-Tech-2002-070.pdf:8.74MB
no abstracts in English
Yanagisawa, Hiroshi; Nakajima, Ken; Ono, Akio; Miyoshi, Yoshinori
Journal of Nuclear Science and Technology, 39(7), p.800 - 803, 2002/07
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
-ray and thermal neutron detectorsYanagisawa, Hiroshi; Ono, Akio
Journal of Nuclear Science and Technology, 39(6), p.597 - 602, 2002/06
Times Cited Count：2 Percentile：17.03(Nuclear Science & Technology)no abstracts in English
-ray exposure rate from short-lived fission products under criticality accident conditionsYanagisawa, Hiroshi; Ono, Akio; Aizawa, Eiju
Journal of Nuclear Science and Technology, 39(5), p.499 - 505, 2002/05
Times Cited Count：4 Percentile：29.25(Nuclear Science & Technology)no abstracts in English
Aizawa, Eiju; Ogawa, Kazuhiko; Sakuraba, Koichi; Tsukamoto, Michio; Sugawara, Susumu; Takeuchi, Masaki*; Miyauchi, Masakatsu; Yanagisawa, Hiroshi; Ono, Akio
JAERI-Tech 2002-031, 120 Pages, 2002/03
JAERI-Tech-2002-031.pdf:4.32MB
TRACY (Transient Experiment Critical Facility) in NUCEF (Nuclear Safety Research Facility) is the pulse-type critical facility using uranyl nitrate solution which can carry out various supercritical experiments changing reactivity addition up to 3$.TRACY achieved its first criticality on 20th December 1995,and transient operations have been conducted Since1996.This report summarizes the operation data of 176 experiments from the first criticality to FY2000.
Saito, Yuichi; Nakajima, Yoshinori; Narumi, Kazumasa; Shibata, Hiromi*; Ito, Akio*; *; Ono, K. L.*
JNC TN7200 2001-001, p.122 - 125, 2002/01
no abstracts in English
Yanagisawa, Hiroshi; Ono, Akio
Journal of Nuclear Science and Technology, 39(1), p.76 - 81, 2002/01
Times Cited Count：3 Percentile：23.41(Nuclear Science & Technology)no abstracts in English
-ray absorbed doses under criticality accident conditions at TRACY using tissue-equivalent dosimetersSono, Hiroki; Yanagisawa, Hiroshi; Ono, Akio; Kojima, Takuji; Soramasu, Noboru*
Nuclear Science and Engineering, 139(2), p.209 - 220, 2001/10
Times Cited Count：7 Percentile：48.68(Nuclear Science & Technology)no abstracts in English
Onodera, Seiji; Hirose, Hideyuki; Izawa, Kazuhiko; Tanino, Shuichi; Kaminaga, Jota*; Sakuraba, Koichi; Miyauchi, Masakatsu; Tonoike, Kotaro; Miyoshi, Yoshinori; Yanagisawa, Hiroshi; et al.
JAERI-Tech 2001-057, 54 Pages, 2001/09
JAERI-Tech-2001-057.pdf:4.28MB
no abstracts in English
Yanagisawa, Hiroshi; Ono, Akio
Journal of Nuclear Science and Technology, 38(9), p.804 - 806, 2001/09
Times Cited Count：2 Percentile：19.66(Nuclear Science & Technology)no abstracts in English
Suzuki, Yasufumi; Dojiri, Shigeru; Ono, Akio; Maeda, Atsushi; Sugikawa, Susumu
Proceedings of International Conference on Back-End of the Fuel Cycle: From Research to Solutions (GLOBAL 2001) (CD-ROM), 7 Pages, 2001/09
no abstracts in English
Yanagisawa, Hiroshi; Ono, Akio; Ogawa, Kazuhiko; Aizawa, Eiju; Yokoyama, Mitsutaka*
Journal of Nuclear Science and Technology, 38(8), p.591 - 599, 2001/08
Times Cited Count：6 Percentile：44.09(Nuclear Science & Technology)no abstracts in English
Ogawa, Kazuhiko; Morita, Toshio*; Yanagisawa, Hiroshi; Aizawa, Eiju; Sakuraba, Koichi; Sugawara, Susumu; Ono, Akio
Journal of Nuclear Science and Technology, 37(12), p.1088 - 1097, 2000/12
no abstracts in English
Onodera, Seiji; Sono, Hiroki; Hirose, Hideyuki; Tanino, Shuichi; Kaminaga, Jota*; Myomae, Tomoki*; Murakami, Kiyonobu; Sakuraba, Koichi; Miyauchi, Masakatsu; Tonoike, Kotaro; et al.
JAERI-Tech 2000-059, 46 Pages, 2000/11
JAERI-Tech-2000-059.pdf:2.86MB
no abstracts in English
-ray doses on criticality accidents of low-enriched uranyl nitrate solution using tissue-equivalent dosimeters at the TRACY facilitySono, Hiroki; Yanagisawa, Hiroshi; Ono, Akio; Kojima, Takuji; Miyoshi, Yoshinori; Soramasu, Noboru*
Proceedings of the ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR2000) (CD-ROM), 9 Pages, 2000/05
no abstracts in English
