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Cs concentrations in east Japanese riversTsuji, Hideki*; Ishii, Yumiko*; Shin, M.*; Taniguchi, Keisuke*; Arai, Hirotsugu*; Kurihara, Momo*; Yasutaka, Tetsuo*; Kuramoto, Takayuki*; Nakanishi, Takahiro; Lee, S*; et al.
Science of the Total Environment, 697, p.134093_1 - 134093_11, 2019/12
Times Cited Count：17 Percentile：59.38(Environmental Sciences)To investigate the main factors that control the dissolved radiocesium concentration in river water in the area affected by the Fukushima Daiichi Nuclear Power Plant accident, the correlations between the dissolved Cs concentrations at 66 sites normalized to the average Cs inventories for the watersheds with the land use, soil components, topography, and water quality factors were assessed. We found that the topographic wetness index is significantly and positively correlated with the normalized dissolved Cs concentration. Similar positive correlations have been found for European rivers because wetland areas with boggy organic soils that weakly retain Cs are mainly found on plains. However, for small Japanese river watersheds, the building area ratio in the watershed strongly affected the dissolved Cs concentration.
Kurihara, Momo*; Yasutaka, Tetsuo*; Aono, Tatsuo*; Ashikawa, Nobuo*; Ebina, Hiroyuki*; Iijima, Takeshi*; Ishimaru, Kei*; Kanai, Ramon*; Karube, Jinichi*; Konnai, Yae*; et al.
Journal of Radioanalytical and Nuclear Chemistry, 322(2), p.477 - 485, 2019/11
Times Cited Count：2 Percentile：21.58(Chemistry, Analytical)We assessed the repeatability and reproducibility of methods for determining low dissolved radiocesium concentrations in freshwater in Fukushima. Twenty-one laboratories pre-concentrated three of 10 L samples by five different pre-concentration methods (prussian-blue-impregnated filter cartridges, coprecipitation with ammonium phosphomolybdate, evaporation, solid-phase extraction disks, and ion-exchange resin columns), and activity of radiocesium was measured. The z-scores for all of the Cs results were within 
2, indicating that the methods were accurate. The relative standard deviations (RSDs) indicating the variability in the results from different laboratories were larger than the RSDs indicating the variability in the results from each separate laboratory.
Takada, Chie; Kurihara, Osamu*; Kanai, Katsuta; Nakagawa, Takahiro; Tsujimura, Norio; Momose, Takumaro
NIRS-M-252, p.3 - 11, 2013/03
A massive earthquake and tsunami on March 11, 2011 resulted in an enormous amount of release of radioactivity to the environment. On the day after the earthquake occurrence, Japan Atomic Energy Agency (JAEA) started emergency radiological monitoring. The measurements with whole body counter (WBC) for the staff members who had returned from Fukushima started at the end of March. The measured activity of 
I due to inhalation for emergency staff varied from LLD to 7 kBq, which corresponded to a range of estimated initial intakes of 
1 to 60 kBq when extrapolated back to the date on which the staff started the operation in Fukushima. The measured activity of 
Cs and Cs were both in the ranges of LLD - 3 kBq. The range of initial intake of Cs to I was 11 when taking a median from all the measurements. The maximum committed effective dose of 0.8 mSv was recorded for a worker, a member of the 2nd monitoring team dispatched from March 13 to 14.
I in the thyroids of employees involved in the Fukushima Daiichi Nuclear Power Station accidentKurihara, Osamu*; Kanai, Katsuta; Nakagawa, Takahiro; Takada, Chie; Tsujimura, Norio; Momose, Takumaro; Furuta, Sadaaki
Journal of Nuclear Science and Technology, 50(2), p.122 - 129, 2013/02
Times Cited Count：6 Percentile：44.02(Nuclear Science & Technology)no abstracts in English
Momose, Takumaro; Kurihara, Osamu; Takada, Chie; Furuta, Sadaaki
Proceedings of 1st International Symposium on Radiation Emergency Medicine at Hirosaki University, p.65 - 72, 2010/07
The basic principle of radiation control at plutonium facility such as characteristics of plutonium and relevant radionuclide which are operated in nuclear fuel cycle facilities is introduced and potential radioactive contaminations in accident is discussed. As a practice, decontamination procedure of skin at Tokai Reprocessing Plant, some of the operating principles and applications of various radiation detection and measurement instruments for contamination control and occupational monitoring for internal contamination are introduced. Special methods of measurement for alpha emitters for performing radiological monitoring such as radio autography of plutonium contamination on smear samples, nasal swab sampling and measurement, in vivo and in vitro analysis for plutonium and uranium have been improved and proven. The internal dose calculation code was originally developed in order to estimate retrospectively in case of accidental intake of plutonium.
Kurihara, Osamu; Takada, Chie; Takasaki, Koji; Ito, Kimio; Momose, Takumaro; Miyabe, Kenjiro
Radiation Protection Dosimetry, 127(1-4), p.411 - 414, 2007/11
Times Cited Count：7 Percentile：47.34(Environmental Sciences)Practical action levels for beginning chelation therapy to remove plutonium in the body are now under discussion in Japan since there has been no experience in administrating agents to a subject in accidental intake in Japan although a first commercial reprocessing plant is about to start operation. Recently, International Commission on Radiological Protection (ICRP) proposed some medical intervention levels for chelation therapy on ICRP Publication 96. These levels are determined based on internal dose however common monitoring methods such as lung counting or excreta analysis are not necessarily suitable in terms of both sensitivity and promptness. As an alternative, the authors paid attention to nose swabs and introduced the practical action levels.
Kurihara, Osamu; Hato, Shinji; Kanai, Katsuta; Takada, Chie; Takasaki, Koji; Ito, Kimio; Ikeda, Hiroshi*; Oeda, Mikihiro*; Kurosawa, Naohiro*; Fukutsu, Kumiko*; et al.
Journal of Nuclear Science and Technology, 44(10), p.1337 - 1346, 2007/10
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)In the case of internal contamination of radionuclides, it is necessary to perform internal dose assessment for radiation protection. For this purpose, the ICRP has given the dose coefficients and the retention and excretion rates for various radionuclides. However, these dosimetric quantities are calculated only in typical conditions, therefore, are not necessarily covered enough in the case of dose assessment in which specific information on the incident or/and individual biokinetic characteristics should be taken into account retrospectively. This paper describes a developed PC-based package of software REIDAC to meet the needs in retrospective dose assessment. REIDAC was verified by comparisons with dosimetric quantities given on the ICRP publications and several examples of practical use were also shown.
Am lung monitoring system using an imaging plateHirota, Masahiro*; Kurihara, Osamu; Takada, Chie; Takasaki, Koji; Momose, Takumaro; Deji, Shizuhiko*; Ito, Shigeki*; Saze, Takuya*; Nishizawa, Kunihide*
Health Physics, 93(1), p.28 - 35, 2007/07
Times Cited Count：4 Percentile：31.41(Environmental Sciences)A new Am lung monitoring system without shielding was devised by using an imaging plate system. The Lawrence Livermore National Laboratory's realistic torso phantom containing a Am lung was covered by imaging plates sealed in lightproof bags. The imaging plate system displayed Am lung images characteristic of the lung shape of the torso phantom. The imaging plate system's lower detection limits of 14 Bq for 60 min exposure and 6 Bq for 300 min were the same levels as those of the phoswich detectors and the germanium detectors placed in shielded rooms. The imagingplate system for 60 min exposure detected about 2% of the annual limit of 740 Bq for Am inhalation. A lung monitoring system using imaging plates is applicable for Am lung monitoring.
Kurihara, Osamu; Takasaki, Koji; Momose, Takumaro; Terakado, Yoshinori*; Takahashi, Koji*
Journal of Nuclear Science and Technology, 41(Suppl.4), p.243 - 246, 2004/03
None
Kurihara, Osamu; Takasaki, Koji; Momose, Takumaro; Terakado, Yoshinori*; Takahashi, Koji*
IRPA-11, 0 Pages, 2004/00
As an alternative to the phantom used for calibrating whole-body counters, in this study the Monte Carlo simulation was used to evaluate peak efficiencies for a whole-body counter installed at the JNC, to examine the validity of using the simulation technique to calibrate the whole-body counter. Prior to simulating a phantom, the sensitive region of the crystal in the Ge detectors which are used with the whole-body counter, was evaluated by assuming dead layers in the simulation. The phantom was then simulated based on the determined configuration of the sensitive region. As a result, the calculated peak efficiencies were fairly consistent with the measured ones. For an entire body scanning measurement, the discrepancy between the measurement and the simulation was within 4% for peak energies ranging from 81.0 keV to 1460.8 keV. The simulation technique is therefore both effective and practical for situations that are difficult to be simulated by a phantom.
Kurihara, Osamu; Takasaki, Koji; Momose, Takumaro
Hoken Butsuri, 38(2), p.109 - 112, 2003/00
None
Kurihara, Osamu; Tasaki, Takashi; Momose, Takumaro; Hayashi, Naomi; Shinohara, Kunihiko
Radiation Protection Dosimetry, 102(2), p.137 - 141, 2002/00
Times Cited Count：7 Percentile：44.35(Environmental Sciences)None
Takasaki, Koji; Kurihara, Osamu; Tasaki, Takashi; Momose, Takumaro; Maruo, Yoshihiro; Shinohara, Kunihiko
THE 47TH ANNUAL CONFERENCE ON BIOASSAY,ANALYTICAL & ENVIRONMENTAL RADIOCHEMISTRY, 0 Pages, 2002/00
None
Miyahara, H.*; Narita, N.*; Ikeda, Keiichi*; Kato, Y.*; Fujiki, K.*; Momose, Takumaro; Tasaki, Takashi; Kurihara, Osamu; Hayashi, Naomi
JNC TY8400 2001-002, 81 Pages, 2001/07
JNC-TY8400-2001-002.pdf:2.35MB
no abstracts in English
Kurihara, Osamu; Tsujimura, Norio; Takasaki, Koji; Momose, Takumaro; Maruo, Yoshihiro
Proceedings of iTRS International Symposium on Radiation Safety and Detection Technology (ISORD-1), 0 Pages, 2001/00
None
Pu distribution in the lungHirota, Masahiro; Kurihara, Osamu; Takada, Chie; Takasaki, Koji; Momose, Takumaro; Deji, Shizuhiko*; Ito, Shigeki*; Saze, Takuya*; Nishizawa, Kunihide*
no journal, ,
no abstracts in English
Pu distribution in the lung by an imaging plateHirota, Masahiro; Kurihara, Osamu; Takada, Chie; Takasaki, Koji; Momose, Takumaro; Deji, Shizuhiko*; Ito, Shigeki*; Saze, Takuya*; Nishizawa, Kunihide*
no journal, ,
no abstracts in English
Kanai, Katsuta; Kurihara, Osamu; Terakado, Yoshinori*; Takada, Chie; Ito, Kimio; Momose, Takumaro
no journal, ,
In JAEA Nuclear Fuel Cycle Engineering Laboratory(JAEA-NFCEL), MOX fuel fabrication facilities and spent fuel reprocessig facilities are operated during over several ten years for the purpose of establishing the nuclear fuel cycle technology. In these facilities, we have to need to pay attention to plutonium. We present the internal monitoring technique for plutonium in JAEA-NFCEL.
Kanai, Katsuta; Kurihara, Osamu*; Takada, Chie; Nakagawa, Takahiro; Morishita, Yuki; Hokama, Tomonori; Takimoto, Misaki; Maruo, Yoshihiro; Momose, Takumaro
no journal, ,
no abstracts in English
Hashimoto, Makoto; Takada, Chie; Takahashi, Masa; Suzuki, Takehiko; Takasaki, Koji; Endo, Akira; Yoshizawa, Michio; Momose, Takumaro; Kim, E.*; Kurihara, Osamu*; et al.
no journal, ,
no abstracts in English
