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Featured researches published by Masaki Andoh.


Journal of Environmental Radioactivity | 2015

Measurement of air dose rates over a wide area around the Fukushima Dai-ichi Nuclear Power Plant through a series of car-borne surveys

Masaki Andoh; Yukio Nakahara; Shuichi Tsuda; Tadayoshi Yoshida; Norihiro Matsuda; Fumiaki Takahashi; Satoshi Mikami; Nobuyuki Kinouchi; Tetsuro Sato; Minoru Tanigaki; Koichi Takamiya; Nobuhiro Sato; Ryo Okumura; Yukio Uchihori; Kimiaki Saito

A series of car-borne surveys using the Kyoto University RAdiation MApping (KURAMA) and KURAMA-II survey systems has been conducted over a wide area in eastern Japan since June 2011 to evaluate the distribution of air dose rates around the Fukushima Dai-ichi Nuclear Power Plant and to evaluate the time-dependent trend of decrease in air dose rates. An automated data processing system for the KURAMA-II system was established, which enabled rapid analysis of large amounts of data obtained using about 100 KURAMA-II units. The initial data used for evaluating the migration status of radioactive cesium were obtained in the first survey, followed by other car-borne surveys conducted over more extensive and wider measurement ranges. By comparing the measured air dose rates obtained in each survey (until December 2012), the decreasing trend of air dose rates measured through car-borne surveys was found to be more pronounced than those expected on the basis of the physical decay of radioactive cesium and of the air dose rates measured using NaI (Tl) survey meters in the areas surrounding the roadways. In addition, it was found that the extent of decrease in air dose rates depended on land use, wherein it decreased faster for land used as building sites than for forested areas.


Journal of Nuclear Science and Technology | 2008

Prediction Accuracy Improvement of Neutronic Characteristics of a Breeding Light Water Reactor Core by Extended Bias Factor Methods with Use of FCA-XXII-1 Critical Experiments

Teruhiko Kugo; Masaki Andoh; Kensuke Kojima; Masahiro Fukushima; Takamasa Mori; Yoshihiro Nakano; Shigeaki Okajima; Takanori Kitada; Toshikazu Takeda

Two extended bias factor methods, the LC and PE methods, were applied to the prediction accuracy evaluation of neutronic characteristics of a breeding light water reactor, using data of FCA-XXII-1 critical experiments, in order to investigate the features and effectiveness of these methods on the basis of an actual core design and existing experimental results. The present study confirms the following features of these methods. Both the LC and PE methods can improve the prediction accuracy the most when all the experimental results are used. The prediction accuracy improvement is achieved mainly by reducing uncertainty due to errors in cross sections. This is done by realizing a profile of sensitivity coefficients closer to that of the target core and suppressing the influence of errors in experiments and experimental analysis methods. The PE method always improves the prediction accuracy with the use of any combination of experimental results. It is always superior to the LC method in the improvement of the prediction accuracy. Concerning the effectiveness of using the extended bias factor methods with the data of FCA XXII-1 critical experiments, it is concluded that the experimental results regarding multiplication factor are more effective than the other experimental results, namely, reaction rate ratios of 238U capture to 239Pu fission (C28/F49) and void reactivity, in reducing prediction uncertainties of all the neutronic characteristics of the target core investigated: the multiplication factor, the C28/F49, and the void reactivity of the target core. This is due to the fact that the extended bias factor methods cannot fully utilize the potential that these experimental results have for the reduction of the uncertainties due to the errors in cross sections because of their strong correlations to the target core characteristics. This failure is due to large errors in the experiments and/or the experimental analysis methods.


Journal of Environmental Radioactivity | 2018

Decreasing trend of ambient dose equivalent rates over a wide area in eastern Japan until 2016 evaluated by car-borne surveys using KURAMA systems

Masaki Andoh; Satoshi Mikami; Shuichi Tsuda; Tadayoshi Yoshida; Norihiro Matsuda; Kimiaki Saito

As part of the investigation of the distribution of ambient dose equivalent rates around the Fukushima Dai-ichi Nuclear Power Plant (FDNPP), car-borne surveys using Kyoto University RAdiation MApping (KURAMA) systems have been conducted over a wide area in eastern Japan since 2011. The enormous volume of measurement data collected until 2016, including those until 2012 which were reported in the previous paper, was analyzed, and dependencies of the decreasing trend of the dose rates in regions within 80u202fkm of the FDNPP on land-use categories, evacuation order areas and magnitude of the dose rates were examined. The air dose rates within 80u202fkm of the FDNPP tended to decrease considerably with respect to the physical decay of radiocaesium. The decrease of the dose rate in the forest was slower than its decrease in other regions, while that in urban area was the fastest. The decrease in the air dose rate from 2011 was the fastest outside the evacuation order area until 2015, and it was the slowest in the difficult-to-return zone. However, the decreasing trend starting from 2013 showed that the decrease in the zone in preparation for the lifting of the evacuation order and in the residence restriction area was the fastest. It was found that the air dose rates decreased depending on the magnitude of the dose rates and elapsed time from the FDNPP accident, i.e. the decrease in air dose rates in areas with relatively low dose ranges (such as 0.2-0.5 μSv/h) was the largest during a period relatively early after the accident, and the decreasing rate in the dose rate ranges of 1.9-3.8 and 3.8-9.5 μSv/h were the fastest after 2013. The averaged ratios were analyzed to obtain the ecological half-lives of the fast and slow decay components, and those in whole area within 80u202fkm of FDNPP were estimated to be 0.44u202f±u202f0.05u202fy and 6.7u202f±u202f1u202fy, respectively. The ecological half-lives with respect to the land use categories, evacuation order areas and magnitude of the dose rates were also evaluated. The decrease in the dose rates obtained by the car-borne survey was larger than that obtained on flat ground with few disturbances using the NaI(Tl) survey meter during approximately 1.5u202fy after the FDNPP accident. Thereafter, the difference of decreasing tendencies in the air dose rates between both the measurements was negligibly small, with the ratio of dose rates by the car-borne survey to those by the fixed-point measurement of 0.72-0.77.


Journal of Nuclear Science and Technology | 2007

Measurement and analysis of 238U doppler reactivity effect in FCA cores simulating light-water-moderated MOX fuel lattices

Masaki Andoh; Masahiro Fukushima; Shigeaki Okajima; Kenji Kawasaki

The Doppler reactivity effect of 238U was measured in simulated MOX fuel using the FCA facility for the purpose of obtaining data on the 238U Doppler reactivity effect in light-water-moderated MOX fuel and evaluating the prediction accuracy of the current analysis code systems and nuclear data library. Experimental data on the Doppler reactivity effect from room temperature up to 800°C were obtained for a uranium fueled core and mockup cores for MOX-fueled LWR using cylindrical natural-uranium samples. With the use of various samples with various neutron spectra, 238U Doppler reactivity effects at energies generally in the low range below 1 keV were evaluated. Analyses were performed using the current standard analysis code systems for fast and thermal reactors, with the JENDL-3.3 data library. Both analyses yielded calculated/experimental value (C/E) ratios of 0.96 to 1.06 for the MOX cores, a good agreement within the experimental error, and those in the uranium core were similar.


Journal of Environmental Radioactivity | 2018

Measurement of ambient dose equivalent rates by walk survey around Fukushima Dai-ichi Nuclear Power Plant using KURAMA-II until 2016

Masaki Andoh; Hideaki Yamamoto; Takashi Kanno; Kimiaki Saito

Ambient dose equivalent rates in various environments related to human lives were measured by walk surveys using the KURAMA-II systems from 2013 to 2016 within an 80-km radius of the Fukushima Dai-ichi Nuclear Power Plant. The dose rate of the locations where the walk survey was performed decreased to about 38% of its initial value in the 42 months from June 2013 to the December 2016, which was beyond that attributable to the physical decay of radiocaesium. The ecological half-life of the slow decreasing component was evaluated to be 4.1u202f±u202f0.2 y. The air dose rates decreased depending on the level of the evacuation areas, and the decrease in the dose rates was slightly larger in populated areas where humans are active. The dose rates as measured by walk surveys exhibited a good correlation with those by car-borne surveys, suggesting that car-borne survey data are reflecting the air dose rates in living environments surrounding roads. The comparison of walk survey data with car-borne survey data indicated that the air dose rate varies largely even within a 100u202fm square area, and the variation is enhanced by human activities. The dose rates measured by the walk surveys were estimated to be medial of those along roads and those of undisturbed flat ground, and they were found to be decreasing quickly compared with the air dose rate from the flat ground fixed-point measurements.


Journal of Nuclear Science and Technology | 2012

Measurement and analysis of reflector reactivity worth by replacing stainless steel with zirconium at the fast critical assembly (FCA)

Masahiro Fukushima; Yasunori Kitamura; Masaki Andoh; Teruhiko Kugo

A reflector reactivity worth was measured by replacing stainless steel with zirconium at the FCA. The experimental result of the positive reflector reactivity worth demonstrates the effectiveness of the zirconium reflector compared with the SS reflector in the fast reactor core. This paper also focuses on the validation of standard calculation methods used for fast reactors with JENDL-4.0. As a result, it is confirmed that the standard calculation methods for the reflector reactivity worth show agreement within the experimental error.


Atomic Energy Society of Japan | 2017

Evaluation of Ambient Dose Equivalent Rates Owing to Natural Radioactive Nuclides in Eastern Japan by Car-Borne Surveys Using KURAMA–II

Masaki Andoh; Norihiro Matsuda; Kimiaki Saito


Atomic Energy Society of Japan | 2018

Investigation on distribution of radioactive substances in Fukushima

Masaki Andoh


Radioisotopes | 2015

IV Practical Aspects of Air Dose Rate Measurements in the Environment

Shuichi Tsuda; Tadayoshi Yoshida; Masaki Andoh; Norihiro Matsuda; Satoshi Mikami; Minoru Tanigaki; Ryo Okumura; Koichi Takamiya; Nobuhiro Sato; Akiyuki Seki; Hiroshi Takemiya; Kimiaki Saito


Radioisotopes | 2015

V Characteristics of Air Dose Rate Distribution in the Environment around the Fukushima Nuclear Power Plant site

Satoshi Mikami; Norihiro Matsuda; Masaki Andoh; Sakae Kinase; Mitsuaki Kitano; Keiichi Kawase; Shinichiro Matsumoto; Hideaki Yamamoto; Kimiaki Saito

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Kimiaki Saito

Japan Atomic Energy Agency

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Norihiro Matsuda

Japan Atomic Energy Agency

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Satoshi Mikami

Japan Atomic Energy Agency

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Shuichi Tsuda

Japan Atomic Energy Agency

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Tadayoshi Yoshida

Japan Atomic Energy Agency

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Teruhiko Kugo

Japan Atomic Energy Agency

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Hideaki Yamamoto

Japan Atomic Energy Agency

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Kensuke Kojima

Japan Atomic Energy Agency

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