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Cs and 
Cs radioactivity measurementsMalins, A.; 今村 直広*; 新里 忠史; 高橋 純子*; Kim, M.; 佐久間 一幸; 篠宮 佳樹*; 三浦 覚*; 町田 昌彦
Journal of Environmental Radioactivity, 226, p.106456_1 - 106456_12, 2021/01
被引用回数：6 パーセンタイル：40.04(Environmental Sciences)Understanding the relationship between the distribution of radioactive 
Cs and 
Cs in forests and ambient dose equivalent rates (
*(10)) in the air is important for researching forests in eastern Japan affected by the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident. This study used a large number of measurements from forest samples, including Cs and Cs radioactivity concentrations, densities and moisture contents, to perform Monte Carlo radiation transport simulations for *(10) between 2011 and 2017. Calculated *(10) at 0.1 and 1 m above the ground had mean residual errors of 19% and 16%, respectively, from measurements taken with handheld NaI(Tl) scintillator survey meters. Setting aside the contributions from natural background radiation, Cs and Cs in the organic layer and the top 5 cm of forest soil generally made the largest contributions to calculated *(10). The contributions from Cs and Cs in the forest canopy were calculated to be largest in the first two years following the accident. Uncertainties were evaluated in the simulation results due to the measurement uncertainties in the model inputs by assuming Gaussian measurement errors. The mean uncertainty (relative standard deviation) of the simulated *(10) at 1 m height was 11%. The main contributors to the total uncertainty in the simulation results were the accuracies to which the Cs and Cs radioactivities of the organic layer and top 5 cm of soil, and the vertical distribution of Cs and Cs within the 5 cm soil layers, were known. Radioactive cesium located in the top 5 cm of soil was the main contributor to *(10) at 1 m by 2016 or 2017 in the calculation results for all sites.
Malins, A.; 越智 康太郎; 町田 昌彦; 眞田 幸尚
Proceedings of Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 2020 (SNA + MC 2020), p.147 - 154, 2020/10
Compton-to-peak analysis is a method for selecting suitable coefficients to convert count rates measured with in situ gamma ray spectrometry to radioactivity concentrations of Cs & Cs in the environment. The Compton-to-peak method is based on the count rate ratio of the spectral regions containing Compton scattered gamma rays to that with the primary Cs & Cs photopeaks. This is known as the Compton-to-peak ratio (RCP). RCP changes as a function of the vertical distribution of Cs & Cs within the ground. Inferring this distribution enables the selection of appropriate count rate to activity concentration conversion coefficients. In this study, the PHITS Monte Carlo radiation transport code was used to simulate the dependency of RCP on different vertical distributions of Cs & Cs within the ground. A model was created of a LaBr
(Ce) detector used in drone helicopter aerial surveys in Fukushima Prefecture. The model was verified by comparing simulated gamma ray spectra to measurements from test sources. Simulations were performed for the infinite half-space geometry to calculate the dependency of RCP on the mass depth distribution (exponential or uniform) of Cs & Cs within the ground, and on the altitude of the detector above the ground. The calculations suggest that the sensitivity of the Compton-to-peak method is greatest for the initial period following nuclear fallout when Cs & Cs are located close to the ground surface, and for aerial surveys conducted at low altitudes. This is because the relative differences calculated between RCP with respect to changes in the mass depth distribution were largest for these two cases. Data on the measurement height above and on the Cs & Cs activity ratio is necessary for applying the Compton-to-peak method to determine the distribution and radioactivity concentration of Cs & Cs in the ground.
線スペクトロメトリーにおける円柱状体積試料のサム効果補正山田 隆志*; 浅井 雅人; 米沢 仲四郎*; 柿田 和俊*; 平井 昭司*
Radioisotopes, 69(9), p.287 - 297, 2020/09
円柱状体積試料に含まれるCsの定量において、日本の標準的な市販線解析プログラムではサム効果の補正の際に試料体積の効果を適切に考慮していないため、補正が不十分となり、定量値が過小評価となることを確認した。本研究では、一般的なGe検出器に対して試料体積を適切に考慮した実用的なサム効果補正方法を開発して有効性を評価し、誤差1%以下の精度で定量できることを確認した。
Malins, A.; 操上 広志; 北村 哲浩; 町田 昌彦
Remediation Measures for Radioactively Contaminated Areas, p.259 - 272, 2019/00
Mechanical strategies for remediating radiocesium contaminated soils, e.g. at farms, schoolyards, gardens or parks, lower air dose rates in one of two characteristic ways. The first is to physically remove radiocesium from the environment, for example by stripping topsoil and sending it for disposal. The second is to redistribute the radiocesium deeper within the ground, e.g. by mixing the topsoil or switching the positions of different soil layers, in order that soil attenuates radiocesium gamma rays before they reach the surface. The amount that air dose rates reduce because of remediation can be calculated using radiation transport methods. This chapter summarizes modelling results for the effect of topsoil removal (with and without recovering with a clean soil layer), topsoil mixing, and soil layer interchange on dose rates. Using measurements of the depth profile of Cs and Cs activity in soil at un-remediated sites across North East Japan, the potential effectiveness of remediation work was estimated considering remediation to different soil depths and different time lags after the accident. The results show that remediation performance would have been essentially constant irrespective of the time at which it was undertaken in the initial five year period following the fallout.
-UO fuel assemblies鶴田 晴通; 須崎 武則; 松浦 祥次郎
Journal of Nuclear Science and Technology, 14(1), p.43 - 53, 1977/01
被引用回数：4照射済PuO-UO燃料集合体内の核分裂生成物の分布を、Ge(Li)検出器を用いた線スペクトロスコピ法によって非破壊的に測定した。PuO-UO燃料の場合について、
Cs強度と
Cs/Cs強度比の間に比例関係のあることを確証した。
Ru/Cs比の分布は集合体内でほとんど一定であり、この比は照射済燃料がPuまたはUであったかを識別するための良い指標になることを示した。
Malins, A.; 今村 直広*; 新里 忠史; Kim, M.; 佐久間 一幸; 篠宮 佳樹*; 三浦 覚*; 町田 昌彦
no journal, ,
PHITS Monte Carlo models were used to assess factors affecting ambient dose equivalent rates (H*(10)) in forests in Fukushima Prefecture. Three models were developed with different levels of detail to understand how the distribution of radioactive cesium within forests, shielding by trees and soil composition affect H*(10). The models were parametrized using measurements from deciduous and coniferous forests in Fukushima Prefecture.
