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Modelling the effect of mechanical remediation on dose rates above radiocesium contaminated land

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 $$^{134}$$Cs and $$^{137}$$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.


OECD/NEA benchmark on pellet-clad mechanical interaction modelling with fuel performance codes; Impact of number of radial pellet cracks and pellet-clad friction coefficient

Dost$'a$l, M.*; Rossiter, G.*; Dethioux, A.*; Zhang, J.*; 天谷 政樹; Rozzia, D.*; Williamson, R.*; Kozlowski, T.*; Hill, I.*; Martin, J.-F.*

Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 10 Pages, 2018/10

The benchmark on PCMI was initiated by OECD/NEA Expert Group on Reactor Fuel Performance (EGRFP) in June 2015 and is currently in the latter stages of compiling results and preparing the final report. The aim of the benchmark is to improve understanding and modelling of PCMI amongst NEA member organisations. This is being achieved by comparing PCMI predictions of different fuel performance codes for a number of cases. Two of these cases are hypothetical cases aiming to facilitate understanding of the effects of code-to-code differences in fuel performance models. The two remaining cases are actual irradiations, where code predictions are compared with measured data. During analysis of participants' results of the hypothetical cases, the assumptions for number of radial pellet cracks and the pellet-clad friction coefficient (which can be zero, finite or infinite) were identified to be important factors in explaining differences between predictions once pellet-cladding contact occurs. However, these parameters varied in the models and codes used originally by the participants. This fact led to the extension of the benchmark by inclusion of two additional cases, where the number of radial pellet cracks and three different values of the friction coefficient were prescribed in the case definition. Seven calculations from six organisations contributed results were compared and analysed in this paper.


Modeling watershed-scale $$^{137}$$Cs transport in a forested catchment affected by the Fukushima Dai-ichi Nuclear Power Plant accident

Wei, L.*; 木内 豪*; 吉村 和也; Velleux, M. L.*

Journal of Environmental Radioactivity, 171, p.21 - 33, 2017/05

 被引用回数:6 パーセンタイル:29.97(Environmental Sciences)

This study developed a watershed $$^{137}$$Cs migration model on the basis of the Two-Dimensional Runoff, Erosion, and Export model (TREX) framework and was applied in a forested catchment in Fukushima. This model considered the conditions of $$^{137}$$Cs field loss from the vegetation layer and downward movement in soil, two $$^{137}$$Cs distribution phases in water, and multiple solid particle classes. The model represented observed $$^{137}$$Cs transport well. Our simulations show that the $$^{137}$$Cs was transported from the catchment by clay, silt, and sand at a ratio of 17:70:13. The source of transported $$^{137}$$Cs is estimated to originate from hillside and areas near the river bank, and the accumulation of $$^{137}$$Cs was also evaluated.


A Modelling study on water radiolysis for primary coolant in PWR

向井 悟*; 梅原 隆司*; 塙 悟史; 笠原 茂樹; 西山 裕孝

Proceedings of 20th International Conference on Water Chemistry of Nuclear Reactor Systems (NPC 2016) (USB Flash Drive), 9 Pages, 2016/10



Advance in integrated modelling towards prediction and control of JT-60SA plasmas

林 伸彦; 本多 充; 白石 淳也; 宮田 良明; 若月 琢馬; 星野 一生; 藤間 光徳; 鈴木 隆博; 浦野 創; 清水 勝宏; et al.

Europhysics Conference Abstracts (Internet), 39E, p.P5.145_1 - P5.145_4, 2015/06

Towards prediction and control of JT-60SA plasmas, we are developing codes/models which can describe physics/engineering factors, and integrating them to one code TOPICS. Physics modelling: Coupling with MINERVA/RWMaC code showed that MHD equilibrium variation by centrifugal force largely affects RWM stability and the toroidal rotation shear stabilizes RWM. Coupling with OFMC code for NB torques, 3D MHD equilibrium code VMEC and drift-kinetic code FORTEC-3D for NTV torque, and toroidal momentum boundary model, predicted the core rotation of $$sim$$2% of Alfv$'e$n speed for a ITER hydrogen L-mode plasma. Coupling with core impurity transport code IMPACT showed the accumulation of Ar seeded to reduce the divertor heat load is so mild that plasma performance can be recovered by additional heating in JT-60SA steady-state (SS) scenario. Simulations coupled with MARG2D code showed that plasma current can be ramped-up to reach $$beta_N ge$$3 with MHD modes stabilized by ideal wall and with no additional flux consumption of central solenoid in JT-60SA. Engineering modelling: Coupling with integrated real-time controller showed that simultaneous control of $$beta_N$$ and $$V_{loop}$$ is possible at $$beta_N ge$$4 in JT-60SA SS scenarios. MHD equilibrium control simulator MECS demonstrated equilibrium control during heating phase and collapse induced events within power supply capability of PF coils in JT-60SA.


Engineering aspects in modeling of high burnup LWR fuel behavior

鈴木 元衛

Proceedings of 2nd Japan-Korea-China (5th Japan-Korea) Seminar on Nuclear Reactor Fuel and Materials, p.4 - 10, 2004/03




清水 勝宏; 滝塚 知典

プラズマ・核融合学会誌, 71(11), p.1135 - 1146, 1995/11



Proceedings of the Third CSNI Workshop on Iodine Chemistry in Reactor Safety; September 11-13, 1991, Tokai-mura, Japan

石榑 顯吉*; 佐伯 正克; 早田 邦久; 杉本 純

JAERI-M 92-012, 522 Pages, 1992/03




The GTS-LTD MONOPOLE-2 experiment at grimsel; Predictive modeling and comparison with monitoring data

Soler, J. M.*; Martin, A. J.*; Lanyon, G. W.*; Havlov$'a$, V.*; Siitari-Kauppi, M.*; 舘 幸男

no journal, , 

原位置の擾乱の少ない結晶質岩中のマトリクス拡散を現実的に評価することを目的に、スイスのグリムゼル原位置試験場において原位置長期拡散(LTD)プロジェクトを進めている。現在2回目の原位置拡散試験(モノポール2)を実施中である。1回目の原位置試験(モノポール1)の結果及び室内拡散試験の結果に基づき、モノポール2試験の予測解析を実施し、トレーサー注入孔及び観察孔中のモニタリングデータと比較した。非収着性トレーサー(HTO, Cl)については、室内での透過拡散試験から導出された拡散パラメータによって、モニタリングデータ、特に注入孔のデータがより良く説明された。収着性のCsとBaの初期の濃度減少は、これらの元素の高い収着性の影響を示すものである。モノポール1試験で得られたCsのパラメータは、モノポール2にも適用可能であった。しかしながら、Baについては、予測される以上に収着の影響が大きいと評価された。


SKB GWFTS task force: Predictive modeling of a matrix diffusion experiment in gneiss at ONKALO (Finland)

Soler, J. M.*; L$"o$fgren, M.*; Nilsson, K.*; Lanyon, G. W.*; Gylling, B.*; Vidstrand, P.*; Neretnieks, I.*; Moreno, L.*; Liu, L.*; Meng, S.*; et al.

no journal, , 




Kim, M.; Malins, A.; 吉村 和也; 佐久間 一幸; 操上 広志; 北村 哲浩; 町田 昌彦

no journal, , 

空間線量率のシミュレーションには、異なる土地タイプ、建物表面や森林において異なる放射性セシウムの分布を考慮する必要がある。さらに建物, 地形, 樹木, 土壌の複雑な遮蔽効果を空間線量率に反映する必要がある。本研究では、放射線輸送解析プログラムのPHITSによる空間線量率評価のシミュレーションを行うために、対象エリアにおける土地表面, 土地タイプ, 建物および樹木の3次元モデル作成が可能なツールを開発した。このツールは、対象エリアのオルソ画像, 数値表層モデル(DSM), 数値標高モデル(DEM)を用いて、PHITSのジオメトリ入力ファイルが作成できる。また、建物については、日本の典型的な9種類の建物モデルを用いて、樹木については広葉樹と針葉樹モデルを用いて作成されるため対象エリアに合わせて現実的なモデルの作成が可能である。線源設定は、$$^{134}$$Cs及び$$^{137}$$Csの放射能分布をモデルの様々な環境要素に対し任意に分布設定が可能である。今回は、東京電力福島第一原子力発電所から約5km離れた大熊町の200m$$times$$200m大きさのエリアを選定しモデルを作成した。また$$^{134}$$Cs及び$$^{137}$$Csの線源設定は、$$gamma$$線スペクトロメトリーによる測定値に基づいて設定した。選定エリアに対して、PHITSによる空間線量率の計算結果と歩行サーベイによる観測結果と比較を行った。また、モデルの様々な構成要素の空間線量率への影響を評価するために、建物や樹木のない平坦な地形、さらに選定エリアの$$^{134}$$Cs及び$$^{137}$$Cs分布の平均値を考慮した、より単純な系でのシミュレーションを行った。

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