Analysis of particles containing alpha emitters in stagnant water in Fukushima Daiichi Nuclear Power Station's Unit 3 reactor building

蓬田 匠; 大内 和希; 森井 志織; 岡 壽崇; 北辻 章浩; 駒 義和; 今野 勝弘*

Scientific Reports (Internet), 14, p.14945_1 - 14945_11, 2024/06

https://doi.org/10.1038/s41598-024-65522-2

福島第一原子力発電所3号機建屋滞留水中の固形分の多数の粒子状物質の中から、核種を含有する微粒子の検出を試みた。核種濃度の異なる、トーラス室と主蒸気隔離弁室の2か所から採取した試料について分析を行った。大部分の核種は10m以上の固形分に存在していた。SEM-EDXを用いる元素分析により、mサイズのUを主成分とする微粒子を検出した。また、アルファトラック法により検出した粒子では、粒径100m程度までの鉄粒子上に核種が分布する様子を観測できた。3号機滞留水中におけるUやその他の核種の存在形態が明らかになった。

Attempts to estimate the amount of contamination by Cs and Sr in cracked concrete considering realistic contamination conditions

山田 一夫*; 洞 秀幸*; 丸山 一平*; 粟飯原 はるか; 富田 さゆり*; 東條 安匡*; 渋谷 和俊*; 細川 佳史*; 五十嵐 豪*; 駒 義和

Proceedings of Waste Management Symposia 2024 (WM2024) (Internet), 7 Pages, 2024/03

Estimation of Cs and Sr contamination of concrete below the turbine pits after the Fukushima Daiichi NPP accident was carried out. Considerations were based on the type of cement and aggregate used, drying, carbonation and cracking of the concrete, and the contamination history, i.e. contact with contaminated water after a one-day immersion in seawater from the tsunami. The relationship between crack density and the amount of contaminated concrete was determined from the reproduction of crack density and the acquisition of apparent diffusion coefficients for cracked and uncracked areas from the immersion experiment with contamination history.

Penetration of Cs and Sr into cracked dry carbonated mortar considering the contamination history of Fukushima Daiichi NPP

山田 一夫*; 東條 安匡*; 粟飯原 はるか; 富田 さゆり*; 洞 秀幸*; 渋谷 和俊*; 駒 義和; 五十嵐 豪*; 細川 佳史*; 丸山 一平*

Proceedings of Waste Management Symposia 2023 (WM2023) (Internet), 12 Pages, 2023/02

Experiments were conducted on mortar made from aggregates used in the Fukushima Daiichi NPP, which were dry carbonated and further cracks were introduced to reproduce the contamination history of the lower part of the turbine pit. The concrete was exposed to contaminated water after being in contact with seawater for one day due to the post-earthquake tsunami; Cs and Sr interacted differently with the constituent materials of the concrete and competitively adsorbed with ions in the seawater. The effects of various factors were quantitatively evaluated by experiment. Dry carbonation conditions enhanced infiltration but had a limited effect on cracking.

Analysis of particles containing alpha-emitters in stagnant water at torus room of Fukushima Dai-ichi Nuclear Power Station's Unit 2 reactor

蓬田 匠; 大内 和希; 岡 壽崇; 北辻 章浩; 駒 義和; 今野 勝弘*

Scientific Reports (Internet), 12(1), p.7191_1 - 7191_10, 2022/05

AA2021-0706.pdf:2.48MB

https://doi.org/10.1038/s41598-022-11334-1

福島第一原子力発電所2号機トーラス室滞留水に含まれる線放出核種の存在形態を、走査型電子顕微鏡X線検出(SEM-EDX)やアルファトラック法により分析した。SEM-EDXによる観察の結果、Uを主成分とするサブm数mサイズの粒子を複数同定できた。これらの粒子はZrなどの燃料被覆管や構造材を構成する元素を含んでいる。また、同じ粒径フラクションの固形分に含まれるU同位体比(235/238)は、原子炉燃料のそれと一致した。このことから、U粒子は原子炉に由来し、これが微細化したものであることを示している。アルファトラック分析により同定した核種含有粒子は、粒径数10m~数100mのサイズであり、SEM-EDXの元素分析の結果、鉄を主成分としていた。核種の物質量は極わずかであることから、Pu, Am, Cm等が鉄粒子上に付着する形態であると考えられる。分析した滞留水中の固形分試料では、Uと他の核種の存在形態が異なる場合があることが明らかになった。

Radioactive waste sampling for characterisation; A Bayesian upgrade

Pyke, C. K.*; Hiller, P. J.*; 駒 義和; 大木 恵一

Nuclear Engineering and Technology, 54(1), p.414 - 422, 2022/01

https://doi.org/10.1016/j.net.2021.07.042

Presented in this paper is a methodology for combining a Bayesian statistical approach with the Data Quality Objectives structured decision-making methodology to provide increased levels of confidence in analytical data when approaching a waste boundary. Development of sampling and analysis plans for the characterisation of radioactive waste often use a simple, one pass statistical approach as underpinning for the sampling schedule. Using a Bayesian statistical approach introduces the concept of Prior information giving an adaptive sample strategy based on previous knowledge. This aligns more closely with the iterative approach demanded of the most commonly used structured decision-making tool in this area (Data Quality Objectives) and the potential to provide a more fully underpinned justification than the more traditional statistical approach. The approach described has been developed in a UK regulatory context but is translated to a waste stream from the Fukushima Daiichi nuclear power station to demonstrate how the methodology can be applied in this context to support decision making regarding the ultimate disposal option for radioactive waste in a more global context.

Stochastic estimation of radionuclide composition in wastes generated at Fukushima Daiichi Nuclear Power Station using Bayesian inference

杉山 大輔*; 中林 亮*; 田中 真悟*; 駒 義和; 高畠 容子

Journal of Nuclear Science and Technology, 58(4), p.493 - 506, 2021/04

https://doi.org/10.1080/00223131.2021.1884137

A modeling calculation methodology for estimating the radionuclide composition in the wastes generated at the Fukushima Daiichi nuclear power station has been upgraded by introducing an approach using Bayesian inference. The developed stochastic method describes the credible interval of the regression curve for the log-normal distribution of the measured transport ratio, which is used to calibrate the radionuclide transport parameters included in the modeling calculation. Consequently, the method can predict the robability distribution of the radionuclide composition in the Fukushima Daiichi wastes. The notable feature of the developed method is that it can explicitly investigate the improvement in the accuracy and confidence (degree of belief) of the estimation of the waste inventory using Bayesian inference. Specifically, the developed method can update and improve the degree of belief of the estimation of the radionuclide composition by visualizing the reduction in the width of uncertainty in the radionuclide transport parameters in the modeling calculation in accordance with the accumulation of analytically measured data. Further investigation is expected to improve the credibility of waste inventory estimation through iteration between modeling calculations and analytical measurements and to reduce excessive conservativeness in the estimated waste inventory dataset.

Hydrothermal-treatment desorption of cesium from clay minerals; The Roles of organic acids and implications for soil decontamination

Yin, X.; Zhang, L.*; 針貝 美樹*; Wang, X.*; Ning, S.*; 中瀬 正彦*; 駒 義和; 稲葉 優介*; 竹下 健二*

Water Research, 177, p.115804_1 - 115804_10, 2020/06

https://doi.org/10.1016/j.watres.2020.115804

The adsorption and desorption of cesium (Cs) on clays of contaminated soil in a rhizosphere zone can be greatly affected by various biogeochemical processes, the timespans of which are usually months to years. Herein, we present several representative scenarios of the binding of Cs on diverse sites of vermiculitized biotite by controlled Cs adsorption to particles of different sizes. We investigated whether and how the fixed Cs in the different scenarios is desorbed by ambient and hydrothermal treatments with several low-molecular-weight organic acids (LMWOAs).

福島第一原子力発電所廃棄物分析の現況

駒 義和

原子力バックエンド研究(CD-ROM), 26(2), p.133 - 136, 2019/12

https://nuce.aesj.or.jp/jnuce/vol26/Jnuce-Vol26-2-p133-136.pdf

福島第一原子力発電所では廃炉工程の進展に伴い廃棄物が発生している。廃棄物管理技術の研究開発のために実施している分析の概要を報告する。

Development of calculation methodology for estimation of radionuclide composition in wastes generated at Fukushima Daiichi Nuclear Power Station

杉山 大輔*; 中林 亮*; 駒 義和; 高畠 容子; 塚本 政樹*

Journal of Nuclear Science and Technology, 56(9-10), p.881 - 890, 2019/09

https://doi.org/10.1080/00223131.2019.1595765

A calculation methodology for estimating the radionuclide composition in the wastes generated at the F1NPS has been developed by constructing a skeleton overview of the distribution of radionuclides considering the material balance in the system and calculation flowcharts of the transportation of radionuclides into the wastes. The wastes have a distinctive feature that their level of contamination includes considerable uncertainties. The developed method can explicitly specify the intrinsic uncertainties as a band to be included in the estimated radionuclide composition and can quantitatively describe the uncertainties by calibration using data on actual waste samples. Further studies to improve the quality of the calculation method, and acquiring a quantitative understanding of the spatial distribution of radionuclides inside the reactor building are suggested to be important steps toward reasonable and sustainable waste management as an integral part of the decommissioning.

Investigation of the contamination on the operation floor of unit 2 based on the radiochemical analysis data

高畠 容子; 駒 義和

Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR 2019) (Internet), 4 Pages, 2019/05

Radioactive nuclides contaminated F1NPS on the severe accident. It is necessary to discuss about radioactive waste processing and disposal. To investigate contamination process for the waste is important to establish methodologies for their management. Operation floor of unit 2 reactor building was highly contaminated, and boring cores of floor and ceiling were radiochemicaly analyzed. Comparing with distribution of Cs and dose rate indicated the difference of degree of contamination between the floor and ceiling. Contamination with Pu, Am and Cm was higher at the floor above the reactor shield plug, where is considered that the contaminated gas leaked. Degree of contamination of H, Co, Tc, Am and Cm were highest at the point of the opposite side of the blow out panel among several sampling point of the ceiling. From the activity ratio of U to U with samples, the origin of uranium was the damaged fuel.