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Leaching characteristics of $$^{137}$$Cs for forest floor affected by the Fukushima nuclear accident; A Litterbag experiment

佐久間 一幸; 吉村 和也; 中西 貴宏

Chemosphere, 264, p.128480_1 - 128480_9, 2021/02

福島県太田川上流域において、リターバックを用いて針葉樹および広葉樹からの溶存態$$^{137}$$Csの溶出特性を調査した。各樹種のリターを36個のリターバックにそれぞれ封入し、2017年6, 12月に各林床に設置した。2017年8, 12月および2018年3, 5, 8, 12月に、各林床から3つずつサンプルを採取し、純水に浸漬した。その後溶出水を、浸漬後20分, 140分, 1日後に採取した。溶存態$$^{137}$$Cs濃度を分析した。溶存態$$^{137}$$Cs溶出率については、針葉樹(0.13-2.0%)に比べ、広葉樹(0.81-6.6%)が高かった。溶出率に対して、先行降雨,先行温度及び積算温度を用いた重回帰モデルは、実測値をよく再現した(R$$^{2}$$=0.61-0.99)。


Performance of in situ gamma-ray spectrometry in the assessment of radioactive cesium deposition around the Fukushima Daiichi Nuclear Power Plant

Ji, Y.-Y.*; 越智 康太郎; Hong, S. B.*; 中間 茂雄; 眞田 幸尚; 三上 智

Radiation Physics and Chemistry, 179, p.109205_1 - 109205_11, 2021/02

福島第一原子力発電所周辺の異なる線量レベルのエリアで、様々なサーベイプラットフォームを用いin-situ $$gamma$$線スペクトロメトリーを実施した。地表における放射性セシウム沈着量を、高純度Ge半導体検出器とLaBr$$_{3}$$(Ce)検出器を用いて評価するために、福島第一原子力発電所周辺の6か所のサイト(うち2つは帰還困難区域)が選択された。2018年10月に行ったin-situ測定の結果、$$^{137}$$Csの沈着量は6つのサイトで30-3000kBq m$$^{-2}$$の範囲にあった。また、広範囲の代表的な深度分布を直接的に計算するin-situ測定手法を導入し、その結果が同じサイトで採取された土壌サンプルの結果をよく表現していることが分かった。


Solidification and re-melting mechanisms of SUS-B$$_{4}$$C eutectic mixture

墨田 岳大; 北垣 徹; 高野 公秀; 池田 篤史

Journal of Nuclear Materials, 543, p.152527_1 - 152527_15, 2021/01

Fundamental understanding of the high-temperature interaction between stainless steel (SUS) and B$$_{4}$$C is indispensable for estimating and characterizing the fuel debris generated during severe accidents of boiling water reactors (BWR), such as Fukushima Dai-ichi Nuclear Power Station (FDNPS, also referred to as "1F") in Japan. This study aims at systematically characterizing the solidified products of molten SUS-B$$_{4}$$C mixtures by powder X-ray diffraction (PXRD), scanning electron microscopy- energy dispersive X-ray spectroscopy (SEM-EDS), and thermogravimetry-differential thermal analysis (TG-DTA) with a range of the B$$_{4}$$C content relevant to the fuel debris composition expected at 1F, in order to elucidate the solidification and re-melting mechanisms. The results indicated that $$gamma$$-Fe and (Cr,Fe)$$_{2}$$B are the major solidified phases when the B$$_{4}$$C content is below 3 mass%, while (Cr,Fe)$$_{23}$$(C,B)$$_{6}$$ is formed as an additional third phase when the B$$_{4}$$C content exceeds 3 mass%. The solidification of molten SUS-B$$_{4}$$C mixture and re-melting of solidified SUS-B$$_{4}$$C melt are eutectic, which is mainly controlled by the pseudo-binary Fe-B system that is influenced by the C and Cr content and additional minor components such as Mo.


Distribution map of natural gamma-ray dose rates for studies of the additional exposure dose after the Fukushima Dai-ichi Nuclear Power Station accident

眞田 幸尚; 吉村 和也; 卜部 嘉*; 岩井 毅行*; Katengeza, E. W.*

Journal of Environmental Radioactivity, 223-224, p.106397_1 - 106397_9, 2020/11

The information on the absorbed dose rate which is derived from natural radionuclides needs to evaluate additional exposure dose around Fukushima Daiichi Nuclear Power Station. However, there are not enough position resolution and precision for data for this evaluation. In this study, we created the map of the absorbed dose rate which is derived from natural radionuclides based on several airborne radiation monitoring data. The created map was made sure to have sufficient reliable accuracy by comparing with the many in-situ measurement on the ground. These data were applied to discriminate the absorbed dose rate of background from an actual periodic dose rate survey results as an application study. Evaluation results for the distribution of absorbed dose rate of background are expected to contribute to the summarization of international studies of the FDNPS accident.


Measurements of the doses of eye lens for the workers of Fukushima Daiichi Nuclear Power Plant

横山 須美*; 江崎 巌*; 立崎 英夫*; 立木 秀一*; 平尾 一茂*; 青木 克憲; 谷村 嘉彦; 星 勝也; 吉富 寛; 辻村 憲雄

Radiation Measurements, 138, p.106399_1 - 106399_5, 2020/11

In Japan, the possibility to change the current dose limit of the lens of the eye for the radiation workers working in the planned exposure situation (normal controlled situations) to a new ICRP dose limit was discussed. It was further discussed how to appropriately monitor and manage the equivalent dose of the eye lenses for these workers exposed to radiation at their workplaces, such as nuclear and medical facilities. Among the workers exposed to a high-dose radiation at the water storage flange tank deconstructed $$^{90}$$Sr/$$^{90}$$Y dominant areas and the nuclear reactor buildings (high dose gamma-ray) of the Fukushima Daiichi Nuclear Power Plant (1F-NPP), H$$_{p}$$(10), H$$_{p}$$(3), and H$$_{p}$$(0.07) at the head and the chest (or the upper arm) were estimated by passive personal dosimeters using thermoluminescence dosimeters (TLDs) and radio photoluminescence glass dosimeters (RPLGDs). The relationship between H$$_{p}$$(10), H$$_{p}$$(3), and H$$_{p}$$(0.07) along with the effects of the sites of wearing dosimeters on the head inside a full-face mask and the chest (or upper arm) were discussed.


Reservoir sediments as a long-term source of dissolved radiocaesium in water system; a mass balance case study of an artificial reservoir in Fukushima, Japan

舟木 泰智; 佐久間 一幸; 中西 貴宏; 吉村 和也; Katengeza, E. W.*

Science of the Total Environment, 743, p.140668_1 - 140668_9, 2020/11

This study provides new insights regarding to the long-term temporal change and the mass balance of dissolved $$^{137}$$Cs in an artificial reservoir affected by the Fukushima Dai-ichi Nuclear Power Plant accident. Time-series water samples were collected from 2014 to 2019 for $$^{137}$$Cs concentration measurements in and around Ogaki Dam Reservoir in which the catchment has a high $$^{137}$$Cs inventory. We revealed that the arithmetic mean of dissolved $$^{137}$$Cs concentration was significantly higher in the output water than in the main input water, and the effective ecological half-live of dissolved $$^{137}$$Cs of the output water was longer than that in the main input water. Remarkably, it is considered that the output dissolved $$^{137}$$Cs was significantly larger than the total input dissolved $$^{137}$$Cs. Reservoir sediments containing high $$^{137}$$Cs activity may become even more important in the future as sources of bioavailable dissolved $$^{137}$$Cs.



御園生 敏治; 鶴田 忠彦; 中西 貴宏; 眞田 幸尚; 尻引 武彦; 宮本 賢治*; 卜部 嘉*

JAEA-Research 2020-008, 166 Pages, 2020/10




Status of study of long-term assessment of transport of radioactive contaminants in the environment of Fukushima (FY2018) (Translated document)

長尾 郁弥; 新里 忠史; 佐々木 祥人; 伊藤 聡美; 渡辺 貴善; 土肥 輝美; 中西 貴宏; 佐久間 一幸; 萩原 大樹; 舟木 泰智; et al.

JAEA-Research 2020-007, 249 Pages, 2020/10




A Model intercomparison of atmospheric $$^{137}$$Cs concentrations from the Fukushima Daiichi Nuclear Power Plant accident, phase III; Simulation with an identical source term and meteorological field at 1-km resolution

佐藤 陽祐*; 関山 剛*; Fang, S.*; 梶野 瑞王*; Qu$'e$rel, A.*; Qu$'e$lo, D.*; 近藤 裕昭*; 寺田 宏明; 門脇 正尚; 滝川 雅之*; et al.

Atmospheric Environment; X (Internet), 7, p.100086_1 - 100086_12, 2020/10



Construction of virtual reality system for radiation working environment reproduced by gamma-ray imagers combined with SLAM technologies

佐藤 優樹; 峯本 浩二郎*; 根本 誠*; 鳥居 建男

Nuclear Instruments and Methods in Physics Research A, 976, p.164286_1 - 164286_6, 2020/10

 被引用回数:0 パーセンタイル:100(Instruments & Instrumentation)

The Fukushima Daiichi Nuclear Power Station (FDNPS), operated by Tokyo Electric Power Company Holdings, Inc., experienced a meltdown as a result of a large tsunami caused by the Great East Japan Earthquake on March 11, 2011. At that time, it was necessary to understand the aspects of the decommissioning working environment inside the FDNPS, such as establishing how the radioactive substances were distributed across the site, for work to be done efficiently without exposure to large amounts of radiation. Therefore, virtual reality (VR) emerged as a solution. There have been previous reports done on a technique for visualizing the distribution of radioactive substances in three dimensions utilizing a freely moving gamma-ray imager combined with simultaneous localization and mapping (SLAM) technology. In this paper, we introduce imaging technologies for the acquisition of image data from radioactive substances and three-dimensional (3D) structural models of the working environment, using a freely moving gamma-ray imager combined with SLAM technology. For this research, we also constructed a VR system and displayed the 3D data in a VR space, which enables users to experience the actual working environment without radiation exposure. In creating the VR system, any user can implement this method by donning an inexpensive head-mounted display apparatus and using a free, or low-cost, application software.


Development of side thruster system for ASV

加藤 哲*; 川村 大和*; 田原 淳一郎*; 馬場 尚一郎*; 眞田 幸尚

Proceedings of the 30th (2020) International Ocean and Polar Engineering Conference (ISOPE 2020) (USB Flash Drive), p.1255 - 1260, 2020/10

This paper describes the development of side thruster system can keep the heading direction for ASV (Autonomous Surface Vehicle). At present, JAMSTEC, JAEA, and TUMSAT are jointly working on the investigation of radioactivity in mud deposited in estuaries in Fukushima Prefecture, Japan. The main objective of this project is unmanned mud collect using the ASV. We developed and controlled the side thruster system for applying ASV to mud collecting operation. As the result of the bollard test, turn and parallel movement test, we confirmed that it can maintain the heading direction for the ASV.




JAEA-Review 2020-016, 67 Pages, 2020/09




Development and validation of the eutectic reaction model in JUPITER code

Chai, P.; 山下 晋; 吉田 啓之

Annals of Nuclear Energy, 145, p.107606_1 - 107606_13, 2020/09

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)



Radiocesium distribution in the sediments of the Odaka River estuary, Fukushima, Japan

萩原 大樹; 中西 貴宏; 小西 博巳*; 鶴田 忠彦; 御園生 敏治; 藤原 健壮; 北村 哲浩

Journal of Environmental Radioactivity, 220-221, p.106294_1 - 106294_9, 2020/09

 被引用回数:0 パーセンタイル:100(Environmental Sciences)

Radiocesium that originated from the Fukushima Daiichi Nuclear Power Plant accident was deposited on the ground surface and has been transported via fluvial discharge, primarily in the form of particulates, to downstream areas and eventually to the ocean. During transportation, some of the radiocesium accumulated on the riverbed. In this study, we quantified the radiocesium deposition on the riverbed in the Odaka River estuary and investigated the radiocesium sedimentation process of the river bottom. Our results show that the radiocesium inventory in the seawater intrusion area is larger than those in the freshwater and marine parts of the estuary. Moreover, the particle-size distribution in the seawater intrusion area shows a high proportion of silt and clay particles compared with the distribution in other areas. The increased radiocesium inventory in this area is attributed to the sedimentation of fine particles caused by hydrodynamic factors (negligible velocity of the river flow) rather than flocculation factor by salinity variation.


Investigation of high-temperature chemical interaction of calcium silicate insulation and cesium hydroxide

Rizaal, M.; 中島 邦久; 斉藤 拓巳*; 逢坂 正彦; 岡本 孝司*

Journal of Nuclear Science and Technology, 57(9), p.1062 - 1073, 2020/09

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)



Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF Project

Pellegrini, M.*; Herranz, L.*; Sonnenkalb, M.*; Lind, T.*; 丸山 結; Gauntt, R.*; Bixler, N.*; Morreale, A.*; Dolganov, K.*; Sevon, T.*; et al.

Nuclear Technology, 206(9), p.1449 - 1463, 2020/09

 被引用回数:1 パーセンタイル:19.53(Nuclear Science & Technology)

The OECD/NEA Benchmark Study at the Accident of Fukushima Daiichi Nuclear Power Station (BSAF) project, which started in 2012 and continued until 2018, was one of the earliest responses to the accident at Fukushima Daiichi. The project, divided into two phases addressed the investigation of the accident at Unit 1, 2 and 3 by Severe Accident (SA) codes until 500 h focusing on thermal-hydraulics, core relocation, Molten Corium Concrete Interaction (MCCI) and fission products release and transport. The objectives of BSAF were to make up plausible scenarios based primarily on SA forensic analysis, support the decommissioning and inform SA codes modeling. The analysis and comparison among the institutes have brought up vital insights regarding the accident progression identifying periods of core meltdown and relocation, Reactor Pressure Vessel (RPV) and Primary Containment Vessel (PCV) leakage/failure through the comparison of pressure, water level and CAMS signatures. The combination of code results and inspections (muon radiography, PCV inspection) has provided a picture of the current status of the debris distribution and plant status. All units present a large relocation of core materials and all of them present ex-vessel debris with Unit 1 and Unit 3 showing evidences of undergoing MCCI. Uncertainties have been identified in particular on the time and magnitude of events such as corium relocation in RPV and into cavity floor, RPV and PCV rupture events. Main uncertainties resulting from the project are the large and continuous MCCI progression predicted by basically all the SA codes and the leak pathways from RPV to PCV and PCV to reactor building and environment. The BSAF project represents a pioneering exercise which has set the basis and provided lessons learned not only for code improvement but also for the development of new related projects to investigate in detail further aspects of the Fukushima Daiichi accident.


Observation of morphological abnormalities in silkworm pupae after feeding $$^{137}$$CsCl-supplemented diet to evaluate the effects of low dose-rate exposure

田中 草太; 木野内 忠稔*; 藤井 告*; 今中 哲二*; 高橋 知之*; 福谷 哲*; 牧 大介*; 納冨 昭弘*; 高橋 千太郎*

Scientific Reports (Internet), 10, p.16055_1 - 16055_7, 2020/09




大谷 恭平; 塚田 隆; 上野 文義; 加藤 千明

材料と環境, 69(9), p.246 - 252, 2020/09




阿部 智久; 荻谷 尚司*; 柴田 和哉*; 塙 竜明*; 眞田 幸尚

JAEA-Data/Code 2020-004, 280 Pages, 2020/08




Seven-year temporal variation of caesium-137 discharge inventory from the port of Fukushima Daiichi Nuclear Power Plant; Continuous monthly estimation of caesium-137 discharge in the period from April 2011 to June 2018

町田 昌彦; 山田 進; 岩田 亜矢子; 乙坂 重嘉; 小林 卓也; 渡辺 将久; 船坂 英之; 森田 貴己*

Journal of Nuclear Science and Technology, 57(8), p.939 - 950, 2020/08

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)


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