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Post-test analyses of the CMMR-4 test

山下 拓哉; 間所 寛; 佐藤 一憲

Journal of Nuclear Engineering and Radiation Science, 8(2), p.021701_1 - 021701_13, 2022/04

Understanding the final distribution of core materials and their characteristics is important for decommissioning the Fukushima Daiichi Nuclear Power Station (1F). Such characteristics depend on the accident progression in each unit. However, boiling water reactor accident progression involves great uncertainty. This uncertainty, which was clarified by MAAP-MELCOR Crosswalk, cannot be resolved with existing knowledge and was thus addressed in this work through core material melting and relocation (CMMR) tests. For the test bundle, ZrO$$_{2}$$ pellets were installed instead of UO$$_{2}$$ pellets. A plasma heating system was used for the tests. In the CMMR-4 test, useful information was obtained on the core state just before slumping. The presence of macroscopic gas permeability of the core approaching ceramic fuel melting was confirmed, and the fuel columns remained standing, suggesting that the collapse of fuel columns, which is likely in the reactor condition, would not allow effective relocation of the hottest fuel away from the bottom of the core. This information will help us comprehend core degradation in boiling water reactors, similar to those in 1F. In addition, useful information on abrasive water suspension jet (AWSJ) cutting for debris-containing boride was obtained in the process of dismantling the test bundle. When the mixing debris that contains oxide, metal, and boride material is cut, AWSJ may be repelled by the boride in the debris, which may cut unexpected parts, thus generating a large amount of waste in cutting the boride part in the targeted debris. This information will help the decommissioning of 1F.


Joint environmental radiation survey by JAEA and KAERI around the Fukushima Daiichi Nuclear Power Plant; Performance of mobile gamma-ray spectrometry using backpack and carborne survey platforms

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

Health Physics, 121(6), p.613 - 620, 2021/12



Evaluation of the dissolution behavior of zircon using high-resolution phase-shift interferometry microscope

北垣 徹

Journal of Nuclear Materials, 557, p.153254_1 - 153254_8, 2021/12


The dissolution behavior of the zircon mineral in ultrapure water, 1 M HCl (aq), and 1 M NaOH (aq), under room temperature and nearly atmospheric pressure was evaluated by in situ measurement of the change in the surface height. A high-resolution phase-shift interferometry microscope (HR-PSI) was employed to evaluate the velocity of the change in the surface height of zircon in different solutions, and the application of this method in evaluating the dissolution behaviors of nuclear materials was examined. As a result, the velocity of surface change and the precipitation behaviors of zircon was successfully evaluated using HR-PSI. This relatively quick method would be useful for evaluating the detailed surface change behaviors of nuclear materials, such as fuel debris, ceramic waste forms and UO$$_{2}$$, during the reaction with various solutions, since it minimises radiation exposure times and also the amount of radioactive waste generation during measurement.


High temperature reaction of multiple eutectic-component system; The Case of solid metallic Zr and molten stainless steel-B$$_{4}$$C

墨田 岳大; 小畠 雅明; 高野 公秀; 池田 篤史

Materialia, 20, p.101197_1 - 101197_11, 2021/12

The eutectic melting, one of the fundamental phenomena in high temperature reactions involving liquid phases, is a primitive but important subject for both scientific and industrial fields associated with metallurgy. The present study aims at revealing the formation and reaction mechanisms of the multiple eutectic-component system consisting of solid metallic Zr and molten stainless steel- boron carbide (SS-B$$_{4}$$C) by combining multiple analytical methods (i.e. powder X-ray diffraction (PXRD), scanning electron microscopy- energy dispersive X-ray spectroscopy (SEM-EDS), and dynamic secondary ion mass spectrometry (D-SIMS)) with thermodynamical consideration. The results indicate that the solidified Zr-SS-B$$_{4}$$C mixture is composed of major phases of (Fe,Cr)$$_{2}$$Zr, (Fe,Cr,Ni)$$_{2}$$Zr, (Ni,Fe)Zr$$_{2}$$, ZrB$$_{2}$$, and a minor phase of ZrC. The results also reveal that the eutectic melting between solid metallic Zr and molten SS-B$$_{4}$$C can be described as the combination of diffusion kinetics and thermodynamic stability. That is, the initial formation of ZrC and ZrB$$_{2}$$ layers at the reaction interface significantly retards the diffusion of other SS-B$$_{4}$$C components (i.e. Cr, Fe, and Ni) into solid metallic Zr.


原子力災害対応用ロボットの性能試験法; 貫通孔を介した展開後の走破性能試験(JAEA-TM-0004、JAEA-TM-0005)

川端 邦明; 山田 大地; 阿部 浩之*

JAEA-Technology 2021-021, 30 Pages, 2021/11





普天間 章; 眞田 幸尚; 佐々木 美雪; 川崎 義晴*; 岩井 毅行*; 平賀 祥吾*; 佐藤 一彦*; 萩野谷 仁*; 松永 祐樹*; 菊池 陽*; et al.

JAEA-Technology 2021-020, 138 Pages, 2021/11




動作不能からの復帰を可能とする多連結移動ロボットの半自律遠隔操作技術の確立(委託研究); 令和2年度英知を結集した原子力科学技術・人材育成推進事業

廃炉環境国際共同研究センター; 電気通信大学*

JAEA-Review 2021-025, 33 Pages, 2021/11




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

JAEA-Research 2021-004, 214 Pages, 2021/11




Spatial variations in radiocesium deposition and litter-soil distribution in a mountainous forest catchment affected by the Fukushima nuclear accident

安藤 麻里子; 小嵐 淳; 都築 克紀; 竹内 絵里奈; 西村 周作; 武藤 琴美*; 松永 武*

Journal of Environmental Radioactivity, 238-239, p.106725_1 - 106725_8, 2021/11



Dynamics of radiocaesium within forests in Fukushima; Results and analysis of a model inter-comparison

橋本 昌司*; 田中 拓*; 小松 雅史*; Gonze, M.-A.*; 坂下 渉*; 操上 広志; 仁科 一哉*; 太田 雅和; 大橋 伸太*; Calmon, P.*; et al.

Journal of Environmental Radioactivity, 238-239, p.106721_1 - 106721_10, 2021/11

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



A Modeling study on the oceanic dispersion and sedimentation of radionuclides off the coast of Fukushima

上平 雄基; 内山 雄介*; 川村 英之; 小林 卓也; 乙坂 重嘉*

Journal of Environmental Radioactivity, 238-239, p.106724_1 - 106724_16, 2021/11

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



Determination of $$^{135}$$Cs/$$^{137}$$Cs isotopic ratio in soil collected near Fukushima Daiichi Nuclear Power Station through mass spectrometry

島田 亜佐子; 塚原 剛彦*; 野村 雅夫*; Kim, M. S.*; 島田 太郎; 武田 聖司; 山口 徹治

Journal of Nuclear Science and Technology, 58(11), p.1184 - 1194, 2021/11

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

土壌中の主要元素や質量分析における妨害元素を含む多元素混合溶液を用いて土壌中のCsを分離精製するためのCalix[4]arene-bis(t-octylbenzo-crown-6)(BOBCalixC6)の1-オクタノール溶液による溶媒抽出法を最適化した。一部のKやMo, Sn, SbがCsと共に有機相に抽出されたが、0.5M硝酸により逆抽出された。一方、抽出されたCsは0.5M硝酸ではほとんど逆抽出されないため、分離が改善された。抽出されたCsの回収は温度を323Kまで上げ、有機相を3倍量の1-ドデカノールで希釈することで達成された。開発した手法を40gの土壌を溶解した硝酸溶液に対して適用し、分離精製・濃縮後の溶液中には土壌の主要元素が合計で10$$mu$$g/ml、妨害元素はng/ml以下しか含まれないことを確認した。さらに、この手法を用いて福島第一原子力発電所(FDNPS)周辺で採取された土壌中のCsを分離し、$$^{135}$$Cs/$$^{137}$$Cs同位体比を表面電離型質量分析計(TIMS)とトリプル四重極質量分析計(ICP-QQQ)により分析した。TIMSにより1桁ほど高い精度が得られたが、アバンダンス感度はICP-QQQの方が高かった。FDNPSの北西側の試料に対してわずかに高い$$^{135}$$Cs/$$^{137}$$Cs同位体比が観測されたが、それ以外の地点では誤差の範囲で同じ同位体比が得られた。この結果は報告されている$$^{134}$$Cs/$$^{137}$$Csの放射能比の分布と一致しており、$$^{135}$$Cs/$$^{137}$$Cs同位体比が放射性セシウムの起源を特定できる可能性を示している。


Isotope shift and hyperfine structure measurements on triple resonance excitation to the autoionizing Rydberg state of atomic strontium

岩田 圭弘; 宮部 昌文; 赤岡 克昭; 若井田 育夫

Journal of Quantitative Spectroscopy & Radiative Transfer, 275, p.107882_1 - 107882_9, 2021/11




Analysis of Fukushima-Daiichi Nuclear Power Plant Unit 3 pressure data and obtained insights on accident progression behavior

佐藤 一憲

Nuclear Engineering and Design, 383, p.111426_1 - 111426_19, 2021/11

The D/W (Drywell) and S/C (Suppression Chamber) pressure data of Fukushima-Daiichi Nuclear Power Plant Unit 3 was analyzed in depth. This analysis provided valuable information related to the accident progression behavior on one hand, and gave a hint for understanding of the debris-to-coolant heat transfer when fuel debris relocated to the pedestal on the other hand. In this unit, the D/W and S/C pressure increased and decreased cyclically with a relationship, which seems to have been dependent on the composition of vapor and non-condensable gases in the S/C cover gas region. Based on this characteristic, the vapor pressure in the S/C cover gas region was evaluated for two pressure decrease cycles during and after the expected debris relocation to the pedestal respectively. This evaluation allowed an understanding that the S/C vapor pressure increased due to the heat transfer from the debris relocated to the pedestal.



眞田 幸尚

放計協ニュース, (68), p.2 - 6, 2021/10

東京電力ホールディングス福島第一原子力発電所事故(以下、発電所事故)の影響により、周辺環境中は放射性セシウム等の放射性物質により汚染された。原子力発電所事故後、適用された線や面的な放射線測定技術の一つとしてプラスチックシンチレーションファイバ が挙げられる。本稿では、一連の開発から実機投入までの開発の経緯についてまとめる。


Impact of extreme typhoon events on the fluvial discharge of particulate radiocesium in Fukushima Prefecture

中西 貴宏; 大山 卓也; 萩原 大樹; 佐久間 一幸

Journal of Coastal Research, 114(SI), p.310 - 314, 2021/10



Dynamics of radioactive cesium in coastal area linked with river discharge

御園生 敏治; 鶴田 忠彦; 尻引 武彦; 中西 貴宏; 長尾 誠也*; 落合 伸也*; 眞田 幸尚

Journal of Coastal Research, 114(SI), p.315 - 319, 2021/10



Validity of the source term for the Fukushima Dai-ichi Nuclear Power Station accident estimated using local-scale atmospheric dispersion simulations to reproduce the large-scale atmospheric dispersion of $$^{137}$$Cs

門脇 正尚; 古野 朗子; 永井 晴康; 川村 英之; 寺田 宏明; 都築 克紀; El-Asaad. H.

Journal of Environmental Radioactivity, 237, p.106704_1 - 106704_18, 2021/10

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



Simulation study of a shield-free directional gamma-ray detector using Small-Angle Compton Scattering

北山 佳治; 寺阪 祐太; 佐藤 優樹; 鳥居 建男

Journal of Nuclear Engineering and Radiation Science, 7(4), p.042006_1 - 042006_7, 2021/10

Gamma-ray imaging is a technique to visualize the spatial distribution of radioactive materials. Recently, gamma-ray imaging has been applied to research on decommissioning of the Fukushima Daiichi Nuclear Power Station (FDNPS) accident and environmental restoration, and active research has been conducted. This study is the elemental technology study of the new gamma-ray imager GISAS (Gamma-ray Imager using Small-Angle Scattering), which is assumed to be applied to the decommissioning site of FDNPS. GISAS consists of a set of directional gamma-ray detectors that do not require a shield. In this study, we investigated the feasibility of the shield free directional gamma-ray detector by simulation. The simulation result suggests that by measuring several keV of scattered electron energy by scatterer detector, gamma rays with ultra-small angle scattering could be selected. By using Compton scattering kinematics, a shield-free detector with directivity of about 10$$^{circ}$$ could be feasible. By arranging the directional gamma-ray detectors in an array, it is expected to realize the GISAS, which is small, light, and capable of quantitative measurement.


Feasibility study of the one-dimensional radiation distribution sensing method using an optical fiber sensor based on wavelength spectrum unfolding

寺阪 祐太; 渡辺 賢一*; 瓜谷 章*; 山崎 淳*; 佐藤 優樹; 鳥居 建男; 若井田 育夫

Journal of Nuclear Engineering and Radiation Science, 7(4), p.042002_1 - 042002_7, 2021/10


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