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Thermodynamic analysis for solidification path of simulated ex-vessel corium

佐藤 拓未; 永江 勇二; 倉田 正輝; Quaini, A.*; Gu$'e$neau, C.*

CALPHAD; Computer Coupling of Phase Diagrams and Thermochemistry, 79, p.102481_1 - 102481_11, 2022/12

 被引用回数:0 パーセンタイル:0.01(Thermodynamics)

Investigation of the primary containment vessel inside the Fukushima Daiichi Nuclear Power Station showed that a significant amount of the molten corium reached the bottom of the pedestal region. The molten corium and concrete likely caused a complex interaction called Molten Corium Concrete Interaction. The solidification hysteresis of these ex-vessel debris significantly influences its properties. We performed a thermodynamic analysis using the TAF-ID database to infer the solidification path of U-Zr-Al-Ca-Si-O molten corium, which was chosen for a prototypic system of ex-vessel debris. The solidification path for the CaO-rich sim-corium showed that (i) melting as a single liquid phase above 2430 K, (ii) selective solidification of the oxide-rich corium mainly consisted of fuel materials, and (iii) solidification of the remaining materials as a silicate matrix. In contrast, the solidification path for the SiO$$_{2}$$-rich corium indicated that (i) formation of liquid miscibility gap above 2200 K between U-rich and Zr-rich oxidic melts, (ii) individual precipitation of solid phases in each liquid phase.


Mass-spectrometric determination of iodine-129 using O$$_{2}$$-CO$$_{2}$$ mixed-gas reaction in inductively coupled plasma tandem quadrupole mass spectrometry

松枝 誠; 青木 譲; 小荒井 一真; 寺島 元基; 高貝 慶隆*

Analytical Sciences, 38(11), p.1371 - 1376, 2022/11

 被引用回数:0 パーセンタイル:0(Chemistry, Analytical)

$$^{129}$$IのICP-MS分析はキセノン-129($$^{129}$$Xe)と過剰な安定同位体$$^{127}$$Iから発生する$$^{127}$$IH$$_{2}$$により妨害される。本研究では、ICP-MS/MS内のダイナミックリアクションセルにO$$_{2}$$+CO$$_{2}$$の混合ガスを導入することで、$$^{129}$$Iと干渉物質($$^{129}$$Xeと$$^{127}$$IH$$_{2}$$)を気相反応により分別した。その結果、(m/z129のバックグラウンドノイズ強度)/$$^{127}$$Iの比は4.6$$times$$10$$^{-10}$$となった。本法を用いて、100mg/L $$^{127}$$Iと10mBq/L $$^{129}$$Iを添加した雨水試料を分析し、9.8mBq $$^{129}$$Iの良好な定量値を得た。



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

月刊海洋, 54(11), p.558 - 561, 2022/11




墨田 岳大; 池田 篤史

Isotope News, (783), p.28 - 32, 2022/10

原著論文「High temperature reaction of multiple eutectic-component system; The Case of solid metallic Zr and molten SUS-B$$_{4}$$C」の解説記事


Estimation of the effect of GNSS positioning errors on the dose rate calculation concerning aerial radiation monitoring

森 愛理; 瀬口 栄作*; 普天間 章; 岩井 毅行*; 眞田 幸尚

Journal of Instrumentation (Internet), 17(10), p.P10015_1 - P10015_11, 2022/10


Four global navigation satellite system (GNSS) receivers were installed in a helicopter to reduce positioning errors in aerial radiation monitoring. The effect of positioning errors on the conversion of the counting rate of the detector to the ambient dose equivalent rate at the ground level was evaluated. The positioning results obtained by receiving the centimeter-class augmentation signal known as the L-band experiment, which the Quasi-Zenith Satellite System generates on an experimental basis for a limited time, were used as the reference values. A comparison between horizontal and vertical positioning errors among four receivers demonstrated that the vertical errors were larger than the horizontal errors. They did not differ among receivers, whereas the horizontal errors varied according to the characteristics of the receivers, particularly in mountainous areas; the errors tended to be larger when the terrain change at the measurement point was larger. The median effects of the vertical and horizontal errors on the calculated values of the radiation dose rate at the ground level were 3%-6% and 1%-5%, respectively, and the maximum possible effect of the positioning error was 20%-32%. The fact that the receiver with the highest number of available satellites had larger errors than the other receivers indicated that the elevation angles of satellites and the augmentation signals play an important role in improving the positioning accuracy when the number of available satellites reduces in mountainous areas. This study has provided insight into selecting a suitable GNSS receiver for surveying by vehicles such as helicopters, aircraft, and drones, which are required to perform 3D positioning in complex terrains.


放射線分布可視化に向けた計測技術; 福島第一原発事故後の放射線分布のイメージングとマッピング

鳥居 建男; 眞田 幸尚

計測技術, 50(11), p.23 - 28, 2022/10



Characterization of bremsstrahlung and $$gamma$$-rays of fuel debris

松村 太伊知; 奥村 啓介; 藤田 学*; 坂本 雅洋; 寺島 顕一; Riyana, E. S.

Radiation Physics and Chemistry, 199, p.110298_1 - 110298_8, 2022/10

 被引用回数:0 パーセンタイル:0.01(Chemistry, Physical)

The characterization of bremsstrahlung and $$gamma$$-rays from fuel debris differs from that of spent fuels evaluated to date, due to factors such as material composition and release of volatile fission products. In this work, in order to clarify the conditions under which the effect of bremsstrahlung compared to the total photons (bremsstrahlung and $$gamma$$-rays) in fuel debris is maximized, the average energies and dose rates from the energy spectra of bremsstrahlung and $$gamma$$-rays on the fuel debris surface were obtained using a Monte Carlo simulation. In the simulation, the average energies and dose rates were evaluated with consideration of the composition, size, fission product release, and retrieval time of the fuel debris. The simulation showed that the composition with the largest amount of change to the average total photons energy caused by bremsstrahlung was the molten fuel debris, and the composition with the maximum fraction of bremsstrahlung in the dose rate was the UO$$_{2}$$. The maximum value of the fraction of bremsstrahlung in the dose rate was evaluated to be about 17%. This work is expected to contribute to the prediction of the radiation characteristics of the fuel debris that will be retrieved from the Fukushima Daiichi Nuclear Power Station in the near future.


Cloudwater deposition process of radionuclides based on water droplets retrieved from pollen sensor data

兼保 直樹*; 忽那 周三*; 飯田 健次郎*; 眞田 幸尚; 田尻 拓也*

Environmental Science & Technology, 56(17), p.12036 - 12044, 2022/09

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



Microdosimetric modeling of relative biological effectiveness for skin reactions; Possible linkage between in vitro and in vivo data

佐藤 達彦; 松谷 悠佑; 浜田 信行*

International Journal of Radiation Oncology, Biology, Physics, 114(1), p.153 - 162, 2022/09

 被引用回数:1 パーセンタイル:75.2(Oncology)



Analysis of the activities of the website "Question and Answer about radiation in daily life" after the accident at the Fukushima Daiichi Nuclear Power Plant and some lessons learned from it; To pass on this experience to the future

河野 恭彦; 田中 雅人*; 田中 仁美*; 下 道國*; 鳥居 寛之*; 宇野 加津子*

Journal of Radiation Protection and Research, 47(3), p.167 - 179, 2022/09



Cesium-rich microparticles runoff during rainfall; A Case study in the Takase River

辰野 宇大*; 脇 嘉理*; 角間 海七渡*; 二瓶 直登*; 和田 敏裕*; 吉村 和也; 中西 貴宏; 大手 信人*

Radiation Protection Dosimetry, 198(13-15), p.1052 - 1057, 2022/09

 被引用回数:0 パーセンタイル:0.01(Environmental Sciences)

Cesium-rich microparticles (CsMPs) with high cesium-137 ($$^{137}$$Cs) concentrations were released and deposited in surface soil after the Fukushima Daiichi Nuclear Power Plant accident. Radioactive materials on the soil surface layer enter rivers owing to soil erosion during rainfall. In this study, we investigated CsMPs runoff through the river via soil erosion during rainfall in the Takase River watershed in Namie Town, Fukushima Prefecture, Japan. CsMPs were rarely detected in suspended solids (SS) in water samples collected during four rainfalls between February and July 2021. Furthermore, the proportion of $$^{137}$$Cs concentration derived from CsMPs to $$^{137}$$Cs concentration in the form of SS (particulate $$^{137}$$Cs) in the water was $$sim$$6% on average, which suggests that $$^{137}$$Cs runoff in the form of CsMPs from the forest to the Takase River was not large.


Performance evaluation of commercial scintillation cocktails for low-level tritium counting by high-capacity liquid scintillation counter

桑田 遥*; 田副 博文*; Kranrod, C.*; 藤原 健壮; 寺島 元基; 松枝 誠; 平尾 茂一*; 赤田 尚史*

Radiation Protection Dosimetry, 198(13-15), p.1014 - 1018, 2022/09

 被引用回数:0 パーセンタイル:0.01(Environmental Sciences)

Low-background liquid scintillation counter is one of the popular measuring instruments used to investigate tritium radioactivity in environmental media. These instruments require the liquid sample and organic solvent to be mixed for tritium measurement. In the European Union, the registration, evaluation, authorization and restriction of chemicals regulation was established to control the use of chemical substances of very high concern. It is important to find continuously available alternative reagents. In this paper, a performance evaluation was conducted using four scintillation cocktails according to Japanese conventional procedure; although one of them, Gold Star LT$$^{2}$$, contains nonylphenol ethoxylate, it will continue to be available for research and development. From the evaluation results it was confirmed that Gold Star LT$$^{2}$$ would be a satisfactory alternative scintillator, which is similar performance of Ultima Gold LLT.


BWR lower head penetration failure test focusing on eutectic melting

山下 拓哉; 佐藤 拓未; 間所 寛; 永江 勇二

Annals of Nuclear Energy, 173, p.109129_1 - 109129_15, 2022/08

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

Decommissioning work occasioned by the Fukushima Daiichi Nuclear Power Station (1F) accident of March 2011 is in progress. Severe accident (SA) analysis, testing, and internal investigation are being used to grasp the 1F internal state. A PWR system that refers to the TMI-2 accident is typical for SA codes and testing, on the other hand, a BWR system like 1F is uncommon, understanding the 1F internal state is challenging. The present study conducted the ELSA-1 test, a test that focused on damage from eutectic melting of the liquid metal pool and control rod drive (CRD), to elucidate the lower head (LH) failure mechanism in the 1F accident. The results demonstrated that depending on the condition of the melt pool formed in the lower plenum, a factor of LH boundary failure was due to eutectic melting. In addition, the state related to the CRD structure of 1F unit 2 were estimated.


Structure, stability, and actinide leaching of simulated nuclear fuel debris synthesized from UO$$_{2}$$, Zr, and stainless-steel

桐島 陽*; 秋山 大輔*; 熊谷 友多; 日下 良二; 中田 正美; 渡邉 雅之; 佐々木 隆之*; 佐藤 修彰*

Journal of Nuclear Materials, 567, p.153842_1 - 153842_15, 2022/08

 被引用回数:2 パーセンタイル:80.22(Materials Science, Multidisciplinary)

福島第一原子力発電所事故では、UO$$_{2}$$やZr,ステンレス鋼(SUS)の高温反応により燃料デブリが形成されたとみられる。この燃料デブリの化学構造や安定性を理解するため、UO$$_{2}$$-Zr-SUS系模擬デブリ試料の合成と物性評価を行い、より単純な組成の試料と比較した。模擬デブリ試料の合成では、不活性雰囲気(Ar)もしくは酸化雰囲気(Ar + 2% O$$_{2}$$)において1600$$^{circ}$$Cで1時間から12時間の加熱処理を行った。$$^{237}$$Npおよび$$^{241}$$Amをトレーサーとして添加し、浸漬試験ではUに加えてこれらの核種の溶出を測定した。試料の物性評価は、XRD, SEM-EDX,ラマン分光法およびメスバウアー分光法により行った。その結果、模擬デブリの主なU含有相は、加熱処理時の雰囲気に依らず、Zr(IV)およびFe(II)が固溶したUO$$_{2}$$相であることが分かった。模擬デブリ試料の純水もしくは海水への浸漬試験では、1年以上の浸漬の後も主な固相の結晶構造には変化が観測されず、化学的に安定であることが示された。さらに、U, Np, Amの溶出率はいずれも0.08%以下と、溶出は極めて限定的であることが明らかとなった。


Uranium dissolution and uranyl peroxide formation by immersion of simulated fuel debris in aqueous H$$_{2}$$O$$_{2}$$ solution

熊谷 友多; 日下 良二; 中田 正美; 渡邉 雅之; 秋山 大輔*; 桐島 陽*; 佐藤 修彰*; 佐々木 隆之*

Journal of Nuclear Science and Technology, 59(8), p.961 - 971, 2022/08

 被引用回数:1 パーセンタイル:0.01(Nuclear Science & Technology)



Identification and quantification of a $$^{60}$$Co radiation source under an intense $$^{137}$$Cs radiation field using an application-specific CeBr$$_3$$ spectrometer suited for use in intense radiation fields

冠城 雅晃; 島添 健次*; 加藤 昌弘*; 黒澤 忠弘*; 高橋 浩之*

Journal of Nuclear Science and Technology, 59(8), p.983 - 992, 2022/08

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

Passive $$gamma$$-ray spectroscopy is a useful technique for surveying the radioactive wastes and spent nuclear fuels under nuclear decommissioning. However, this method depends on material properties such as the activity, density, element, scale, and (especially) low-energy $$gamma$$ rays from $$^{235}$$U and $$^{239}$$Pu. The $$gamma$$-decay lines of $$^{134}$$Cs, $$^{137}$$Cs, $$^{60}$$Co, and $$^{154}$$Eu occur at greater energies (than those of $$^{235}$$U and $$^{239}$$Pu), and these nuclides provide significant information on spent nuclear fuel and radioactive wastes. A CeBr$$_{3}$$ spectrometer with a small-volume crystal has been previously developed for use in intense radiation measurements. We exposed the spectrometer to radiation dose rates of 0.025, 0.151, 0.342, 0.700, and 0.954 Sv/h under a standard $$^{137}$$Cs radiation field. A 6.38 MBq $$^{60}$$Co calibration source was placed in front of the detector surface. Identification of the full energy peak at 1173 keV was impossible at dose rates higher than 0.700 Sv/h. However, subtraction of the $$^{137}$$Cs radiation spectra from the $$gamma$$-ray spectra enabled the identification of the full energy peaks at 1173 and 1333 keV at dose rates of up to 0.954 Sv/h; the relative energy resolution at 1173 and 1333 keV was only slightly degraded at this dose rate.


Novel $$^{90}$$Sr analysis of environmental samples by ion-laser interaction mass spectrometry

本多 真紀; Martschini, M.*; Marchhart, O.*; Priller, A.*; Steier, P.*; Golser, R.*; 佐藤 哲也; 塚田 和明; 坂口 綾*

Analytical Methods, 14(28), p.2732 - 2738, 2022/07

 被引用回数:1 パーセンタイル:77.26(Chemistry, Analytical)



Using CO$$_{2}$$ Reactions to Achieve Mass-spectrometric Discrimination in Simultaneous Plutonium-isotope Speciation with Inductively Coupled Plasma-Tandem Mass Spectrometry

松枝 誠; 川上 智彦*; 小荒井 一真; 寺島 元基; 藤原 健壮; 飯島 和毅; 古川 真*; 高貝 慶隆*

Chemistry Letters, 51(7), p.678 - 682, 2022/07

 被引用回数:0 パーセンタイル:0(Chemistry, Multidisciplinary)

誘導結合プラズマ質量分析法(ICP-MS)を用いて、複雑な同位体干渉を受けることなく、様々なPu同位体を同時に同定するための新しい方法論を開発した。ICP-MS/MS及びDRC内でのCO$$_{2}$$ガス反応を用いて、Pu同位体分析($$^{239}$$Pu, $$^{240}$$Pu, $$^{241}$$Pu, $$^{242}$$Pu, $$^{244}$$Pu)におけるAm, Cm, Uなどの同重体干渉によるバックグラウンドノイズ強度を除去した。


Experimental study on the localization and estimation of radioactivity in concrete rubble using image reconstruction algorithms

高井 静霞; 行川 正和*; 島田 太郎; 武田 聖司

IEEE Transactions on Nuclear Science, 69(7), p.1789 - 1798, 2022/07

 被引用回数:0 パーセンタイル:0.01(Engineering, Electrical & Electronic)

福島第一原子力発電所内に保管されている大量の汚染コンクリートがれきの量を減らすためには、サイト内で低い放射能のがれきを再利用することが有用である。事故によるがれきの汚染の詳細は明らかでなくホットスポットを含む可能性がある。そのため、安全性を確保しながら再利用を進めるためには、コンクリートがれきの平均放射能だけでなく放射能濃度分布を効率的に評価する必要がある。しかし、厚いまたは密な物質の不均質な汚染の評価は、クリアランスモニタ等の従来の測定システムでは困難であった。本研究では、容器内に収納されたコンクリートの放射能濃度分布の評価に対する、画像再構成アルゴリズムの適用可能性を実験的に確認した。放射線は容器(50$$times$$50$$times$$40cm$$^{3}$$)の周囲に設置したプラスチックシンチレーションファイバーにより測定した。局所的なホットスポットは、汚染瓦礫の主要核種の一つである、$$^{137}$$Csの標準線源により模擬した。放射能濃度分布は容器内の100または50のボクセル(ボクセルのサイズ: (10cm)$$^{3}$$または10$$times$$10$$times$$20cm$$^{3}$$)に対して評価した。ボクセル数が100の場合容器内部のホットスポットは検知できなかったが、ボクセル数が50の場合容器内部・表面の両者のホットスポットを再現できた。画像再構成アルゴリズムのうち、ML-EM法により評価された濃度分布が最も精度が良く、全7つの実験ケースに対し70%の精度で平均濃度を評価できた。


Detection limit of electron spin resonance for Japanese deciduous tooth enamel and density separation method for enamel-dentine separation

岡 壽崇; 高橋 温*; 小荒井 一真; 木野 康志*; 関根 勉*; 清水 良央*; 千葉 美麗*; 鈴木 敏彦*; 小坂 健*; 佐々木 啓一*; et al.

Journal of Radiation Research (Internet), 63(4), p.609 - 614, 2022/07

 被引用回数:0 パーセンタイル:0.01(Biology)


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