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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

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.


Quantitative X-ray diffraction analysis of solute-enriched stacking faults in $$hcp$$-Mg alloys based on peak asymmetry analysis

江草 大佑*; 眞鍋 怜*; 川崎 卓郎; Harjo, S.; 佐藤 成男*; 阿部 英司*

Materials Today Communications (Internet), 31, p.103344_1 - 103344_6, 2022/06

Based on X-ray diffraction analysis we attempt to quantify a volume fraction of stacking faults, which are essentially enriched by solute elements (solute-enriched stacking faults; SESFs) in Mg-Zn-Gd alloys with a hexagonal-close-packed ($$hcp$$) structure. We find that the SESFs with a local face-center-cubic stacking mostly occurs as a limited thickness less than several unit-cell dimensions, causing anisotropic broadening of the diffraction peaks including $$c*$$-component. By dealing the SESFs as intergrowth-like precipitates, we have successfully decomposed the asymmetric peak profile into the $$hcp$$-matrix and the SESF peaks, by which the relevant volume fractions can be estimated in a highly quantitative manner.


Fully chelating N$$_{3}$$O$$_{2}$$-pentadentate planar ligands designed for the strongest and selective capture of uranium from seawater

水町 匠*; 佐藤 みなみ*; 金子 政志; 竹山 知志*; 津島 悟*; 鷹尾 康一朗*

Inorganic Chemistry, 61(16), p.6175 - 6181, 2022/04



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.


Breakdown of linear spin-wave theory and existence of spinon bound states in the frustrated kagome-lattice antiferromagnet

Mattan, K.*; 小野 俊雄*; 河村 聖子; 中島 健次; 南部 雄亮*; 佐藤 卓*

Physical Review B, 105(13), p.134403_1 - 134403_8, 2022/04



LIVE-J1 experiment on debris melting behavior toward understanding late in-vessel accident progression of the Fukushima Daiichi Nuclear Power Station

間所 寛; 山下 拓哉; 佐藤 一憲; Gaus-Liu, X.*; Cron, T.*; Fluhrer, B.*; St$"a$ngle, R.*; Wenz, T.*; Vervoortz, M.*; 溝上 伸也

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 16 Pages, 2022/03

Debris and molten pool behavior in the reactor pressure vessel (RPV) lower plenum is a key factor to determine its failure mode, which affects the initial condition of ex-vessel accident progression and the debris characteristics. These are necessary information to accomplish safe decommissioning of the Fukushima Daiichi Nuclear Power Station. After dryout of the solidified debris in the lower plenum, metallic debris is expected to melt prior to the oxide debris due to its lower melting temperature. The lower head failure is likely be originated by the local thermal load attack of a melting debris bed. Numerous experiments have been conducted in the past decades to investigate the homogeneous molten pool behavior with external cooling. However, few experiments address the transient heat transfer of solid-liquid mixture without external cooling. In order to enrich the experimental database of melting and heat transfer process of debris bed consisted of materials with different melting temperatures, LIVE-J1 experiment was conducted using ceramic and nitrate particles as high melting and low melting temperature simulant materials, respectively. The test results showed that debris height decreased gradually as the nitrate particles melt, and molten zone and thermal load on vessel wall were shifted from bottom upwards. Both conductive and convective heat transfer could take place in a solid-liquid mixture pool. These results can support the information from the internal investigations of the primary containment vessel and deepen the understanding of the accident progression.


Space weather benchmarks on Japanese society

石井 守*; 塩田 大幸*; 垰 千尋*; 海老原 祐輔*; 藤原 均*; 石井 貴子*; 一本 潔*; 片岡 龍峰*; 古賀 清一*; 久保 勇樹*; et al.

Earth, Planets and Space (Internet), 73(1), p.108_1 - 108_20, 2021/12

 被引用回数:1 パーセンタイル:72.01(Geosciences, Multidisciplinary)




森下 一喜; 佐藤 匠; 大西 貴士; 関 崇行*; 関根 伸一*; 興津 裕一*

JAEA-Technology 2021-024, 27 Pages, 2021/10




Implementation of simplified stochastic microdosimetric kinetic models into PHITS for application to radiation treatment planning

佐藤 達彦; 橋本 慎太郎; 稲庭 拓*; 高田 健太*; 熊田 博明*

International Journal of Radiation Biology, 97(10), p.1450 - 1460, 2021/10

 被引用回数:0 パーセンタイル:0.01(Biology)



Design for detecting recycling muon after muon-catalyzed fusion reaction in solid hydrogen isotope target

奥津 賢一*; 山下 琢磨*; 木野 康志*; 中島 良太*; 宮下 湖南*; 安田 和弘*; 岡田 信二*; 佐藤 元泰*; 岡 壽崇; 河村 成肇*; et al.

Fusion Engineering and Design, 170, p.112712_1 - 112712_4, 2021/09



Technical Note: Validation of a material assignment method for a retrospective study of carbon-ion radiotherapy using Monte Carlo simulation

Chang, W.*; 古場 裕介*; 古田 琢哉; 米内 俊祐*; 橋本 慎太郎; 松本 真之介*; 佐藤 達彦

Journal of Radiation Research (Internet), 62(5), p.846 - 855, 2021/09



Medical application of Particle and Heavy Ion Transport code System PHITS

古田 琢哉; 佐藤 達彦

Radiological Physics and Technology, 14(3), p.215 - 225, 2021/09



Time evolution calculation of muon catalysed fusion; Emission of recycling muons from a two-layer hydrogen film

山下 琢磨*; 奥津 賢一*; 木野 康志*; 中島 良太*; 宮下 湖南*; 安田 和弘*; 岡田 信二*; 佐藤 元泰*; 岡 壽崇; 河村 成肇*; et al.

Fusion Engineering and Design, 169, p.112580_1 - 112580_5, 2021/08



Distribution of studtite and metastudtite generated on the surface of U$$_{3}$$O$$_{8}$$; Application of Raman imaging technique to uranium compound

日下 良二; 熊谷 友多; 蓬田 匠; 高野 公秀; 渡邉 雅之; 佐々木 隆之*; 秋山 大輔*; 佐藤 修彰*; 桐島 陽*

Journal of Nuclear Science and Technology, 58(6), p.629 - 634, 2021/06

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

Studtite and metastudtite are uranyl peroxides formed on nuclear fuel in water through the reaction with H$$_{2}$$O$$_{2}$$ produced by the radiolysis of water. However, it is unclear how the two types of uranyl peroxides are generated and distributed on the surface of nuclear fuel. Here, we used Raman imaging technique to exemplify distribution data of the two uranyl peroxides formed on the surface of a U$$_{3}$$O$$_{8}$$ pellet through immersion in a H$$_{2}$$O$$_{2}$$ aqueous solution. As a result, we observed that studtite and metastudtite are heterogeneously distributed on the U$$_{3}$$O$$_{8}$$ surface. No clear correlation between the distributions of studtite and metastudtite was observed, suggesting that the two uranyl peroxides are independently generated on the surface of U$$_{3}$$O$$_{8}$$. We anticipate that this Raman imaging technique could reveal how these uranyl peroxides are generated and distributed on the surface of the nuclear fuel debris in the Fukushima-Daiichi Nuclear Power Plants.


Experimental evaluation of Sr and Ba distribution in ex-vessel debris under a temperature gradient

須藤 彩子; 佐藤 拓未; 多木 寛; 高野 公秀

Journal of Nuclear Science and Technology, 58(4), p.473 - 481, 2021/04

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

ex-vessel debrisから冷却水へのSrおよびBa溶出挙動の把握は、福島第一原子力発電所における二次的ソースターム評価のため重要である。このメカニズムを理解するためには、ex-vessel debris中のSrおよびBaの分布状態に関する知見が必要となる。模擬コリウムとコンクリートの反応試験の結果、凝固したサンプル中に二層構造((A)上部表面領域のケイ酸ガラス相(((Si,Al,Ca,Fe,Zr,Cr,U,Sr,Ba)-O)リッチ層、(B)内部領域の(U,Zr)O$$_{2}$$相リッチ層)が観測された。SrおよびBaは(A)層に濃集した。((B)層の約1.7倍)熱力学解析により、(U,Zr)O$$_{2}$$相が、コンクリートを主成分とする液相中で2177$$^{circ}$$C付近で凝固することが予測された。その後、残りの液相がケイ酸ガラスとして凝固し、SrおよびBaはケイ酸ガラス相に優先的に溶け込むことがわかった。試験中、(U,Zr)O$$_{2}$$粒子はその高い密度により液相中で下方に沈み、ケイ酸ガラス相は表面層で凝固したことが考えられる。一方、SrおよびBaを含むケイ酸ガラスは水に溶けにくく、化学的に安定していることが予測される。


Observation of Coulomb-assisted nuclear bound state of $$Xi^-$$-$$^{14}$$N system

早川 修平; 藤田 真奈美; 長谷川 勝一; 橋本 直; 細見 健二; 市川 裕大; 今井 憲一*; 七村 拓野; 成木 恵; 佐甲 博之; et al.

Physical Review Letters, 126(6), p.062501_1 - 062501_6, 2021/02

 被引用回数:6 パーセンタイル:97.77(Physics, Multidisciplinary)

In an emulsion-counter hybrid experiment performed at J-PARC, a $$Xi^-$$ absorption event was observed which decayed into twin single-$$Lambda$$ hypernuclei. Kinematic calculations enabled a unique identification of the reaction process as $$Xi^{-} + ^{14}$$N$$ rightarrow ^{10}_Lambda$$Be + $$^5_Lambda$$He. For the binding energy of the $$Xi^{-}$$ hyperon in the $$Xi^-$$-$$^{14}$$N system a value of $$1.27 pm 0.21$$ MeV was deduced. The energy level of $$Xi^-$$ is likely a nuclear $$1p$$ state which indicates a weak $${Xi}N$$-$$LambdaLambda$$ coupling.


Individual dosimetry system for targeted alpha therapy based on PHITS coupled with microdosimetric kinetic model

佐藤 達彦; 古田 琢哉; Liu, Y.*; 仲 定宏*; 永森 收志*; 金井 好克*; 渡部 直史*

EJNMMI Physics (Internet), 8, p.4_1 - 4_16, 2021/01

 被引用回数:2 パーセンタイル:90.15(Radiology, Nuclear Medicine & Medical Imaging)



Study on the baryon interaction by $$Xi$$ hypernuclear spectroscopy with the $$(K^-, K^+)$$ reaction

後神 利志*; 藤田 真奈美; 長谷川 勝一; 細見 健二; 今井 憲一*; 市川 裕大; 七村 拓野; 成木 恵; 佐甲 博之; 佐藤 進; et al.

Journal of Physics; Conference Series, 1643, p.012133_1 - 012133_6, 2020/12

We performed $$Xi$$ hypernuclear spectroscopy with the $$(K^-, K^+)$$ reaction at J-PARC to investigate the $$Xi N$$ interaction (J-PARC E05). A new experiment (J-PARC E70) in which a better energy resolution could be achieved is now being prepared. In this article, an analysis status of J-PARC E05 and a preparation status of J-PARC E70 are described.


Modernization of the DCHAIN-PHITS activation code with new features and updated data libraries

Ratliff, H.; 松田 規宏; 安部 晋一郎; 三浦 孝充*; 古田 琢哉; 岩元 洋介; 佐藤 達彦

Nuclear Instruments and Methods in Physics Research B, 484, p.29 - 41, 2020/12

 被引用回数:0 パーセンタイル:0.02(Instruments & Instrumentation)

This paper details the recent improvements made to the DCHAIN-PHITS code, the activation, buildup, burnup, and decay code coupled to and distributed with PHITS. The recent improvements include the addition of numerous new decay and cross section nuclear data libraries, statistical uncertainty propagation implementation, support for 3-D grid mesh and tetrahedral geometries, reaction tracking, performance improvements, and more. The paper covers the DCHAIN's history, theory, usage, and improvements made to it and also includes example calculations showcasing these improvements. This is the first publication covering DCHAIN since the PHITS group obtained the code and will become the new reference journal paper for DCHAIN-PHITS. (The current reference document for DCHAIN is a JAERI document in Japanese only from 2001.)


Bound spinon excitations in the spin-$$frac{1}{2}$$ anisotropic triangular antiferromagnet Ca$$_{3}$$ReO$$_{5}$$Cl$$_{2}$$

那波 和宏*; 平井 大悟郎*; 古府 麻衣子; 中島 健次; 村崎 遼*; 小金 聖史*; 木俣 基*; 野尻 浩之*; 広井 善二*; 佐藤 卓*

Physical Review Research (Internet), 2(4), p.043121_1 - 043121_11, 2020/12


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