{"title":"Interaction studies between U-Zr alloy system and ceramic plasma-spray coated layer at elevated temperature","authors":"Ki-hwan Kim, Ki-Won Hong, H. Song, S. Oh, J. Park","doi":"10.15669/PNST.5.192","DOIUrl":"https://doi.org/10.15669/PNST.5.192","url":null,"abstract":"","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"83 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85535621","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Various types of post-accident radioactive waste have been generated from cleanup and decommissioning activities at the Fukushima Daiichi nuclear power plant. Perturbation effects resulting from co-existing substances may influence radionuclide sorption. For the disposal of these wastes, perturbation effects on sorption parameters must be critically evaluated for the safety assessment of the disposal systems. The present study focuses on developing a methodology to quantify sorption parameters in the presence of such perturbation effects and on illustrating example calculations regarding sorption reduction factors (SRFs) due to the presence of organic ligands (ISA; isosaccharinic acid) for cement systems. Three approaches for the derivation of SRFs; 1) semi-quantitative estimation based on analogy with solubility enhancement factors (SEFs) derived from measured solubility, 2) prediction based on radionuclide speciation calculation, and 3) quantification from experimental sorption data in ternary systems were coupled and tested for the Am-ISA-cement system. Our approach allows to critically evaluate the dependence of sorption reduction factors for various perturbed systems on the chosen method of quantification, in accordance with the data availability for a given perturbation.
福岛第一核电站的清理和退役活动产生了各种类型的事故后放射性废物。共存物质引起的扰动效应可能影响放射性核素的吸收。对于这些废物的处置，必须严格评估摄动对吸附参数的影响，以便对处置系统进行安全评估。本研究的重点是开发一种方法来量化存在这种扰动效应的吸附参数，并举例说明由于有机配体的存在而导致的吸附减少因子(srf)的计算。异糖酸)用于水泥体系。srf的三种推导方法1)基于溶解度增强因子(SEFs)类比的半定量估计，2)基于放射性核素形态计算的预测，以及3)基于三元体系中实验吸附数据的定量预测，对am - isa -水泥体系进行了耦合和测试。我们的方法允许根据给定扰动的数据可用性，批判性地评估各种摄动系统的吸收减少因子对所选择的量化方法的依赖性。
{"title":"Sorption parameter setting approaches for radioactive waste disposal considering perturbation effects: sorption reduction factors for organics","authors":"Y. Tachi, M. Ochs","doi":"10.15669/PNST.5.229","DOIUrl":"https://doi.org/10.15669/PNST.5.229","url":null,"abstract":"Various types of post-accident radioactive waste have been generated from cleanup and decommissioning activities at the Fukushima Daiichi nuclear power plant. Perturbation effects resulting from co-existing substances may influence radionuclide sorption. For the disposal of these wastes, perturbation effects on sorption parameters must be critically evaluated for the safety assessment of the disposal systems. The present study focuses on developing a methodology to quantify sorption parameters in the presence of such perturbation effects and on illustrating example calculations regarding sorption reduction factors (SRFs) due to the presence of organic ligands (ISA; isosaccharinic acid) for cement systems. Three approaches for the derivation of SRFs; 1) semi-quantitative estimation based on analogy with solubility enhancement factors (SEFs) derived from measured solubility, 2) prediction based on radionuclide speciation calculation, and 3) quantification from experimental sorption data in ternary systems were coupled and tested for the Am-ISA-cement system. Our approach allows to critically evaluate the dependence of sorption reduction factors for various perturbed systems on the chosen method of quantification, in accordance with the data availability for a given perturbation.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"36 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82662185","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
H. Kofuji, Sou Watanabe, M. Takeuchi, Hideya Suzuki, T. Matsumura, H. Shiwaku, T. Yaita
Characteristics of TPDN/SiO2-P adsorbent for MA(III) recovery Hirohide Kofuji, Sou Watanabe, Masayuki Takeuchi, Hideya Suzuki, Tatsuro Matsumura, Hideaki Shiwaku and Tsuyoshi Yaita Japan Atomic Energy Agency, 4-33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-pref., 319-1194, Japan; Japan Atomic Energy Agency,. Shirakata, Tokai-mura, Naka-gun, Ibaraki-pref., 319-1195, Japan; Japan Atomic Energy Agency, 1-1-1, Kouto, Sayo-cho, Sayo-gun, Hyogo-pref., 679-5148, Japan
{"title":"Characteristics of TPDN/SiO2-P adsorbent for MA(III) recovery","authors":"H. Kofuji, Sou Watanabe, M. Takeuchi, Hideya Suzuki, T. Matsumura, H. Shiwaku, T. Yaita","doi":"10.15669/PNST.5.61","DOIUrl":"https://doi.org/10.15669/PNST.5.61","url":null,"abstract":"Characteristics of TPDN/SiO2-P adsorbent for MA(III) recovery Hirohide Kofuji, Sou Watanabe, Masayuki Takeuchi, Hideya Suzuki, Tatsuro Matsumura, Hideaki Shiwaku and Tsuyoshi Yaita Japan Atomic Energy Agency, 4-33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki-pref., 319-1194, Japan; Japan Atomic Energy Agency,. Shirakata, Tokai-mura, Naka-gun, Ibaraki-pref., 319-1195, Japan; Japan Atomic Energy Agency, 1-1-1, Kouto, Sayo-cho, Sayo-gun, Hyogo-pref., 679-5148, Japan","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"82 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74711084","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Plutonium dioxide is one of the main components of nuclear fuels. In this paper, we evaluated formation energies of charged vacancies and site-interstitial atoms in plutonium dioxide based on density functional theory with spin-orbit coupling and strongly-correlated electron effect using LDA+U method. We also estimated migration energies of oxygen defects. We found that oxygen vacancies with double positive charge and interstitials with double negative charge are the most stable and that the calculated migration energy of an oxygen vacancy is comparable with that of an oxygen interstitial.
{"title":"A first-principles study on point defects in plutonium dioxide","authors":"Hiroki Nakamura, M. Machida","doi":"10.15669/PNST.5.132","DOIUrl":"https://doi.org/10.15669/PNST.5.132","url":null,"abstract":"Plutonium dioxide is one of the main components of nuclear fuels. In this paper, we evaluated formation energies of charged vacancies and site-interstitial atoms in plutonium dioxide based on density functional theory with spin-orbit coupling and strongly-correlated electron effect using LDA+U method. We also estimated migration energies of oxygen defects. We found that oxygen vacancies with double positive charge and interstitials with double negative charge are the most stable and that the calculated migration energy of an oxygen vacancy is comparable with that of an oxygen interstitial.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"131 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77818223","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
In the context of management of the waste streams arising from the reprocessing of spent nuclear fuel, studies have been conducted into the solvent extraction kinetics of lanthanide fission products by the oxygen-donor ligand N,N,N’,N’-tetraoctyl diglycolamide (TODGA) and the effects of solvent phase acidity on the effectiveness of this organic extractant molecule. In this study, we observe a reduction in the rate of cerium extraction as solvent phase acidity increases, attributed to aggregation of the extractant. The effect is shown to be reversible through neutralization while a permanent prevention method is the subject of further work.
{"title":"A study of cerium extraction kinetics by TODGA in acidified and non-acidified organic solvent phases in the context of fission product management","authors":"Michael A. Bromley, C. Boxall","doi":"10.15669/PNST.5.70","DOIUrl":"https://doi.org/10.15669/PNST.5.70","url":null,"abstract":"In the context of management of the waste streams arising from the reprocessing of spent nuclear fuel, studies have been conducted into the solvent extraction kinetics of lanthanide fission products by the oxygen-donor ligand N,N,N’,N’-tetraoctyl diglycolamide (TODGA) and the effects of solvent phase acidity on the effectiveness of this organic extractant molecule. In this study, we observe a reduction in the rate of cerium extraction as solvent phase acidity increases, attributed to aggregation of the extractant. The effect is shown to be reversible through neutralization while a permanent prevention method is the subject of further work.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"126 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85709860","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
The chemical state of uranium, zirconium, iron and lanthanide elements in simulated corium debris samples prepared in lab-scale were investigated by synchrotron radiation based extended X-ray absorption fine structure (EXFAS) technique. According to the EXAFS analysis of uranium, their most likely local structure was cubic like fluorite UO2. Exceptionally, pentavalent uranium was observed in the UO2-ZrO2-Fe2O3-CaO sample, in which the nearest U-O distance was clearly shorter than those of other samples containing tetravalent uranium. The local structure around zirconium could be classified into cubic, tetragonal and calcia stabilized zirconia with CaO. The oxidation state of iron was divalent for the most samples and a metallic phase was also detected in some of them. The small amount lanthanide elements (Nd and Gd) in the simulated debris seem to exist as a solid solution with UO2.
{"title":"Chemical state analysis of simulated corium debris by EXAFS","authors":"Y. Okamoto, M. Takano","doi":"10.15669/PNST.5.200","DOIUrl":"https://doi.org/10.15669/PNST.5.200","url":null,"abstract":"The chemical state of uranium, zirconium, iron and lanthanide elements in simulated corium debris samples prepared in lab-scale were investigated by synchrotron radiation based extended X-ray absorption fine structure (EXFAS) technique. According to the EXAFS analysis of uranium, their most likely local structure was cubic like fluorite UO2. Exceptionally, pentavalent uranium was observed in the UO2-ZrO2-Fe2O3-CaO sample, in which the nearest U-O distance was clearly shorter than those of other samples containing tetravalent uranium. The local structure around zirconium could be classified into cubic, tetragonal and calcia stabilized zirconia with CaO. The oxidation state of iron was divalent for the most samples and a metallic phase was also detected in some of them. The small amount lanthanide elements (Nd and Gd) in the simulated debris seem to exist as a solid solution with UO2.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"24 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90360304","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
The clean-up activities related to the accident at the Fukushima nuclear power plant give rise to several types of wastes containing cementitious materials as well as substances that can influence radionuclide migration, especially organic complexing substances, boron, and chloride salts. The present study focuses on a methodology, based on available literature information, for quantifying the retention behavior of uranium (VI) in cement materials of different degradation states and in the presence of organics, boron, and salts. To account for the many variables defining uranium uptake in cement systems a stepwise approach is proposed and illustrated: 1) definition of conditions and U speciation in each relevant degradation state, 2) assessment of U(VI) uptake processes based on a critical review of literature information, 3) Kd setting on the basis of original experimental data that are consistent with the identified processes and speciation, 4) assessment of ligand effects based on data preferably from ternary systems, or from speciation and analogue information.
{"title":"Retention of uranium in cement systems: effects of cement degradation and complexing ligands","authors":"M. Ochs, B. Vriens, Y. Tachi","doi":"10.15669/PNST.5.208","DOIUrl":"https://doi.org/10.15669/PNST.5.208","url":null,"abstract":"The clean-up activities related to the accident at the Fukushima nuclear power plant give rise to several types of wastes containing cementitious materials as well as substances that can influence radionuclide migration, especially organic complexing substances, boron, and chloride salts. The present study focuses on a methodology, based on available literature information, for quantifying the retention behavior of uranium (VI) in cement materials of different degradation states and in the presence of organics, boron, and salts. To account for the many variables defining uranium uptake in cement systems a stepwise approach is proposed and illustrated: 1) definition of conditions and U speciation in each relevant degradation state, 2) assessment of U(VI) uptake processes based on a critical review of literature information, 3) Kd setting on the basis of original experimental data that are consistent with the identified processes and speciation, 4) assessment of ligand effects based on data preferably from ternary systems, or from speciation and analogue information.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"76 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83849405","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
In November 2016, four new chemical elements, nihonium (Nh, Z=113), moscovium (Mc, Z=115), tennessine (Ts, Z=117), and oganesson (Og, Z=118) joined the periodic table. Elements 117 and 118 are the highest atomic numbers Z reached to date, and the A=294 isotopes of these elements are the heaviest nuclei ever synthesized. The existence of these elements, together with a consistent trend of increasing lifetimes for superheavy isotopes as neutron number N increases, provide strong evidence for the long sought “island of stability” for superheavy nuclei as the nuclear shell closure at N=184 is approached. Mc, Ts, and Og were discovered using the hot fusion process, bombarding actinide targets with intense beams of doubly-magic Ca ions at the Dubna Gas-Filled Recoil Separator at the Joint Institute for Nuclear Research in Russia. For element 117, a berkelium target from Oak Ridge National Laboratory (ORNL) was required. The berkelium was produced by intense neutron irradiation at ORNL’s High Flux Isotope Reactor and chemically separated at the adjoining Radiochemical Engineering Development Center. The Bk + Ca reaction produced two isotopes of element 117 with atomic weights A=293 and 294. These isotopes decayed into ten additional heaviest isotopes of elements 115, 113, 111, 109, 107, and 105, all closer to the predicted island of stability than previously achieved. The discovery of element 117 will be described together with results of other recent experiments in superheavy element research in the context of the critical importance of actinide target materials, implications for the periodic table and the island of stability, and opportunities to synthesize even heavier nuclei, including heavy isotopes of element 118 and new elements 119 and 120.
{"title":"The discovery of element 117 (INVITED)","authors":"J. Roberto","doi":"10.15669/PNST.5.14","DOIUrl":"https://doi.org/10.15669/PNST.5.14","url":null,"abstract":"In November 2016, four new chemical elements, nihonium (Nh, Z=113), moscovium (Mc, Z=115), tennessine (Ts, Z=117), and oganesson (Og, Z=118) joined the periodic table. Elements 117 and 118 are the highest atomic numbers Z reached to date, and the A=294 isotopes of these elements are the heaviest nuclei ever synthesized. The existence of these elements, together with a consistent trend of increasing lifetimes for superheavy isotopes as neutron number N increases, provide strong evidence for the long sought “island of stability” for superheavy nuclei as the nuclear shell closure at N=184 is approached. Mc, Ts, and Og were discovered using the hot fusion process, bombarding actinide targets with intense beams of doubly-magic Ca ions at the Dubna Gas-Filled Recoil Separator at the Joint Institute for Nuclear Research in Russia. For element 117, a berkelium target from Oak Ridge National Laboratory (ORNL) was required. The berkelium was produced by intense neutron irradiation at ORNL’s High Flux Isotope Reactor and chemically separated at the adjoining Radiochemical Engineering Development Center. The Bk + Ca reaction produced two isotopes of element 117 with atomic weights A=293 and 294. These isotopes decayed into ten additional heaviest isotopes of elements 115, 113, 111, 109, 107, and 105, all closer to the predicted island of stability than previously achieved. The discovery of element 117 will be described together with results of other recent experiments in superheavy element research in the context of the critical importance of actinide target materials, implications for the periodic table and the island of stability, and opportunities to synthesize even heavier nuclei, including heavy isotopes of element 118 and new elements 119 and 120.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"119 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90259959","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
M. Chimes, C. Boxall, S. Edwards, M. Sarsfield, R. Taylor, D. Woodhead
Neptunium has been previously shown to present challenges within a used nuclear fuel reprocessing scheme due to its tendency to exist in the (IV), (V), and (VI) oxidation states simultaneously. In order to control this neptunium speciation, and informed by relevant work in the literature, we are currently engaged in a study of nitric/nitrous acid redox chemistry with Np(V) and Np(VI). To minimize radiological exposure risks, we are also exploring the validity of using vanadium as an analogue for the study of the kinetics of the Np(VI)/Np(V) reduction by nitrous acid. The kinetics of the reduction of vanadium(V) by nitrous acid in solutions of nitric acid was investigated spectrophotometrically by the method of initial rates. Orders of reaction with respect to V(V), and HNO2 were found to be 0.90, and 1.24 respectively, in reasonable agreement with the analogous reaction orders for the reduction of Np(VI) by nitrous acid previously reported by Precek and Paulenova – suggesting that, for this particular reduction, V(V) can serve as a good kinetic analogue for Np(VI). The value of the rate constant k for the rate law -d[V(V)]/dt = k[V(V)][HNO2]/[H] was found to be 7.5 × 10 M s at 20 °C, two orders of magnitude smaller than that for the reduction of Np(VI) by HNO2, a difference that is attributable to the loss of one of the oxygens during the VO2 to VO reduction reaction.
由于镎倾向于同时以(IV)、(V)和(VI)氧化态存在，先前已证明在乏燃料后处理方案中存在挑战。为了控制这种镎的形态，并根据文献相关工作，我们目前正在研究Np(V)和Np(VI)对硝酸/亚硝酸氧化还原化学的影响。为了最大限度地降低辐射暴露风险，我们也在探索使用钒作为亚硝酸还原Np(VI)/Np(V)动力学研究的类似物的有效性。用初始速率法研究了硝酸溶液中硝酸还原钒的动力学。V(V)和HNO2的反应阶数分别为0.90和1.24，与preprek和Paulenova先前报道的硝酸还原Np(VI)的类似反应阶数基本一致，这表明，对于这种特殊的还原，V(V)可以作为Np(VI)的良好动力学类似物。在20℃时，速率定律-d[V(V)]/dt = k[V(V)][HNO2]/[H]的速率常数k值为7.5 × 10 M s，比HNO2还原Np(VI)的速率常数小两个数量级，这是由于在VO2还原成VO的反应中损失了一个氧所致。
{"title":"Nitrous acid-driven reduction of vanadium as a neptunium analogue","authors":"M. Chimes, C. Boxall, S. Edwards, M. Sarsfield, R. Taylor, D. Woodhead","doi":"10.15669/PNST.5.37","DOIUrl":"https://doi.org/10.15669/PNST.5.37","url":null,"abstract":"Neptunium has been previously shown to present challenges within a used nuclear fuel reprocessing scheme due to its tendency to exist in the (IV), (V), and (VI) oxidation states simultaneously. In order to control this neptunium speciation, and informed by relevant work in the literature, we are currently engaged in a study of nitric/nitrous acid redox chemistry with Np(V) and Np(VI). To minimize radiological exposure risks, we are also exploring the validity of using vanadium as an analogue for the study of the kinetics of the Np(VI)/Np(V) reduction by nitrous acid. The kinetics of the reduction of vanadium(V) by nitrous acid in solutions of nitric acid was investigated spectrophotometrically by the method of initial rates. Orders of reaction with respect to V(V), and HNO2 were found to be 0.90, and 1.24 respectively, in reasonable agreement with the analogous reaction orders for the reduction of Np(VI) by nitrous acid previously reported by Precek and Paulenova – suggesting that, for this particular reduction, V(V) can serve as a good kinetic analogue for Np(VI). The value of the rate constant k for the rate law -d[V(V)]/dt = k[V(V)][HNO2]/[H] was found to be 7.5 × 10 M s at 20 °C, two orders of magnitude smaller than that for the reduction of Np(VI) by HNO2, a difference that is attributable to the loss of one of the oxygens during the VO2 to VO reduction reaction.","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"210 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77555111","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
S. Nakamura, T. Sakakibara, Y. Shimizu, S. Kittaka, Y. Kono, Y. Haga, J. Pospíšil, E. Yamamoto
Shota Nakamura, Toshiro Sakakibara, Yusei Shimizu, Shunichiro Kittaka, Yohei Kono, Yoshinori Haga, Jiří Pospíšil and Etsuji Yamamoto Institute for Solid State Physics, The University of Tokyo, Kashiwa 277-8581, Japan; Institute for Materials Research, Tohoku University, Oarai 311-1313, Japan; Japan Atomic Energy Agency, Tokai 319-1106, Japan; Charles University in Prague, Faculty of Mathematics and Physics, DCMP, Ke Karlovu 5, 121 16 Prague 2, Czech Republic
中村正太，坂原敏郎，清水佑成，北孝一弘，河野洋平，长贺义德，Jiří Pospíšil，东京大学固体物理研究所山本越司，日本柏华277-8581;东北大学材料研究所，日本大原311-1313;日本原子能机构，日本东海319-1106;布拉格查尔斯大学，数学与物理学院，DCMP, Ke Karlovu 5, 121 16布拉格2，捷克共和国
{"title":"Magnetization study on the ising ferromagnet URhGe with high-precision angle-resolved magnetic field near the hard axis","authors":"S. Nakamura, T. Sakakibara, Y. Shimizu, S. Kittaka, Y. Kono, Y. Haga, J. Pospíšil, E. Yamamoto","doi":"10.15669/PNST.5.123","DOIUrl":"https://doi.org/10.15669/PNST.5.123","url":null,"abstract":"Shota Nakamura, Toshiro Sakakibara, Yusei Shimizu, Shunichiro Kittaka, Yohei Kono, Yoshinori Haga, Jiří Pospíšil and Etsuji Yamamoto Institute for Solid State Physics, The University of Tokyo, Kashiwa 277-8581, Japan; Institute for Materials Research, Tohoku University, Oarai 311-1313, Japan; Japan Atomic Energy Agency, Tokai 319-1106, Japan; Charles University in Prague, Faculty of Mathematics and Physics, DCMP, Ke Karlovu 5, 121 16 Prague 2, Czech Republic","PeriodicalId":20706,"journal":{"name":"Progress in Nuclear Science and Technology","volume":"8 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74267670","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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