tandf: Journal of Nuclear Science and Technology: Table of ContentsTable of Contents for Journal of Nuclear Science and Technology. List of articles from both the latest and ahead of print issues.
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tandf: Journal of Nuclear Science and Technology: Table of Contentstandfen-USJournal of Nuclear Science and TechnologyJournal of Nuclear Science and Technologyhttps://www.tandfonline.com/cms/asset/849f2f83-d39b-4f38-8f63-7e8cb6af2f5e/default_cover.jpg
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Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2239810?af=R
<a href="/toc/tnst20/61/4">Volume 61, Issue 4</a>, April 2024, Page 448-458<br/>. <br/>Volume 61, Issue 4, April 2024, Page 448-458<br/>. <br/>Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysisdoi:10.1080/00223131.2023.2239810Journal of Nuclear Science and Technology2023-07-31T11:38:49ZKuniki HataSatoshi HanawaYasuhiro ChimiShunsuke UchidaNuclear Safety Research Center, Japan Atomic Energy Agency, Ibaraki, JapanJournal of Nuclear Science and Technology6144484582024-04-02T07:00:00Z2024-04-02T07:00:00Z10.1080/00223131.2023.2239810https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2239810?af=R241Am Neutron Capture Cross Section Measurement using the NaI(Tl) spectrometer of the ANNRI beamline of J-PARC
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2239885?af=R
<a href="/toc/tnst20/61/4">Volume 61, Issue 4</a>, April 2024, Page 459-477<br/>. <br/>Volume 61, Issue 4, April 2024, Page 459-477<br/>. <br/>241Am Neutron Capture Cross Section Measurement using the NaI(Tl) spectrometer of the ANNRI beamline of J-PARCdoi:10.1080/00223131.2023.2239885Journal of Nuclear Science and Technology2023-08-22T11:16:02ZGerard RoviraAtsushi KimuraShoji NakamuraShunsuke EndoOsamu IwamotoNobuyuki IwamotoTatsuya KatabuchiYu KodamaHideto NakanoYaoki Satoa Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Ibaraki, Japanb Laboratory for Zero-Carbon Energy, Institute of Innovative Research, Tokyo Institute of Technology, Tokyo, JapanJournal of Nuclear Science and Technology6144594772024-04-02T07:00:00Z2024-04-02T07:00:00Z10.1080/00223131.2023.2239885https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2239885?af=RTRU oxide sample reactivity worths measured in the FCA-IX assemblies with systematically changed neutron energy spectra
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2240872?af=R
<a href="/toc/tnst20/61/4">Volume 61, Issue 4</a>, April 2024, Page 478-497<br/>. <br/>Volume 61, Issue 4, April 2024, Page 478-497<br/>. <br/>TRU oxide sample reactivity worths measured in the FCA-IX assemblies with systematically changed neutron energy spectradoi:10.1080/00223131.2023.2240872Journal of Nuclear Science and Technology2023-08-22T11:38:41ZMasahiro FukushimaShigeaki OkajimaTakehiko MukaiyamaJapan Atomic Energy Agency (JAEA), Ibaraki, JapanJournal of Nuclear Science and Technology6144784972024-04-02T07:00:00Z2024-04-02T07:00:00Z10.1080/00223131.2023.2240872https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2240872?af=RThe effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2243935?af=R
<a href="/toc/tnst20/61/4">Volume 61, Issue 4</a>, April 2024, Page 498-508<br/>. <br/>Volume 61, Issue 4, April 2024, Page 498-508<br/>. <br/>The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrationsdoi:10.1080/00223131.2023.2243935Journal of Nuclear Science and Technology2023-08-22T11:18:43ZKoji KitanoMasaaki OzawaRegulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R), Tokyo, JapanJournal of Nuclear Science and Technology6144985082024-04-02T07:00:00Z2024-04-02T07:00:00Z10.1080/00223131.2023.2243935https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2243935?af=RMicrostructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2243947?af=R
<a href="/toc/tnst20/61/4">Volume 61, Issue 4</a>, April 2024, Page 530-540<br/>. <br/>Volume 61, Issue 4, April 2024, Page 530-540<br/>. <br/>Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 Kdoi:10.1080/00223131.2023.2243947Journal of Nuclear Science and Technology2023-08-14T01:57:20ZAyumi ItohRyotaro HagiwaraShintaro YasuiYoshinao KobayashiKan SakamotoMasato MizokamiMutsumi HiraiKenichi Itoa Laboratory for Zero-Carbon Energy, Tokyo Institute of Technology, Meguro-Ku, Tokyo, Japanb Department of Materials Science and Engineering, Tokyo Institute of Technology, Meguro-Ku, Tokyo, Japanc Nippon Nuclear Fuel Development Co. Ltd, Igaraki-gun, Ibaraki, Japand Tokyo Electronic Power Company Holdings, Inc, Chiyoda-Ku, Tokyo, JapanJournal of Nuclear Science and Technology6145305402024-04-02T07:00:00Z2024-04-02T07:00:00Z10.1080/00223131.2023.2243947https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2243947?af=RMeasurement and simulations of high-energy neutrons through a various thickness of concrete and steel shields using activation detectors at CHARM and CSBF
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2239243?af=R
<a href="/toc/tnst20/61/4">Volume 61, Issue 4</a>, April 2024, Page 429-447<br/>. <br/>Volume 61, Issue 4, April 2024, Page 429-447<br/>. <br/>Measurement and simulations of high-energy neutrons through a various thickness of concrete and steel shields using activation detectors at CHARM and CSBFdoi:10.1080/00223131.2023.2239243Journal of Nuclear Science and Technology2023-08-14T05:36:54ZNoriaki NakaoToshiya SanamiTsuyoshi KajimotoHiroshi YashimaRobert FroeschlDavide BozzatoElpida IliopoulouAngelo InfantinoEunji LeeTakahiro OyamaMasayuki HagiwaraSeiji NagaguroTetsuro MatsumotoAkihiko MasudaYoshitomo UwaminoArnaud DevienneFabio PozziMarco TisiTommaso LorenzonNabil MenaaHeinz VinckeStefan RoeslerMarkus Bruggera Shimizu Corporation, Institute of Technology, Tokyo, Japanb Radiation Science Center, High Energy Accelerator Research Organization (KEK), Tsukuba, Ibaraki, Japanc Graduate School of Advanced Science and Engineering, Hiroshima University, Hiroshima, Japand Kyoto University Institute for Integrated Radiation and Nuclear Science (KURNS), Osaka, Japane Radiation Protection Group, CERN, Geneva, Switzerlandf Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoka, Japang National Metrology Institute of Japan (NMIJ), National Institute of Advanced Industrial Science and Technology (AIST), Ibaraki, JapanJournal of Nuclear Science and Technology6144294472024-04-02T07:00:00Z2024-04-02T07:00:00Z10.1080/00223131.2023.2239243https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2239243?af=REvaluation of the production amount of 225Ac and its uncertainty through the 226Ra(n,2n) reaction in the experimental fast reactor Joyo
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2243941?af=R
<a href="/toc/tnst20/61/4">Volume 61, Issue 4</a>, April 2024, Page 509-520<br/>. <br/>Volume 61, Issue 4, April 2024, Page 509-520<br/>. <br/>Evaluation of the production amount of 225Ac and its uncertainty through the 226Ra(n,2n) reaction in the experimental fast reactor Joyodoi:10.1080/00223131.2023.2243941Journal of Nuclear Science and Technology2023-08-21T11:53:34ZYuto SasakiAaru SanoShinji SasakiNobuyuki IwamotoKazuki OuchiYoshihiro KitatsujiNaoyuki TakakiShigetaka Maedaa Nuclear Energy Systems Laboratory, Cooperative Major in Nuclear Energy, Graduate School of Integrative Science and Engineering, Tokyo City University, Setagaya-Ku, Tokyo, Japanb Oarai Research and Development Institute, Japan Atomic Energy Agency, Higashi-Ibaraki-Gun, Ibaraki, Japanc Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Naka-Gun, Ibaraki, JapanJournal of Nuclear Science and Technology6145095202024-04-02T07:00:00Z2024-04-02T07:00:00Z10.1080/00223131.2023.2243941https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2243941?af=RTensile properties of modified 316 stainless steel (PNC316) after neutron irradiation over 100 dpa
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2243943?af=R
<a href="/toc/tnst20/61/4">Volume 61, Issue 4</a>, April 2024, Page 521-529<br/>. <br/>Volume 61, Issue 4, April 2024, Page 521-529<br/>. <br/>Tensile properties of modified 316 stainless steel (PNC316) after neutron irradiation over 100 dpadoi:10.1080/00223131.2023.2243943Journal of Nuclear Science and Technology2023-08-11T11:36:04ZYasuhide YanoTomoyuki UwabaTakashi TannoTsunemitsu YoshitakeSatoshi OhtsukaTakeji KaitoSector of Fast Reactor and Advanced Reactor Research and Development, Oarai Research and Development Insititute, Japan Atomic Energy Agency, Oarai-Machi, Ibaraki, JapanJournal of Nuclear Science and Technology6145215292024-04-02T07:00:00Z2024-04-02T07:00:00Z10.1080/00223131.2023.2243943https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2243943?af=RBenchmark specifications of TCA critical experiments for validation of thermal scattering laws of water
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2243933?af=R
<a href="/toc/tnst20/61/4">Volume 61, Issue 4</a>, April 2024, Page 549-559<br/>. <br/>Volume 61, Issue 4, April 2024, Page 549-559<br/>. <br/>Benchmark specifications of TCA critical experiments for validation of thermal scattering laws of waterdoi:10.1080/00223131.2023.2243933Journal of Nuclear Science and Technology2023-08-23T07:29:39ZToru YamamotoNuclear Engineering Consultant, Yokohama, JapanJournal of Nuclear Science and Technology6145495592024-04-02T07:00:00Z2024-04-02T07:00:00Z10.1080/00223131.2023.2243933https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2243933?af=RDosimetric effect of carbon fiber treatment couch in boron neutron capture therapy
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2233966?af=R
<a href="/toc/tnst20/61/4">Volume 61, Issue 4</a>, April 2024, Page 541-548<br/>. <br/>Volume 61, Issue 4, April 2024, Page 541-548<br/>. <br/>Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapydoi:10.1080/00223131.2023.2233966Journal of Nuclear Science and Technology2023-07-17T05:46:31ZYongquan WangHuangxin WuJunliang DuJinyang LiXingcai GuanLong Gua School of Nuclear Science and Technology, Lanzhou University, Lanzhou, Chinab Southeast Research Institute of Lanzhou University, Putian, ChinaJournal of Nuclear Science and Technology6145415482024-04-02T07:00:00Z2024-04-02T07:00:00Z10.1080/00223131.2023.2233966https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2233966?af=RHigh temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environment
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2273469?af=R
. <br/>. <br/>High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environmentdoi:10.1080/00223131.2023.2273469Journal of Nuclear Science and Technology2023-11-10T04:52:11ZYoichi WadaKazushige IshidaMasahiko TachibanaMayu SasakiMakoto NagaseRyosuke Shimizua Nuclear Energy Systems Research Department, Decarbonized Energy Innovation Center, Hitachi, Japanb Nuclear Plant Engineering Department, Hitachi Works, Hitachi-GE Nuclear Energy, Hitach-shi, JapanJournal of Nuclear Science and Technology11310.1080/00223131.2023.2273469https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2273469?af=RBenchmark simulation code for the thermal-hydraulics design tool of the accelerator-driven system: validation and benchmark simulation of flow behavior around the beam window
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2268676?af=R
. <br/>. <br/>Benchmark simulation code for the thermal-hydraulics design tool of the accelerator-driven system: validation and benchmark simulation of flow behavior around the beam windowdoi:10.1080/00223131.2023.2268676Journal of Nuclear Science and Technology2023-10-19T02:19:28ZSusumu YamashitaNao KondoTakanori SugawaraHideaki MonjiHiroyuki Yoshidaa Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Ibaraki, Japanb Department of Engineering Mechanics and Energy, University of Tsukuba, Ibaraki, JapanJournal of Nuclear Science and Technology12210.1080/00223131.2023.2268676https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2268676?af=RProposal of uncertainty analysis methodology for L1PRA using Markov state-transition model
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2287111?af=R
. <br/>. <br/>Proposal of uncertainty analysis methodology for L1PRA using Markov state-transition modeldoi:10.1080/00223131.2023.2287111Journal of Nuclear Science and Technology2023-12-08T07:36:19ZMasanobu HaruharaHitoshi MutaYasuki OhtoriShohei YamagishiShota Terayamaa Common Major in Nuclear Energy, Tokyo City University, Setagaya-ku Tokyo, Japanb ITOCHU Techno-Solutions Corporation, Minato-ku, Tokyo, JapanJournal of Nuclear Science and Technology11410.1080/00223131.2023.2287111https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2287111?af=RCryogenic distribution system design for cryomodules and cavities test in HIAF project
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2253812?af=R
. <br/>. <br/>Cryogenic distribution system design for cryomodules and cavities test in HIAF projectdoi:10.1080/00223131.2023.2253812Journal of Nuclear Science and Technology2023-09-08T01:45:56ZWang Xian JinChen Shu PingWen JunZhang PengBai FengFan Da JunLi Ya NanNiu Xiao FeiZhang Junhuia College of Petrochemical Engineering, Lanzhou University of Technology, Lanzhou, Chinab Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou ChinaJournal of Nuclear Science and Technology11410.1080/00223131.2023.2253812https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2253812?af=REvaluation of radiation dose caused by bremsstrahlung photons generated by high-energy beta rays using the PHITS and GEANT4 simulation codes
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2285934?af=R
. <br/>. <br/>Evaluation of radiation dose caused by bremsstrahlung photons generated by high-energy beta rays using the PHITS and GEANT4 simulation codesdoi:10.1080/00223131.2023.2285934Journal of Nuclear Science and Technology2023-12-04T07:18:49ZYoshiaki ShikazeNuclear Emergency Assistance and Training Center, Japan Atomic Energy Agency, Kashiwa, JapanJournal of Nuclear Science and Technology11710.1080/00223131.2023.2285934https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2285934?af=RDevelopment of a radiation tolerant laser-induced breakdown spectroscopy system using a single crystal micro-chip laser for remote elemental analysis
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2298485?af=R
. <br/>. <br/>Development of a radiation tolerant laser-induced breakdown spectroscopy system using a single crystal micro-chip laser for remote elemental analysisdoi:10.1080/00223131.2023.2298485Journal of Nuclear Science and Technology2024-01-03T10:09:44ZKoji TamuraRyuzo NakanishiHironori OhbaTakahiro KarinoTakuya ShibataTakunori TairaIkuo Wakaidaa Foundational Quantum Technology Research Directorate, National Institutes for Quantum Science and Technology (QST), Takasaki, Japanb Collaborative Laboratories for Advanced Decommissioning Science, Japan Atomic Energy Agency (JAEA), Tokai-mura, Japanc Division of Research Innovation and Collaboration, Institute for Molecular Science (IMS), Okazaki, Japand Laser-Driven Electron-Acceleration Technology Group, Riken SPring-8 center (RSC), Hyogo, JapanJournal of Nuclear Science and Technology1810.1080/00223131.2023.2298485https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2298485?af=RThe effect of a cyclic bending load on the bending resistance of ballooned, ruptured, and oxidized Zircaloy-4 cladding
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2293100?af=R
. <br/>. <br/>The effect of a cyclic bending load on the bending resistance of ballooned, ruptured, and oxidized Zircaloy-4 claddingdoi:10.1080/00223131.2023.2293100Journal of Nuclear Science and Technology2023-12-17T05:16:11ZFeng LiTakafumi NarukawaYutaka Udagawaa Nuclear Safety Research Center, Japan Atomic Energy Agency, Naka-gun, Ibaraki, Japanb Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, Bunkyo-ku, Tokyo, JapanJournal of Nuclear Science and Technology11210.1080/00223131.2023.2293100https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2293100?af=RStudy on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2297787?af=R
. <br/>. <br/>Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluidsdoi:10.1080/00223131.2023.2297787Journal of Nuclear Science and Technology2024-01-08T05:09:38ZXing-Kang SuJin-Biao ZhangJing QiuQi-Jian ChenYue-Feng GuoXian-Wen LiLong Gua School of Nuclear Science and Technology, Lanzhou University, Lanzhou, Chinab Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, Chinac School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing, ChinaJournal of Nuclear Science and Technology12010.1080/00223131.2023.2297787https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2297787?af=RFirst-principles calculations to investigate thermodynamic and mechanical behaviors of molybdenum-lanthanum alloy
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2246478?af=R
. <br/>. <br/>First-principles calculations to investigate thermodynamic and mechanical behaviors of molybdenum-lanthanum alloydoi:10.1080/00223131.2023.2246478Journal of Nuclear Science and Technology2023-08-22T09:12:46ZLu WangKun Jie YangChenguang LiuYue-Lin LiuDepartment of Nuclear Engineering, Yantai University, Yantai, ChinaJournal of Nuclear Science and Technology11110.1080/00223131.2023.2246478https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2246478?af=RCreep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2269178?af=R
. <br/>. <br/>Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°Cdoi:10.1080/00223131.2023.2269178Journal of Nuclear Science and Technology2023-10-24T06:15:10ZYuya ImagawaRyuta HashidateTakeshi MiyazawaTakashi OnizawaSatoshi OhtsukaYasuhide YanoTakashi TannoTakeji KaitoMasato OhnumaMasatoshi MitsuharaTakeshi Toyamaa Oarai Research Institute, Sector of Fast Reactor and Advanced Reactor Research and Development, Japan Atomic Energy Agency, Ibaraki, Japanb Division of Quantum Science and Engineering, Hokkaido University, Sapporo, Hokkaido, Japanc Department of molecular and material Sciences, Kyushu University, Kasuga, Fukuoka, Japand Institute for Materials Research, Tohoku University, Oarai, Ibaraki, JapanJournal of Nuclear Science and Technology11610.1080/00223131.2023.2269178https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2269178?af=RDirect disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2293106?af=R
. <br/>. <br/>Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculationsdoi:10.1080/00223131.2023.2293106Journal of Nuclear Science and Technology2023-12-14T06:58:38ZTakumi AbeKenji NishiharaNuclear Science and Engineering Center, Japan Atomic Energy Agency, Naka-gun, Ibaraki, JapanJournal of Nuclear Science and Technology11310.1080/00223131.2023.2293106https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2293106?af=RA multiclass classification model for predicting the thermal conductivity of uranium compounds
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2269974?af=R
. <br/>. <br/>A multiclass classification model for predicting the thermal conductivity of uranium compoundsdoi:10.1080/00223131.2023.2269974Journal of Nuclear Science and Technology2023-11-09T05:35:56ZY. SunM. KumagaiM. JinE. SatoM. AokiY. OhishiK. Kurosakia Institute for Integrated Radiation and Nuclear Science, Kyoto University, Kumatori, Sennan, Japanb SAKURA internet Research Center, SAKURA internet Inc, Kita-ku, Osaka, Japanc Center for Advanced Intelligence Project, RIKEN, Chuo-ku, Tokyo, Japand Graduate School of Engineering, Osaka University, Suita, Osaka, Japane Research Institute of Nuclear Engineering, University of Fukui, Tsuruga, Fukui, JapanJournal of Nuclear Science and Technology11110.1080/00223131.2023.2269974https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2269974?af=RKinetic modeling of IG-110 oxidation in inert atmosphere with low oxygen concentration for innovative high-temperature gas-cooled reactor applications
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2274928?af=R
. <br/>. <br/>Kinetic modeling of IG-110 oxidation in inert atmosphere with low oxygen concentration for innovative high-temperature gas-cooled reactor applicationsdoi:10.1080/00223131.2023.2274928Journal of Nuclear Science and Technology2023-11-15T08:17:43ZYosuke NishimuraAnna GubarevichKatsumi YoshidaAvadhesh Kumar SharmaKoji Okamotoa The Department of Nuclear Engineering and Management, Graduate School of Engineering, The University of Tokyo, Tokyo, Japanb Laboratory for Zero-Carbon Energy, Institute of Innovative Research, Tokyo Institute of Technology, Tokyo, JapanJournal of Nuclear Science and Technology1810.1080/00223131.2023.2274928https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2274928?af=RPower profile analysis of criticality accidents involving fissile solution boiling with considering evaporation
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2290711?af=R
. <br/>. <br/>Power profile analysis of criticality accidents involving fissile solution boiling with considering evaporationdoi:10.1080/00223131.2023.2290711Journal of Nuclear Science and Technology2023-12-07T03:59:55ZTomoaki WatanabeYuichi YamaneNuclear Safety Research Center, Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki, JapanJournal of Nuclear Science and Technology1910.1080/00223131.2023.2290711https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2290711?af=RDevelopment of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithm
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2259908?af=R
. <br/>. <br/>Development of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithmdoi:10.1080/00223131.2023.2259908Journal of Nuclear Science and Technology2023-10-04T10:31:31ZYongquan WangYang LiuHuangxin WuJinyang LiLong GuXingcai Guana School of Nuclear Science and Technology, Lanzhou University, Lanzhou, 730000, Chinab Southeast Research Institute of Lanzhou University, Putian, 351153, ChinaJournal of Nuclear Science and Technology11010.1080/00223131.2023.2259908https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2259908?af=RMultiple scattering double compton model: determination of intrinsic efficiencies by calculating electron energies
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2252830?af=R
. <br/>. <br/>Multiple scattering double compton model: determination of intrinsic efficiencies by calculating electron energiesdoi:10.1080/00223131.2023.2252830Journal of Nuclear Science and Technology2023-09-12T07:45:22ZVictor Pérez Medina-OllivaryEsteban Chávez-AlarcónJaime KlappDepartamento de Metrología, Instituto Nacional de Investigaciones Nucleares (ININ), Ocoyoacac, Estado de México, MéxicoJournal of Nuclear Science and Technology11410.1080/00223131.2023.2252830https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2252830?af=RNumerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2290712?af=R
. <br/>. <br/>Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platformdoi:10.1080/00223131.2023.2290712Journal of Nuclear Science and Technology2023-12-06T02:58:19ZGuopeng LiangYunlong WangGuan GuanChaoguang JinMing Chena School of Naval Architecture, Dalian University of Technology, Dalian, Chinab State Key Laboratory of Structural Analysis for Industrial Equipment, Dalian University of Technology, Dalian, ChinaJournal of Nuclear Science and Technology11610.1080/00223131.2023.2290712https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2290712?af=RThinning behavior of solid boron carbide immersed in molten stainless steel for core disruptive accident of sodium-cooled fast reactor
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2287109?af=R
. <br/>. <br/>Thinning behavior of solid boron carbide immersed in molten stainless steel for core disruptive accident of sodium-cooled fast reactordoi:10.1080/00223131.2023.2287109Journal of Nuclear Science and Technology2023-12-01T08:31:53ZYuki EmuraToshihide TakaiShin KikuchiKenji KamiyamaHidemasa YamanoHiroki YokoyamaKan Sakamotoa Sector of Fast Reactor and Advanced Reactor Research and Development, Japan Atomic Energy Agency (JAEA) Ibaraki, Japanb Research Department, Nippon Nuclear Fuel Development Co. Ltd. (NFD), Ibaraki, JapanJournal of Nuclear Science and Technology11010.1080/00223131.2023.2287109https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2287109?af=RTwo-dimensional elemental mapping of simulated fuel debris using laser-induced breakdown spectroscopy
https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2255186?af=R
. <br/>. <br/>Two-dimensional elemental mapping of simulated fuel debris using laser-induced breakdown spectroscopydoi:10.1080/00223131.2023.2255186Journal of Nuclear Science and Technology2023-09-21T03:45:22ZMunkhbat BatsaikhanKatsuaki AkaokaMorihisa SaekiTakahiro KarinoHironori OhbaIkuo Wakaidaa Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Japan Atomic Energy Agency (JAEA), Ibaraki, Japanb Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Sector of Fukushima Research and Development, Japan Atomic Energy Agency (JAEA), Fukushima, Japanc Foundational Quantum Technology Research Directorate, National Institute for Quantum Science and Technology, Gunma, JapanJournal of Nuclear Science and Technology11310.1080/00223131.2023.2255186https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2255186?af=RTechnical research on rapid source term calculation and prediction technology of nuclear accidents based on Bayesian network
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. <br/>. <br/>Technical research on rapid source term calculation and prediction technology of nuclear accidents based on Bayesian networkdoi:10.1080/00223131.2023.2294193Journal of Nuclear Science and Technology2023-12-17T05:20:00ZMingliang XieYuqing ChenLei YuWei WeiBoyu ChenZhengquan XieXueyan Houa College of Nuclear Science and Technology, Naval University of Engineering, Wuhan, Chinab Nuclear Power Simulation, China Nuclear Power Operation Technology Corporation, LTD, Wuhan, ChinaJournal of Nuclear Science and Technology11410.1080/00223131.2023.2294193https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2294193?af=RThermodynamic analysis and heat transfer optimization of the CRAFT NNBI calorimeter
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. <br/>. <br/>Thermodynamic analysis and heat transfer optimization of the CRAFT NNBI calorimeterdoi:10.1080/00223131.2023.2247406Journal of Nuclear Science and Technology2023-08-29T01:00:36ZNing TangChun-Dong HuYuan-Lai Xiea Department of Hefei Institutes of Physical Science, Chinese Academy of Sciences, University of Science and Technology of China, Hefei, P.R. Chinab Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, P.R. ChinaJournal of Nuclear Science and Technology11210.1080/00223131.2023.2247406https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2247406?af=RIrradiated mechanical properties predicted by a machine learning method with the Fourier-transform-based feature extension
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. <br/>. <br/>Irradiated mechanical properties predicted by a machine learning method with the Fourier-transform-based feature extensiondoi:10.1080/00223131.2023.2267044Journal of Nuclear Science and Technology2023-10-19T06:01:25ZYingxuan DongJunnan LvHong ZuoQun Lia State Key Laboratory for Strength and Vibration of Mechanical Structures, School of Aerospace, Xi’an Jiaotong University, Xi’an, Chinab Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu, ChinaJournal of Nuclear Science and Technology12010.1080/00223131.2023.2267044https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2267044?af=RDevelopment of extremely high-temperature X-ray absorption fine structure measurement method for oxide samples
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. <br/>. <br/>Development of extremely high-temperature X-ray absorption fine structure measurement method for oxide samplesdoi:10.1080/00223131.2023.2267560Journal of Nuclear Science and Technology2023-10-13T05:52:19ZKeisuke NiinoYuji AritaKenji KonashiHiromichi WatanabeTsuyoshi YaitaHajime TanidaTohru KobayashiKyoichi MorimotoMasashi WatanabeYusuke Miuraa Graduate School of Engineering, University of Fukui, Tsuruga, Japanb Research Institute of Nuclear Engineering, University of Fukui, Tsuruga, Japanc Institute for Materials Research, Tohoku University, Higashi-Ibaraki-gun, Japand Research Institute for Material and Chemical Measurement, National Institute of Advanced Industrial Science and Technology, Tsukuba, Japane Material Sciences Research Center, Japan Atomic Energy Agency, Sayo, Japanf Sector of Fast Reactor and Advanced Reactor Research and Development, Japan Atomic Energy Agency, Higashi-Ibaraki-gun, Japang Research Department Fuel Group, Nippon Nuclear Fuel Development Co. Ltd., Higashi-Ibaraki-gun, JapanJournal of Nuclear Science and Technology1710.1080/00223131.2023.2267560https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2267560?af=RThe development of Petri net-based continuous Markov chain Monte Carlo methodology applying to dynamic probability risk assessment for multi-state resilience systems with repairable multi-component interdependency under longtermly thereat
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. <br/>. <br/>The development of Petri net-based continuous Markov chain Monte Carlo methodology applying to dynamic probability risk assessment for multi-state resilience systems with repairable multi-component interdependency under longtermly thereatdoi:10.1080/00223131.2023.2290067Journal of Nuclear Science and Technology2023-12-09T06:39:49ZChun-Yen LiAkira WatanabeAkihiro UchiboriYasushi Okanoa Fast Reactor Life-Cycle Safety and Integrity Evaluation Technology Development Department, Japan Atomic Energy Agency, Ibaraki, Japanb Analysis System Department, NDD Corporation, Ibaraki, JapanJournal of Nuclear Science and Technology12310.1080/00223131.2023.2290067https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2290067?af=RThe effect of boron carbide doping content on the mechanical properties of polyethylene
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. <br/>. <br/>The effect of boron carbide doping content on the mechanical properties of polyethylenedoi:10.1080/00223131.2024.2305740Journal of Nuclear Science and Technology2024-01-29T02:07:27ZX. Q. PanY. WuS. Zhanga National Key Laboratory for Reactor Fuel and Materials, Nuclear Power Institute of China, Chengdu, Sichuan Province, Chinab School of Nuclear Science and Technology, Lanzhou University, Lanzhou, Gansu Province, ChinaJournal of Nuclear Science and Technology1810.1080/00223131.2024.2305740https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2305740?af=RThe relationship between human error and occupational stress of commissioning workers in nuclear power plants: the mediating effects of anxiety
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. <br/>. <br/>Isoplethal study of phase formation and morphology in uranium-304L steel via scanning electron microscopydoi:10.1080/00223131.2023.2252823Journal of Nuclear Science and Technology2023-09-19T10:11:32ZAndrew MiskowiecZachary E. BrubakerJenn NeuJ. L. NiedzielaLiam CollinsAlexander Braatza Nuclear Nonproliferation Division, Oak Ridge National Laboratory, Oak Ridge, TN, USAb Center for Nanophase Materials Analysis, Oak Ridge National Laboratory, Oak Ridge, TN, USAc Nuclear Nonproliferation R&D, Y-12 National Security Complex, Oak Ridge, TN, USAJournal of Nuclear Science and Technology11210.1080/00223131.2023.2252823https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2252823?af=RMutual separation of Am and Cm using ADAAM (alkyl DiAmide AMine) and reduction of volumes for liquid waste generated via batch-wise multistage extractions
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. <br/>. <br/>Mutual separation of Am and Cm using ADAAM (alkyl DiAmide AMine) and reduction of volumes for liquid waste generated via batch-wise multistage extractionsdoi:10.1080/00223131.2023.2283214Journal of Nuclear Science and Technology2023-11-20T03:18:59ZYuji SasakiMasashi KanekoYasutoshi BanHideya SuzukiSector of Nuclear Science Research, Japan Atomic Energy Agency, Tokai, JapanJournal of Nuclear Science and Technology11110.1080/00223131.2023.2283214https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2283214?af=RStudy on iodine adsorption capacity and adsorption mechanism of AgY
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. <br/>. <br/>Study on iodine adsorption capacity and adsorption mechanism of AgYdoi:10.1080/00223131.2023.2276397Journal of Nuclear Science and Technology2023-11-13T05:41:07ZCheng ZhangZexiang ChenJianrong HouHongzheng RenZhen WangXin LiYongguo LiHaixia KongHaifeng YuJie YuKey Laboratory of Nuclear Air Purification Technology, China Institute of Radiation Protection, Taiyuan, Shanxi, ChinaJournal of Nuclear Science and Technology11210.1080/00223131.2023.2276397https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2276397?af=RInvestigation of random beam trips in a linear accelerator at the Japan proton accelerator research complex for the development of an accelerator-driven nuclear transmutation system
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. <br/>. <br/>Investigation of random beam trips in a linear accelerator at the Japan proton accelerator research complex for the development of an accelerator-driven nuclear transmutation systemdoi:10.1080/00223131.2023.2296039Journal of Nuclear Science and Technology2024-01-09T12:38:07ZHayanori TakeiJ-PARC Center, Japan Atomic Energy Agency, Ibaraki, JapanJournal of Nuclear Science and Technology11410.1080/00223131.2023.2296039https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2296039?af=RInteraction of europium with calcium silicate hydrate under conditions saturated with groundwater
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. <br/>. <br/>Interaction of europium with calcium silicate hydrate under conditions saturated with groundwaterdoi:10.1080/00223131.2024.2307437Journal of Nuclear Science and Technology2024-01-30T08:56:04ZTaiji ChidaKengo SutoTsugumi SekiYuichi NiiboriGraduate School of Engineering, Tohoku University, Sendai-shi, JapanJournal of Nuclear Science and Technology11010.1080/00223131.2024.2307437https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2307437?af=RAnalytical studies on effects of wind on dispersion of hydrogen leaked in a partially open space
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. <br/>. <br/>Analytical studies on effects of wind on dispersion of hydrogen leaked in a partially open spacedoi:10.1080/00223131.2024.2302540Journal of Nuclear Science and Technology2024-01-22T01:45:51ZAtsuhiko TeradaRyuji NagaishiCollaborative Laboratories for Advanced Decommissioning Science Japan Atomic Energy Agency, Ibaraki, JapanJournal of Nuclear Science and Technology12010.1080/00223131.2024.2302540https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2302540?af=RResearch on the design of a radiation biodevice based on a compact D-D neutron generator
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. <br/>. <br/>Research on the design of a radiation biodevice based on a compact D-D neutron generatordoi:10.1080/00223131.2023.2276409Journal of Nuclear Science and Technology2023-11-09T05:37:50ZDapeng XuZhiqi GuoXu YangXiaohou BaiZhiming HuChangqi LiuJunrun WangYu ZhangZe’en Yaoa School of Nuclear Science and Technology, Lanzhou University, Lanzhou, Chinab Engineering Research Center for Neutron Application Technology, Ministry of Education, Lanzhou University, Lanzhou, ChinaJournal of Nuclear Science and Technology1810.1080/00223131.2023.2276409https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2276409?af=RNumerical study of initiating phase of core disruptive accident in small sodium-cooled fast reactors with negative void reactivity
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. <br/>. <br/>Numerical study of initiating phase of core disruptive accident in small sodium-cooled fast reactors with negative void reactivitydoi:10.1080/00223131.2023.2243949Journal of Nuclear Science and Technology2023-08-11T06:33:42ZShinya IshidaYoshitaka FukanoYoshiharu TobitaYasushi OkanoFast Reactor Cycle System Research and Development Center, Japan Atomic Energy Agency, Ibaraki, JapanJournal of Nuclear Science and Technology11310.1080/00223131.2023.2243949https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2243949?af=RSpatial evolution mechanism of vortex structure in the highly-loaded helium compressor cascade
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. <br/>. <br/>Spatial evolution mechanism of vortex structure in the highly-loaded helium compressor cascadedoi:10.1080/00223131.2023.2282550Journal of Nuclear Science and Technology2023-11-29T10:57:41ZKe SunZhitao TianYingqi FanHuawei LuJianchi Xina Marine Engineering College, Dalian Maritime University, Dalian, Liaoning, Chinab Naval Architecture & Ocean Engineering College, Dalian Maritime University, Dalian, Liaoning, ChinaJournal of Nuclear Science and Technology11510.1080/00223131.2023.2282550https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2282550?af=RHigh-efficient removal of tungsten from hafnium by TOA/XAD-7 extraction resin from HCl-HF media
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. <br/>. <br/>High-efficient removal of tungsten from hafnium by TOA/XAD-7 extraction resin from HCl-HF mediadoi:10.1080/00223131.2023.2257225Journal of Nuclear Science and Technology2023-09-13T01:32:49ZJinlong FanYufeng WangLi DuanXiangbo ZhangGuowei ChenPengju QiuGongshuo YuNorthwest Institute of Nuclear Technology, Xi’an, Shaanxi, ChinaJournal of Nuclear Science and Technology1810.1080/00223131.2023.2257225https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2257225?af=RHuman reliability analysis of shared equipment in multi-unit site
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. <br/>. <br/>Human reliability analysis of shared equipment in multi-unit sitedoi:10.1080/00223131.2023.2300304Journal of Nuclear Science and Technology2024-01-04T01:04:02ZWanxin FengJinkai WangZhixin XuMing WangLi WenYu YuZecong Lia State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Engineering Co., Ltd., Shenzhen, Chinab Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy, North China Electric Power University, Beijing, ChinaJournal of Nuclear Science and Technology1910.1080/00223131.2023.2300304https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2300304?af=RNumerical analysis of flow-induced deflection of curved nuclear reactor fuel plates under high velocity flows
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. <br/>. <br/>Numerical analysis of flow-induced deflection of curved nuclear reactor fuel plates under high velocity flowsdoi:10.1080/00223131.2024.2307430Journal of Nuclear Science and Technology2024-02-01T07:55:16ZJunwen ZhengXiaoxin WangLi ShiWenli GuoQin ZhouInstitute of Nuclear and New Energy Technology, Tsinghua University, Beijing, ChinaJournal of Nuclear Science and Technology11510.1080/00223131.2024.2307430https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2307430?af=RDesign of moderator and collimator based on compact D-T neutron source for neutron imaging
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. <br/>. <br/>Design of moderator and collimator based on compact D-T neutron source for neutron imagingdoi:10.1080/00223131.2024.2310573Journal of Nuclear Science and Technology2024-02-12T06:04:32ZHao ChenShuang QiaoChenyi ZhaoTian ZhangXiangyu Yaoa School of Physics, Northeast Normal University, Changchun, Chinab Instrumentation Business Unit, China Nuclear (Beijing) Nuclear Instrument Co, Ltd, Beijing, Chinac Department of Engineering Physics, Tsinghua University, Beijing, ChinaJournal of Nuclear Science and Technology1710.1080/00223131.2024.2310573https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2310573?af=RNumerical study of turbulent heat transfer of annular fuel assembly in a sodium-cooled fast reactor by a SST k-ω-kθ-εθ model
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. <br/>. <br/>Numerical study of turbulent heat transfer of annular fuel assembly in a sodium-cooled fast reactor by a SST k-ω-kθ-εθ modeldoi:10.1080/00223131.2024.2310563Journal of Nuclear Science and Technology2024-02-12T06:05:05ZYuefeng GuoXingkang SuGuan WangXianwen LiLong Gua School of Nuclear Science and Technology, Lanzhou University, Lanzhou, Chinab Chinese Academy of Sciences, Institute of Modern Physics, Lanzhou, Chinac School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing, ChinaJournal of Nuclear Science and Technology11610.1080/00223131.2024.2310563https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2310563?af=RExperiences from the cutting of metallic blocks from simulant Fukushima Daiichi fuel debris
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. <br/>. <br/>Experiences from the cutting of metallic blocks from simulant Fukushima Daiichi fuel debrisdoi:10.1080/00223131.2024.2310580Journal of Nuclear Science and Technology2024-02-14T01:33:23ZC. JourneauD. MolinaE. BrackxR. BerlemontY. Tsubotaa Severe Accident Experimental Laboratory, CEA, DES, IRESNE, DTN, SMTA, Cadarache, Franceb Sodium Technology and Advanced Coolant Laboratory, CEA, DES, IRESNE, DTN, STCP, Cadarache Francec CEA, DES, ISEC, DMRC, Univ Montpellier, Marcoule, Franced Process Engineering Department, ONET Technologies, Pierrelatte, Francee International Research Institute for Nuclear Decommissioning (IRID)/Japan Atomic Energy Agency (JAEA), CLADS, Ibaraki, JapanJournal of Nuclear Science and Technology1910.1080/00223131.2024.2310580https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2310580?af=RA study on the fracture pattern change of high-burnup fuel cladding failed by pellet-cladding mechanical interaction failure under reactivity-initiated accident conditions
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. <br/>. <br/>A study on the fracture pattern change of high-burnup fuel cladding failed by pellet-cladding mechanical interaction failure under reactivity-initiated accident conditionsdoi:10.1080/00223131.2024.2313553Journal of Nuclear Science and Technology2024-02-16T06:47:43ZFeng LiTakeshi MiharaYutaka UdagawaNuclear Safety Research Center, Japan Atomic Energy Agency, Ibaraki JapanJournal of Nuclear Science and Technology11110.1080/00223131.2024.2313553https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2313553?af=RActivation level of the concrete building and pressure vessel in JAEA-Tokai tandem accelerator
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. <br/>. <br/>Activation level of the concrete building and pressure vessel in JAEA-Tokai tandem acceleratordoi:10.1080/00223131.2024.2313558Journal of Nuclear Science and Technology2024-02-19T01:11:55ZGo YoshidaHiroshi MatsumuraHajime NakamuraTaichi MiuraAkihiro ToyodaKazuyoshi MasumotoTakayuki NakabayashiMakoto Matsudaa Radiation Science Center, High Energy Accelerator Research Organization (KEK), Tsukuba-Ibaraki, Japanb Radiation Facilities Decommissioning Division, Japan Radioisotope Association, Bunkyo-ku, Tokyo, Japanc Tandem accelerator research devision, Japan Atomic Energy Agency, Tokai-Ibaraki, JapanJournal of Nuclear Science and Technology11010.1080/00223131.2024.2313558https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2313558?af=RHigh temperature electrochemical reaction parameters affecting electrochemical corrosion potential of nickel-base Alloy 82 weld metal
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. <br/>. <br/>High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of nickel-base Alloy 82 weld metaldoi:10.1080/00223131.2024.2317225Journal of Nuclear Science and Technology2024-02-20T06:57:19ZYoichi WadaHikari MurotaniKazushige IshidaMayu SasakiMakoto NagaseRyosuke ShimizuShinobu Okidoa Nuclear energy systems research department, Decarbonized Energy Innovation Center Hitachi Ltd, Hitachi, Japanb Nuclear plant engineering department, Hitachi Works Hitachi-GE Nuclear Energy Ltd, Hitachi, JapanJournal of Nuclear Science and Technology11210.1080/00223131.2024.2317225https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2317225?af=RUncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks
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. <br/>. <br/>Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networksdoi:10.1080/00223131.2024.2310564Journal of Nuclear Science and Technology2024-02-22T01:55:15ZElvan SahinBrian LattimerMohammad Amer AllafJuliana Pacheco Duartea Mechanical Engineering, Virginia Polytechnic Institute and State University, Blacksburg, VA, USAb Nuclear Engineering and Engineering Physics, University of Wisconsin-Madison, Madison, WI, USAJournal of Nuclear Science and Technology11410.1080/00223131.2024.2310564https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2310564?af=RThe effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatment
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. <br/>. <br/>The effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatmentdoi:10.1080/00223131.2024.2318042Journal of Nuclear Science and Technology2024-02-27T01:49:03ZJiaqin WeiWenhong HanGuilin WeiXiaoyan ShuBeilong YuanJiahong WangXirui Lua Anhui Province Engineering Laboratory for Mine Ecological Remediation, Anhui University, Hefei, PR Chinab State Key Laboratory of Environmental Friendly Energy Materials, Southwest University of Science and Technology, Mianyang, PR Chinac Collaborative Innovation Center of Nuclear Wastes and Environmental Safety, Southwest University of Science and Technology, Mianyang, PR Chinad Tianfu Institute of Research and Innovation, Southwest University of Science and Technology, Chengdu, ChinaJournal of Nuclear Science and Technology1910.1080/00223131.2024.2318042https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2318042?af=RBayesian statistical model for cladding high-temperature burst under loss-of-coolant accident conditions
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. <br/>. <br/>Bayesian statistical model for cladding high-temperature burst under loss-of-coolant accident conditionsdoi:10.1080/00223131.2024.2321342Journal of Nuclear Science and Technology2024-02-29T12:59:43ZYudai TasakiTakafumi NarukawaYutaka Udagawaa Nuclear Safety Research Center, Japan Atomic Energy Agency, Ibaraki, Japanb Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, Tokyo, JapanJournal of Nuclear Science and Technology11110.1080/00223131.2024.2321342https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2321342?af=RMolecular dynamics simulation study of the effect of Ce4+ incorporation at Zr site on the threshold displacement energy in Y4Zr3O12 material
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. <br/>. <br/>Molecular dynamics simulation study of the effect of Ce4+ incorporation at Zr site on the threshold displacement energy in Y4Zr3O12 materialdoi:10.1080/00223131.2024.2320792Journal of Nuclear Science and Technology2024-03-04T12:38:20ZMohammed AdoQingyu WangShehu Adam IbrahimSimon Ochieng AdedeYushou SongIbrahim Alfasatleha Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University, Harbin, Chinab Nigerian Nuclear Regulatory Authority (NNRA), Abuja, Nigeriac Department of Science Laboratory Technology, Binyaminu Usman Polytechnic, Hadejia, Jigawa State, Nigeriad Xi’an Jiatong University, Xi’an, Chinae School of Chemistry and Material Science, Technical University of Kenya, Nairobi, Kenyaf Jordan Atomic Energy Commission, Amman, JordanJournal of Nuclear Science and Technology1810.1080/00223131.2024.2320792https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2320792?af=RApplication of the spectral determination method to liquid scintillation spectra
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. <br/>. <br/>Application of the spectral determination method to liquid scintillation spectradoi:10.1080/00223131.2023.2282552Journal of Nuclear Science and Technology2023-11-26T05:20:40ZMasumi OshimaJun GotoTakehito HayakawaHirofumi ShinoharaKatsuyuki SuzukiYuichi SanoMasato AsaiTomoko Haragaa Japan Chemical Analysis Center, Chiba, Japanb NAT Co Ltd, Tokai, Naka, Ibaraki, Japanc Institute for Research Administration, Niigata University, Niigata, Japand Kansai Photon Science Institute, National Institutes for Quantum and Radiological Science and Technology, Kyoto, Japane Institute of Laser Engineering, Osaka University, Suita, Osaka, Japanf Nuclear Science Research Institute, Japan Atomic Energy Agency, Tokai, Naka, Ibaraki, JapanJournal of Nuclear Science and Technology11210.1080/00223131.2023.2282552https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2282552?af=RExperimental investigations on flow-induced vibration characteristics of fuel rod with an independent channel for small lead-based reactor
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. <br/>. <br/>Experimental investigations on flow-induced vibration characteristics of fuel rod with an independent channel for small lead-based reactordoi:10.1080/00223131.2024.2324003Journal of Nuclear Science and Technology2024-03-07T03:48:04ZGuowei YangYong ZhangYong SongTiandi FanJianwei ChenYunqing Baia Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei, Chinab University of Science and Technology of China, Hefei, Chinac International Academy of Neutron Science, Qingdao, Chinad National Institute of Neutronic Energy Co. Ltd, Qingdao, Chinae Shandong Key Laboratory of Neutron Science and Technology, Qingdao, Chinaf Institute of Nuclear Science and Technology, Shandong University, Jinan, ChinaJournal of Nuclear Science and Technology11410.1080/00223131.2024.2324003https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2324003?af=RDetailed visualization of radioactive hotspots inside the unit 1 reactor building of the Fukushima Daiichi Nuclear Power Station using an integrated Radiation Imaging System mounted on a Mecanum wheel robot
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. <br/>. <br/>Detailed visualization of radioactive hotspots inside the unit 1 reactor building of the Fukushima Daiichi Nuclear Power Station using an integrated Radiation Imaging System mounted on a Mecanum wheel robotdoi:10.1080/00223131.2023.2282551Journal of Nuclear Science and Technology2023-12-04T01:34:16ZYuki SatoYuta TerasakaMasatoshi Ouraa Collaborative Laboratories for Advanced Decommissioning Science, Japan Atomic Energy Agency, Fukushima, Japanb Fukushima Daiichi Decontamination and Decommissioning Engineering Company, Tokyo Electric Power Company Holdings, Inc, Fukushima, JapanJournal of Nuclear Science and Technology11510.1080/00223131.2023.2282551https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2282551?af=RRare earth elements and radioactive elements in black sands from the Konkan and Malabar coasts of India
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. <br/>. <br/>Rare earth elements and radioactive elements in black sands from the Konkan and Malabar coasts of Indiadoi:10.1080/00223131.2023.2234366Journal of Nuclear Science and Technology2024-03-19T11:57:23ZV. K. ShuklaAbhishek Kr RaiS. DubeyR. KumarP. K. ShahiN. RaiA. K. Raia Department of Physics, University of Allahabad, Prayagraj Indiab Department of Earth and Planetary Science, University of Allahabad, Prayagraj, Indiac Department of Physics, C. M.P. Degree College, University of Allahabad, Prayagraj, Indiad Department of Physics, S. P. M. Government Degree College, University of Allahabad, Prayagraj, Indiae Department of Earth Sciences, Indian Institute of Technology, Roorkee, IndiaJournal of Nuclear Science and Technology11710.1080/00223131.2023.2234366https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2234366?af=RApplication of new axial power distribution synthesis method using in-core detector signal in digital core protection system
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. <br/>. <br/>Application of new axial power distribution synthesis method using in-core detector signal in digital core protection systemdoi:10.1080/00223131.2024.2329575Journal of Nuclear Science and Technology2024-03-22T08:48:28ZWook LeeKyung Woo ShimDong Su KimByung Chan Baeka COLSS/CPCS Design Section, KEPCO Nuclear Fuel Co Ltd, Daejeon, Republic of Koreab Design Quality Licensing Section, KEPCO Nuclear Fuel Co Ltd, Daejeon Republic of KoreaJournal of Nuclear Science and Technology11110.1080/00223131.2024.2329575https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2329575?af=RHeat of transport for hydrogen and hydrides in Zircaloy
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. <br/>. <br/>Heat of transport for hydrogen and hydrides in Zircaloydoi:10.1080/00223131.2024.2319285Journal of Nuclear Science and Technology2024-03-22T08:50:26ZG. A. McRaeC. E. ColemanMechanical and Aerospace Engineering, Carleton University, Ottawa, CanadaJournal of Nuclear Science and Technology11210.1080/00223131.2024.2319285https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2319285?af=RA study on the establishment of database for local government disaster response and decision support system in the nuclear accidents
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. <br/>. <br/>A study on the establishment of database for local government disaster response and decision support system in the nuclear accidentsdoi:10.1080/00223131.2023.2290713Journal of Nuclear Science and Technology2023-12-14T06:48:44ZSeunghyeon KimMinho ChaYounwon ParkMinsang RyuSooyeun ParkKyeongil AhnWonjo KimHaeyeol Gonga New-Tech, BEES, Inc, Daejeon, Republic of Koreab Development, BARON SYSTEM, Inc, Daejeon, Republic of Koreac Ulju County Office, Dept. Energy Policy, Guncheong-ro, Cheongnyang-eup, Ulju-gun, Ulsan, Republic of KoreaJournal of Nuclear Science and Technology11710.1080/00223131.2023.2290713https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2290713?af=RA simulation research on thermal-pressure coupling loading of a 1:3.2 containment model
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. <br/>. <br/>A simulation research on thermal-pressure coupling loading of a 1:3.2 containment modeldoi:10.1080/00223131.2024.2305739Journal of Nuclear Science and Technology2024-02-01T12:01:42ZXuze ZhaoDi YaoJingwei GaoJianyu TanXiaowen Haoa School of New Energy, Harbin Institute of Technology, Weihai, Shandong, Chinab Advanced Nuclear Energy Technology Research Institute, China Nuclear Power Engineering Co. Ltd, Beijing, ChinaJournal of Nuclear Science and Technology11410.1080/00223131.2024.2305739https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2305739?af=RThe effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment
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. <br/>. <br/>The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessmentdoi:10.1080/00223131.2024.2313551Journal of Nuclear Science and Technology2024-02-19T01:07:14ZKodai WadayamaRetsu KojoTamon NiisoeRegulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R), Tokyo, JapanJournal of Nuclear Science and Technology11710.1080/00223131.2024.2313551https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2313551?af=RA new separation method of hydrogen isotope by dynamically created nonequilibrium state
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. <br/>. <br/>A new separation method of hydrogen isotope by dynamically created nonequilibrium statedoi:10.1080/00223131.2023.2284765Journal of Nuclear Science and Technology2023-11-21T03:20:59ZTakashi YabeTakayoshi NorimatsuKohei YamanoiFeng Xiaoa Department of Mechanical Engineering, Tokyo Institute of Technology, Tokyo, Japanb Institute of Laser Engineering, Osaka University, Suita, JapanJournal of Nuclear Science and Technology1410.1080/00223131.2023.2284765https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2284765?af=RA review on failure behavior and life prediction of circulation pumps in lead-bismuth eutectic cooled reactors
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. <br/>. <br/>A review on failure behavior and life prediction of circulation pumps in lead-bismuth eutectic cooled reactorsdoi:10.1080/00223131.2023.2295440Journal of Nuclear Science and Technology2023-12-28T11:29:24ZFan WangFei XiaoMa WenshengTianzhou WangTao Wanga Chongqing Pump Industry Co. Ltd, Chongqing, Chinab School of Power and Energy Engineering, Harbin Engineering University, Harbin, Chinac Huanxiling Oil Production Plant, Panjin, ChinaJournal of Nuclear Science and Technology11710.1080/00223131.2023.2295440https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2295440?af=RExperimental techniques for investigating thermal transport in nuclear materials
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. <br/>. <br/>Experimental techniques for investigating thermal transport in nuclear materialsdoi:10.1080/00223131.2024.2332781Journal of Nuclear Science and Technology2024-03-28T07:08:12ZYuzhou WangYaoyang ZhangQiang ZhangFei ZhuVinay ChauhanMarat KhafizovXianfeng MaZhenqi Changa Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Zhuhai, Guangdong, Chinab Technology Development, Intel Corporation, Chandler, AZ, USAc Department of Mechanical and Aerospace Engineering, The Ohio State University, Columbus, OH, USAd School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, Anhui, ChinaJournal of Nuclear Science and Technology12110.1080/00223131.2024.2332781https://www.tandfonline.com/doi/full/10.1080/00223131.2024.2332781?af=RApplicability of the kernel method for macroscopic cross section tabulation to planar MOC-based core transient analysis code
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. <br/>. <br/>Applicability of the kernel method for macroscopic cross section tabulation to planar MOC-based core transient analysis codedoi:10.1080/00223131.2023.2252432Journal of Nuclear Science and Technology2023-09-11T04:50:50ZTatsuya FujitaRegulatory Standard and Research Department, Nuclear Regulation Authority, Tokyo, JapanJournal of Nuclear Science and Technology11410.1080/00223131.2023.2252432https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2252432?af=RDevelopment of nuclear data processing code FRENDY version 2
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. <br/>. <br/>Development of nuclear data processing code FRENDY version 2doi:10.1080/00223131.2023.2278600Journal of Nuclear Science and Technology2023-11-13T12:35:16ZKenichi TadaAkio YamamotoSatoshi KuniedaChikara KonnoRyoichi KondoTomohiro EndoGo ChibaMichitaka OnoMasayuki Tojoa Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Tokai-mura, Ibaraki, Japanb Graduate School of Engineering, Nagoya University, Chikusa-ku, Nagoya, Japanc Graduate School of Engineering, Hokkaido University, Sapporo, Japand Global Nuclear Fuel-Japan Co, Ltd, Yokosuka-shi, Kanagawa, JapanJournal of Nuclear Science and Technology11010.1080/00223131.2023.2278600https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2278600?af=RBasic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant
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. <br/>. <br/>Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plantdoi:10.1080/00223131.2023.2258880Journal of Nuclear Science and Technology2023-09-24T08:10:45ZYukihisa SanadaTomohisa AbeMiyuki SasakiMarina KannoTsutomu YamadaTakamasa NakasoneNobuyuki MiyazakiKeisuke OshikiriHiroshi Watabea Sector of Fukushima Research and Development, Japan Atomic Energy Agency, Minamisoma, Japanb PESCO Co. Ltd, Minato-ku, Tokyo, Japanc Japan Radiation Engineering Co. Ltd, Hitach, Japand Clear-Pulse Co. Ltd, Tokyo, Japane Nippon RayTech Co. Ltd,Musashino-shi, Tokyo, Japanf Cyclotron and Radioisotope Center, Tohoku University, Sendai, JapanJournal of Nuclear Science and Technology11010.1080/00223131.2023.2258880https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2258880?af=RMonte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO2 and BWR-MOX fuels in the RUBUS program
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. <br/>. <br/>Monte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO2 and BWR-MOX fuels in the RUBUS programdoi:10.1080/00223131.2023.2290068Journal of Nuclear Science and Technology2023-12-06T12:11:25ZToru YamamotoNuclear Engineering Consultant, Kanazawa-ku, Yokohama JapanJournal of Nuclear Science and Technology11810.1080/00223131.2023.2290068https://www.tandfonline.com/doi/full/10.1080/00223131.2023.2290068?af=R