Journal of Nuclear Science and Technology

Papers
(The median citation count of Journal of Nuclear Science and Technology is 1. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2022-06-01 to 2026-06-01.)
ArticleCitations
Experimental and numerical simulation study on the combustion characteristics of nuclear-grade activated carbon388
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids354
Cesium immobilization from aqueous solution by struvite synthesis18
The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations18
Evaluation of 60 Co inventory in the core of the Fukushima Daiichi Nuclear Power Plant – contribution of fuel deposits to the reactor core inventory14
JENDL photonuclear data file 201613
Development of a new method for simultaneous monitoring of criticality and nuclear material security/accountancy in a multiplicative system13
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique13
A new separation method of hydrogen isotope by dynamically created nonequilibrium state12
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel12
Effect of part-length rod arrangement on vapor redistribution in 5 × 5 rod bundle with high-energy X-ray CT measurement12
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations12
Study on response surface method to optimize radioactive resin degradation by microwave-assisted Fenton reaction11
Radioactivation analysis of a concrete wall in a high-energy electron accelerator facility11
Advances in the interfacial interactions and decontamination strategies of radionuclides on cement surfaces: a review11
Radio-tellurium released into the environment during the complete oxidation of fuel cladding, containment venting and reactor building failure of the Fukushima accident11
Sodium science and technology training at Indian sodium school11
EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-24210
Study on criticality uncertainties of MCCI products due to concrete compositions10
Exploration of the mechanism of controllable decomposition of polyurethane based on carbonate molten salt10
Correction10
Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations9
Startup core design of metallic-fueled lead-bismuth eutectic-cooled rotational fuel-shuffling breed-and-burn fast reactor9
Sorption of Cs + and Eu 3+ onto coherent and melange-type pre-neogene sedimentary rocks9
Discrimination of disposal-restricted materials in waste containers by nondestructive testing and image analysis with high-energy X-ray computed tomography9
Basic research on estimation of contamination of internal surface of spent nuclear fuel transport casks by Lasso regression9
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O28
Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages8
Absolute quantification of 137Cs activity in spent nuclear fuel with calculated detector response function8
Transient parameter prediction and fault diagnosis for nuclear power plants based on machine learning8
Study on iodine adsorption capacity and adsorption mechanism of AgY8
Exploratory study of nuclear magnetic resonance well logging technology on the hydrogeological characteristics of deep geological formations8
Thermal performance analysis of molten salt in transversely grooved tube for nuclear reactor7
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates7
A simulation study of hypervelocity jet underwater: physical protection design of offshore floating nuclear power plant against light torpedo threats7
Leaching behavior of arsenic and selenium in coal fly ash by aging treatment and cement mixing7
Development of an ultra-fast dynamic time-over-threshold system with a 30 ps timing resolution7
Deterministic sampling method using simplex ensemble and scaling method for efficient and robust uncertainty quantification7
Development of ACE file perturbation tool using FRENDY7
The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment6
Clarification of key input parameters for site boundary dose due to criticality of fuel debris at the Fukushima Daiichi nuclear power plant6
Measurement of the thermal neutron capture-cross section of 191 Ir at ANNRI MLF J-PARC6
Development of an integrated non-destructive analysis system, Active-N6
Urinary stone component identification by energy-resolved X-ray computed tomography6
Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow6
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 wheel5
Irradiation hardening and void swelling behaviors of F82H IEA by using dual-ion irradiation5
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environment5
Sensitivity analysis of risk assessment for continuous Markov process Monte Carlo method using correlated sampling method5
Estimation of temporal variation of tritium inventory discharged from the port of Fukushima Dai-ichi Nuclear Power Plant:analysis of the temporal variation and comparison with released tritium invento5
Modeling of vapor mass formation under forced convective boiling condition5
Power distribution re-construction based on the PHOEBE method using the method of characteristics code ‘GENESIS’5
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy5
A level 2 site risk assessment for internal event and seismic event: a case study5
Measurement of the water-vapor void fraction in a 4x4 unheated rod bundle5
Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis5
A TOF spectrometer for neutron spectral measurements in a wide energy range base on a fast ionization chamber containing 6Li-235U5
Design and experimental analysis of a nuclear fuel rod enrichment detection system5
Verification of direct coupling code system using FRENDY version 2 and GENESIS for light water reactor lattices5
Correction5
Ensuring a prudent combination of risk insights and a defense-in-depth philosophy through a reinterpretation of hierarchical safety goals5
ACE-FRENDY-CBZ: a new neutronics analysis sequence using multi-group neutron transport calculations5
Physics-guided machine learning recovers Archie-type scaling and interlayer diffusion mechanisms for sodium transport in compacted bentonite buffers5
A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries5
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.335
Simple technique for the preparation of uranium-impregnated porous silica particles and their application as working standard particles for analysis of the safeguards environmental samples5
Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy5
Performance evaluation for rapid-dose estimation of radioactive plume dispersion based on pre-simulation database of wind conditions by large-eddy simulation5
Redistribution of elements in simulated high-level waste glass with aggregation of platinum group elements5
Numerical simulation of bubble hydrodynamics for pool scrubbing4
Enhancement of random sampling by a combined approach of control variates and Latin hypercube sampling for uncertainty quantification in light water reactor lattice calculations4
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions4
Research on the powderization treatment of uranium-zirconium solid solution simulated nuclear fuel debris using thermochemical redox reaction4
Measurement and simulations of high-energy neutrons through a various thickness of concrete and steel shields using activation detectors at CHARM and CSBF4
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments4
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator4
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model4
Experimental techniques for investigating thermal transport in nuclear materials4
Gamma-ray irradiation induced dislocation loops in hexagonal zirconium4
Experimental research and transient modeling of aerosol transport considering re-entrainment effects in turbulent horizontal circular pipe flow4
Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector4
Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons4
Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K4
Uncertainty analysis for fission product inventories based on covariance data of fission product yields in JENDL-4.0 and ENDF/B-VIII.04
Study on key technical issues of accident selection in emergency planning zone development for small modular reactors4
Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system4
CFD simulation of the XR2-1 experiment with the JUPITER code4
Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility4
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure4
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level4
A finite element analysis study on the fracture pattern change of fuel cladding under PCMI loading conditions4
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning4
Radiation imaging of a highly contaminated filter train inside Fukushima Daiichi Nuclear Power Station unit 2 using an integrated Radiation Imaging System based on a Compton camera4
Solubility of FeSe2(cr) at 318 K in the presence of iron4
Effects of correlations in uncertainties of total cross section and elastic angular distribution for a deep penetration of 14-MeV neutrons in Cu4
Experimental investigation of spray cooling behavior in 4×4 simulated fuel bundle4
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): 58 Fe(n,γ) 59 Fe4
Novel concept for a filtered containment venting system with an ionic liquid to remove organic iodine (1)-proof of concept for organic iodine removal4
Effect of temperature on radiolytically generated hydrogen yield from actual nuclear fuel-derived solution4
Research on nonlinear generalized predictive control method for reactor core power based on parameter identification4
Computer code analysis of irradiation performance of an annular mixed oxide fuel element3
Development of a simple calculation method for the conductance of rarefied gas flow in cylindrical pipe applicable to divertor exhaust investigation of nuclear fusion reactor3
Validation of self-adjoint angular flux neutron transport code with TAKEDA benchmark3
Measurement of the neutron capture cross section of 185 Re in the keV energy region3
Sub-pin level distribution tallies and statistical error estimation with POD tallies in two-dimensional C5G7 benchmark3
Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel3
The effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatment3
Evaluation method of hydrogen generation rate by water radiolysis in fuel debris canisters considering the radiation energy absorption rate of water dependence on particle size3
Measurement of neutron spectra for various thicknesses of concrete and steel shielding at 24-GeV/c proton beam facility using Bonner sphere spectrometer3
Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant3
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH3
A spurious-count effect observed in Rossi-α and Feynman-α analysis using fission counter for Kyoto University Reactor3
Experimental and numerical studies of backflow aerosol leakage from an enclosure under dynamic confinement due to internal flow perturbations3
Status of the 226 Ra nuclear data library and its impact on the production amount of 225 Ac via th3
Fretting wear behavior test and numerical simulation of Inconel 690 alloy3
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor3
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (III): 170 Er(n,γ) 171 3
Comparison of cost-reduced computational methods for nuclide transmutation problems3
Continuous-Time Markov Chain-based examination of safeguards- and security-by-design of nuclear reactors3
Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform3
Experiences from the cutting of metallic blocks from simulant Fukushima Daiichi fuel debris3
Integrating DeblurGAN and CNN to improve the accuracy of motion blur X-Ray image classification3
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks3
Nuclear data adjustment using a deterministic sampling method with unscented transformation3
Subcooled forced convection boiling on a vertical surface and gas-liquid structure near the heat transfer surface3
Development of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithm3
Impact of MOX fuel use in light-water reactors: long-term radiological consequences of disposal of high-level waste in a geological repository3
JENDL-5 benchmarking for fission reactor applications3
YouTube-based topic modeling and large language model sentiment analysis of Japanese online discourse on nuclear energy2
Applicability of differential die-away self-interrogation technique for quantification of spontaneous fission nuclides for fuel debris at Fukushima Daiichi Nuclear Power Plants2
Study on corrosion of T-22 alloy under high temperature condition of VHTR2
Gamma-ray radiation-induced modifications in the optical, fluorescence, and dielectric behavior of PM-355 nuclear detector films2
Monte Carlo-informed reliability and availability framework for innovative inspection timelines: a case study of the PA01-BC01 heat exchanger2
Fractal characteristics of radioactive contaminant transport in porous media: critical porosity threshold analysis2
Diffusion of Cs + , I and HDO onto pre-Neogene sedimentary rocks2
Dynamic performance analysis of a new low-temperature nuclear heating system with APROS2
Establishing an evaluation method for the aging phenomenon by physical force in fuel debris2
Revised neutron capture cross section of 204 Pb by combining activation method and high-precision thermal ionization mass spectrometry2
Development of integrated FEPs for safety case scenario development2
Correction2
Treatment of corner crossing ray-traces in CMFD acceleration of MOC2
Simulated performance evaluation of d-Be compact fast neutron source2
Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C2
Enhancing magnetohydrodynamic performance of liquid metal with solid insulating powders for fusion reactor applications2
A novel strategy for iodine removal from nuclear reactor accidental gases: Efficient adsorption of CH 3 I on the moderately hydrophobic modified silver-loaded zeolit2
Development of general purpose neutronics analysis code GenesisRPC and its verification for light water reactor lattices2
Experimental study on design optimization of the core catcher for the CEFR2
A membrane, pseudo-vertical p-i-n diamond detector2
Reactor antineutrinos and novel application to real-time remote monitoring of nuclear reactors2
Development of glass gas electron multiplier-based pulse counting imaging system with FPD front-end electronics2
Multi-scenario validation and parameter sensitivity of the GPU-QES dispersion model under local-scale wind tunnel experiments at a nuclear power plant site2
Hybrid data assimilation methods for nuclear-data-induced uncertainties2
EXFOR-based simultaneous evaluation for fast neutron-induced fission cross section of thorium-2322
Alteration of fuel debris simulants by Bacillus subtilis2
Role of solute titanium and oxidation in cesium chemisorption onto stainless steel2
Development of Internal Dose Calculation Code (IDCC)2
Formation of Ni 3 S 2 from the reactions between Ni and seawater-derived MgSO 2
Data processing and visualization of X-ray computed tomography images of a JOYO MK-III fuel assembly2
HHT-based investigation on the two-phase flow regime in the mixer for a nuclear-coupled liquid metal MHD power generation system2
Monte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO 2 and BWR-MOX fuels in the RUBUS program2
Reactor reactivity calculations with simplified-P3 and perturbation theories2
Applicability of the kernel method for macroscopic cross section tabulation to planar MOC-based core transient analysis code2
Development of a theoretical scaling factor method for the inventory estimation of difficult-to-measure nuclide Cs-135 in fuel debris and radioactive wastes2
Benchmark specifications of TCA critical experiments for validation of thermal scattering laws of water2
A study on the establishment of database for local government disaster response and decision support system in the nuclear accidents2
Technical research on rapid source term calculation and prediction technology of nuclear accidents based on Bayesian network2
Calculations and analysis of n+ 52 Cr reactions below 20 MeV2
Physics-based method for generating probability table using random-matrix approach2
Correction2
Bayesian approach to energy dependence of fission product yields of 235 U by data augmentation2
Verification of in-core power distribution reconstruction based on POD for high-temperature gas-cooled reactors using ex-core detectors2
Modeling axial void fraction profile for subcooled boiling flow in rod bundles under atmospheric to high-pressure conditions2
Corrosion behavior of zirconium alloys in the aqueous environment. Phenomenological aspects. Overview2
Diffusion and sorption of Cs in the mudstone matrix at the Horonobe URL: comparative experimental and modeling analysis between in situ and laboratory conditions2
Heat of transport for hydrogen and hydrides in Zircaloy2
An automatic defects detection system for nuclear fuel pellets end face based on deep learning and structured light2
Design and development of the machine protection system for HIAF2
High-efficient removal of tungsten from hafnium by TOA/XAD-7 extraction resin from HCl-HF media2
Cohesive/Adhesive strengths of CsOH-chemisorbed SS304 surfaces2
Radiation-induced amorphization behavior of thermally-aged M23C6 in F82H-BA12 steel2
Preface to a special issue of journal of nuclear science and Technology on “Nuclear Data and Code Systems as a Basis of Nuclear Technology”2
Irradiation behavior of HfNbTaTiV in comparison of HfNbTaTiZr and F82H2
Water-leaching behavior for cesium chemisorbed on stainless steel at room temperature2
Degradation of nuclear fuel debris analog by siderophore-releasing microorganisms2
Evaluation of influence of wall roughness on wall turbulence using LES simulation with MSGD model for liquid Li flow inside two-staged contraction nozzle2
Molecular dynamics simulation study of the effect of Ce 4+ incorporation at Zr site on the threshold displacement energy in Y 4 Zr2
Passive fast neutron multiplicity counting system based on a symmetric spherical design1
Predictive accuracy of neutronics of light-water-moderated and graphite-reflected core with low-enriched uranium fuel at UTR-KINKI1
A novel Compton camera with an annular absorber for enhancing the imaging efficiency in regions directly ahead: A simulation study1
Simulation using representative data selection for transboundary radiation effect evaluation by Nuclear Accident Consequence Analysis Code (NACAC)1
Accurate measurement of the 129 I neutron capture cross-section in the keV neutron region1
Numerical simulation method using a Cartesian grid for oxidation of core materials under steam-starved conditions1
Development of nuclear de-excitation model EBITEM Ver.21
Optimization of BP neural network for fault parameter prediction in nuclear power plants utilizing the firefly algorithm1
Extraction behaviors of minor actinides and rare earth elements with NTA amide extractants1
Redistribution of Nb and other alloying elements in Nb-doped Zr alloy under high dose ion irradiation1
A scattered X-ray correction method for transmission measurements and its verification using energy-resolved computed tomography1
Hot zone formation in combustion tests simulating solvent fires in reprocessing plants – concerns on boilover phenomenon1
Development of an in-situ mechanical property identification system for use in high radiation fields1
Request for 35 Cl(n,p) reaction cross-section measurements and re-evaluations from the standpoint of molten chloride salt fast reactor design1
Reduced order SP 3 core calculation based on local/global iterations using proper orthogonal decomposition1
Thermal diffusivity of composite pellets with aligned Mo microplates1
Development of neutron self-indication thermometry at J-PARC1
Correction1
Regeneration of TEHDGA-impregnated adsorbents via solvent stripping and re-impregnation for application in extraction chromatography-based MA(III) separation1
Criticality evaluation considering nonuniformity effect using Monte Carlo perturbation method1
Numerical simulation of the fluid flow and heat transfer of the supercritical water in the 64-element Canadian SCWR fuel bundle1
A three-step chromatographic method for ultra-trace 242m Am purification prior to ICP-MS analysis1
Validation of LWR fuel depletion calculation module of reactor physics code system CBZ1
A prototype of beam profile measurement system for HIAF-HFRS beam line1
Rare earth elements and radioactive elements in black sands from the Konkan and Malabar coasts of India1
Novel concept for a filtered containment venting system with an ionic liquid to remove organic iodine (2) – Decomposition mechanism of an ionic liquid by heat and gamma-ray irradiation1
The effects of unburned-gas temperature and pressure on the unstable behavior of cellular-flame fronts generated by intrinsic instability in hydrogen-air lean premixed flames under adiabatic and non-a1
Neutron total and capture cross-section measurements of 155Gd and 157Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC·MLF·1
Measurements of keV-Neutron capture cross sections and capture gamma-ray spectra of 74,76,78,80,82 Se1
Tensile properties of irradiated modified 316 stainless steel (PNC316) at slow strain rates1
Ikaros3D: a real-time 3D fine spatial mesh kinetics simulator using POD1
Correlative Investigation on physical, microstructure, magnetism, and gamma-neutron attenuation properties of mechanically alloyed multifunctional (Fe/Co/Ni)Nb 10 1
Analytical studies on effects of wind on dispersion of hydrogen leaked in a partially open space1
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 in1
A support vector machine framework for fault detection in molecular pump1
The effect of a cyclic bending load on the bending resistance of ballooned, ruptured, and oxidized Zircaloy-4 cladding1
Recovery of the laser-induced breakdown spectroscopy system using a ceramic microchip deteriorated by radiation for the remote elemental analysis1
Numerical study of turbulent heat transfer of annular fuel assembly in a sodium-cooled fast reactor by a SST k-ω-k θ1
Influence of organic dispersant on nuclear grade anion exchange resin and their interaction behavior1
EPMA and EBSD observations of unirradiated MIMAS-MOX fuels for the study of fission gas release and thermal conductivity1
Consideration on the concrete spalling behavior in high-temperature environments during severe accidents1
Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 21
Improved neutron spectrum unfolding using residual networks and generative adversarial networks: a comparative study with baseline deep models1
Meteorological effects on atmospheric radioactive particles: a review of recent research1
Steady-state thermal-structural analysis of high-temperature heat pipes based on thermal-fluid coupling1
Effect of Ni and Si addition on dislocation loop formation in Fe-Mn alloys1
Effect of weld geometry on irradiation damage resistance of 316L stainless steel weld at 400 ℃1
Limited linear source approximation with edge detection for convergence stability of method of characteristics1
Kinetic modeling of IG-110 oxidation in inert atmosphere with low oxygen concentration for innovative high-temperature gas-cooled reactor applications1
Experimental investigations on flow-induced vibration characteristics of fuel rod with an independent channel for small lead-based reactor1
TRU oxide sample reactivity worths measured in the FCA-IX assemblies with systematically changed neutron energy spectra1
Effect of radiation and substitution of Ce4+ at Zr site in Y4Zr3O12 using collision cascades: a molecular dynamics simulation study1
Chemical interaction of CsOH vapor with UO 2 and Fe-Zr melt1
Effects of azimuthal temperature distribution and rod internal gas energy on ballooning deformation and rupture opening formation of a 17 × 17 type PWR fuel cladding tube under LOCA-simulated burst co1
An energy equivalent method to determine the stress–strain relations of ductile materials by small punch testing1
Towards safe, efficient long-reach manipulation in nuclear decommissioning: A case study on fuel debris retrieval at Fukushima Daiichi1
Measurement of 107-MeV proton-induced double-differential thick target neutron yields for Fe, Pb, and Bi using a fixed-field alternating gradient accelerator at Kyoto University1
Application of the spectral determination method to liquid scintillation spectra1
Development of a radiation tolerant laser-induced breakdown spectroscopy system using a single crystal micro-chip laser for remote elemental analysis1
Pop-in behavior during nanoindentation in Fe-ion-irradiated RPV model alloy1
Double-differential cross sections for charged particle emissions from α particle impinging on Al at 230 MeV/u1
Double diffusive dissolution model of UO2 pellet in molten Zr cladding1
Synergism of radiation and steam on mechanical properties of cable insulation removed from a nuclear power plant1
Human reliability analysis of shared equipment in multi-unit site1
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