Journal of Nuclear Science and Technology

Papers
(The TQCC of Journal of Nuclear Science and Technology is 3. 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 2021-09-01 to 2025-09-01.)
ArticleCitations
The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations256
Consideration of delayed neutron effect on Rossi-α analysis for a subcritical thermal reactor194
Transient heat transfer analysis of double-layer molten pool under severe accident32
Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator28
JENDL photonuclear data file 201626
Cesium immobilization from aqueous solution by struvite synthesis26
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique15
Experimental and numerical simulation study on the combustion characteristics of nuclear-grade activated carbon14
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids14
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations13
Evaluation of 60 Co inventory in the core of the Fukushima Daiichi Nuclear Power Plant – contribution of fuel deposits to the reactor core inventory13
Comprehensive simulation study on CT isotope imaging beyond the experiment on the 208 Pb based on nuclear resonance fluorescence11
Sodium science and technology training at Indian sodium school11
Effect of part-length rod arrangement on vapor redistribution in 5 × 5 rod bundle with high-energy X-ray CT measurement11
A new separation method of hydrogen isotope by dynamically created nonequilibrium state11
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel11
Sorption of Cs + and Eu 3+ onto coherent and melange-type pre-neogene sedimentary rocks10
Discrimination of disposal-restricted materials in waste containers by nondestructive testing and image analysis with high-energy X-ray computed tomography10
Advances in the interfacial interactions and decontamination strategies of radionuclides on cement surfaces: a review10
Radio-tellurium released into the environment during the complete oxidation of fuel cladding, containment venting and reactor building failure of the Fukushima accident10
EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-2429
Radioactivation analysis of a concrete wall in a high-energy electron accelerator facility9
Basic research on estimation of contamination of internal surface of spent nuclear fuel transport casks by Lasso regression9
High temperature electrochemical reaction parameters affecting elecrochemical corrosion potential of type 316L stainless steel9
High-temperature ex-vessel corium spreading. Part 1: experimental investigations on ceramic and sacrificial concrete substrates9
Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages8
Leaching behavior of arsenic and selenium in coal fly ash by aging treatment and cement mixing8
Molten salt oxidation and process analysis of anionic exchange resin in Na 2 CO 3 -K 2 CO 8
Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations8
Thermal-Neutron capture cross-section measurements of Neptunium-237 with graphite thermal column in KUR7
A simulation study of hypervelocity jet underwater: physical protection design of offshore floating nuclear power plant against light torpedo threats7
Absolute quantification of 137Cs activity in spent nuclear fuel with calculated detector response function7
Revolatilization of iodine by bubbly flow in the suppression pool during an accident7
Development of ACE file perturbation tool using FRENDY7
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O27
Thermodynamic properties of liquid alkali-metal coolants: from the perspective of molecular dynamics7
Exploratory study of nuclear magnetic resonance well logging technology on the hydrogeological characteristics of deep geological formations7
Deterministic sampling method using simplex ensemble and scaling method for efficient and robust uncertainty quantification7
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates6
A TOF spectrometer for neutron spectral measurements in a wide energy range base on a fast ionization chamber containing 6Li-235U6
Thermal performance analysis of molten salt in transversely grooved tube for nuclear reactor6
High-temperature ex-vessel corium spreading. Part 2: scaling principles for gravity-viscous spreading with slip at the melt–substrate interface6
Transient parameter prediction and fault diagnosis for nuclear power plants based on machine learning6
Urinary stone component identification by energy-resolved X-ray computed tomography6
The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment6
Study on iodine adsorption capacity and adsorption mechanism of AgY6
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
Correction5
Measurement of the thermal neutron capture-cross section of 191 Ir at ANNRI MLF J-PARC5
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.335
ACE-FRENDY-CBZ: a new neutronics analysis sequence using multi-group neutron transport calculations5
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy5
Subcriticality determination methodology during fuel loading of accelerator-driven system5
Sensitivity analysis of risk assessment for continuous Markov process Monte Carlo method using correlated sampling method5
Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy5
Neutron yield calculation of p-Li thick target by using PHITS with JENDL-4.0/HE and ENDF/B-VII for BNCT application5
Investigation on the similarity of turbine cascade with different working fluids5
Uranium dissolution and uranyl peroxide formation by immersion of simulated fuel debris in aqueous H 2 O 2 solution5
Ensuring a prudent combination of risk insights and a defense-in-depth philosophy through a reinterpretation of hierarchical safety goals5
Power distribution re-construction based on the PHOEBE method using the method of characteristics code ‘GENESIS’5
Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow5
Verification of direct coupling code system using FRENDY version 2 and GENESIS for light water reactor lattices5
Development of an integrated non-destructive analysis system, Active-N5
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
Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis5
Novel concept for a filtered containment venting system with an ionic liquid to remove organic iodine (1)-proof of concept for organic iodine removal4
Study on key technical issues of accident selection in emergency planning zone development for small modular reactors4
Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons4
Numerical simulation of bubble hydrodynamics for pool scrubbing4
Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants4
Experimental techniques for investigating thermal transport in nuclear materials4
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
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure4
Integral experiment of 129 I(n, γ) reaction using fast neutron source in the ‘YAYOI’ reactor4
Highly promising recycled low-density polyethylene sheet adsorbents for uranium recovery from seawater4
Enhancement of random sampling by a combined approach of control variates and Latin hypercube sampling for uncertainty quantification in light water reactor lattice calculations4
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level4
Investigation into activation of accelerators at various synchrotron radiation facilities in Japan4
Measurement and simulations of high-energy neutrons through a various thickness of concrete and steel shields using activation detectors at CHARM and CSBF4
Correction of X-ray scattering in energy-resolved computed tomography imaging of 20-cm-diameter phantom4
Effects of correlations in uncertainties of total cross section and elastic angular distribution for a deep penetration of 14-MeV neutrons in Cu4
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environment4
Incineration of trans-uranium elements using chlorides molten salt fast reactors – A proposal of incineration in three steps4
Reactivity estimation based on the linear equation of characteristic time profile of power in subcritical quasi-steady state4
Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility4
Develop a framework of human reliability analysis to evaluate the human error probability in DMCR of NPPs4
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model4
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): 58 Fe(n,γ) 59 Fe4
Experimental investigation of spray cooling behavior in 4×4 simulated fuel bundle4
In-situ TEM observation of migration behavior of helium bubbles in F82H4
Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector4
Test of 107 Pd transmutation with macroscopic quantities4
Measurement of the water-vapor void fraction in a 4x4 unheated rod bundle4
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions4
Recovery and immobilization of cesium from aqueous solution after hydrothermal treatment using functional porous glass4
A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries4
Solubility of FeSe2(cr) at 318 K in the presence of iron4
Research on nonlinear generalized predictive control method for reactor core power based on parameter identification4
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator4
Computer code analysis of irradiation performance of an annular mixed oxide fuel element3
Bayesian approach to energy dependence of fission product yields of 235 U by data augmentation3
Measurement of neutron spectra for various thicknesses of concrete and steel shielding at 24-GeV/c proton beam facility using Bonner sphere spectrometer3
Integrating DeblurGAN and CNN to improve the accuracy of motion blur X-Ray image classification3
Corrosion behavior of zirconium alloys in the aqueous environment. Phenomenological aspects. Overview3
Development of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithm3
Experiences from the cutting of metallic blocks from simulant Fukushima Daiichi fuel debris3
Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system3
Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel3
Fretting wear behavior test and numerical simulation of Inconel 690 alloy3
Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform3
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks3
Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K3
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
The effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatment3
Thermophysical properties of molten FeO 1.5 , (FeO 1.5 ) 0.86 –(ZrO 2 3
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
Activity and weight ratios of cesium, uranium, plutonium, and curium isotopes based on elaborate inventory calculations of Fukushima Dai-ichi NPP units 1 to 33
Research on frequency modulation technology and its verifications of superconducting synchrocyclotron for cancer therapy3
JENDL-5 benchmarking for fission reactor applications3
New variance reduction techniques for Monte-Carlo calculation based on first-collision source method3
Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant3
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments3
Study on corrosion of T-22 alloy under high temperature condition of VHTR3
Status of the 226 Ra nuclear data library and its impact on the production amount of 225 Ac via the 226 3
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH3
Measurement of the neutron capture cross section of 185 Re in the keV energy region3
Nuclear data adjustment using a deterministic sampling method with unscented transformation3
A spurious-count effect observed in Rossi-α and Feynman-α analysis using fission counter for Kyoto University Reactor3
Reactor antineutrinos and novel application to real-time remote monitoring of nuclear reactors3
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (III): 170 Er(n,γ) 171 Er and 3
Uncertainty quantification of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly3
Development of AR-based scanning support system for 3D model reconstruction of work sites3
Identification and quantification of a 60 Co radiation source under an intense 137 Cs radiation field using an application-specifi3
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor3
Benchmark study of particle and heavy-ion transport code system using shielding integral benchmark archive and database for accelerator-shielding experiments3
Research on the powderization treatment of uranium-zirconium solid solution simulated nuclear fuel debris using thermochemical redox reaction3
Impact of MOX fuel use in light-water reactors: long-term radiological consequences of disposal of high-level waste in a geological repository3
Uncertainty analysis for fission product inventories based on covariance data of fission product yields in JENDL-4.0 and ENDF/B-VIII.03
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning3
Gamma-ray irradiation induced dislocation loops in hexagonal zirconium3
Phase stability of Cs-Si-O and Cs-Si-Fe-O compounds on stainless steel3
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