OOIR: Observatory of International Research

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 2021-06-01 to 2025-06-01.)

Article	Citations
The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations	219
JENDL photonuclear data file 2016	137
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids	30
Consideration of delayed neutron effect on Rossi-α analysis for a subcritical thermal reactor	25
Application of continuous Markov-chain Monte-Carlo method to multi-unit risk evaluations considering interdependence of accident progression among multiple units	25
Transient heat transfer analysis of double-layer molten pool under severe accident	21
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel	15
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique	15
Experimental and numerical simulation study on the combustion characteristics of nuclear-grade activated carbon	14
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	13
Cesium immobilization from aqueous solution by struvite synthesis	13
Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator	12
Evaluation of uncertainties derived from meteorological forecast inputs in plume directions predicted by atmospheric dispersion simulations	12
Sorption of Cs ⁺ and Eu ³⁺ onto coherent and melange-type pre-neogene sedimentary rocks	11
Comprehensive simulation study on CT isotope imaging beyond the experiment on the ²⁰⁸ Pb based on nuclear resonance fluorescence	11
Discrimination of disposal-restricted materials in waste containers by nondestructive testing and image analysis with high-energy X-ray computed tomography	11
Basic research on estimation of contamination of internal surface of spent nuclear fuel transport casks by Lasso regression	10
A new separation method of hydrogen isotope by dynamically created nonequilibrium state	10
Radioactivation analysis of a concrete wall in a high-energy electron accelerator facility	9
Radio-tellurium released into the environment during the complete oxidation of fuel cladding, containment venting and reactor building failure of the Fukushima accident	9
High temperature electrochemical reaction parameters affecting elecrochemical corrosion potential of type 316L stainless steel	9
EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242	8
Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages	8
Deterministic sampling method using simplex ensemble and scaling method for efficient and robust uncertainty quantification	8
Thermal-Neutron capture cross-section measurements of Neptunium-237 with graphite thermal column in KUR	8

Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations	8
Leaching behavior of arsenic and selenium in coal fly ash by aging treatment and cement mixing	8
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O₂	8
A simulation study of hypervelocity jet underwater: physical protection design of offshore floating nuclear power plant against light torpedo threats	8
Absolute quantification of ¹³⁷Cs activity in spent nuclear fuel with calculated detector response function	8
Molten salt oxidation and process analysis of anionic exchange resin in Na ₂ CO ₃ -K ₂ CO	8
High-temperature ex-vessel corium spreading. Part 1: experimental investigations on ceramic and sacrificial concrete substrates	8
Development of ACE file perturbation tool using FRENDY	8
Revolatilization of iodine by bubbly flow in the suppression pool during an accident	8
Experimental analysis of small sample reactivity measured in the SEG experiment by a deterministic reactor physics code system CBZ	7
Study on iodine adsorption capacity and adsorption mechanism of AgY	7
Thermal performance analysis of molten salt in transversely grooved tube for nuclear reactor	7
Exploratory study of nuclear magnetic resonance well logging technology on the hydrogeological characteristics of deep geological formations	7
Urinary stone component identification by energy-resolved X-ray computed tomography	7
Thermodynamic properties of liquid alkali-metal coolants: from the perspective of molecular dynamics	7
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates	7
A TOF spectrometer for neutron spectral measurements in a wide energy range base on a fast ionization chamber containing ⁶Li-²³⁵U	7
Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy	6
Development of an integrated non-destructive analysis system, Active-N	6
The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment	6
Verification of direct coupling code system using FRENDY version 2 and GENESIS for light water reactor lattices	6
Correction	6
Improvement of analysis results from the GAGG scintillator Compton camera operated on an unmanned helicopter by selecting stable flight conditions	6
Improvement of thermal conductivity by adding tungsten and/or copper wire in F82H	6
Neutron yield calculation of p-Li thick target by using PHITS with JENDL-4.0/HE and ENDF/B-VII for BNCT application	6
Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow	6
High-temperature ex-vessel corium spreading. Part 2: scaling principles for gravity-viscous spreading with slip at the melt–substrate interface	6
Validation of three-dimensional simulation method for two-phase flow in triangular-pitch tube bundle in secondary side of steam generators on porous two-fluid model	6
Measurement of the thermal neutron capture-cross section of ¹⁹¹ Ir at ANNRI MLF J-PARC	5
Cross-domain fault diagnosis of rotating machinery in nuclear power plant based on improved domain adaptation method	5
Investigation on the similarity of turbine cascade with different working fluids	5
Irradiation hardening and void swelling behaviors of F82H IEA by using dual-ion irradiation	5
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 invento	5
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33	5
Subcriticality determination methodology during fuel loading of accelerator-driven system	5
Uranium dissolution and uranyl peroxide formation by immersion of simulated fuel debris in aqueous H ₂ O ₂ solution	5
Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis	5
Sensitivity analysis of risk assessment for continuous Markov process Monte Carlo method using correlated sampling method	5
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy	5
Flame structures and ignition thresholds of hydrogen jets containing sodium mist under various gas concentrations	5
Recovery and immobilization of cesium from aqueous solution after hydrothermal treatment using functional porous glass	4
Highly promising recycled low-density polyethylene sheet adsorbents for uranium recovery from seawater	4
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 camera	4
Effects of correlations in uncertainties of total cross section and elastic angular distribution for a deep penetration of 14-MeV neutrons in Cu	4
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): ⁵⁸ Fe(n,γ) ⁵⁹ Fe	4
Experimental techniques for investigating thermal transport in nuclear materials	4
Safety assessment of second-phase disposal facility in Gyeongju low- and intermediate-level radioactive waste (LILW) repository using RESRAD-OFFSITE code	4
Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons	4
Test of ¹⁰⁷ Pd transmutation with macroscopic quantities	4
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environment	4

Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector	4
Reactivity estimation based on the linear equation of characteristic time profile of power in subcritical quasi-steady state	4
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions	4
Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants	4
Numerical simulation of bubble hydrodynamics for pool scrubbing	4
Measurement of the water-vapor void fraction in a 4x4 unheated rod bundle	4
Ensuring a prudent combination of risk insights and a defense-in-depth philosophy through a reinterpretation of hierarchical safety goals	4
Develop a framework of human reliability analysis to evaluate the human error probability in DMCR of NPPs	4
Investigation into activation of accelerators at various synchrotron radiation facilities in Japan	4
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure	4
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator	4
Enhancement of random sampling by a combined approach of control variates and Latin hypercube sampling for uncertainty quantification in light water reactor lattice calculations	4
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level	4
Incineration of trans-uranium elements using chlorides molten salt fast reactors – A proposal of incineration in three steps	4
Correction of X-ray scattering in energy-resolved computed tomography imaging of 20-cm-diameter phantom	4
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	4
ACE-FRENDY-CBZ: a new neutronics analysis sequence using multi-group neutron transport calculations	4
A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries	4
Thermodynamic analysis and optimization for steam methane reforming hydrogen production system using high temperature gas-cooled reactor pebble-bed module	3
Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant	3
Reactor antineutrinos and novel application to real-time remote monitoring of nuclear reactors	3
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (III): ¹⁷⁰ Er(n,γ) ¹⁷¹ Er and	3
Status of the ²²⁶ Ra nuclear data library and its impact on the production amount of ²²⁵ Ac via the ²²⁶	3
Identification and quantification of a ⁶⁰ Co radiation source under an intense ¹³⁷ Cs radiation field using an application-specifi	3
Research on the powderization treatment of uranium-zirconium solid solution simulated nuclear fuel debris using thermochemical redox reaction	3
Uncertainty analysis for fission product inventories based on covariance data of fission product yields in JENDL-4.0 and ENDF/B-VIII.0	3
Impact of MOX fuel use in light-water reactors: long-term radiological consequences of disposal of high-level waste in a geological repository	3
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments	3
Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform	3
A spurious-count effect observed in Rossi-α and Feynman-α analysis using fission counter for Kyoto University Reactor	3
Phase stability of Cs-Si-O and Cs-Si-Fe-O compounds on stainless steel	3
Integral experiment of ¹²⁹ I(n, γ) reaction using fast neutron source in the ‘YAYOI’ reactor	3
Computer code analysis of irradiation performance of an annular mixed oxide fuel element	3
Experimental investigation of spray cooling behavior in 4×4 simulated fuel bundle	3
Development of AR-based scanning support system for 3D model reconstruction of work sites	3
Novel concept for a filtered containment venting system with an ionic liquid to remove organic iodine (1)-proof of concept for organic iodine removal	3
Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system	3
Development of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithm	3
JENDL-5 benchmarking for fission reactor applications	3
Activity and weight ratios of cesium, uranium, plutonium, and curium isotopes based on elaborate inventory calculations of Fukushima Dai-ichi NPP units 1 to 3	3
Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K	3
Bayesian approach to energy dependence of fission product yields of ²³⁵ U by data augmentation	3
Measurement of the neutron capture cross section of ¹⁸⁵ Re in the keV energy region	3
Nuclear data adjustment using a deterministic sampling method with unscented transformation	3
The effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatment	3
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks	3
Experiences from the cutting of metallic blocks from simulant Fukushima Daiichi fuel debris	3
Integrating DeblurGAN and CNN to improve the accuracy of motion blur X-Ray image classification	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 size	3
Experience with valuation methods for the creation of real options enabling diversity of nuclear fuel supply	3
Development of a simple calculation method for the conductance of rarefied gas flow in cylindrical pipe applicable to divertor exhaust investigation of nuclear fusion reactor	3
In-situ TEM observation of migration behavior of helium bubbles in F82H	3
Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility	3
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor	3
Thermophysical properties of molten FeO _1.5 , (FeO _1.5 ) _0.86 –(ZrO ₂	3
Measurement of neutron spectra for various thicknesses of concrete and steel shielding at 24-GeV/c proton beam facility using Bonner sphere spectrometer	3
Uncertainty quantification of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly	3
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning	3
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH	3
Study on corrosion of T-22 alloy under high temperature condition of VHTR	3
Fretting wear behavior test and numerical simulation of Inconel 690 alloy	3
New variance reduction techniques for Monte-Carlo calculation based on first-collision source method	3
Gamma-ray irradiation induced dislocation loops in hexagonal zirconium	3
Benchmark study of particle and heavy-ion transport code system using shielding integral benchmark archive and database for accelerator-shielding experiments	3
Solubility of FeSe₂(cr) at 318 K in the presence of iron	3
Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel	3
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model	3
Research on frequency modulation technology and its verifications of superconducting synchrocyclotron for cancer therapy	3
Measurement and simulations of high-energy neutrons through a various thickness of concrete and steel shields using activation detectors at CHARM and CSBF	3