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 2022-05-01 to 2026-05-01.)

Article	Citations
The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations	380
Effect of part-length rod arrangement on vapor redistribution in 5 × 5 rod bundle with high-energy X-ray CT measurement	334
Experimental and numerical simulation study on the combustion characteristics of nuclear-grade activated carbon	18
JENDL photonuclear data file 2016	18
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids	14
Development of a new method for simultaneous monitoring of criticality and nuclear material security/accountancy in a multiplicative system	13
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel	12
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique	12
Evaluation of ⁶⁰ Co inventory in the core of the Fukushima Daiichi Nuclear Power Plant – contribution of fuel deposits to the reactor core inventory	12
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	12
Cesium immobilization from aqueous solution by struvite synthesis	12
Discrimination of disposal-restricted materials in waste containers by nondestructive testing and image analysis with high-energy X-ray computed tomography	11
A new separation method of hydrogen isotope by dynamically created nonequilibrium state	11
Startup core design of metallic-fueled lead-bismuth eutectic-cooled rotational fuel-shuffling breed-and-burn fast reactor	11
Radioactivation analysis of a concrete wall in a high-energy electron accelerator facility	11
Correction	10
Study on criticality uncertainties of MCCI products due to concrete compositions	10
Basic research on estimation of contamination of internal surface of spent nuclear fuel transport casks by Lasso regression	10
Exploration of the mechanism of controllable decomposition of polyurethane based on carbonate molten salt	10
EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242	10
Study on response surface method to optimize radioactive resin degradation by microwave-assisted Fenton reaction	9
Sodium science and technology training at Indian sodium school	9
Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations	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
Sorption of Cs ⁺ and Eu ³⁺ onto coherent and melange-type pre-neogene sedimentary rocks	9

Advances in the interfacial interactions and decontamination strategies of radionuclides on cement surfaces: a review	9
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O₂	8
Study on iodine adsorption capacity and adsorption mechanism of AgY	8
Absolute quantification of ¹³⁷Cs activity in spent nuclear fuel with calculated detector response function	8
Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages	8
Exploratory study of nuclear magnetic resonance well logging technology on the hydrogeological characteristics of deep geological formations	8
Development of an ultra-fast dynamic time-over-threshold system with a 30 ps timing resolution	7
Deterministic sampling method using simplex ensemble and scaling method for efficient and robust uncertainty quantification	7
Development of ACE file perturbation tool using FRENDY	7
Thermal performance analysis of molten salt in transversely grooved tube for nuclear reactor	7
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates	7
Transient parameter prediction and fault diagnosis for nuclear power plants based on machine learning	7
A simulation study of hypervelocity jet underwater: physical protection design of offshore floating nuclear power plant against light torpedo threats	7
Leaching behavior of arsenic and selenium in coal fly ash by aging treatment and cement mixing	7
Urinary stone component identification by energy-resolved X-ray computed tomography	6
Measurement of the thermal neutron capture-cross section of ¹⁹¹ Ir at ANNRI MLF J-PARC	6
The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment	6
Development of an integrated non-destructive analysis system, Active-N	6
Sensitivity analysis of risk assessment for continuous Markov process Monte Carlo method using correlated sampling method	6
Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow	6
Ensuring a prudent combination of risk insights and a defense-in-depth philosophy through a reinterpretation of hierarchical safety goals	5
Test of ¹⁰⁷ Pd transmutation with macroscopic quantities	5
Performance evaluation for rapid-dose estimation of radioactive plume dispersion based on pre-simulation database of wind conditions by large-eddy simulation	5
A TOF spectrometer for neutron spectral measurements in a wide energy range base on a fast ionization chamber containing ⁶Li-²³⁵U	5
Clarification of key input parameters for site boundary dose due to criticality of fuel debris at the Fukushima Daiichi nuclear power plant	5
Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis	5
ACE-FRENDY-CBZ: a new neutronics analysis sequence using multi-group neutron transport calculations	5
Irradiation hardening and void swelling behaviors of F82H IEA by using dual-ion irradiation	5
Measurement of the water-vapor void fraction in a 4x4 unheated rod bundle	5
Design and experimental analysis of a nuclear fuel rod enrichment detection system	5
Verification of direct coupling code system using FRENDY version 2 and GENESIS for light water reactor lattices	5
Modeling of vapor mass formation under forced convective boiling condition	5
Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy	5
Redistribution of elements in simulated high-level waste glass with aggregation of platinum group elements	5
Power distribution re-construction based on the PHOEBE method using the method of characteristics code ‘GENESIS’	5
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	5
A level 2 site risk assessment for internal event and seismic event: a case study	5
Simple technique for the preparation of uranium-impregnated porous silica particles and their application as working standard particles for analysis of the safeguards environmental samples	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
Correction	5
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33	5
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy	5
Effects of correlations in uncertainties of total cross section and elastic angular distribution for a deep penetration of 14-MeV neutrons in Cu	4
Experimental techniques for investigating thermal transport in nuclear materials	4
Uncertainty analysis for fission product inventories based on covariance data of fission product yields in JENDL-4.0 and ENDF/B-VIII.0	4
Research on the powderization treatment of uranium-zirconium solid solution simulated nuclear fuel debris using thermochemical redox reaction	4
Numerical simulation of bubble hydrodynamics for pool scrubbing	4
Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system	4
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions	4
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): ⁵⁸ Fe(n,γ) ⁵⁹ Fe	4

Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector	4
Research on nonlinear generalized predictive control method for reactor core power based on parameter identification	4
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure	4
A finite element analysis study on the fracture pattern change of fuel cladding under PCMI loading conditions	4
Measurement and simulations of high-energy neutrons through a various thickness of concrete and steel shields using activation detectors at CHARM and CSBF	4
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning	4
Solubility of FeSe₂(cr) at 318 K in the presence of iron	4
Experimental investigation of spray cooling behavior in 4×4 simulated fuel bundle	4
Novel concept for a filtered containment venting system with an ionic liquid to remove organic iodine (1)-proof of concept for organic iodine removal	4
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator	4
Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons	4
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environment	4
Experimental research and transient modeling of aerosol transport considering re-entrainment effects in turbulent horizontal circular pipe flow	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
Study on key technical issues of accident selection in emergency planning zone development for small modular reactors	4
Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K	4
Integrating DeblurGAN and CNN to improve the accuracy of motion blur X-Ray image classification	4
Gamma-ray irradiation induced dislocation loops in hexagonal zirconium	4
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model	4
Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility	4
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level	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
CFD simulation of the XR2-1 experiment with the JUPITER code	4
A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries	4
Nuclear data adjustment using a deterministic sampling method with unscented transformation	3
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor	3
Monte Carlo-informed reliability and availability framework for innovative inspection timelines: a case study of the PA01-BC01 heat exchanger	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
Comparison of cost-reduced computational methods for nuclide transmutation problems	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
A spurious-count effect observed in Rossi-α and Feynman-α analysis using fission counter for Kyoto University Reactor	3
Subcooled forced convection boiling on a vertical surface and gas-liquid structure near the heat transfer surface	3
Experiences from the cutting of metallic blocks from simulant Fukushima Daiichi fuel debris	3
Experimental and numerical studies of backflow aerosol leakage from an enclosure under dynamic confinement due to internal flow perturbations	3
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks	3
Development of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithm	3
Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel	3
The effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatment	3
Water-leaching behavior for cesium chemisorbed on stainless steel at room temperature	3
Study on corrosion of T-22 alloy under high temperature condition of VHTR	3
Computer code analysis of irradiation performance of an annular mixed oxide fuel element	3
Continuous-Time Markov Chain-based examination of safeguards- and security-by-design of nuclear reactors	3
Measurement of the neutron capture cross section of ¹⁸⁵ Re in the keV energy region	3
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments	3
Status of the ²²⁶ Ra nuclear data library and its impact on the production amount of ²²⁵ Ac via th	3
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH	3
Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant	3
Bayesian approach to energy dependence of fission product yields of ²³⁵ U by data augmentation	3
JENDL-5 benchmarking for fission reactor applications	3
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (III): ¹⁷⁰ Er(n,γ) ¹⁷¹	3
Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform	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
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
Sub-pin level distribution tallies and statistical error estimation with POD tallies in two-dimensional C5G7 benchmark	3
Fretting wear behavior test and numerical simulation of Inconel 690 alloy	3
Validation of self-adjoint angular flux neutron transport code with TAKEDA benchmark	3