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 2022-06-01 to 2026-06-01.)

Article	Citations
Experimental and numerical simulation study on the combustion characteristics of nuclear-grade activated carbon	388
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids	354
The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations	18
Cesium immobilization from aqueous solution by struvite synthesis	18
Evaluation of ⁶⁰ Co inventory in the core of the Fukushima Daiichi Nuclear Power Plant – contribution of fuel deposits to the reactor core inventory	14
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique	13
JENDL photonuclear data file 2016	13
Development of a new method for simultaneous monitoring of criticality and nuclear material security/accountancy in a multiplicative system	13
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	12
A new separation method of hydrogen isotope by dynamically created nonequilibrium state	12
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel	12
Effect of part-length rod arrangement on vapor redistribution in 5 × 5 rod bundle with high-energy X-ray CT measurement	12
Sodium science and technology training at Indian sodium school	11
Study on response surface method to optimize radioactive resin degradation by microwave-assisted Fenton reaction	11
Radioactivation analysis of a concrete wall in a high-energy electron accelerator facility	11
Advances in the interfacial interactions and decontamination strategies of radionuclides on cement surfaces: a review	11
Radio-tellurium released into the environment during the complete oxidation of fuel cladding, containment venting and reactor building failure of the Fukushima accident	11
EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242	10
Study on criticality uncertainties of MCCI products due to concrete compositions	10
Exploration of the mechanism of controllable decomposition of polyurethane based on carbonate molten salt	10
Correction	10
Basic research on estimation of contamination of internal surface of spent nuclear fuel transport casks by Lasso regression	9
Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations	9
Startup core design of metallic-fueled lead-bismuth eutectic-cooled rotational fuel-shuffling breed-and-burn fast reactor	9
Sorption of Cs ⁺ and Eu ³⁺ onto coherent and melange-type pre-neogene sedimentary rocks	9

Discrimination of disposal-restricted materials in waste containers by nondestructive testing and image analysis with high-energy X-ray computed tomography	9
Study on iodine adsorption capacity and adsorption mechanism of AgY	8
Exploratory study of nuclear magnetic resonance well logging technology on the hydrogeological characteristics of deep geological formations	8
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O₂	8
Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages	8
Absolute quantification of ¹³⁷Cs activity in spent nuclear fuel with calculated detector response function	8
Transient parameter prediction and fault diagnosis for nuclear power plants based on machine learning	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
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
Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow	6
The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment	6
Clarification of key input parameters for site boundary dose due to criticality of fuel debris at the Fukushima Daiichi nuclear power plant	6
Measurement of the thermal neutron capture-cross section of ¹⁹¹ Ir at ANNRI MLF J-PARC	6
Development of an integrated non-destructive analysis system, Active-N	6
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33	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
Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy	5
Performance evaluation for rapid-dose estimation of radioactive plume dispersion based on pre-simulation database of wind conditions by large-eddy simulation	5
Redistribution of elements in simulated high-level waste glass with aggregation of platinum group elements	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
Irradiation hardening and void swelling behaviors of F82H IEA by using dual-ion irradiation	5
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environment	5
Sensitivity analysis of risk assessment for continuous Markov process Monte Carlo method using correlated sampling method	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
Modeling of vapor mass formation under forced convective boiling condition	5
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 therapy	5
A level 2 site risk assessment for internal event and seismic event: a case study	5
Measurement of the water-vapor void fraction in a 4x4 unheated rod bundle	5
Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis	5
A TOF spectrometer for neutron spectral measurements in a wide energy range base on a fast ionization chamber containing ⁶Li-²³⁵U	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
Correction	5
Ensuring a prudent combination of risk insights and a defense-in-depth philosophy through a reinterpretation of hierarchical safety goals	5
ACE-FRENDY-CBZ: a new neutronics analysis sequence using multi-group neutron transport calculations	5
Physics-guided machine learning recovers Archie-type scaling and interlayer diffusion mechanisms for sodium transport in compacted bentonite buffers	5
A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries	5
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
Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons	4
Study on key technical issues of accident selection in emergency planning zone development for small modular reactors	4
Research on nonlinear generalized predictive control method for reactor core power based on parameter identification	4

CFD simulation of the XR2-1 experiment with the JUPITER code	4
Numerical simulation of bubble hydrodynamics for pool scrubbing	4
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure	4
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions	4
Research on the powderization treatment of uranium-zirconium solid solution simulated nuclear fuel debris using thermochemical redox reaction	4
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments	4
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model	4
Gamma-ray irradiation induced dislocation loops in hexagonal zirconium	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
Experimental research and transient modeling of aerosol transport considering re-entrainment effects in turbulent horizontal circular pipe flow	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
Effect of temperature on radiolytically generated hydrogen yield from actual nuclear fuel-derived solution	4
Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K	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
Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system	4
Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility	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
Measurement and simulations of high-energy neutrons through a various thickness of concrete and steel shields using activation detectors at CHARM and CSBF	4
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator	4
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level	4
Experimental techniques for investigating thermal transport in nuclear materials	4
A finite element analysis study on the fracture pattern change of fuel cladding under PCMI loading conditions	4
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning	4
Sub-pin level distribution tallies and statistical error estimation with POD tallies in two-dimensional C5G7 benchmark	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
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
Measurement of neutron spectra for various thicknesses of concrete and steel shielding at 24-GeV/c proton beam facility using Bonner sphere spectrometer	3
Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant	3
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH	3
A spurious-count effect observed in Rossi-α and Feynman-α analysis using fission counter for Kyoto University Reactor	3
Experimental and numerical studies of backflow aerosol leakage from an enclosure under dynamic confinement due to internal flow perturbations	3
Status of the ²²⁶ Ra nuclear data library and its impact on the production amount of ²²⁵ Ac via th	3
Fretting wear behavior test and numerical simulation of Inconel 690 alloy	3
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor	3
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 problems	3
Continuous-Time Markov Chain-based examination of safeguards- and security-by-design of nuclear reactors	3
Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform	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
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks	3
Nuclear data adjustment using a deterministic sampling method with unscented transformation	3
Subcooled forced convection boiling on a vertical surface and gas-liquid structure near the heat transfer surface	3
Development of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithm	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
JENDL-5 benchmarking for fission reactor applications	3
Computer code analysis of irradiation performance of an annular mixed oxide fuel element	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
Validation of self-adjoint angular flux neutron transport code with TAKEDA benchmark	3
Measurement of the neutron capture cross section of ¹⁸⁵ Re in the keV energy region	3