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 2021-11-01 to 2025-11-01.)

Article	Citations
Consideration of delayed neutron effect on Rossi-α analysis for a subcritical thermal reactor	283
Transient heat transfer analysis of double-layer molten pool under severe accident	225
Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator	28
Effect of part-length rod arrangement on vapor redistribution in 5 × 5 rod bundle with high-energy X-ray CT measurement	27
Evaluation of ⁶⁰ Co inventory in the core of the Fukushima Daiichi Nuclear Power Plant – contribution of fuel deposits to the reactor core inventory	16
The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations	13
JENDL photonuclear data file 2016	13
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids	11
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique	11
Experimental and numerical simulation study on the combustion characteristics of nuclear-grade activated carbon	11
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel	11
Cesium immobilization from aqueous solution by struvite synthesis	11
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	10
Radioactivation analysis of a concrete wall in a high-energy electron accelerator facility	10
A new separation method of hydrogen isotope by dynamically created nonequilibrium state	10
Sodium science and technology training at Indian sodium school	10
Radio-tellurium released into the environment during the complete oxidation of fuel cladding, containment venting and reactor building failure of the Fukushima accident	10
Correction	10
EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242	9
Advances in the interfacial interactions and decontamination strategies of radionuclides on cement surfaces: a review	9
Discrimination of disposal-restricted materials in waste containers by nondestructive testing and image analysis with high-energy X-ray computed tomography	9
Comprehensive simulation study on CT isotope imaging beyond the experiment on the ²⁰⁸ Pb based on nuclear resonance fluorescence	9
Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations	8
Exploration of the mechanism of controllable decomposition of polyurethane based on carbonate molten salt	8
Deterministic sampling method using simplex ensemble and scaling method for efficient and robust uncertainty quantification	8

Sorption of Cs ⁺ and Eu ³⁺ onto coherent and melange-type pre-neogene sedimentary rocks	8
Basic research on estimation of contamination of internal surface of spent nuclear fuel transport casks by Lasso regression	8
Absolute quantification of ¹³⁷Cs activity in spent nuclear fuel with calculated detector response function	7
Thermodynamic properties of liquid alkali-metal coolants: from the perspective of molecular dynamics	7
Development of ACE file perturbation tool using FRENDY	7
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates	7
Exploratory study of nuclear magnetic resonance well logging technology on the hydrogeological characteristics of deep geological formations	7
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O₂	7
Transient parameter prediction and fault diagnosis for nuclear power plants based on machine learning	7
Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages	6
The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment	6
A simulation study of hypervelocity jet underwater: physical protection design of offshore floating nuclear power plant against light torpedo threats	6
Leaching behavior of arsenic and selenium in coal fly ash by aging treatment and cement mixing	6
Urinary stone component identification by energy-resolved X-ray computed tomography	6
Revolatilization of iodine by bubbly flow in the suppression pool during an accident	6
Development of an ultra-fast dynamic time-over-threshold system with a 30 ps timing resolution	6
Study on iodine adsorption capacity and adsorption mechanism of AgY	6
A TOF spectrometer for neutron spectral measurements in a wide energy range base on a fast ionization chamber containing ⁶Li-²³⁵U	6
Performance evaluation for rapid-dose estimation of radioactive plume dispersion based on pre-simulation database of wind conditions by large-eddy simulation	6
Thermal-Neutron capture cross-section measurements of Neptunium-237 with graphite thermal column in KUR	6
Thermal performance analysis of molten salt in transversely grooved tube for nuclear reactor	6
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
Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow	5
Modeling of vapor mass formation under forced convective boiling condition	5
Neutron yield calculation of p-Li thick target by using PHITS with JENDL-4.0/HE and ENDF/B-VII for BNCT application	5
Investigation on the similarity of turbine cascade with different working fluids	5
Power distribution re-construction based on the PHOEBE method using the method of characteristics code ‘GENESIS’	5
Sensitivity analysis of risk assessment for continuous Markov process Monte Carlo method using correlated sampling method	5
Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy	5
Correction	5
Development of an integrated non-destructive analysis system, Active-N	5
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33	5
Uranium dissolution and uranyl peroxide formation by immersion of simulated fuel debris in aqueous H ₂ O ₂ solution	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
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
Measurement of the thermal neutron capture-cross section of ¹⁹¹ Ir at ANNRI MLF J-PARC	5
Verification of direct coupling code system using FRENDY version 2 and GENESIS for light water reactor lattices	5
Design and experimental analysis of a nuclear fuel rod enrichment detection system	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
Irradiation hardening and void swelling behaviors of F82H IEA by using dual-ion irradiation	5
Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons	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
Reactivity estimation based on the linear equation of characteristic time profile of power in subcritical quasi-steady state	4
Research on nonlinear generalized predictive control method for reactor core power based on parameter identification	4
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environment	4
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure	4
Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis	4
Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector	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

Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions	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
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
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator	4
Numerical simulation of bubble hydrodynamics for pool scrubbing	4
Experimental research and transient modeling of aerosol transport considering re-entrainment effects in turbulent horizontal circular pipe flow	4
A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries	4
Highly promising recycled low-density polyethylene sheet adsorbents for uranium recovery from seawater	4
Measurement of the water-vapor void fraction in a 4x4 unheated rod bundle	4
Study on key technical issues of accident selection in emergency planning zone development for small modular reactors	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
Experimental techniques for investigating thermal transport in nuclear materials	4
Incineration of trans-uranium elements using chlorides molten salt fast reactors – A proposal of incineration in three steps	4
Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility	4
Recovery and immobilization of cesium from aqueous solution after hydrothermal treatment using functional porous glass	4
Test of ¹⁰⁷ Pd transmutation with macroscopic quantities	4
Develop a framework of human reliability analysis to evaluate the human error probability in DMCR of NPPs	4
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy	4
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level	4
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model	4
In-situ TEM observation of migration behavior of helium bubbles in F82H	4
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): ⁵⁸ Fe(n,γ) ⁵⁹ Fe	4
Development of AR-based scanning support system for 3D model reconstruction of work sites	3
Status of the ²²⁶ Ra nuclear data library and its impact on the production amount of ²²⁵ Ac via the ²²⁶	3
A spurious-count effect observed in Rossi-α and Feynman-α analysis using fission counter for Kyoto University Reactor	3
Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K	3
Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system	3
Solubility of FeSe₂(cr) at 318 K in the presence of iron	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
Identification and quantification of a ⁶⁰ Co radiation source under an intense ¹³⁷ Cs radiation field using an application-specifi	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
Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant	3
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks	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
Experimental investigation of spray cooling behavior in 4×4 simulated fuel bundle	3
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning	3
Gamma-ray irradiation induced dislocation loops in hexagonal zirconium	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
Study on corrosion of T-22 alloy under high temperature condition of VHTR	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
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor	3
Research on frequency modulation technology and its verifications of superconducting synchrocyclotron for cancer therapy	3
Integrating DeblurGAN and CNN to improve the accuracy of motion blur X-Ray image classification	3
Development of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithm	3
Nuclear data adjustment using a deterministic sampling method with unscented transformation	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
Fretting wear behavior test and numerical simulation of Inconel 690 alloy	3
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH	3
New variance reduction techniques for Monte-Carlo calculation based on first-collision source method	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
The effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatment	3
Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel	3