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 2021-04-01 to 2025-04-01.)

Article	Citations
Criticality evaluation considering nonuniformity effect using Monte Carlo perturbation method	199
Numerical simulation of bubble hydrodynamics for pool scrubbing	111
Fuel cycle features of RFBB fast reactor with advanced fuel	27
Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 2	24
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): ⁵⁸ Fe(n,γ) ⁵⁹ Fe	22
Research on soft errors induced by alpha particles and atmospheric neutrons based on 28 nm field programmable gate array	21
Bayesian statistical model for cladding high-temperature burst under loss-of-coolant accident conditions	15
Effects of azimuthal temperature distribution and rod internal gas energy on ballooning deformation and rupture opening formation of a 17 × 17 type PWR fuel cladding tube under LOCA-simulated burst co	13
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator	12
Applicability of differential die-away self-interrogation technique for quantification of spontaneous fission nuclides for fuel debris at Fukushima Daiichi Nuclear Power Plants	12
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
Verification of human error traps in NPP procedures utilizing syntactic and semantic information extraction	11
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions	11
Enhancement of random sampling by a combined approach of control variates and Latin hypercube sampling for uncertainty quantification in light water reactor lattice calculations	11
Double diffusive dissolution model of UO₂ pellet in molten Zr cladding	11
Review of prediction models for tsunami-induced lateral fluid force for revision of engineering design code for nuclear power plant structures	10
Condensation heat fluxes from mixed convection flows of steam and air mixtures on a vertical flat plate	10
Evaluations on the thermal properties of Cs–B–O compounds using density functional theory and phonon vibration calculations	9
Passive fast neutron multiplicity counting system based on a symmetric spherical design	9
New JENDL-4.0/HE neutron and proton ACE files	9
Effects of correlations in uncertainties of total cross section and elastic angular distribution for a deep penetration of 14-MeV neutrons in Cu	9
Comparison and evaluation of resolved resonance region covariance representations	8
Benchmark simulation code for the thermal-hydraulics design tool of the accelerator-driven system: validation and benchmark simulation of flow behavior around the beam window	8
Validation of LWR fuel depletion calculation module of reactor physics code system CBZ	8
Radiation imaging using an integrated Radiation Imaging System based on a compact Compton camera under unit 1/2 exhaust stack of Fukushima Daiichi Nuclear Power Station	8

Rare earth elements and radioactive elements in black sands from the Konkan and Malabar coasts of India	8
Degradation of nuclear fuel debris analog by siderophore-releasing microorganisms	8
Calculations and analysis of n+ ⁵² Cr reactions below 20 MeV	8
Role of solute titanium and oxidation in cesium chemisorption onto stainless steel	8
Cryogenic distribution system design for cryomodules and cavities test in HIAF project	8
Human reliability analysis of shared equipment in multi-unit site	8
Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility	7
Development of a water Cherenkov neutron detector for the active rotation method and demonstration of nuclear material detection	7
Numerical analysis of flow-induced deflection of curved nuclear reactor fuel plates under high velocity flows	7
Coupled chemo-hydro-mechanical effects on volume change behaviour of compacted bentonite used as buffer/backfill material in high-level radioactive waste repository	7
Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons	7
Experimental techniques for investigating thermal transport in nuclear materials	7
Measurements of capture cross-section of ⁹³ Nb by activation method and half-life of ⁹⁴ Nb by mass analysis	7
JENDL photonuclear data file 2016	7
A safety enhanced sodium-cooled MOX fueled fast reactor core concept	7
Study on melting behavior of tungsten under high heat load including verification of simulation code using other metals	6
Ten years after the NPP accident at Fukushima : review on fuel debris behavior in contact with water	6
Experimental study on mechanical properties of corroded steel used as containment liner in nuclear power plant	6
Application of continuous Markov-chain Monte-Carlo method to multi-unit risk evaluations considering interdependence of accident progression among multiple units	6
Micro-mechanical investigation about degradation of grain boundary cohesive strength of neutron-irradiated stainless steels	6
Recovery and immobilization of cesium from aqueous solution after hydrothermal treatment using functional porous glass	6
Evaluation of anisotropic elastic and plastic parameters of zircaloy-4 fuel cladding from biaxial stress test data and their application to a fracture mechanics analysis	6
A thermal-hydraulic analysis model of printed circuit heat exchangers for system simulation using Modelica	6
Consideration of delayed neutron effect on Rossi-α analysis for a subcritical thermal reactor	6
Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants	5
Nuclear data generation by machine learning (I) application to angular distributions for nucleon-nucleus scattering	5
The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations	5
Design and actual performance of J-PARC 3 GeV rapid cycling synchrotron for high-intensity operation	5
Effect of surface oxidation on the cesium chemisorption behavior of SS 304, Inconel 600 and X-750	5
A surface cracks detection method for nuclear fuel pellets using an improved fully convolutional network	5
Incineration of trans-uranium elements using chlorides molten salt fast reactors – A proposal of incineration in three steps	5
Correction	5
Dose rate distribution measuring method using personal dosimeters and localization devices	5
Drag coefficient of circular cylinder in axial flow of water for a wide range of length to diameter ratios	5
Thermal-neutron capture cross-section measurement of Tantalum-181 using graphite thermal column at KUR	5
Novel concept for a filtered containment venting system with an ionic liquid to remove organic iodine (1)-proof of concept for organic iodine removal	5
Steady-state thermal-structural analysis of high-temperature heat pipes based on thermal-fluid coupling	4
Arsenazo III-spectrophotometry for the determination of thorium content	4
A Raman spectroscopy study of bicarbonate effects on UO _2+x	4
Reactivity estimation based on the linear equation of characteristic time profile of power in subcritical quasi-steady state	4
Investigation into activation of accelerators at various synchrotron radiation facilities in Japan	4
Walking survey technique for ambient gamma dose rate measurement established in Fukushima Medical University	4
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids	4
A study on the establishment of database for local government disaster response and decision support system in the nuclear accidents	4
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique	4
Investigation of random beam trips in a linear accelerator at the Japan proton accelerator research complex for the development of an accelerator-driven nuclear transmutation system	4
Evaluating the irradiation hardening of reactor pressure vessel steels by nanoindentation hardness test and micropillar compression test	4
Research on the design of a radiation biodevice based on a compact D-D neutron generator	4
Transient heat transfer analysis of double-layer molten pool under severe accident	4
Localizing unknown radiation sources by unscented particle filtering based on divide-and-conquer sampling	4

Using Lorentz force flowmeter to measure the narrow channel flow that mimics lead-bismuth cooled reactors	4
Development of glass gas electron multiplier-based pulse counting imaging system with FPD front-end electronics	4
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel	4
Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector	4
In-situ TEM observation of migration behavior of helium bubbles in F82H	4
Evaluation of the structural integrity of a BWR core shroud with non-regular locations of circumferential cracks. Part I fracture analysis	4
A membrane, pseudo-vertical p-i-n diamond detector	4
A design study on a metal fuel fast reactor core for high efficiency minor actinide transmutation by loading silicon carbide composite material	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
Correction	4
Proposal of quantification method of dynamic system reliability model of digital RPS using Markov state-transition model	3
Convergence behavior of statistical uncertainty in probability table for cross section in unresolved resonance region	3
Two-dimensional elemental mapping of simulated fuel debris using laser-induced breakdown spectroscopy	3
Design and development of the machine protection system for HIAF	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
Monte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO ₂ and BWR-MOX fuels in the RUBUS program	3
Study on the drop impact acceleration of the radioactive package by new approximation method based on velocity obtained by integrating acceleration	3
A numerical approach for inlet-outlet boundary conditions with least-square moving particle explicit (LSMPE) method on GPU	3
Japanese evaluated nuclear data library version 5: JENDL-5	3
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level	3
Development of a theoretical scaling factor method for the inventory estimation of difficult-to-measure nuclide Cs-135 in fuel debris and radioactive wastes	3
Radiation-induced amorphization behavior of thermally-aged M₂₃C₆ in F82H-BA12 steel	3
Numerical simulation method using a Cartesian grid for oxidation of core materials under steam-starved conditions	3
Preface to a special issue of journal of nuclear science and Technology on “Nuclear Data and Code Systems as a Basis of Nuclear Technology”	3
Diffusion behavior of cesium in graphite matrix for a high-temperature reactor pebble-bed module: a first-principles study	3
Neutron total and capture cross-section measurements of ¹⁵⁵Gd and ¹⁵⁷Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC·MLF·	3
Experimental investigation of spray cooling behavior in 4×4 simulated fuel bundle	3
Energy dependent calculations of fission product, prompt, and delayed neutron yields for neutron induced fission on ²³⁵ U, ²³⁸ U,	3
Tensile properties of irradiated modified 316 stainless steel (PNC316) at slow strain rates	3
Evaluation of shielding performance and light emission characteristics of luminescent radiation shields using Gd ₂ O ₂ S	3
A new separation method of hydrogen isotope by dynamically created nonequilibrium state	3
Molecular dynamics simulation study of the effect of Ce ⁴⁺ incorporation at Zr site on the threshold displacement energy in Y ₄ Zr	3
A review of efforts for volume reduction of contaminated soil in the ten years after the accident at the Fukushima Daiichi Nuclear Power Plant	3
Cesium immobilization from aqueous solution by struvite synthesis	3
²⁴¹ Am Neutron Capture Cross Section Measurement using the NaI(Tl) spectrometer of the ANNRI beamline of J-PARC	3
Reactor reactivity calculations with simplified-P3 and perturbation theories	3
A dynamic probabilistic risk assessment platform for nuclear power plants under single and concurrent transients	3
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH	3
Tsunami flooding analysis graded-approach framework for tsunami probabilistic risk assessment	3
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning	3
Numerical study of initiating phase of core disruptive accident in small sodium-cooled fast reactors with negative void reactivity	3
Development of a multipoint liquid film sensor using an optical waveguide film on simulated fuel rod of BWRs	3
A review on failure behavior and life prediction of circulation pumps in lead-bismuth eutectic cooled reactors	3
The development of Petri net-based continuous Markov chain Monte Carlo methodology applying to dynamic probability risk assessment for multi-state resilience systems with repairable multi-component in	3
Redistribution of Nb and other alloying elements in Nb-doped Zr alloy under high dose ion irradiation	3
Simulated performance evaluation of d-Be compact fast neutron source	3
Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV	3
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	3
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	3
Solubility of FeSe₂(cr) at 318 K in the presence of iron	3
Estimation of influence of implicit effect due to multi-group cross-section perturbations on uncertainty analysis in PWR-UO ₂ and -MOX lattice calculations	3
Study on chemical interaction between UO₂ and Zr at precisely controlled high temperatures	3