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 2020-04-01 to 2024-04-01.)

Article	Citations
Japanese evaluated nuclear data library version 5: JENDL-5	81
JENDL/DEU-2020: deuteron nuclear data library for design studies of accelerator-based neutron sources	25
Development of a laser-induced breakdown spectroscopy system using a ceramic micro-laser for fiber-optic remote analysis	21
Effects of gamma irradiation on the degradation of silicone rubber by steam exposure	21
Robust bubble feature extraction in gas-liquid two-phase flow using object detection technique	19
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	17
Ten years after the NPP accident at Fukushima : review on fuel debris behavior in contact with water	16
Fukushima Daiichi fuel debris retrieval: results of aerosol characterization during laser cutting of non-radioactive corium simulants	16
Pressure drop in a prototypical 3D magnetohydrodynamic flow across contraction of a fusion blanket manifold	14
Bearing fault diagnosis using weakly supervised long short-term memory	14
Evaluation of fission product yields and associated covariance matrices	14
Comparison of degradation behavior between soft and hard epoxy resins	13
Exhaust behavior of tritium from the large helical device in the first deuterium plasma experiment	13
Encapsulation of Sr-loaded titanate spent adsorbents in potassium aluminosilicate geopolymer	12
Comparison of the observed Fukushima Dai-Ichi Unit 2 debris with simulated debris from the CLADS-MADE-01 control blade degradation test	12
Step-by-step challenge of debris characterization for the decommissioning of Fukushima-Daiichi Nuclear Power Station (FDNPS)	12
Radiation dose rate effects on the properties of a laser-induced breakdown spectroscopy system developed using a ceramics micro-laser for fiber-optic remote analysis	12
Cross-domain fault diagnosis of rotating machinery in nuclear power plant based on improved domain adaptation method	11
A sensitive method for Sr-90 analysis by accelerator mass spectrometry	10
Source multiplication measurements and neutron correlation analyses for a highly enriched uranium subcritical core driven by an inherent source in Kyoto University Critical Assembly	10
Energy dependent calculations of fission product, prompt, and delayed neutron yields for neutron induced fission on ²³⁵U, ²³⁸U, and ²³⁹Pu	10
Measurement of displacement cross-sections of copper and iron for proton with kinetic energies in the range 0.4 – 3 GeV	10
Decomposition behavior of gaseous ruthenium tetroxide under atmospheric conditions assuming evaporation to dryness accident of high-level liquid waste	10
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33	9
Modeling of gap conductance for LWR fuel rods applied in the BISON code	9

Estimation of the sugar content of fruit by energy-resolved computed tomography using a material decomposition method	8
Evaluation of core material energy change during the in-vessel phase of Fukushima Daiichi Unit 3 based on observed pressure data utilizing GOTHIC code analysis	8
Development of local-scale high-resolution atmospheric dispersion model using large-eddy simulation part 6: introduction of detailed dose calculation method	8
Removal of uranium from aqueous solutions using amine-functionalized magnetic platelet large-pore SBA-15	8
Leaching behavior of radionuclides from samples prepared from spent fuel rod comparable to core debris in the 1F NPS	8
Design and actual performance of J-PARC 3 GeV rapid cycling synchrotron for high-intensity operation	7
Multi-group neutron cross section generation capability for FRENDY nuclear data processing code	7
Use of Bayesian networks and improved SPAR-H for quantitative analysis of human reliability during severe accidents mitigation process in nuclear power plant	7
Theoretical and experimental estimation of the relative optically stimulated luminescence efficiency of an optical-fiber-based BaFBr:Eu detector for swift ions	7
A review of efforts for volume reduction of contaminated soil in the ten years after the accident at the Fukushima Daiichi Nuclear Power Plant	7
New-designed in-situ measurement system for radon concentration in soil air and its application in vertical profile observation	7
Attenuation length of high energy neutrons through a thick concrete shield measured by activation detectors at CHARM	7
Evaluation of the technical options of radioactive waste management for utilization of MOX fuel: thermal impact of minor actinide separation with geological disposal of high-level waste	7
Distribution of studtite and metastudtite generated on the surface of U₃O₈: application of Raman imaging technique to uranium compound	7
Investigation of high-temperature chemical interaction of calcium silicate insulation and cesium hydroxide	7
Benchmark study of particle and heavy-ion transport code system using shielding integral benchmark archive and database for accelerator-shielding experiments	7
Molten salt oxidation and process analysis of anionic exchange resin in Na₂CO₃-K₂CO₃ melt	7
Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV	7
Development of local-scale high-resolution atmospheric dispersion and dose assessment system	6
Microparticles with diverse sizes and morphologies from mechanical and laser cutting of fuel debris simulants and geopolymer as a covering material	6
A molten metal jet impingement on a flat spreading surface	6
Implementation of surface crack detection method for nuclear fuel pellets guided by convolution neural network	6
Thermal-neutron capture cross-section measurement of Tantalum-181 using graphite thermal column at KUR	6
Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator	6
Application of dynamic mode decomposition to Rossi-α method in a critical state using file-by-file moving block bootstrap method	6
EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5	6
Mechanistic study on the removal of Cs from contaminated soil by rapid ion exchange in subcritical water	6
Revolatilization of iodine by bubbly flow in the suppression pool during an accident	6
First-principles investigation of grain boundary structure effects on hydrogen solubility and segregation in tungsten	6
A thermal-hydraulic analysis model of printed circuit heat exchangers for system simulation using Modelica	6
Applicability of several Feynman-α formulae to a subcritical thermal reactor	6
Determination of ¹³⁵Cs/¹³⁷Cs isotopic ratio in soil collected near Fukushima Daiichi nuclear power station through mass spectrometry	6
Evaluation of decreasing trend in air dose rate and ecological half-life within an 80 km range from Fukushima Dai-ichi Nuclear Power Plant, using car-borne survey data measured by KURAMA systems up to	6
High-temperature ex-vessel corium spreading. Part 1: experimental investigations on ceramic and sacrificial concrete substrates	6
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	6
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	5
JENDL-5 benchmark test for shielding applications	5
Examining the influence of public participation on public acceptance of nuclear power plants: the case study of Qinshan NPP, China	5
Safety assessment of second-phase disposal facility in Gyeongju low- and intermediate-level radioactive waste (LILW) repository using RESRAD-OFFSITE code	5
JENDL-5 benchmarking for fission reactor applications	5
Utilizing PUNITA experiments to evaluate fundamental delayed gamma-ray spectroscopy interrogation requirements for nuclear safeguards	5
Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants	5
Development and validation of an agglomeration model for CFD simulations of aerosol dispersion in the frame of Fukushima fuel debris retrieval	5
Recovery of the laser-induced breakdown spectroscopy system using a ceramic microchip deteriorated by radiation for the remote elemental analysis	5
Strontium adsorption characteristics of natural Zeolites for permeable reactive barrier in Fukushima Daiichi nuclear power station	5
Experimental study on transport behavior of cesium iodide in the reactor coolant system under LWR severe accident conditions	5
A preliminary site risk assessment	5
Fast reproduction of time-dependent diffusion calculations using the reduced order model based on the proper orthogonal and singular value decompositions	5
Designs and neutronic characteristics of an epithermal neutron moderator at ambient temperature for neutron time-of-flight measurements	5
Experimental evaluation of Sr and Ba distribution in ex-vessel debris under a temperature gradient	5

Air dose rates and cesium-137 in urban areas—deposition, migration, and time dependencies after nuclear power plant accidents	5
G-HyND: a hybrid nuclear data estimator with Gaussian processes	5
The dependence of pool scrubbing decontamination factor on particle number density: modeling based on bubble mass and energy balances	4
Investigation on free-surface vortices within a closed pump intake under different pressure conditions using stereo PIV	4
Measurements of the neutron capture cross section of ²⁴³Am around 23.5 keV	4
Frequency domain Monte Carlo simulations of void velocity measurements in an actual experimental setup using a neutron noise technique	4
Application of a particle-grid hybrid method in multiphase flow calculation	4
Research on optimization design of PWR flow distribution device based on numerical simulation	4
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure	4
Distribution, dynamics, and fate of radiocesium derived from FDNPP accident in the ocean	4
High-temperature ex-vessel corium spreading. Part 2: scaling principles for gravity-viscous spreading with slip at the melt–substrate interface	4
H₂ generation at metal oxide particle surfaces under γ-radiation in water	4
A BWR control blade degradation observed in situ during a CLADS-MADE-02 test under Fukushima Dai-Ichi Unit 3 postulated conditions	4
Application of ensemble method to predict radiation doses from a radioactive release during hypothetical severe accidents at Russian NPP	4
Thermal-neutron capture cross sections and resonance integrals of the ²⁴³Am(n,γ)^244gAm and ²⁴³Am(n,γ)^244m+gAm reactions	4
The buildup factor calculations of concrete with different proportions of CRT based on a BP neural network by MCNP	4
Precipitation behavior of M₂₃C₆ carbides and its effect on mechanical properties of Ni-based Alloy 690	4
Cesium Chemistry in the LWR severe accident and towards the decommissioning of Fukushima Daiichi Nuclear Power Station	4
Iterative reconstruction algorithm comparison using Poisson noise distributed sinogram data in passive gamma emission tomography	4
Development of interaction model on the risk assessment method for nuclear facilities using a system model with a multi-layer structure	4
KeV-region analysis of the neutron capture cross-section of ²³⁷Np	4
Walking survey technique for ambient gamma dose rate measurement established in Fukushima Medical University	4
Study on cesium compound formation by chemical interaction of CsOH and concrete at elevated temperatures	4
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy	3
Impact of nuclear data revised from JENDL-4.0 to JENDL-5 on PWR spent fuel nuclide composition	3
Measurements and Monte Carlo simulations of high-energy neutron streaming through the access maze using activation detectors at 24 GeV/c proton beam facility of CERN/CHARM	3
Improvement of thermal conductivity by adding tungsten and/or copper wire in F82H	3
Sintering and microstructural behaviors of mechanically blended Nd/Sm-doped MOX	3
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates	3
Granular fuel debris shape modeling in MPS-DEM for the simulation of fuel debris bed formation in water	3
Improvement of the optimally-weighted predictor-corrector method for nuclear fuel burnup calculations	3
Sensitivity and uncertainty analyses of fission product nuclide inventories for passive gamma spectroscopy	3
Model design of a deuterium-deuterium neutron generator moderator and evaluation for delayed gamma-ray nondestructive assay for safeguards verification	3
Cross-section adjustment method based on Bayesian theory for specific cross-section set	3
Test of ¹⁰⁷Pd transmutation with macroscopic quantities	3
Stochastic estimation of radionuclide composition in wastes generated at Fukushima Daiichi nuclear power station using Bayesian inference	3
Crystallographic orientation dependent of blisters formation on tungsten surface exposed to helium ions	3
Nuclear security system effectiveness assessment using bounded analysis approach: a case study of different adversary scenarios	3
Present status and practical issues on dosimetry for the lens of the eye at JAEA MOX fuel facilities	3
Online measurement of the atmosphere around geopolymers under gamma irradiation	3
An improved theoretical method for determining the mean D-T neutron energies in large solid angle sample	3
Dependency of the source term estimation method for radionuclides released into the atmosphere on the available environmental monitoring data and its applicability to real-time source term estimation	3
Estimation of uncertainty in transmutation rates of LLFPs in a fast reactor transmutation system via an estimation of the cross-section covariances	3
Neutron capture cross sections of curium isotopes measured with ANNRI at J-PARC	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
Neutron yield calculation of thin and thick d-D targets by using PHITS with frag data table	3
Multi-objective optimization based on economic analysis for a printed circuit heat exchanger with application to Brayton cycle	3
Evaluation of uncertainties derived from meteorological forecast inputs in plume directions predicted by atmospheric dispersion simulations	3
Calculation of recoil nucleus spectrum in the presence of multi-particle emission in nuclear reaction with Monte Carlo method as an extension of CCONE code	3
In-situ TEM observation of migration behavior of helium bubbles in F82H	3
Measurement of 107-MeV proton-induced double-differential thick target neutron yields for Fe, Pb, and Bi using a fixed-field alternating gradient accelerator at Kyoto University	3
Density functional modeling of Am³⁺/Eu³⁺ selectivity with diethylenetriaminepentaacetic acid and its bisamide chelates.	3
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	3
Transient analysis of TMSR-SF0 simulator	3
Restraint effect of coexisting nitrite ion in simulated high level liquid waste on releasing volatile ruthenium under boiling condition	3
Evaluation of the production amount of ²²⁵ Ac and its uncertainty through the ²²⁶ Ra(n,2n) reaction in the experimental fast react	3
Chemical species of iodine during sorption by activated carbon -Effects of original chemical species and fulvic acids	3
High temperature electrochemical reaction parameters affecting elecrochemical corrosion potential of type 316L stainless steel	3
Boiling and drying accident of high-level liquid waste in a reprocessing plant: Examination of the NO₂ and NO generation using the simulated waste	3
Exact Monte Carlo calculation method for K-eigenvalue change using perturbation source method	3
Degradation mechanism of stainless steel by U-Zr-O molten mixture during core degradation of BWR severe accident	3
Feynman-α and Rossi-α analyses for a subcritical reactor system driven by a pulsed spallation neutron source in Kyoto University Critical Assembly	3
Investigation into activation of accelerators at various synchrotron radiation facilities in Japan	3
Modeling of distribution parameters for upward steam-water boiling flows in subchannels of a vertical rod bundle	3