Journal of Nuclear Science and Technology

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 2020-05-01 to 2024-05-01.)
ArticleCitations
Japanese evaluated nuclear data library version 5: JENDL-599
JENDL/DEU-2020: deuteron nuclear data library for design studies of accelerator-based neutron sources25
Robust bubble feature extraction in gas-liquid two-phase flow using object detection technique23
Development of a laser-induced breakdown spectroscopy system using a ceramic micro-laser for fiber-optic remote analysis21
Effects of gamma irradiation on the degradation of silicone rubber by steam exposure21
Fukushima Daiichi fuel debris retrieval: results of aerosol characterization during laser cutting of non-radioactive corium simulants17
Ten years after the NPP accident at Fukushima : review on fuel debris behavior in contact with water17
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 Station17
Evaluation of fission product yields and associated covariance matrices14
Pressure drop in a prototypical 3D magnetohydrodynamic flow across contraction of a fusion blanket manifold14
Bearing fault diagnosis using weakly supervised long short-term memory14
Exhaust behavior of tritium from the large helical device in the first deuterium plasma experiment13
Comparison of degradation behavior between soft and hard epoxy resins13
Encapsulation of Sr-loaded titanate spent adsorbents in potassium aluminosilicate geopolymer12
Comparison of the observed Fukushima Dai-Ichi Unit 2 debris with simulated debris from the CLADS-MADE-01 control blade degradation test12
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 analysis12
Cross-domain fault diagnosis of rotating machinery in nuclear power plant based on improved domain adaptation method11
Source multiplication measurements and neutron correlation analyses for a highly enriched uranium subcritical core driven by an inherent source in Kyoto University Critical Assembly11
A sensitive method for Sr-90 analysis by accelerator mass spectrometry10
Measurement of displacement cross-sections of copper and iron for proton with kinetic energies in the range 0.4 – 3 GeV10
Energy dependent calculations of fission product, prompt, and delayed neutron yields for neutron induced fission on 235U, 238U, and 239Pu10
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.3310
Decomposition behavior of gaseous ruthenium tetroxide under atmospheric conditions assuming evaporation to dryness accident of high-level liquid waste10
Use of Bayesian networks and improved SPAR-H for quantitative analysis of human reliability during severe accidents mitigation process in nuclear power plant9
Evaluation of core material energy change during the in-vessel phase of Fukushima Daiichi Unit 3 based on observed pressure data utilizing GOTHIC code analysis8
Removal of uranium from aqueous solutions using amine-functionalized magnetic platelet large-pore SBA-158
Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV8
Multi-group neutron cross section generation capability for FRENDY nuclear data processing code8
Benchmark study of particle and heavy-ion transport code system using shielding integral benchmark archive and database for accelerator-shielding experiments8
Leaching behavior of radionuclides from samples prepared from spent fuel rod comparable to core debris in the 1F NPS8
Investigation of high-temperature chemical interaction of calcium silicate insulation and cesium hydroxide8
Estimation of the sugar content of fruit by energy-resolved computed tomography using a material decomposition method8
Development of local-scale high-resolution atmospheric dispersion model using large-eddy simulation part 6: introduction of detailed dose calculation method8
Design and actual performance of J-PARC 3 GeV rapid cycling synchrotron for high-intensity operation8
New-designed in-situ measurement system for radon concentration in soil air and its application in vertical profile observation7
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 waste7
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 camera7
Implementation of surface crack detection method for nuclear fuel pellets guided by convolution neural network7
Theoretical and experimental estimation of the relative optically stimulated luminescence efficiency of an optical-fiber-based BaFBr:Eu detector for swift ions7
Distribution of studtite and metastudtite generated on the surface of U3O8: application of Raman imaging technique to uranium compound7
Molten salt oxidation and process analysis of anionic exchange resin in Na2CO3-K2CO3 melt7
A review of efforts for volume reduction of contaminated soil in the ten years after the accident at the Fukushima Daiichi Nuclear Power Plant7
Development of local-scale high-resolution atmospheric dispersion and dose assessment system6
Determination of 135Cs/137Cs isotopic ratio in soil collected near Fukushima Daiichi nuclear power station through mass spectrometry6
Mechanistic study on the removal of Cs from contaminated soil by rapid ion exchange in subcritical water6
High-temperature ex-vessel corium spreading. Part 1: experimental investigations on ceramic and sacrificial concrete substrates6
Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator6
JENDL-5 benchmark test for shielding applications6
Application of dynamic mode decomposition to Rossi-α method in a critical state using file-by-file moving block bootstrap method6
EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-56
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 to6
First-principles investigation of grain boundary structure effects on hydrogen solubility and segregation in tungsten6
A thermal-hydraulic analysis model of printed circuit heat exchangers for system simulation using Modelica6
Applicability of several Feynman-α formulae to a subcritical thermal reactor6
Microparticles with diverse sizes and morphologies from mechanical and laser cutting of fuel debris simulants and geopolymer as a covering material6
A molten metal jet impingement on a flat spreading surface6
Revolatilization of iodine by bubbly flow in the suppression pool during an accident6
Thermal-neutron capture cross-section measurement of Tantalum-181 using graphite thermal column at KUR6
Designs and neutronic characteristics of an epithermal neutron moderator at ambient temperature for neutron time-of-flight measurements5
Examining the influence of public participation on public acceptance of nuclear power plants: the case study of Qinshan NPP, China5
Distribution, dynamics, and fate of radiocesium derived from FDNPP accident in the ocean5
Air dose rates and cesium-137 in urban areas—deposition, migration, and time dependencies after nuclear power plant accidents5
A preliminary site risk assessment5
Fast reproduction of time-dependent diffusion calculations using the reduced order model based on the proper orthogonal and singular value decompositions5
Development and validation of an agglomeration model for CFD simulations of aerosol dispersion in the frame of Fukushima fuel debris retrieval5
Recovery of the laser-induced breakdown spectroscopy system using a ceramic microchip deteriorated by radiation for the remote elemental analysis5
JENDL-5 benchmarking for fission reactor applications5
Experimental study on transport behavior of cesium iodide in the reactor coolant system under LWR severe accident conditions5
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations5
Safety assessment of second-phase disposal facility in Gyeongju low- and intermediate-level radioactive waste (LILW) repository using RESRAD-OFFSITE code5
Experimental evaluation of Sr and Ba distribution in ex-vessel debris under a temperature gradient5
Strontium adsorption characteristics of natural Zeolites for permeable reactive barrier in Fukushima Daiichi nuclear power station5
G-HyND: a hybrid nuclear data estimator with Gaussian processes5
Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants5
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure4
The dependence of pool scrubbing decontamination factor on particle number density: modeling based on bubble mass and energy balances4
High-temperature ex-vessel corium spreading. Part 2: scaling principles for gravity-viscous spreading with slip at the melt–substrate interface4
Measurements of the neutron capture cross section of 243Am around 23.5 keV4
Application of a particle-grid hybrid method in multiphase flow calculation4
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·4
Thermal-neutron capture cross sections and resonance integrals of the 243Am(n,γ)244gAm and 243Am(n,γ)244m+gAm reactions4
Feynman-α and Rossi-α analyses for a subcritical reactor system driven by a pulsed spallation neutron source in Kyoto University Critical Assembly4
Study on cesium compound formation by chemical interaction of CsOH and concrete at elevated temperatures4
Precipitation behavior of M23C6 carbides and its effect on mechanical properties of Ni-based Alloy 6904
Cesium Chemistry in the LWR severe accident and towards the decommissioning of Fukushima Daiichi Nuclear Power Station4
Iterative reconstruction algorithm comparison using Poisson noise distributed sinogram data in passive gamma emission tomography4
H2 generation at metal oxide particle surfaces under γ-radiation in water4
Application of ensemble method to predict radiation doses from a radioactive release during hypothetical severe accidents at Russian NPP4
KeV-region analysis of the neutron capture cross-section of 237Np4
Walking survey technique for ambient gamma dose rate measurement established in Fukushima Medical University4
The buildup factor calculations of concrete with different proportions of CRT based on a BP neural network by MCNP4
Neutron yield calculation of thin and thick d-D targets by using PHITS with frag data table4
Investigation on free-surface vortices within a closed pump intake under different pressure conditions using stereo PIV4
A BWR control blade degradation observed in situ during a CLADS-MADE-02 test under Fukushima Dai-Ichi Unit 3 postulated conditions4
Frequency domain Monte Carlo simulations of void velocity measurements in an actual experimental setup using a neutron noise technique4
Development of interaction model on the risk assessment method for nuclear facilities using a system model with a multi-layer structure4
Research on optimization design of PWR flow distribution device based on numerical simulation4
High temperature electrochemical reaction parameters affecting elecrochemical corrosion potential of type 316L stainless steel3
Exact Monte Carlo calculation method for K-eigenvalue change using perturbation source method3
Evaluation of uncertainties derived from meteorological forecast inputs in plume directions predicted by atmospheric dispersion simulations3
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 University3
In-situ TEM observation of migration behavior of helium bubbles in F82H3
Crystallographic orientation dependent of blisters formation on tungsten surface exposed to helium ions3
Density functional modeling of Am3+/Eu3+ selectivity with diethylenetriaminepentaacetic acid and its bisamide chelates.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/CHARM3
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 model3
An improved theoretical method for determining the mean D-T neutron energies in large solid angle sample3
Ten years of Fukushima Dai-Ichi post-accident research on the degradation phenomenology of the BWR core components3
Granular fuel debris shape modeling in MPS-DEM for the simulation of fuel debris bed formation in water3
Bayesian-estimation-based method for generating fragility curves for high-fidelity seismic probability risk assessment3
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 estimation3
Neutron capture cross sections of curium isotopes measured with ANNRI at J-PARC3
Sensitivity and uncertainty analyses of fission product nuclide inventories for passive gamma spectroscopy3
Improvement of the optimally-weighted predictor-corrector method for nuclear fuel burnup calculations3
Impact of nuclear data revised from JENDL-4.0 to JENDL-5 on PWR spent fuel nuclide composition3
Investigation into activation of accelerators at various synchrotron radiation facilities in Japan3
Nuclear security system effectiveness assessment using bounded analysis approach: a case study of different adversary scenarios3
Calculation of recoil nucleus spectrum in the presence of multi-particle emission in nuclear reaction with Monte Carlo method as an extension of CCONE code3
Present status and practical issues on dosimetry for the lens of the eye at JAEA MOX fuel facilities3
Transient analysis of TMSR-SF0 simulator3
Composition optimization of radiation resistance ODS alloy with high strength and ductility for advanced reactor based on machine learning3
Development of ACE file perturbation tool using FRENDY3
Restraint effect of coexisting nitrite ion in simulated high level liquid waste on releasing volatile ruthenium under boiling condition3
Chemical species of iodine during sorption by activated carbon -Effects of original chemical species and fulvic acids3
Test of 107Pd transmutation with macroscopic quantities3
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates3
Degradation mechanism of stainless steel by U-Zr-O molten mixture during core degradation of BWR severe accident3
Model design of a deuterium-deuterium neutron generator moderator and evaluation for delayed gamma-ray nondestructive assay for safeguards verification3
Cross-section adjustment method based on Bayesian theory for specific cross-section set3
Monte Carlo analyses of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly3
Stochastic estimation of radionuclide composition in wastes generated at Fukushima Daiichi nuclear power station using Bayesian inference3
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy3
Modeling of distribution parameters for upward steam-water boiling flows in subchannels of a vertical rod bundle3
Corrosion behavior of zirconium alloys in the aqueous environment. Phenomenological aspects. Overview3
Improvement of thermal conductivity by adding tungsten and/or copper wire in F82H3
Online measurement of the atmosphere around geopolymers under gamma irradiation3
Seismic response of electrical cabinets considering primary-secondary structure interaction with contact nonlinearity of anchors3
Evaluation of the production amount of 225 Ac and its uncertainty through the 226 Ra(n,2n) reaction in the experimental fast react3
Boiling and drying accident of high-level liquid waste in a reprocessing plant: Examination of the NO2 and NO generation using the simulated waste3
Sintering and microstructural behaviors of mechanically blended Nd/Sm-doped MOX3
Estimation of uncertainty in transmutation rates of LLFPs in a fast reactor transmutation system via an estimation of the cross-section covariances3
Multi-objective optimization based on economic analysis for a printed circuit heat exchanger with application to Brayton cycle3
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