OOIR: Observatory of International Research

Papers

(The median citation count of Journal of Nuclear Science and Technology is 1. 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 2020-11-01 to 2024-11-01.)

Article	Citations
Japanese evaluated nuclear data library version 5: JENDL-5	138
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33	41
JENDL/DEU-2020: deuteron nuclear data library for design studies of accelerator-based neutron sources	27
Ten years after the NPP accident at Fukushima : review on fuel debris behavior in contact with water	23
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	19
Pressure drop in a prototypical 3D magnetohydrodynamic flow across contraction of a fusion blanket manifold	15
Comparison of degradation behavior between soft and hard epoxy resins	14
Step-by-step challenge of debris characterization for the decommissioning of Fukushima-Daiichi Nuclear Power Station (FDNPS)	13
Comparison of the observed Fukushima Dai-Ichi Unit 2 debris with simulated debris from the CLADS-MADE-01 control blade degradation test	13
Energy dependent calculations of fission product, prompt, and delayed neutron yields for neutron induced fission on ²³⁵U, ²³⁸U, and ²³⁹Pu	13
Benchmark study of particle and heavy-ion transport code system using shielding integral benchmark archive and database for accelerator-shielding experiments	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
Molten salt oxidation and process analysis of anionic exchange resin in Na₂CO₃-K₂CO₃ melt	11
Cross-domain fault diagnosis of rotating machinery in nuclear power plant based on improved domain adaptation method	11
Use of Bayesian networks and improved SPAR-H for quantitative analysis of human reliability during severe accidents mitigation process in nuclear power plant	10
Theoretical and experimental estimation of the relative optically stimulated luminescence efficiency of an optical-fiber-based BaFBr:Eu detector for swift ions	10
Multi-group neutron cross section generation capability for FRENDY nuclear data processing code	9
Design and actual performance of J-PARC 3 GeV rapid cycling synchrotron for high-intensity operation	9
Estimation of the sugar content of fruit by energy-resolved computed tomography using a material decomposition method	9
Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV	9
Implementation of surface crack detection method for nuclear fuel pellets guided by convolution neural network	9
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	9
EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5	8
Development of local-scale high-resolution atmospheric dispersion model using large-eddy simulation part 6: introduction of detailed dose calculation method	8
Application of dynamic mode decomposition to Rossi-α method in a critical state using file-by-file moving block bootstrap method	8

New-designed in-situ measurement system for radon concentration in soil air and its application in vertical profile observation	8
A review of efforts for volume reduction of contaminated soil in the ten years after the accident at the Fukushima Daiichi Nuclear Power Plant	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
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	8
Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator	8
Determination of ¹³⁵Cs/¹³⁷Cs isotopic ratio in soil collected near Fukushima Daiichi nuclear power station through mass spectrometry	7
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	7
Thermal-neutron capture cross-section measurement of Tantalum-181 using graphite thermal column at KUR	7
JENDL-5 benchmark test for shielding applications	7
Microparticles with diverse sizes and morphologies from mechanical and laser cutting of fuel debris simulants and geopolymer as a covering material	7
A thermal-hydraulic analysis model of printed circuit heat exchangers for system simulation using Modelica	7
Development of local-scale high-resolution atmospheric dispersion and dose assessment system	7
Strontium adsorption characteristics of natural Zeolites for permeable reactive barrier in Fukushima Daiichi nuclear power station	7
Distribution of studtite and metastudtite generated on the surface of U₃O₈: application of Raman imaging technique to uranium compound	7
Applicability of several Feynman-α formulae to a subcritical thermal reactor	6
Recovery of the laser-induced breakdown spectroscopy system using a ceramic microchip deteriorated by radiation for the remote elemental analysis	6
Air dose rates and cesium-137 in urban areas—deposition, migration, and time dependencies after nuclear power plant accidents	6
High-temperature ex-vessel corium spreading. Part 1: experimental investigations on ceramic and sacrificial concrete substrates	6
Distribution, dynamics, and fate of radiocesium derived from FDNPP accident in the ocean	6
Cesium Chemistry in the LWR severe accident and towards the decommissioning of Fukushima Daiichi Nuclear Power Station	6
Revolatilization of iodine by bubbly flow in the suppression pool during an accident	6
KeV-region analysis of the neutron capture cross-section of ²³⁷Np	6
Designs and neutronic characteristics of an epithermal neutron moderator at ambient temperature for neutron time-of-flight measurements	6
Experimental evaluation of Sr and Ba distribution in ex-vessel debris under a temperature gradient	6
JENDL-5 benchmarking for fission reactor applications	6
G-HyND: a hybrid nuclear data estimator with Gaussian processes	6
Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants	6
Study on cesium compound formation by chemical interaction of CsOH and concrete at elevated temperatures	5
H₂ generation at metal oxide particle surfaces under γ-radiation in water	5
In-situ TEM observation of migration behavior of helium bubbles in F82H	5
Development and validation of an agglomeration model for CFD simulations of aerosol dispersion in the frame of Fukushima fuel debris retrieval	5
Iterative reconstruction algorithm comparison using Poisson noise distributed sinogram data in passive gamma emission tomography	5
A preliminary site risk assessment	5
Safety assessment of second-phase disposal facility in Gyeongju low- and intermediate-level radioactive waste (LILW) repository using RESRAD-OFFSITE code	5
Seismic response of electrical cabinets considering primary-secondary structure interaction with contact nonlinearity of anchors	5
Development of ACE file perturbation tool using FRENDY	4
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates	4
Cross-section adjustment method based on Bayesian theory for specific cross-section set	4
Neutron yield calculation of thin and thick d-D targets by using PHITS with frag data table	4
The buildup factor calculations of concrete with different proportions of CRT based on a BP neural network by MCNP	4
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	4
Ensuring a prudent combination of risk insights and a defense-in-depth philosophy through a reinterpretation of hierarchical safety goals	4
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	4
A BWR control blade degradation observed in situ during a CLADS-MADE-02 test under Fukushima Dai-Ichi Unit 3 postulated conditions	4
Chemical species of iodine during sorption by activated carbon -Effects of original chemical species and fulvic acids	4
Development of interaction model on the risk assessment method for nuclear facilities using a system model with a multi-layer structure	4
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
Experimental and numerical study of a condensing steam jet	4
Exact Monte Carlo calculation method for K-eigenvalue change using perturbation source method	4
Modeling of distribution parameters for upward steam-water boiling flows in subchannels of a vertical rod bundle	4

The dependence of pool scrubbing decontamination factor on particle number density: modeling based on bubble mass and energy balances	4
High-temperature ex-vessel corium spreading. Part 2: scaling principles for gravity-viscous spreading with slip at the melt–substrate interface	4
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	4
Development of an evaluation method for planning of urgent protection strategies in a nuclear emergency using a level 3 probabilistic risk assessment	4
Application of ensemble method to predict radiation doses from a radioactive release during hypothetical severe accidents at Russian NPP	4
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	4
Walking survey technique for ambient gamma dose rate measurement established in Fukushima Medical University	4
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure	4
Bayesian-estimation-based method for generating fragility curves for high-fidelity seismic probability risk assessment	4
Seismic performance evaluation of base-isolated nuclear power plant reactor building considering aging effect of isolation device	4
A Staged Evacuation Methodology for Emergency Preparedness Plan	4
An improved theoretical method for determining the mean D-T neutron energies in large solid angle sample	4
Measurements of the neutron capture cross section of ²⁴³Am around 23.5 keV	4
Density functional modeling of Am³⁺/Eu³⁺ selectivity with diethylenetriaminepentaacetic acid and its bisamide chelates.	3
A surface cracks detection method for nuclear fuel pellets using an improved fully convolutional network	3
TRU oxide sample reactivity worths measured in the FCA-IX assemblies with systematically changed neutron energy spectra	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
Mutual separation of Am and Cm using ADAAM (Alkyl DiAmide AMine) and reduction of volumes for liquid waste generated via batch-wise multistage extractions	3
Cost-reduced depletion calculation including short half-life nuclides for nuclear fuel cycle simulation	3
Sintering and microstructural behaviors of mechanically blended Nd/Sm-doped MOX	3
Raman identification and characterization of chemical components included in simulated nuclear fuel debris synthesized from uranium, stainless steel, and zirconium	3
Integrating DeblurGAN and CNN to improve the accuracy of motion blur X-Ray image classification	3
Multi-objective optimization based on economic analysis for a printed circuit heat exchanger with application to Brayton cycle	3
Experimental study and modeling of bubble lift-off diameter in subcooled flow boiling including the inclination effect of the heating surface	3
Evaluation of uncertainties derived from meteorological forecast inputs in plume directions predicted by atmospheric dispersion simulations	3
Monte Carlo analyses of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly	3
Experimental study on mechanical properties of corroded steel used as containment liner in nuclear power plant	3
Impact of nuclear data revised from JENDL-4.0 to JENDL-5 on PWR spent fuel nuclide composition	3
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions	3
Uranium dissolution and uranyl peroxide formation by immersion of simulated fuel debris in aqueous H₂O₂ solution	3
²⁴¹Am Neutron Capture Cross Section in the keV region using Si and Fe-filtered neutron beams	3
Activity and weight ratios of cesium, uranium, plutonium, and curium isotopes based on elaborate inventory calculations of Fukushima Dai-ichi NPP units 1 to 3	3
Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant	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
Ten years of Fukushima Dai-Ichi post-accident research on the degradation phenomenology of the BWR core components	3
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments	3
Application of Bayesian machine learning for estimation of uncertainty in forecasted plume directions by atmospheric dispersion simulations	3
Crucial importance of correlation between cross sections and angular distributions in nuclear data of ²⁸Si on estimation of uncertainty of neutron dose penetrating a thick concrete	3
Neutron capture cross sections of curium isotopes measured with ANNRI at J-PARC	3
Validation of several sets of delayed-neutron group parameters for thermal fission of ²³⁵U by a Feynman-α analysis	3
Degradation mechanism of stainless steel by U-Zr-O molten mixture during core degradation of BWR severe accident	3
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy	3
Stochastic estimation of radionuclide composition in wastes generated at Fukushima Daiichi nuclear power station using Bayesian inference	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
Dose rate distribution measuring method using personal dosimeters and localization devices	3
Corrosion behavior of zirconium alloys in the aqueous environment. Phenomenological aspects. Overview	3
Improvement of thermal conductivity by adding tungsten and/or copper wire in F82H	3
Composition optimization of radiation resistance ODS alloy with high strength and ductility for advanced reactor based on machine learning	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
Granular fuel debris shape modeling in MPS-DEM for the simulation of fuel debris bed formation in water	3
Estimation of uncertainty in transmutation rates of LLFPs in a fast reactor transmutation system via an estimation of the cross-section covariances	3
High temperature electrochemical reaction parameters affecting elecrochemical corrosion potential of type 316L stainless steel	3
Test of ¹⁰⁷Pd transmutation with macroscopic quantities	3
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	3
Improvement of the optimally-weighted predictor-corrector method for nuclear fuel burnup calculations	3
Quantitative visualization of a radioactive plume with harmonizing gamma-ray imaging spectrometry and real-time atmospheric dispersion simulation based on 3D wind observation	3
Localizing unknown radiation sources by unscented particle filtering based on divide-and-conquer sampling	3
Crystallographic orientation dependent of blisters formation on tungsten surface exposed to helium ions	3
Investigation into activation of accelerators at various synchrotron radiation facilities in Japan	3
Proposal and applicability of estimated criticality lower-limit multiplication factor using the bootstrap method	2
Behaviors of actinides in chromatographic separation by using TBP resin in nitric acid solution and hydrochloric acid solution	2
Thermodynamic analysis and optimization for steam methane reforming hydrogen production system using high temperature gas-cooled reactor pebble-bed module	2
Development of a water Cherenkov neutron detector for the active rotation method and demonstration of nuclear material detection	2
Thermal-assisted back-extraction of inert platinum group metals from [Hbet][Tf₂N] ionic liquid phase to oxalic acid aqueous solution	2
Coupled chemo-hydro-mechanical effects on volume change behaviour of compacted bentonite used as buffer/backfill material in high-level radioactive waste repository	2
A pseudo-material method for graphite with arbitrary porosities in Monte Carlo criticality calculations	2
JENDL photonuclear data file 2016	2
Improvement of analysis results from the GAGG scintillator Compton camera operated on an unmanned helicopter by selecting stable flight conditions	2
Effect of surface oxidation on the cesium chemisorption behavior of SS 304, Inconel 600 and X-750	2
Iron-induced association between selenium and humic substances in groundwater from deep sedimentary formations	2
Geopolymer and ordinary Portland cement interface analyzed by micro-Raman and SEM	2
Consideration of delayed neutron effect on Rossi-α analysis for a subcritical thermal reactor	2
Correction of X-ray scattering in energy-resolved computed tomography imaging of 20-cm-diameter phantom	2
Nonuniform particle distribution and interference between removal mechanisms during unsteady aerosol deposition from a rising spherical bubble	2
Evaluating the Seismic Diversity and Robustness of Nuclear Power Plants	2
Measurement of forced convection subcooled boiling flow through a vertical annular channel with high-speed video cameras and image reconstruction	2
Study on dominant aspects of unprotected loss-of-flow to be evaluated in the initiating phase for a sodium-cooled fast reactor	2
Mechanical failure of high-burnup fuel rods with stress-relieved annealed and recrystallized M-MDA cladding under reactivity-initiated accident conditions	2
Flow accelerated corrosion of carbon steel containing chromium under water chemistry conditions of boiling water reactor applying mitigation techniques of corrosive environment	2
Nuclear data adjustment using a deterministic sampling method with unscented transformation	2

Conceptualization of the micro research reactor cooled by heat pipes (MRR-HP), part-II: safety analyses	2
Study on chemical interaction between UO₂ and Zr at precisely controlled high temperatures	2
Development of a laser-driven ultrasonic technology for characterizations of heated and aged concrete samples	2
Development of a multipoint liquid film sensor using an optical waveguide film on simulated fuel rod of BWRs	2
Determination of the tensile and fracture properties of ductile materials by small punch testing	2
Development of an integrated non-destructive analysis system, Active-N	2
Cesium immobilization from aqueous solution by struvite synthesis	2
Neutron-induced single event effect in Xilinx 16nm MPSoC configuration RAM (CRAM) using white neutron and 2.72~81.8meV neutron in CSNS-BL20	2
Study on the relationship between fuel fragmentation during a LOCA and pellet microstructure	2
Degradation of nuclear fuel debris analog by siderophore-releasing microorganisms	2
A generalized ternary decision diagram for reliability analysis on fault-tolerant systems in different coverage models	2
Recovery and immobilization of cesium from aqueous solution after hydrothermal treatment using functional porous glass	2
DEM simulations in nuclear engineering: a review of recent progress	2
Phase stability of Cs-Si-O and Cs-Si-Fe-O compounds on stainless steel	2
A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries	2
Two-dimensional elemental mapping of simulated fuel debris using laser-induced breakdown spectroscopy	2
Formulation of Irradiation Assisted Stress Corrosion Crack Growth Rates for Neutron-Irradiated Stainless Steels under Hydrogen Water Chemistry Conditions of Boiling Water Reactors	2
Fretting wear behavior test and numerical simulation of Inconel 690 alloy	2
Iodine tomographic images derived from a small number of X-ray transmission measurements using material thickness distributions	2
Effect of radiation and substitution of Ce⁴⁺ at Zr site in Y₄Zr₃O₁₂ using collision cascades: a molecular dynamics simulation study	2
Evaluation of mechanical cutting for disassembly of fast reactor fuel assemblies	2
Radio-tellurium released into the environment during the complete oxidation of fuel cladding, containment venting and reactor building failure of the Fukushima accident	2
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of Ni-base Alloy 182	2
Study on the drop impact acceleration of the radioactive package by new approximation method based on velocity obtained by integrating acceleration	2
Impact of MOX fuel use in light-water reactors: long-term radiological consequences of disposal of high-level waste in a geological repository	2
Novel concept for a filtered containment venting system with an ionic liquid to remove organic iodine (1)-proof of concept for organic iodine removal	2
Measurement and simulations of high-energy neutrons through a various thickness of concrete and steel shields using activation detectors at CHARM and CSBF	2
Conceptualization of the Micro Research Reactor Cooled by Heat Pipes (MRR-HP), Part-I: neutronics analyses	2
Application of continuous Markov-chain Monte-Carlo method to multi-unit risk evaluations considering interdependence of accident progression among multiple units	2
Development of interfacial velocity correlation for benchmarking porous media based three-dimensional code for steam generator with a square rod array	2
Role of solute titanium and oxidation in cesium chemisorption onto stainless steel	2
Development of a neutron beam monitor with a thin plastic scintillator for nuclear data measurement using spallation neutron source	2
Development of nuclear de-excitation model EBITEM Ver.2	2
Incineration of trans-uranium elements using chlorides molten salt fast reactors – A proposal of incineration in three steps	2
Request for ³⁵ Cl(n,p) reaction cross-section measurements and re-evaluations from the standpoint of molten chloride salt fast reactor design	2
Development of AR-based scanning support system for 3D model reconstruction of work sites	2
The high temperature corrosion of Incoloy 800H alloy at three different atmospheres	2
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH	2
ACE-FRENDY-CBZ: a new neutronics analysis sequence using multi-group neutron transport calculations	2
Identification of occupational stress factors of commissioning workers in nuclear power plants based on a bottom-up survey design and factor analysis	2
A support vector machine framework for fault detection in molecular pump	2
Study of magnetic fringe fields and interference effects on beam dynamics for proton facility gantry	2
RF wave propagation simulation for ICRF antenna in EAST	2
Effects of cold work on solute atom clustering during thermal aging in RPV model alloy	1
Evaluating the irradiation hardening of reactor pressure vessel steels by nanoindentation hardness test and micropillar compression test	1
Measurements of capture cross-section of ⁹³ Nb by activation method and half-life of ⁹⁴ Nb by mass analysis	1
New variance reduction techniques for Monte-Carlo calculation based on first-collision source method	1
Evaluation of the structural integrity of a BWR core shroud with non-regular locations of circumferential cracks. Part I fracture analysis	1
Monte Carlo calculation analysis of PWR-type fuel assembly mockup cores loaded with Gd₂O₃-UO₂ fuel rods in B&W 1810 series critical experiments	1
Preparation of zirconium coating on zirconium-niobium alloy substrate by pulsed current electrodeposition from fluoride molten salt	1
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor	1
A membrane, pseudo-vertical p-i-n diamond detector	1
Transfer of ¹³⁷Cs to web-building spiders, Nephila clavata, and its pathways: a preliminary study using stable carbon and nitrogen isotope analyses	1
Preface to a special issue of journal of nuclear science and Technology on “Nuclear Data and Code Systems as a Basis of Nuclear Technology”	1
Tsunami flooding analysis graded-approach framework for tsunami probabilistic risk assessment	1
²⁴¹ Am Neutron Capture Cross Section Measurement using the NaI(Tl) spectrometer of the ANNRI beamline of J-PARC	1
Experimental investigation of spray cooling behavior in 4×4 simulated fuel bundle	1
Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel	1
Depletion calculation of subcritical system with consideration of spontaneous fission reaction	1
Determination of ²³²Th in an electrodeposited target by neutron-activation analysis	1
Effects of correlations in uncertainties of total cross section and elastic angular distribution for a deep penetration of 14-MeV neutrons in Cu	1
Validation of LWR fuel depletion calculation module of reactor physics code system CBZ	1
Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurised water reactor primary coolant under irradiation (2) evaluation of electrochemical corrosion potentia	1
A design study on a metal fuel fast reactor core for high efficiency minor actinide transmutation by loading silicon carbide composite material	1
Impact of neutron generation time on released energy in falling fuel debris at supercritical condition	1
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator	1
The SLUMBAT Demo of Blockchain Based Nuclear Safeguards	1
Applicability of differential die-away self-interrogation technique for quantification of spontaneous fission nuclides for fuel debris at Fukushima Daiichi Nuclear Power Plants	1
Utilize empirical models of measured relative dose output factor (rDOF) and transverse penumbra (TP) to evaluate dosimetric uncertainties of in-air spot modelling for spot-scanning carbon-ion and prot	1
Monte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO ₂ and BWR-MOX fuels in the RUBUS program	1
Convergence behavior of statistical uncertainty in probability table for cross section in unresolved resonance region	1
Analysis of cyber nuclear terrorism by DTrack consequences in the civilian nuclear power plant	1
HHT-based investigation on the two-phase flow regime in the mixer for a nuclear-coupled liquid metal MHD power generation system	1
Development of nuclear data processing code FRENDY version 2	1
Development of online performance evaluation system of nuclear power plant system	1
Decontamination of corrosion oxides in the heat transport system of a pressurized heavy water reactor using chelate-free inorganic acid	1
A Raman spectroscopy study of bicarbonate effects on UO _2+x	1
Thermophysical and mechanical properties of LaB ₆ and CeB ₆ synthesized through spark plasma sintering	1
Comparison and evaluation of resolved resonance region covariance representations	1
Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility	1
Enhancement of applicability of high-efficiency random sampling method using control variates method and sensitivity coefficients	1
Verification of human error traps in NPP procedures utilizing syntactic and semantic information extraction	1
Development and verification of fast reactor burnup calculation module FRBurner in code system CBZ	1
New JENDL-4.0/HE neutron and proton ACE files	1
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O₂	1
Experimental techniques for investigating thermal transport in nuclear materials	1
Analysis of radioactive cesium-enriched particles and measurement of their distribution in marine sediment near Fukushima Daiichi nuclear power plant	1
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model	1
Proposal of quantification method of dynamic system reliability model of digital RPS using Markov state-transition model	1
Integral experiment of ¹²⁹I(n, γ) reaction using fast neutron source in the ‘YAYOI’ reactor	1
Thin cathode glass gas electron multiplier detector for carbon beam dose imaging	1
Study on iodine adsorption capacity and adsorption mechanism of AgY	1
Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system	1
Thermal-Neutron capture cross-section measurements of Neptunium-237 with graphite thermal column in KUR	1
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	1