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 2022-01-01 to 2026-01-01.)

Article	Citations
Transient heat transfer analysis of double-layer molten pool under severe accident	318
Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator	263
The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations	31
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique	16
Experimental and numerical simulation study on the combustion characteristics of nuclear-grade activated carbon	14
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	13
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids	13
Evaluation of ⁶⁰ Co inventory in the core of the Fukushima Daiichi Nuclear Power Plant – contribution of fuel deposits to the reactor core inventory	12
Radio-tellurium released into the environment during the complete oxidation of fuel cladding, containment venting and reactor building failure of the Fukushima accident	11
Cesium immobilization from aqueous solution by struvite synthesis	11
A new separation method of hydrogen isotope by dynamically created nonequilibrium state	11
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel	11
Effect of part-length rod arrangement on vapor redistribution in 5 × 5 rod bundle with high-energy X-ray CT measurement	11
JENDL photonuclear data file 2016	11
Sodium science and technology training at Indian sodium school	10
Comprehensive simulation study on CT isotope imaging beyond the experiment on the ²⁰⁸ Pb based on nuclear resonance fluorescence	10
Radioactivation analysis of a concrete wall in a high-energy electron accelerator facility	10
Advances in the interfacial interactions and decontamination strategies of radionuclides on cement surfaces: a review	10
Study on criticality uncertainties of MCCI products due to concrete compositions	9
Exploration of the mechanism of controllable decomposition of polyurethane based on carbonate molten salt	9
Basic research on estimation of contamination of internal surface of spent nuclear fuel transport casks by Lasso regression	9
Sorption of Cs ⁺ and Eu ³⁺ onto coherent and melange-type pre-neogene sedimentary rocks	9
Discrimination of disposal-restricted materials in waste containers by nondestructive testing and image analysis with high-energy X-ray computed tomography	9
EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242	9
Absolute quantification of ¹³⁷Cs activity in spent nuclear fuel with calculated detector response function	8

Deterministic sampling method using simplex ensemble and scaling method for efficient and robust uncertainty quantification	8
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O₂	8
Correction	8
Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations	8
Thermal-Neutron capture cross-section measurements of Neptunium-237 with graphite thermal column in KUR	7
Thermal performance analysis of molten salt in transversely grooved tube for nuclear reactor	7
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates	7
Development of ACE file perturbation tool using FRENDY	7
Development of an ultra-fast dynamic time-over-threshold system with a 30 ps timing resolution	7
Leaching behavior of arsenic and selenium in coal fly ash by aging treatment and cement mixing	7
Exploratory study of nuclear magnetic resonance well logging technology on the hydrogeological characteristics of deep geological formations	7
Revolatilization of iodine by bubbly flow in the suppression pool during an accident	7
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
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	6
Urinary stone component identification by energy-resolved X-ray computed tomography	6
Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages	6
Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy	6
Measurement of the thermal neutron capture-cross section of ¹⁹¹ Ir at ANNRI MLF J-PARC	6
Transient parameter prediction and fault diagnosis for nuclear power plants based on machine learning	6
A simulation study of hypervelocity jet underwater: physical protection design of offshore floating nuclear power plant against light torpedo threats	6
The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment	6
Performance evaluation for rapid-dose estimation of radioactive plume dispersion based on pre-simulation database of wind conditions by large-eddy simulation	6
Ensuring a prudent combination of risk insights and a defense-in-depth philosophy through a reinterpretation of hierarchical safety goals	5
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure	5
A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries	5
Develop a framework of human reliability analysis to evaluate the human error probability in DMCR of NPPs	5
Measurement of the water-vapor void fraction in a 4x4 unheated rod bundle	5
ACE-FRENDY-CBZ: a new neutronics analysis sequence using multi-group neutron transport calculations	5
Modeling of vapor mass formation under forced convective boiling condition	5
Development of an integrated non-destructive analysis system, Active-N	5
Sensitivity analysis of risk assessment for continuous Markov process Monte Carlo method using correlated sampling method	5
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy	5
Experimental research and transient modeling of aerosol transport considering re-entrainment effects in turbulent horizontal circular pipe flow	5
Research on nonlinear generalized predictive control method for reactor core power based on parameter identification	5
Irradiation hardening and void swelling behaviors of F82H IEA by using dual-ion irradiation	5
Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow	5
Power distribution re-construction based on the PHOEBE method using the method of characteristics code ‘GENESIS’	5
Verification of direct coupling code system using FRENDY version 2 and GENESIS for light water reactor lattices	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
Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis	5
Test of ¹⁰⁷ Pd transmutation with macroscopic quantities	5
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environment	5
Uranium dissolution and uranyl peroxide formation by immersion of simulated fuel debris in aqueous H ₂ O ₂ solution	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
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33	5
Design and experimental analysis of a nuclear fuel rod enrichment detection system	5
Correction	5
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
Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons	4

Incineration of trans-uranium elements using chlorides molten salt fast reactors – A proposal of incineration in three steps	4
Experimental techniques for investigating thermal transport in nuclear materials	4
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level	4
Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system	4
Recovery and immobilization of cesium from aqueous solution after hydrothermal treatment using functional porous glass	4
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model	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
In-situ TEM observation of migration behavior of helium bubbles in F82H	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
Study on key technical issues of accident selection in emergency planning zone development for small modular reactors	4
Uncertainty analysis for fission product inventories based on covariance data of fission product yields in JENDL-4.0 and ENDF/B-VIII.0	4
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator	4
Measurement of the neutron capture cross section of ¹⁸⁵ Re in the keV energy region	4
Reactivity estimation based on the linear equation of characteristic time profile of power in subcritical quasi-steady state	4
Numerical simulation of bubble hydrodynamics for pool scrubbing	4
Experimental investigation of spray cooling behavior in 4×4 simulated fuel bundle	4
Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility	4
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): ⁵⁸ Fe(n,γ) ⁵⁹ Fe	4
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning	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
Solubility of FeSe₂(cr) at 318 K in the presence of iron	4
Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector	4
Gamma-ray irradiation induced dislocation loops in hexagonal zirconium	4
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions	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
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor	3
Development of AR-based scanning support system for 3D model reconstruction of work sites	3
Development of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithm	3
Fretting wear behavior test and numerical simulation of Inconel 690 alloy	3
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments	3
Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K	3
Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel	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
Multi-scenario validation and parameter sensitivity of the GPU-QES dispersion model under local-scale wind tunnel experiments at a nuclear power plant site	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
Computer code analysis of irradiation performance of an annular mixed oxide fuel element	3
Research on frequency modulation technology and its verifications of superconducting synchrocyclotron for cancer therapy	3
Research on the powderization treatment of uranium-zirconium solid solution simulated nuclear fuel debris using thermochemical redox reaction	3
Nuclear data adjustment using a deterministic sampling method with unscented transformation	3
Status of the ²²⁶ Ra nuclear data library and its impact on the production amount of ²²⁵ Ac via the ²²⁶	3
Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant	3
The effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatment	3
JENDL-5 benchmarking for fission reactor applications	3
Bayesian approach to energy dependence of fission product yields of ²³⁵ U by data augmentation	3
A spurious-count effect observed in Rossi-α and Feynman-α analysis using fission counter for Kyoto University Reactor	3
Experiences from the cutting of metallic blocks from simulant Fukushima Daiichi fuel debris	3
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks	3
Study on corrosion of T-22 alloy under high temperature condition of VHTR	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
New variance reduction techniques for Monte-Carlo calculation based on first-collision source method	3
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH	3
Sub-pin level distribution tallies and statistical error estimation with POD tallies in two-dimensional C5G7 benchmark	3
Integrating DeblurGAN and CNN to improve the accuracy of motion blur X-Ray image classification	3
Continuous-Time Markov Chain-based examination of safeguards- and security-by-design of nuclear reactors	3
Monte Carlo-informed reliability and availability framework for innovative inspection timelines: a case study of the PA01-BC01 heat exchanger	3
Measurement of neutron spectra for various thicknesses of concrete and steel shielding at 24-GeV/c proton beam facility using Bonner sphere spectrometer	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
Irradiation behavior of HfNbTaTiV in comparison of HfNbTaTiZr and F82H	2
Correction	2
A novel strategy for iodine removal from nuclear reactor accidental gases: Efficient adsorption of CH ₃ I on the moderately hydrophobic modified silver-loaded zeolit	2
Degradation of nuclear fuel debris analog by siderophore-releasing microorganisms	2
The effects of unburned-gas temperature and pressure on the unstable behavior of cellular-flame fronts generated by intrinsic instability in hydrogen-air lean premixed flames under adiabatic and non-a	2
HHT-based investigation on the two-phase flow regime in the mixer for a nuclear-coupled liquid metal MHD power generation system	2
Development of a theoretical scaling factor method for the inventory estimation of difficult-to-measure nuclide Cs-135 in fuel debris and radioactive wastes	2
Nuclear data uncertainty in iterative neutron spectrum unfolding	2
Monte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO ₂ and BWR-MOX fuels in the RUBUS program	2
Reactor reactivity calculations with simplified-P3 and perturbation theories	2
High-efficient removal of tungsten from hafnium by TOA/XAD-7 extraction resin from HCl-HF media	2
Evaluation of beamline subsystem performance during technical commissioning of an superconducting proton therapy facility	2
Alteration of fuel debris simulants by Bacillus subtilis	2
Technical research on rapid source term calculation and prediction technology of nuclear accidents based on Bayesian network	2
Molecular dynamics simulation study of the effect of Ce ⁴⁺ incorporation at Zr site on the threshold displacement energy in Y ₄ Zr	2
Development of integrated FEPs for safety case scenario development	2
Uncertainty quantification of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly	2
Role of solute titanium and oxidation in cesium chemisorption onto stainless steel	2
Treatment of corner crossing ray-traces in CMFD acceleration of MOC	2
Water-leaching behavior for cesium chemisorbed on stainless steel at room temperature	2
Applicability of differential die-away self-interrogation technique for quantification of spontaneous fission nuclides for fuel debris at Fukushima Daiichi Nuclear Power Plants	2
Experimental study on design optimization of the core catcher for the CEFR	2

Heat of transport for hydrogen and hydrides in Zircaloy	2
A membrane, pseudo-vertical p-i-n diamond detector	2
EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5	2
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	2
Accurate measurement of the ¹²⁹ I neutron capture cross-section in the keV neutron region	2
Cohesive/Adhesive strengths of CsOH-chemisorbed SS304 surfaces	2
Design and development of the machine protection system for HIAF	2
Data processing and visualization of X-ray computed tomography images of a JOYO MK-III fuel assembly	2
Radiation-induced amorphization behavior of thermally-aged M₂₃C₆ in F82H-BA12 steel	2
An automatic defects detection system for nuclear fuel pellets end face based on deep learning and structured light	2
Correction	2
Modeling axial void fraction profile for subcooled boiling flow in rod bundles under atmospheric to high-pressure conditions	2
Calculations and analysis of n+ ⁵² Cr reactions below 20 MeV	2
Applicability of the kernel method for macroscopic cross section tabulation to planar MOC-based core transient analysis code	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
Verification of in-core power distribution reconstruction based on POD for high-temperature gas-cooled reactors using ex-core detectors	2
Corrosion behavior of zirconium alloys in the aqueous environment. Phenomenological aspects. Overview	2
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	2
Development of glass gas electron multiplier-based pulse counting imaging system with FPD front-end electronics	2
Reactor antineutrinos and novel application to real-time remote monitoring of nuclear reactors	2
EXFOR-based simultaneous evaluation for fast neutron-induced fission cross section of thorium-232	2
Enhancing magnetohydrodynamic performance of liquid metal with solid insulating powders for fusion reactor applications	2
YouTube-based topic modeling and large language model sentiment analysis of Japanese online discourse on nuclear energy	2
Nuclear data generation by machine learning (I) application to angular distributions for nucleon-nucleus scattering	2
Benchmark specifications of TCA critical experiments for validation of thermal scattering laws of water	2
Power profile analysis of criticality accidents involving fissile solution boiling with considering evaporation	2
Measurements of keV-Neutron capture cross sections and capture gamma-ray spectra of ^{74,76,78,80,82} Se	2
Experimental and numerical study of a condensing steam jet	2
Experimental and analytical investigations on aerosol washout in a large vessel with high spray coverage ratio simulating PWR containment spray	2
The behaviors of dislocation loops punched by helium interstitials accumulation under the temperature gradient field in tungsten	2
Simulated performance evaluation of d-Be compact fast neutron source	2
Development of Internal Dose Calculation Code (IDCC)	2
Preface to a special issue of journal of nuclear science and Technology on “Nuclear Data and Code Systems as a Basis of Nuclear Technology”	2
Diffusion of Cs ⁺ , I ⁻ and HDO onto pre-Neogene sedimentary rocks	2
Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C	2
A study on the establishment of database for local government disaster response and decision support system in the nuclear accidents	2
Establishing an evaluation method for the aging phenomenon by physical force in fuel debris	2
Thermophysical properties of molten FeO _1.5 , (FeO _1.5 ) _0.86 –(ZrO ₂	2
Hybrid data assimilation methods for nuclear-data-induced uncertainties	2
Dynamic performance analysis of a new low-temperature nuclear heating system with APROS	2
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (III): ¹⁷⁰ Er(n,γ) ¹⁷¹	2
A design study on a metal fuel fast reactor core for high efficiency minor actinide transmutation by loading silicon carbide composite material	2
Evaluation of influence of wall roughness on wall turbulence using LES simulation with MSGD model for liquid Li flow inside two-staged contraction nozzle	2
Experimental study on mechanical properties of corroded steel used as containment liner in nuclear power plant	1
Effect of Ni and Si addition on dislocation loop formation in Fe-Mn alloys	1
Novel concept for a filtered containment venting system with an ionic liquid to remove organic iodine (2) – Decomposition mechanism of an ionic liquid by heat and gamma-ray irradiation	1
Validation of LWR fuel depletion calculation module of reactor physics code system CBZ	1
Criticality evaluation considering nonuniformity effect using Monte Carlo perturbation method	1
Steady-state thermal-structural analysis of high-temperature heat pipes based on thermal-fluid coupling	1
Double diffusive dissolution model of UO₂ pellet in molten Zr cladding	1
Coupled chemo-hydro-mechanical effects on volume change behaviour of compacted bentonite used as buffer/backfill material in high-level radioactive waste repository	1
Development of local-scale high-resolution atmospheric dispersion and dose assessment system	1
Redistribution of Nb and other alloying elements in Nb-doped Zr alloy under high dose ion irradiation	1
Study of magnetic fringe fields and interference effects on beam dynamics for proton facility gantry	1
Experimental investigations on flow-induced vibration characteristics of fuel rod with an independent channel for small lead-based reactor	1
Human reliability analysis of shared equipment in multi-unit site	1
Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 2	1
Fundamental study on hydrogen production by radiation related to material properties of boron-containing geopolymers with reduced water content	1
Measurements of boiling two-phase flow dynamics in a heated tube using high-speed neutron imaging	1
Recovery of the laser-induced breakdown spectroscopy system using a ceramic microchip deteriorated by radiation for the remote elemental analysis	1
Simulation using representative data selection for transboundary radiation effect evaluation by Nuclear Accident Consequence Analysis Code (NACAC)	1
Localizing unknown radiation sources by unscented particle filtering based on divide-and-conquer sampling	1
Hot zone formation in combustion tests simulating solvent fires in reprocessing plants – concerns on boilover phenomenon	1
Consideration on the concrete spalling behavior in high-temperature environments during severe accidents	1
Rare earth elements and radioactive elements in black sands from the Konkan and Malabar coasts of India	1
Request for ³⁵ Cl(n,p) reaction cross-section measurements and re-evaluations from the standpoint of molten chloride salt fast reactor design	1
Numerical simulation method using a Cartesian grid for oxidation of core materials under steam-starved conditions	1
Towards safe, efficient long-reach manipulation in nuclear decommissioning: A case study on fuel debris retrieval at Fukushima Daiichi	1
High temperature corrosion of two superalloys in the impure helium environment	1
Tensile properties of irradiated modified 316 stainless steel (PNC316) at slow strain rates	1
Numerical simulation of bubble rising and coalescing in liquid sodium using the ISPH-FVM coupling method	1
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·	1
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	1
Application of the spectral determination method to liquid scintillation spectra	1
Double-differential cross sections for charged particle emissions from α particle impinging on Al at 230 MeV/u	1
EPMA and EBSD observations of unirradiated MIMAS-MOX fuels for the study of fission gas release and thermal conductivity	1
Application of dynamic mode decomposition to Rossi-α method in a critical state using file-by-file moving block bootstrap method	1
A three-step chromatographic method for ultra-trace ^242m Am purification prior to ICP-MS analysis	1
Synergism of radiation and steam on mechanical properties of cable insulation removed from a nuclear power plant	1
Meteorological effects on atmospheric radioactive particles: a review of recent research	1
Improved neutron spectrum unfolding using residual networks and generative adversarial networks: a comparative study with baseline deep models	1
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	1
Passive fast neutron multiplicity counting system based on a symmetric spherical design	1
A novel Compton camera with an annular absorber for enhancing the imaging efficiency in regions directly ahead: A simulation study	1
Limited linear source approximation with edge detection for convergence stability of method of characteristics	1
Influence of organic dispersant on nuclear grade anion exchange resin and their interaction behavior	1
Analysis of work activities involved in clearance verification process of decommissioning Fugen Nuclear Power Plant	1
Multi-scenario validation of the self-correction source term inversion method	1
Optimization of BP neural network for fault parameter prediction in nuclear power plants utilizing the firefly algorithm	1
Effect of radiation and substitution of Ce⁴⁺ at Zr site in Y₄Zr₃O₁₂ using collision cascades: a molecular dynamics simulation study	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
The effect of boron carbide doping content on the mechanical properties of polyethylene	1
Development of neutron self-indication thermometry at J-PARC	1
Predictive accuracy of neutronics of light-water-moderated and graphite-reflected core with low-enriched uranium fuel at UTR-KINKI	1
Numerical simulation of the fluid flow and heat transfer of the supercritical water in the 64-element Canadian SCWR fuel bundle	1