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 2021-11-01 to 2025-11-01.)

Article	Citations
Consideration of delayed neutron effect on Rossi-α analysis for a subcritical thermal reactor	283
Transient heat transfer analysis of double-layer molten pool under severe accident	225
Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator	28
Effect of part-length rod arrangement on vapor redistribution in 5 × 5 rod bundle with high-energy X-ray CT measurement	27
Evaluation of ⁶⁰ Co inventory in the core of the Fukushima Daiichi Nuclear Power Plant – contribution of fuel deposits to the reactor core inventory	16
The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations	13
JENDL photonuclear data file 2016	13
Experimental and numerical simulation study on the combustion characteristics of nuclear-grade activated carbon	11
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel	11
Cesium immobilization from aqueous solution by struvite synthesis	11
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids	11
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique	11
A new separation method of hydrogen isotope by dynamically created nonequilibrium state	10
Sodium science and technology training at Indian sodium school	10
Radio-tellurium released into the environment during the complete oxidation of fuel cladding, containment venting and reactor building failure of the Fukushima accident	10
Correction	10
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	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	9
Discrimination of disposal-restricted materials in waste containers by nondestructive testing and image analysis with high-energy X-ray computed tomography	9
Comprehensive simulation study on CT isotope imaging beyond the experiment on the ²⁰⁸ Pb based on nuclear resonance fluorescence	9
EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242	9
Deterministic sampling method using simplex ensemble and scaling method for efficient and robust uncertainty quantification	8
Sorption of Cs ⁺ and Eu ³⁺ onto coherent and melange-type pre-neogene sedimentary rocks	8
Basic research on estimation of contamination of internal surface of spent nuclear fuel transport casks by Lasso regression	8

Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations	8
Exploration of the mechanism of controllable decomposition of polyurethane based on carbonate molten salt	8
Development of ACE file perturbation tool using FRENDY	7
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates	7
Exploratory study of nuclear magnetic resonance well logging technology on the hydrogeological characteristics of deep geological formations	7
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O₂	7
Transient parameter prediction and fault diagnosis for nuclear power plants based on machine learning	7
Absolute quantification of ¹³⁷Cs activity in spent nuclear fuel with calculated detector response function	7
Thermodynamic properties of liquid alkali-metal coolants: from the perspective of molecular dynamics	7
Revolatilization of iodine by bubbly flow in the suppression pool during an accident	6
Development of an ultra-fast dynamic time-over-threshold system with a 30 ps timing resolution	6
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
Performance evaluation for rapid-dose estimation of radioactive plume dispersion based on pre-simulation database of wind conditions by large-eddy simulation	6
Thermal-Neutron capture cross-section measurements of Neptunium-237 with graphite thermal column in KUR	6
Thermal performance analysis of molten salt in transversely grooved tube for nuclear reactor	6
Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages	6
The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment	6
A simulation study of hypervelocity jet underwater: physical protection design of offshore floating nuclear power plant against light torpedo threats	6
Leaching behavior of arsenic and selenium in coal fly ash by aging treatment and cement mixing	6
Urinary stone component identification by energy-resolved X-ray computed tomography	6
Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy	5
Correction	5
Development of an integrated non-destructive analysis system, Active-N	5
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33	5
Uranium dissolution and uranyl peroxide formation by immersion of simulated fuel debris in aqueous H ₂ O ₂ solution	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
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
Measurement of the thermal neutron capture-cross section of ¹⁹¹ Ir at ANNRI MLF J-PARC	5
Verification of direct coupling code system using FRENDY version 2 and GENESIS for light water reactor lattices	5
Design and experimental analysis of a nuclear fuel rod enrichment detection system	5
Ensuring a prudent combination of risk insights and a defense-in-depth philosophy through a reinterpretation of hierarchical safety goals	5
ACE-FRENDY-CBZ: a new neutronics analysis sequence using multi-group neutron transport calculations	5
Irradiation hardening and void swelling behaviors of F82H IEA by using dual-ion irradiation	5
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	5
Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow	5
Modeling of vapor mass formation under forced convective boiling condition	5
Neutron yield calculation of p-Li thick target by using PHITS with JENDL-4.0/HE and ENDF/B-VII for BNCT application	5
Investigation on the similarity of turbine cascade with different working fluids	5
Power distribution re-construction based on the PHOEBE method using the method of characteristics code ‘GENESIS’	5
Sensitivity analysis of risk assessment for continuous Markov process Monte Carlo method using correlated sampling method	5
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator	4
A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries	4
Highly promising recycled low-density polyethylene sheet adsorbents for uranium recovery from seawater	4
Measurement of the water-vapor void fraction in a 4x4 unheated rod bundle	4
Study on key technical issues of accident selection in emergency planning zone development for small modular reactors	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
Experimental techniques for investigating thermal transport in nuclear materials	4
Recovery and immobilization of cesium from aqueous solution after hydrothermal treatment using functional porous glass	4
Incineration of trans-uranium elements using chlorides molten salt fast reactors – A proposal of incineration in three steps	4

Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility	4
Test of ¹⁰⁷ Pd transmutation with macroscopic quantities	4
Develop a framework of human reliability analysis to evaluate the human error probability in DMCR of NPPs	4
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy	4
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level	4
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model	4
In-situ TEM observation of migration behavior of helium bubbles in F82H	4
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): ⁵⁸ Fe(n,γ) ⁵⁹ Fe	4
Reactivity estimation based on the linear equation of characteristic time profile of power in subcritical quasi-steady state	4
Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons	4
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
Research on nonlinear generalized predictive control method for reactor core power based on parameter identification	4
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environment	4
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure	4
Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis	4
Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector	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
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions	4
Numerical simulation of bubble hydrodynamics for pool scrubbing	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
Experimental research and transient modeling of aerosol transport considering re-entrainment effects in turbulent horizontal circular pipe flow	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
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning	3
Gamma-ray irradiation induced dislocation loops in hexagonal zirconium	3
Integral experiment of ¹²⁹ I(n, γ) reaction using fast neutron source in the ‘YAYOI’ reactor	3
Computer code analysis of irradiation performance of an annular mixed oxide fuel element	3
Study on corrosion of T-22 alloy under high temperature condition of VHTR	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
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor	3
Research on frequency modulation technology and its verifications of superconducting synchrocyclotron for cancer therapy	3
Development of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithm	3
Integrating DeblurGAN and CNN to improve the accuracy of motion blur X-Ray image classification	3
Nuclear data adjustment using a deterministic sampling method with unscented transformation	3
Research on the powderization treatment of uranium-zirconium solid solution simulated nuclear fuel debris using thermochemical redox reaction	3
Uncertainty analysis for fission product inventories based on covariance data of fission product yields in JENDL-4.0 and ENDF/B-VIII.0	3
Fretting wear behavior test and numerical simulation of Inconel 690 alloy	3
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH	3
New variance reduction techniques for Monte-Carlo calculation based on first-collision source method	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
The effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatment	3
Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel	3
Development of AR-based scanning support system for 3D model reconstruction of work sites	3
A spurious-count effect observed in Rossi-α and Feynman-α analysis using fission counter for Kyoto University Reactor	3
Status of the ²²⁶ Ra nuclear data library and its impact on the production amount of ²²⁵ Ac via the ²²⁶	3
Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K	3
Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system	3
Solubility of FeSe₂(cr) at 318 K in the presence of iron	3
Measurement of the neutron capture cross section of ¹⁸⁵ Re in the keV energy region	3
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments	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
Experiences from the cutting of metallic blocks from simulant Fukushima Daiichi fuel debris	3
Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant	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
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks	3
Sub-pin level distribution tallies and statistical error estimation with POD tallies in two-dimensional C5G7 benchmark	3
Experimental investigation of spray cooling behavior in 4×4 simulated fuel bundle	3
Bayesian approach to energy dependence of fission product yields of ²³⁵ U by data augmentation	2
Treatment of corner crossing ray-traces in CMFD acceleration of MOC	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
A membrane, pseudo-vertical p-i-n diamond detector	2
Simulated performance evaluation of d-Be compact fast neutron source	2
Experimental and numerical study of a condensing steam jet	2
Thermophysical properties of molten FeO _1.5 , (FeO _1.5 ) _0.86 –(ZrO ₂	2
Degradation of nuclear fuel debris analog by siderophore-releasing microorganisms	2
Monte Carlo-informed reliability and availability framework for innovative inspection timelines: a case study of the PA01-BC01 heat exchanger	2
Irradiation behavior of HfNbTaTiV in comparison of HfNbTaTiZr and F82H	2
Measurement of neutron spectra for various thicknesses of concrete and steel shielding at 24-GeV/c proton beam facility using Bonner sphere spectrometer	2
Nuclear data generation by machine learning (I) application to angular distributions for nucleon-nucleus scattering	2
EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5	2
Development of Internal Dose Calculation Code (IDCC)	2
Development of glass gas electron multiplier-based pulse counting imaging system with FPD front-end electronics	2
Nuclear data uncertainty in iterative neutron spectrum unfolding	2
Verification of in-core power distribution reconstruction based on POD for high-temperature gas-cooled reactors using ex-core detectors	2
Dynamic performance analysis of a new low-temperature nuclear heating system with APROS	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
Data processing and visualization of X-ray computed tomography images of a JOYO MK-III fuel assembly	2
Monte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO ₂ and BWR-MOX fuels in the RUBUS program	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
Reactor reactivity calculations with simplified-P3 and perturbation theories	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
Role of solute titanium and oxidation in cesium chemisorption onto stainless steel	2
Enhancing magnetohydrodynamic performance of liquid metal with solid insulating powders for fusion reactor applications	2
Establishing an evaluation method for the aging phenomenon by physical force in fuel debris	2
Reactor antineutrinos and novel application to real-time remote monitoring of nuclear reactors	2
JENDL-5 benchmarking for fission reactor applications	2
Calculations and analysis of n+ ⁵² Cr reactions below 20 MeV	2
EXFOR-based simultaneous evaluation for fast neutron-induced fission cross section of thorium-232	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
Molecular dynamics simulation study of the effect of Ce ⁴⁺ incorporation at Zr site on the threshold displacement energy in Y ₄ Zr	2
Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C	2
Technical research on rapid source term calculation and prediction technology of nuclear accidents based on Bayesian network	2
A study on the establishment of database for local government disaster response and decision support system in the nuclear accidents	2
High-efficient removal of tungsten from hafnium by TOA/XAD-7 extraction resin from HCl-HF media	2
Alteration of fuel debris simulants by Bacillus subtilis	2
An automatic defects detection system for nuclear fuel pellets end face based on deep learning and structured light	2
Design and development of the machine protection system for HIAF	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
Radiation-induced amorphization behavior of thermally-aged M₂₃C₆ in F82H-BA12 steel	2
Simulation of the self-propagating hydrogen-air premixed flame in a closed-vessel by an open-source CFD code	2
Evaluation of beamline subsystem performance during technical commissioning of an superconducting proton therapy facility	2
A design study on a metal fuel fast reactor core for high efficiency minor actinide transmutation by loading silicon carbide composite material	2
Hybrid data assimilation methods for nuclear-data-induced uncertainties	2
Applicability of the kernel method for macroscopic cross section tabulation to planar MOC-based core transient analysis code	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
Development of integrated FEPs for safety case scenario development	2
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (III): ¹⁷⁰ Er(n,γ) ¹⁷¹ Er and	2
Benchmark specifications of TCA critical experiments for validation of thermal scattering laws of water	2
Multi-scenario validation and parameter sensitivity of the GPU-QES dispersion model under local-scale wind tunnel experiments at a nuclear power plant site	2
Diffusion of Cs ⁺ , I ⁻ and HDO onto pre-Neogene sedimentary rocks	2
YouTube-based topic modeling and large language model sentiment analysis of Japanese online discourse on nuclear energy	2
Uncertainty quantification of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly	2
Correction	2
Corrosion behavior of zirconium alloys in the aqueous environment. Phenomenological aspects. Overview	2
Heat of transport for hydrogen and hydrides in Zircaloy	2
Experimental and analytical investigations on aerosol washout in a large vessel with high spray coverage ratio simulating PWR containment spray	2
Correction	2
Experimental study on design optimization of the core catcher for the CEFR	2
The behaviors of dislocation loops punched by helium interstitials accumulation under the temperature gradient field in tungsten	2
Reduced order SP ₃ core calculation based on local/global iterations using proper orthogonal decomposition	1
Double-differential cross sections for charged particle emissions from α particle impinging on Al at 230 MeV/u	1
Criticality evaluation considering nonuniformity effect using Monte Carlo perturbation method	1
Predictive accuracy of neutronics of light-water-moderated and graphite-reflected core with low-enriched uranium fuel at UTR-KINKI	1
Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 2	1
Impact of zeolite and activated carbon on the performance of High-Density Polyethylene High Integrity Container (HDPE-HIC) loading and dewatering system: process optimization and laboratory validation	1
Steady-state thermal-structural analysis of high-temperature heat pipes based on thermal-fluid coupling	1
Crucial importance of correlation between cross sections and angular distributions in nuclear data of ²⁸ Si on estimation of uncertainty of neutron dose penetrating	1
Experimental study on mechanical properties of corroded steel used as containment liner in nuclear power plant	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
Limited linear source approximation with edge detection for convergence stability of method of characteristics	1
Application of dynamic mode decomposition to Rossi-α method in a critical state using file-by-file moving block bootstrap method	1
Experimental investigations on flow-induced vibration characteristics of fuel rod with an independent channel for small lead-based reactor	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
Coupled chemo-hydro-mechanical effects on volume change behaviour of compacted bentonite used as buffer/backfill material in high-level radioactive waste repository	1
Hot zone formation in combustion tests simulating solvent fires in reprocessing plants – concerns on boilover phenomenon	1
Proposal of uncertainty analysis methodology for L1PRA using Markov state-transition model	1
Application of the spectral determination method to unified β-, γ- and X-ray spectra	1
DALB-MC: dynamic Adaptive load balancing for efficient Monte Carlo particle transport on heterogeneous architectures	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
Consideration on the concrete spalling behavior in high-temperature environments during severe accidents	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
Improved neutron spectrum unfolding using residual networks and generative adversarial networks: a comparative study with baseline deep models	1
A three-step chromatographic method for ultra-trace ^242m Am purification prior to ICP-MS analysis	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
Meteorological effects on atmospheric radioactive particles: a review of recent research	1
Synergism of radiation and steam on mechanical properties of cable insulation removed from a nuclear power plant	1
Validation of LWR fuel depletion calculation module of reactor physics code system CBZ	1
Development of local-scale high-resolution atmospheric dispersion and dose assessment system	1
High temperature corrosion of two superalloys in the impure helium environment	1
Numerical simulation of the fluid flow and heat transfer of the supercritical water in the 64-element Canadian SCWR fuel bundle	1
Analysis of work activities involved in clearance verification process of decommissioning Fugen Nuclear Power Plant	1
Optimization of BP neural network for fault parameter prediction in nuclear power plants utilizing the firefly algorithm	1
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	1
Fundamental study on hydrogen production by radiation related to material properties of boron-containing geopolymers with reduced water content	1
Study on the mechanism of alkali fusion reaction of uranium oxide and sodium peroxide	1
An energy equivalent method to determine the stress–strain relations of ductile materials by small punch testing	1
Development of neutron self-indication thermometry at J-PARC	1
EPMA and EBSD observations of unirradiated MIMAS-MOX fuels for the study of fission gas release and thermal conductivity	1
Human reliability analysis of shared equipment in multi-unit site	1
A support vector machine framework for fault detection in molecular pump	1
Rare earth elements and radioactive elements in black sands from the Konkan and Malabar coasts of India	1
A novel Compton camera with an annular absorber for enhancing the imaging efficiency in regions directly ahead: A simulation study	1
Passive fast neutron multiplicity counting system based on a symmetric spherical design	1
Simulation using representative data selection for transboundary radiation effect evaluation by Nuclear Accident Consequence Analysis Code (NACAC)	1
Double diffusive dissolution model of UO₂ pellet in molten Zr cladding	1
Influence of organic dispersant on nuclear grade anion exchange resin and their interaction behavior	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
Effect of radiation and substitution of Ce⁴⁺ at Zr site in Y₄Zr₃O₁₂ using collision cascades: a molecular dynamics simulation study	1
Redistribution of Nb and other alloying elements in Nb-doped Zr alloy under high dose ion irradiation	1
Localizing unknown radiation sources by unscented particle filtering based on divide-and-conquer sampling	1
Effect of Ni and Si addition on dislocation loop formation in Fe-Mn alloys	1
Analytical studies on effects of wind on dispersion of hydrogen leaked in a partially open space	1
Identification of Chinese materia medica by terahertz time-domain spectroscopy (THz-TDS)	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