Journal of Nuclear Science and Technology

Article	Citations
Criticality evaluation considering nonuniformity effect using Monte Carlo perturbation method	199
Numerical simulation of bubble hydrodynamics for pool scrubbing	111
Fuel cycle features of RFBB fast reactor with advanced fuel	27
Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 2	24
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): 58 Fe(n,γ) 59 Fe	22
Research on soft errors induced by alpha particles and atmospheric neutrons based on 28 nm field programmable gate array	21
Bayesian statistical model for cladding high-temperature burst under loss-of-coolant accident conditions	15
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	13
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator	12
Applicability of differential die-away self-interrogation technique for quantification of spontaneous fission nuclides for fuel debris at Fukushima Daiichi Nuclear Power Plants	12
Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator	12
Verification of human error traps in NPP procedures utilizing syntactic and semantic information extraction	11
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions	11
Enhancement of random sampling by a combined approach of control variates and Latin hypercube sampling for uncertainty quantification in light water reactor lattice calculations	11
Double diffusive dissolution model of UO2 pellet in molten Zr cladding	11
Condensation heat fluxes from mixed convection flows of steam and air mixtures on a vertical flat plate	10
Review of prediction models for tsunami-induced lateral fluid force for revision of engineering design code for nuclear power plant structures	10
Effects of correlations in uncertainties of total cross section and elastic angular distribution for a deep penetration of 14-MeV neutrons in Cu	9
Evaluations on the thermal properties of Cs–B–O compounds using density functional theory and phonon vibration calculations	9
Passive fast neutron multiplicity counting system based on a symmetric spherical design	9
New JENDL-4.0/HE neutron and proton ACE files	9
Calculations and analysis of n+ 52 Cr reactions below 20 MeV	8
Role of solute titanium and oxidation in cesium chemisorption onto stainless steel	8
Cryogenic distribution system design for cryomodules and cavities test in HIAF project	8
Human reliability analysis of shared equipment in multi-unit site	8

Comparison and evaluation of resolved resonance region covariance representations	8
Benchmark simulation code for the thermal-hydraulics design tool of the accelerator-driven system: validation and benchmark simulation of flow behavior around the beam window	8
Validation of LWR fuel depletion calculation module of reactor physics code system CBZ	8
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	8
Rare earth elements and radioactive elements in black sands from the Konkan and Malabar coasts of India	8
Degradation of nuclear fuel debris analog by siderophore-releasing microorganisms	8
JENDL photonuclear data file 2016	7
A safety enhanced sodium-cooled MOX fueled fast reactor core concept	7
Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility	7
Development of a water Cherenkov neutron detector for the active rotation method and demonstration of nuclear material detection	7
Numerical analysis of flow-induced deflection of curved nuclear reactor fuel plates under high velocity flows	7
Coupled chemo-hydro-mechanical effects on volume change behaviour of compacted bentonite used as buffer/backfill material in high-level radioactive waste repository	7
Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons	7
Experimental techniques for investigating thermal transport in nuclear materials	7
Measurements of capture cross-section of 93 Nb by activation method and half-life of 94 Nb by mass analysis	7
Consideration of delayed neutron effect on Rossi-α analysis for a subcritical thermal reactor	6
Study on melting behavior of tungsten under high heat load including verification of simulation code using other metals	6
Ten years after the NPP accident at Fukushima : review on fuel debris behavior in contact with water	6
Experimental study on mechanical properties of corroded steel used as containment liner in nuclear power plant	6
Application of continuous Markov-chain Monte-Carlo method to multi-unit risk evaluations considering interdependence of accident progression among multiple units	6
Micro-mechanical investigation about degradation of grain boundary cohesive strength of neutron-irradiated stainless steels	6
Recovery and immobilization of cesium from aqueous solution after hydrothermal treatment using functional porous glass	6
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	6
A thermal-hydraulic analysis model of printed circuit heat exchangers for system simulation using Modelica	6
Dose rate distribution measuring method using personal dosimeters and localization devices	5
Drag coefficient of circular cylinder in axial flow of water for a wide range of length to diameter ratios	5
Thermal-neutron capture cross-section measurement of Tantalum-181 using graphite thermal column at KUR	5
Novel concept for a filtered containment venting system with an ionic liquid to remove organic iodine (1)-proof of concept for organic iodine removal	5
Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants	5
Nuclear data generation by machine learning (I) application to angular distributions for nucleon-nucleus scattering	5
The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations	5
Design and actual performance of J-PARC 3 GeV rapid cycling synchrotron for high-intensity operation	5
Effect of surface oxidation on the cesium chemisorption behavior of SS 304, Inconel 600 and X-750	5
A surface cracks detection method for nuclear fuel pellets using an improved fully convolutional network	5
Incineration of trans-uranium elements using chlorides molten salt fast reactors – A proposal of incineration in three steps	5
Correction	5
Evaluation of the structural integrity of a BWR core shroud with non-regular locations of circumferential cracks. Part I fracture analysis	4
A membrane, pseudo-vertical p-i-n diamond detector	4
A design study on a metal fuel fast reactor core for high efficiency minor actinide transmutation by loading silicon carbide composite material	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
Correction	4
Steady-state thermal-structural analysis of high-temperature heat pipes based on thermal-fluid coupling	4
Arsenazo III-spectrophotometry for the determination of thorium content	4
A Raman spectroscopy study of bicarbonate effects on UO 2+x	4
Reactivity estimation based on the linear equation of characteristic time profile of power in subcritical quasi-steady state	4
Investigation into activation of accelerators at various synchrotron radiation facilities in Japan	4
Walking survey technique for ambient gamma dose rate measurement established in Fukushima Medical University	4
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids	4
A study on the establishment of database for local government disaster response and decision support system in the nuclear accidents	4
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique	4

Investigation of random beam trips in a linear accelerator at the Japan proton accelerator research complex for the development of an accelerator-driven nuclear transmutation system	4
Evaluating the irradiation hardening of reactor pressure vessel steels by nanoindentation hardness test and micropillar compression test	4
Research on the design of a radiation biodevice based on a compact D-D neutron generator	4
Transient heat transfer analysis of double-layer molten pool under severe accident	4
Localizing unknown radiation sources by unscented particle filtering based on divide-and-conquer sampling	4
Using Lorentz force flowmeter to measure the narrow channel flow that mimics lead-bismuth cooled reactors	4
Development of glass gas electron multiplier-based pulse counting imaging system with FPD front-end electronics	4
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel	4
Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector	4
In-situ TEM observation of migration behavior of helium bubbles in F82H	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·	3
Experimental investigation of spray cooling behavior in 4×4 simulated fuel bundle	3
Energy dependent calculations of fission product, prompt, and delayed neutron yields for neutron induced fission on 235 U, 238 U,	3
Tensile properties of irradiated modified 316 stainless steel (PNC316) at slow strain rates	3
Evaluation of shielding performance and light emission characteristics of luminescent radiation shields using Gd 2 O 2 S	3
A new separation method of hydrogen isotope by dynamically created nonequilibrium state	3
Molecular dynamics simulation study of the effect of Ce 4+ incorporation at Zr site on the threshold displacement energy in Y 4 Zr	3
A review of efforts for volume reduction of contaminated soil in the ten years after the accident at the Fukushima Daiichi Nuclear Power Plant	3
Solubility of FeSe2(cr) at 318 K in the presence of iron	3
Cesium immobilization from aqueous solution by struvite synthesis	3
Reactor reactivity calculations with simplified-P3 and perturbation theories	3
A dynamic probabilistic risk assessment platform for nuclear power plants under single and concurrent transients	3
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH	3
Tsunami flooding analysis graded-approach framework for tsunami probabilistic risk assessment	3
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning	3
Numerical study of initiating phase of core disruptive accident in small sodium-cooled fast reactors with negative void reactivity	3
Development of a multipoint liquid film sensor using an optical waveguide film on simulated fuel rod of BWRs	3
A review on failure behavior and life prediction of circulation pumps in lead-bismuth eutectic cooled reactors	3
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	3
Redistribution of Nb and other alloying elements in Nb-doped Zr alloy under high dose ion irradiation	3
Simulated performance evaluation of d-Be compact fast neutron source	3
Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV	3
Development of a theoretical scaling factor method for the inventory estimation of difficult-to-measure nuclide Cs-135 in fuel debris and radioactive wastes	3
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	3
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	3
Estimation of influence of implicit effect due to multi-group cross-section perturbations on uncertainty analysis in PWR-UO 2 and -MOX lattice calculations	3
Study on chemical interaction between UO2 and Zr at precisely controlled high temperatures	3
Proposal of quantification method of dynamic system reliability model of digital RPS using Markov state-transition model	3
Convergence behavior of statistical uncertainty in probability table for cross section in unresolved resonance region	3
Two-dimensional elemental mapping of simulated fuel debris using laser-induced breakdown spectroscopy	3
Design and development of the machine protection system for HIAF	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
Monte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO 2 and BWR-MOX fuels in the RUBUS program	3
Study on the drop impact acceleration of the radioactive package by new approximation method based on velocity obtained by integrating acceleration	3
A numerical approach for inlet-outlet boundary conditions with least-square moving particle explicit (LSMPE) method on GPU	3
Japanese evaluated nuclear data library version 5: JENDL-5	3
241 Am Neutron Capture Cross Section Measurement using the NaI(Tl) spectrometer of the ANNRI beamline of J-PARC	3
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level	3
Radiation-induced amorphization behavior of thermally-aged M23C6 in F82H-BA12 steel	3
Numerical simulation method using a Cartesian grid for oxidation of core materials under steam-starved conditions	3
Preface to a special issue of journal of nuclear science and Technology on “Nuclear Data and Code Systems as a Basis of Nuclear Technology”	3
Diffusion behavior of cesium in graphite matrix for a high-temperature reactor pebble-bed module: a first-principles study	3
Molten salt oxidation and process analysis of anionic exchange resin in Na 2 CO 3 -K 2 CO	2
Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K	2
Depletion calculation of subcritical system with consideration of spontaneous fission reaction	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
Development of online performance evaluation system of nuclear power plant system	2
Correction	2
Experience with valuation methods for the creation of real options enabling diversity of nuclear fuel supply	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
High temperature electrochemical reaction parameters affecting elecrochemical corrosion potential of type 316L stainless steel	2
Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages	2
Thermodynamic analysis and optimization for steam methane reforming hydrogen production system using high temperature gas-cooled reactor pebble-bed module	2
Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurised water reactor primary coolant under irradiation (2) evaluation of electrochemical corrosion potentia	2
KeV-region analysis of the neutron capture cross-section of 237 Np	2
Extraction behaviors of minor actinides and rare earth elements with NTA amide extractants	2
Limited linear source approximation with edge detection for convergence stability of method of characteristics	2
HHT-based investigation on the two-phase flow regime in the mixer for a nuclear-coupled liquid metal MHD power generation system	2
Measurement of forced convection subcooled boiling flow through a vertical annular channel with high-speed video cameras and image reconstruction	2
Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system	2
Improvement of the optimally-weighted predictor-corrector method for nuclear fuel burnup calculations	2
Effect of radiation and substitution of Ce4+ at Zr site in Y4Zr3O12 using collision cascades: a molecular dynamics simulation study	2
The behaviors of dislocation loops punched by helium interstitials accumulation under the temperature gradient field in tungsten	2
Analysis of cyber nuclear terrorism by DTrack consequences in the civilian nuclear power plant	2
Radioactivation analysis of a concrete wall in a high-energy electron accelerator facility	2
Experimental investigations on flow-induced vibration characteristics of fuel rod with an independent channel for small lead-based reactor	2
Sensitivity analysis of waste resin agitation and extraction in a mock-up test	2
Characterization of a HPGe detector response for activation cross section measurements: regression method versus Monte Carlo method	2
Comprehensive simulation study on CT isotope imaging beyond the experiment on the 208 Pb based on nuclear resonance fluorescence	2

Nuclear data adjustment using a deterministic sampling method with unscented transformation	2
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments	2
A spurious-count effect observed in Rossi-α and Feynman-α analysis using fission counter for Kyoto University Reactor	2
Analysis of work activities involved in clearance verification process of decommissioning Fugen Nuclear Power Plant	2
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O2	2
A new method of measuring ruthenium activity in ruthenium-containing alloys by using thermogravimetric analysis	2
Estimation of the activity median aerodynamic diameter of plutonium particles using image analysis	2
Integral experiment of 129 I(n, γ) reaction using fast neutron source in the ‘YAYOI’ reactor	2
Optimization of BP neural network for fault parameter prediction in nuclear power plants utilizing the firefly algorithm	2
Research on the powderization treatment of uranium-zirconium solid solution simulated nuclear fuel debris using thermochemical redox reaction	2
Theoretical and experimental estimation of the relative optically stimulated luminescence efficiency of an optical-fiber-based BaFBr:Eu detector for swift ions	2
Cross-section adjustment method based on Bayesian theory for specific cross-section set	2
Integrating DeblurGAN and CNN to improve the accuracy of motion blur X-Ray image classification	2
Status of the 226 Ra nuclear data library and its impact on the production amount of 225 Ac via the 226	2
EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242	2
Discrimination of disposal-restricted materials in waste containers by nondestructive testing and image analysis with high-energy X-ray computed tomography	2
Cohesive/Adhesive strengths of CsOH-chemisorbed SS304 surfaces	2
High-temperature ex-vessel corium spreading. Part 1: experimental investigations on ceramic and sacrificial concrete substrates	2
Study of magnetic fringe fields and interference effects on beam dynamics for proton facility gantry	2
Evaluation of beamline subsystem performance during technical commissioning of an superconducting proton therapy facility	2
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	2
Design of moderator and collimator based on compact D-T neutron source for neutron imaging	2
Research on rare-earth element reaction processes with fuel cladding materials in FBR	2
Sorption of Cs + and Eu 3+ onto coherent and melange-type pre-neogene sedimentary rocks	2
Leaching behavior of arsenic and selenium in coal fly ash by aging treatment and cement mixing	2
Proposal and applicability of estimated criticality lower-limit multiplication factor using the bootstrap method	2
Computer code analysis of irradiation performance of an annular mixed oxide fuel element	2
Measurement of the neutron capture cross section of 185 Re in the keV energy region	2
Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel	2
Evaluation of uncertainties derived from meteorological forecast inputs in plume directions predicted by atmospheric dispersion simulations	2
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model	2
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor	2
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks	2
High temperature corrosion of two superalloys in the impure helium environment	2
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	2
Gamma-ray irradiation induced dislocation loops in hexagonal zirconium	2
Preliminary study of the criticality monitoring method based on the simulation for the activity ratio of short half-life noble-gas fission products from fuel debris	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
Study on corrosion of T-22 alloy under high temperature condition of VHTR	1
TRU oxide sample reactivity worths measured in the FCA-IX assemblies with systematically changed neutron energy spectra	1
Seismic response of electrical cabinets considering primary-secondary structure interaction with contact nonlinearity of anchors	1
Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow	1
Thermal-Neutron capture cross-section measurements of Neptunium-237 with graphite thermal column in KUR	1
X-ray absorption study of oxide film formed on Alloy 600 in PWR primary water at 290°C with a decreased concentration of dissolved hydrogen	1
An operation optimization of cooling system for reactor shutdown in pebble bed gas-cooled reactor	1
Development and verification of fast reactor burnup calculation module FRBurner in code system CBZ	1
Kinetic modeling of IG-110 oxidation in inert atmosphere with low oxygen concentration for innovative high-temperature gas-cooled reactor applications	1
XGBoost-based anomaly detection for quality management of spent fuel safety information	1
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates	1
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of Ni-base Alloy 182	1
Benchmark study of particle and heavy-ion transport code system using shielding integral benchmark archive and database for accelerator-shielding experiments	1
Estimation for mass transfer coefficient under two-phase flow conditions using two gas components	1
Development of three-dimensional simulation method for two-phase flow in square-pitch tube bundle in secondary side of steam generators based on porous drift-flux model	1
Sensitivity analysis of risk assessment for continuous Markov process Monte Carlo method using correlated sampling method	1
Measurement of neutron spectra for various thicknesses of concrete and steel shielding at 24-GeV/c proton beam facility using Bonner sphere spectrometer	1
Impact of MOX fuel use in light-water reactors: long-term radiological consequences of disposal of high-level waste in a geological repository	1
Effect of feeding amount on tail gas and waste salt obtained from molten salt oxidation process of cation exchange resins	1
The effect of a cyclic bending load on the bending resistance of ballooned, ruptured, and oxidized Zircaloy-4 cladding	1
Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform	1
Nonuniform particle distribution and interference between removal mechanisms during unsteady aerosol deposition from a rising spherical bubble	1
Uncertainty quantification of criticality in light-water-moderated and graphite-reflected core with highly enriched uranium fuel at university teaching and research reactor	1
Thermodynamic properties of liquid alkali-metal coolants: from the perspective of molecular dynamics	1
A simulation study of hypervelocity jet underwater: physical protection design of offshore floating nuclear power plant against light torpedo threats	1
Chemical interaction of CsOH vapor with UO 2 and Fe-Zr melt	1
Geopolymer and ordinary Portland cement interface analyzed by micro-Raman and SEM	1
Enhancement of applicability of high-efficiency random sampling method using control variates method and sensitivity coefficients	1
Evaluating the diffusion of Kr in UO 2 and ADOPT TM using time-of-flight elastic recoil detection analysis (ToF-erda)	1
Chemical species of iodine during sorption by activated carbon -Effects of original chemical species and fulvic acids	1
Conceptualization of the Micro Research Reactor Cooled by Heat Pipes (MRR-HP), Part-I: neutronics analyses	1
Neutron capture cross-section measurement by mass spectrometry for Pb-204 irradiated in JRR-3	1
241Am Neutron Capture Cross Section in the keV region using Si and Fe-filtered neutron beams	1
Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy	1
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	1
Transferring from Eu 3+ to Eu 2+ in Eu 2 O 3 -LiCl-KCl molte	1
Development of nuclear data processing code FRENDY version 2	1
Development of an in-situ mechanical property identification system for use in high radiation fields	1
Analytical studies on effects of wind on dispersion of hydrogen leaked in a partially open space	1
Revolatilization of iodine by bubbly flow in the suppression pool during an accident	1
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (III): 170 Er(n,γ) 171 Er and	1
Development of AR-based scanning support system for 3D model reconstruction of work sites	1
An energy equivalent method to determine the stress–strain relations of ductile materials by small punch testing	1
Use of Bayesian networks and improved SPAR-H for quantitative analysis of human reliability during severe accidents mitigation process in nuclear power plant	1
Effect of sea salt on the interaction between simulated corium and concrete	1
Temperature dependence of hydrogen yields from the radiolysis of reprocessing solutions: the dissolved solution of spent nuclear fuel	1
Accident severity assessment method for nuclear power plants based on Temporal Convolutional Network (TCN) and Bayesian optimization	1
Thermal performance analysis of molten salt in transversely grooved tube for nuclear reactor	1
A scattered X-ray correction method for transmission measurements and its verification using energy-resolved computed tomography	1
Effect of weld geometry on irradiation damage resistance of 316L stainless steel weld at 400 ℃	1
Influence of plutonium content in dissolver solutions derived from irradiated fast reactor fuels on plutonium stripping in multistage countercurrent liquid–liquid extraction with acid split flowsheet	1
Urinary stone component identification by energy-resolved X-ray computed tomography	1
Influence of composition and temperature on oxide film formation for Fe-Cr-Ni alloys in simulated PWR primary water	1
Development of an integrated non-destructive analysis system, Active-N	1
Behaviors of actinides in chromatographic separation by using TBP resin in nitric acid solution and hydrochloric acid solution	1
Verification of direct coupling code system using FRENDY version 2 and GENESIS for light water reactor lattices	1
Granular fuel debris shape modeling in MPS-DEM for the simulation of fuel debris bed formation in water	1