Journal of Nuclear Science and Technology

Article	Citations
The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations	207
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	120
JENDL photonuclear data file 2016	27
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids	24
Consideration of delayed neutron effect on Rossi-α analysis for a subcritical thermal reactor	23
Application of continuous Markov-chain Monte-Carlo method to multi-unit risk evaluations considering interdependence of accident progression among multiple units	21
Transient heat transfer analysis of double-layer molten pool under severe accident	15
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique	14
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel	13
Cesium immobilization from aqueous solution by struvite synthesis	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
Discrimination of disposal-restricted materials in waste containers by nondestructive testing and image analysis with high-energy X-ray computed tomography	11
Experimental and numerical simulation study on the combustion characteristics of nuclear-grade activated carbon	11
Evaluation of uncertainties derived from meteorological forecast inputs in plume directions predicted by atmospheric dispersion simulations	11
Radioactivation analysis of a concrete wall in a high-energy electron accelerator facility	10
High-temperature ex-vessel corium spreading. Part 1: experimental investigations on ceramic and sacrificial concrete substrates	10
Radio-tellurium released into the environment during the complete oxidation of fuel cladding, containment venting and reactor building failure of the Fukushima accident	9
Comprehensive simulation study on CT isotope imaging beyond the experiment on the 208 Pb based on nuclear resonance fluorescence	9
A new separation method of hydrogen isotope by dynamically created nonequilibrium state	9
Sorption of Cs + and Eu 3+ onto coherent and melange-type pre-neogene sedimentary rocks	9
Basic research on estimation of contamination of internal surface of spent nuclear fuel transport casks by Lasso regression	9
Molten salt oxidation and process analysis of anionic exchange resin in Na 2 CO 3 -K 2 CO	8
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O2	8
Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations	8
High temperature electrochemical reaction parameters affecting elecrochemical corrosion potential of type 316L stainless steel	8

Absolute quantification of 137Cs activity in spent nuclear fuel with calculated detector response function	8
Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages	8
Thermal performance analysis of molten salt in transversely grooved tube for nuclear reactor	8
EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242	8
Leaching behavior of arsenic and selenium in coal fly ash by aging treatment and cement mixing	8
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates	8
Study on iodine adsorption capacity and adsorption mechanism of AgY	8
Development of ACE file perturbation tool using FRENDY	7
Revolatilization of iodine by bubbly flow in the suppression pool during an accident	7
Thermodynamic properties of liquid alkali-metal coolants: from the perspective of molecular dynamics	7
Thermal-Neutron capture cross-section measurements of Neptunium-237 with graphite thermal column in KUR	7
Deterministic sampling method using simplex ensemble and scaling method for efficient and robust uncertainty quantification	7
A simulation study of hypervelocity jet underwater: physical protection design of offshore floating nuclear power plant against light torpedo threats	7
Exploratory study of nuclear magnetic resonance well logging technology on the hydrogeological characteristics of deep geological formations	7
Urinary stone component identification by energy-resolved X-ray computed tomography	6
Sensitivity analysis of risk assessment for continuous Markov process Monte Carlo method using correlated sampling method	6
The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment	6
Verification of direct coupling code system using FRENDY version 2 and GENESIS for light water reactor lattices	6
A TOF spectrometer for neutron spectral measurements in a wide energy range base on a fast ionization chamber containing 6Li-235U	6
Neutron yield calculation of p-Li thick target by using PHITS with JENDL-4.0/HE and ENDF/B-VII for BNCT application	6
Improvement of thermal conductivity by adding tungsten and/or copper wire in F82H	6
High-temperature ex-vessel corium spreading. Part 2: scaling principles for gravity-viscous spreading with slip at the melt–substrate interface	6
Experimental analysis of small sample reactivity measured in the SEG experiment by a deterministic reactor physics code system CBZ	6
Cross-domain fault diagnosis of rotating machinery in nuclear power plant based on improved domain adaptation method	6
Measurement of the thermal neutron capture-cross section of 191 Ir at ANNRI MLF J-PARC	6
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	6
Improvement of analysis results from the GAGG scintillator Compton camera operated on an unmanned helicopter by selecting stable flight conditions	5
Development of an integrated non-destructive analysis system, Active-N	5
Safety assessment of second-phase disposal facility in Gyeongju low- and intermediate-level radioactive waste (LILW) repository using RESRAD-OFFSITE code	5
Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow	5
Correction	5
Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis	5
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33	5
Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy	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
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy	5
Investigation into activation of accelerators at various synchrotron radiation facilities in Japan	4
Highly promising recycled low-density polyethylene sheet adsorbents for uranium recovery from seawater	4
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environment	4
Irradiation hardening and void swelling behaviors of F82H IEA by using dual-ion irradiation	4
Subcriticality determination methodology during fuel loading of accelerator-driven system	4
Test of 107 Pd transmutation with macroscopic quantities	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
A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries	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
In-situ TEM observation of migration behavior of helium bubbles in F82H	4
Measurement of the water-vapor void fraction in a 4x4 unheated rod bundle	4
Ensuring a prudent combination of risk insights and a defense-in-depth philosophy through a reinterpretation of hierarchical safety goals	4
ACE-FRENDY-CBZ: a new neutronics analysis sequence using multi-group neutron transport calculations	4
Flame structures and ignition thresholds of hydrogen jets containing sodium mist under various gas concentrations	4

Develop a framework of human reliability analysis to evaluate the human error probability in DMCR of NPPs	4
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator	4
Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons	4
Reactivity estimation based on the linear equation of characteristic time profile of power in subcritical quasi-steady state	4
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	4
Investigation on the similarity of turbine cascade with different working fluids	4
Uranium dissolution and uranyl peroxide formation by immersion of simulated fuel debris in aqueous H 2 O 2 solution	4
Correction of X-ray scattering in energy-resolved computed tomography imaging of 20-cm-diameter phantom	4
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure	4
Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility	4
Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector	3
Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K	3
Benchmark study of particle and heavy-ion transport code system using shielding integral benchmark archive and database for accelerator-shielding experiments	3
Phase stability of Cs-Si-O and Cs-Si-Fe-O compounds on stainless steel	3
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning	3
Enhancement of random sampling by a combined approach of control variates and Latin hypercube sampling for uncertainty quantification in light water reactor lattice calculations	3
Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel	3
Integral experiment of 129 I(n, γ) reaction using fast neutron source in the ‘YAYOI’ reactor	3
A spurious-count effect observed in Rossi-α and Feynman-α analysis using fission counter for Kyoto University Reactor	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
Numerical simulation of bubble hydrodynamics for pool scrubbing	3
Experimental techniques for investigating thermal transport in nuclear materials	3
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions	3
Recovery and immobilization of cesium from aqueous solution after hydrothermal treatment using functional porous glass	3
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH	3
Measurement of the neutron capture cross section of 185 Re in the keV energy region	3
Computer code analysis of irradiation performance of an annular mixed oxide fuel element	3
Development of AR-based scanning support system for 3D model reconstruction of work sites	3
Nuclear data adjustment using a deterministic sampling method with unscented transformation	3
Integrating DeblurGAN and CNN to improve the accuracy of motion blur X-Ray image classification	3
New variance reduction techniques for Monte-Carlo calculation based on first-collision source method	3
Experience with valuation methods for the creation of real options enabling diversity of nuclear fuel supply	3
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks	3
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model	3
Status of the 226 Ra nuclear data library and its impact on the production amount of 225 Ac via the 226	3
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): 58 Fe(n,γ) 59 Fe	3
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level	3
Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants	3
Gamma-ray irradiation induced dislocation loops in hexagonal zirconium	3
Development of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithm	3
Experiences from the cutting of metallic blocks from simulant Fukushima Daiichi fuel debris	3
Research on frequency modulation technology and its verifications of superconducting synchrocyclotron for cancer therapy	3
Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant	3
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor	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
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
Thermodynamic analysis and optimization for steam methane reforming hydrogen production system using high temperature gas-cooled reactor pebble-bed module	3
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments	3
Experimental investigation of spray cooling behavior in 4×4 simulated fuel bundle	3
Research on the powderization treatment of uranium-zirconium solid solution simulated nuclear fuel debris using thermochemical redox reaction	3
Effects of correlations in uncertainties of total cross section and elastic angular distribution for a deep penetration of 14-MeV neutrons in Cu	3
Measurement and simulations of high-energy neutrons through a various thickness of concrete and steel shields using activation detectors at CHARM and CSBF	3
Incineration of trans-uranium elements using chlorides molten salt fast reactors – A proposal of incineration in three steps	3
Uncertainty quantification of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly	2
Establishing an evaluation method for the aging phenomenon by physical force in fuel debris	2
Study on corrosion of T-22 alloy under high temperature condition of VHTR	2
EXFOR-based simultaneous evaluation for fast neutron-induced fission cross section of thorium-232	2
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	2
Role of solute titanium and oxidation in cesium chemisorption onto stainless steel	2
EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5	2
Nuclear data generation by machine learning (I) application to angular distributions for nucleon-nucleus scattering	2
Neutron yield calculation of thin and thick d-D targets by using PHITS with frag data table	2
Reactor reactivity calculations with simplified-P3 and perturbation theories	2
Corrosion behavior of zirconium alloys in the aqueous environment. Phenomenological aspects. Overview	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
Experimental study on design optimization of the core catcher for the CEFR	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
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
A study on the establishment of database for local government disaster response and decision support system in the nuclear accidents	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
A membrane, pseudo-vertical p-i-n diamond detector	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
Benchmark specifications of TCA critical experiments for validation of thermal scattering laws of water	2
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (III): 170 Er(n,γ) 171 Er and	2
Identification and quantification of a 60 Co radiation source under an intense 137 Cs radiation field using an application-specifi	2
Observation of nepheline crystallization in the Na 2 O-B 2 O 3 -Al 2	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

Treatment of corner crossing ray-traces in CMFD acceleration of MOC	2
Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform	2
Evaluation of the structural integrity of a BWR core shroud with non-regular locations of circumferential cracks. Part I fracture analysis	2
High-efficient removal of tungsten from hafnium by TOA/XAD-7 extraction resin from HCl-HF media	2
Experimental and numerical study of a condensing steam jet	2
Monte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO 2 and BWR-MOX fuels in the RUBUS program	2
Multi-group neutron cross section generation capability for FRENDY nuclear data processing code	2
Evaluation of beamline subsystem performance during technical commissioning of an superconducting proton therapy facility	2
Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C	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
A design study on a metal fuel fast reactor core for high efficiency minor actinide transmutation by loading silicon carbide composite material	2
Alteration of fuel debris simulants by Bacillus subtilis	2
Enhancing magnetohydrodynamic performance of liquid metal with solid insulating powders for fusion reactor applications	2
Data processing and visualization of X-ray computed tomography images of a JOYO MK-III fuel assembly	2
A new method of measuring ruthenium activity in ruthenium-containing alloys by using thermogravimetric analysis	2
Bayesian approach to energy dependence of fission product yields of 235 U by data augmentation	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
Experimental and analytical investigations on aerosol washout in a large vessel with high spray coverage ratio simulating PWR containment spray	2
JENDL-5 benchmarking for fission reactor applications	2
Development of integrated FEPs for safety case scenario development	2
The effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatment	2
Dynamic performance analysis of a new low-temperature nuclear heating system with APROS	2
Applicability of the kernel method for macroscopic cross section tabulation to planar MOC-based core transient analysis code	2
Calculations and analysis of n+ 52 Cr reactions below 20 MeV	2
Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV	2
Simulated performance evaluation of d-Be compact fast neutron source	2
Irradiation behavior of HfNbTaTiV in comparison of HfNbTaTiZr and F82H	2
Nuclear data uncertainty in iterative neutron spectrum unfolding	2
Technical research on rapid source term calculation and prediction technology of nuclear accidents based on Bayesian network	2
Design and development of the machine protection system for HIAF	2
Monte Carlo analyses of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly	2
Development of glass gas electron multiplier-based pulse counting imaging system with FPD front-end electronics	2
Heat of transport for hydrogen and hydrides in Zircaloy	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
Formulation of Irradiation Assisted Stress Corrosion Crack Growth Rates for Neutron-Irradiated Stainless Steels under Hydrogen Water Chemistry Conditions of Boiling Water Reactors	2
Correction	2
Reactor antineutrinos and novel application to real-time remote monitoring of nuclear reactors	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
Synergism of radiation and steam on mechanical properties of cable insulation removed from a nuclear power plant	1
Double diffusive dissolution model of UO2 pellet in molten Zr cladding	1
A novel Compton camera with an annular absorber for enhancing the imaging efficiency in regions directly ahead: A simulation study	1
Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 2	1
Evaluation of nanofluids for enhancing critical heat flux for in-vessel retention during sever reactor accidents	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
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
Human reliability analysis of shared equipment in multi-unit site	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
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
Redistribution of Nb and other alloying elements in Nb-doped Zr alloy under high dose ion irradiation	1
Measurements of keV-Neutron capture cross sections and capture gamma-ray spectra of 74,76,78,80,82 Se	1
Criticality evaluation considering nonuniformity effect using Monte Carlo perturbation method	1
Effect of weld geometry on irradiation damage resistance of 316L stainless steel weld at 400 ℃	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
A scattered X-ray correction method for transmission measurements and its verification using energy-resolved computed tomography	1
Reduced order SP 3 core calculation based on local/global iterations using proper orthogonal decomposition	1
Development of neutron self-indication thermometry at J-PARC	1
Development of local-scale high-resolution atmospheric dispersion and dose assessment system	1
Influence of organic dispersant on nuclear grade anion exchange resin and their interaction behavior	1
Experimental study on mechanical properties of corroded steel used as containment liner in nuclear power plant	1
Consideration on the concrete spalling behavior in high-temperature environments during severe accidents	1
Passive fast neutron multiplicity counting system based on a symmetric spherical design	1
Spectral determination method and its application to γ-ray determination	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
Application of dynamic mode decomposition to Rossi-α method in a critical state using file-by-file moving block bootstrap method	1
Validation of LWR fuel depletion calculation module of reactor physics code system CBZ	1
Numerical simulation method using a Cartesian grid for oxidation of core materials under steam-starved conditions	1
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	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
Numerical study of turbulent heat transfer of annular fuel assembly in a sodium-cooled fast reactor by a SST k-ω-k θ -ε	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
Extraction behaviors of minor actinides and rare earth elements with NTA amide extractants	1
Validation of several sets of delayed-neutron group parameters for thermal fission of 235 U by a Feynman-α analysis	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
Investigation on multi-dimensional short-term behaviour through benchmark analysis of a large-volume sodium combustion experiment	1
Study on the mechanism of alkali fusion reaction of uranium oxide and sodium peroxide	1
Development of a radiation tolerant laser-induced breakdown spectroscopy system using a single crystal micro-chip laser for remote elemental analysis	1
Application of the spectral determination method to unified β-, γ- and X-ray spectra	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
Towards safe, efficient long-reach manipulation in nuclear decommissioning: a case study on fuel debris retrieval at Fukushima Daiichi	1
Rare earth elements and radioactive elements in black sands from the Konkan and Malabar coasts of India	1
Simulation using representative data selection for transboundary radiation effect evaluation by Nuclear Accident Consequence Analysis Code (NACAC)	1
Steady-state thermal-structural analysis of high-temperature heat pipes based on thermal-fluid coupling	1
Double-differential cross sections for charged particle emissions from α particle impinging on Al at 230 MeV/u	1
Localizing unknown radiation sources by unscented particle filtering based on divide-and-conquer sampling	1
Depletion calculation of subcritical system with consideration of spontaneous fission reaction	1
Limited linear source approximation with edge detection for convergence stability of method of characteristics	1
A thermal-hydraulic analysis model of printed circuit heat exchangers for system simulation using Modelica	1
Nonuniform particle distribution and interference between removal mechanisms during unsteady aerosol deposition from a rising spherical bubble	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
Enhancement of applicability of high-efficiency random sampling method using control variates method and sensitivity coefficients	1
Hand calculation method for secondary impact assessment of radioactive materials transport casks under oblique drop test	1
EPMA and EBSD observations of unirradiated MIMAS-MOX fuels for the study of fission gas release and thermal conductivity	1
A support vector machine framework for fault detection in molecular pump	1