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	231
Consideration of delayed neutron effect on Rossi-α analysis for a subcritical thermal reactor	158
Application of continuous Markov-chain Monte-Carlo method to multi-unit risk evaluations considering interdependence of accident progression among multiple units	31
Transient heat transfer analysis of double-layer molten pool under severe accident	26
Cesium immobilization from aqueous solution by struvite synthesis	25
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	23
JENDL photonuclear data file 2016	15
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique	14
Experimental and numerical simulation study on the combustion characteristics of nuclear-grade activated carbon	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	13
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids	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
Evaluation of uncertainties derived from meteorological forecast inputs in plume directions predicted by atmospheric dispersion simulations	11
Basic research on estimation of contamination of internal surface of spent nuclear fuel transport casks by Lasso regression	11
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel	11
Comprehensive simulation study on CT isotope imaging beyond the experiment on the 208 Pb based on nuclear resonance fluorescence	11
Sorption of Cs + and Eu 3+ onto coherent and melange-type pre-neogene sedimentary rocks	11
A new separation method of hydrogen isotope by dynamically created nonequilibrium state	10
Molten salt oxidation and process analysis of anionic exchange resin in Na 2 CO 3 -K 2 CO	10
Radioactivation analysis of a concrete wall in a high-energy electron accelerator facility	9
Radio-tellurium released into the environment during the complete oxidation of fuel cladding, containment venting and reactor building failure of the Fukushima accident	9
Discrimination of disposal-restricted materials in waste containers by nondestructive testing and image analysis with high-energy X-ray computed tomography	9
High temperature electrochemical reaction parameters affecting elecrochemical corrosion potential of type 316L stainless steel	9
High-temperature ex-vessel corium spreading. Part 1: experimental investigations on ceramic and sacrificial concrete substrates	9
EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242	9

Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages	8
Revolatilization of iodine by bubbly flow in the suppression pool during an accident	8
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O2	8
Absolute quantification of 137Cs activity in spent nuclear fuel with calculated detector response function	8
Thermal-Neutron capture cross-section measurements of Neptunium-237 with graphite thermal column in KUR	8
Leaching behavior of arsenic and selenium in coal fly ash by aging treatment and cement mixing	8
Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations	8
Deterministic sampling method using simplex ensemble and scaling method for efficient and robust uncertainty quantification	8
Transient parameter prediction and fault diagnosis for nuclear power plants based on machine learning	7
Thermal performance analysis of molten salt in transversely grooved tube for nuclear reactor	7
Thermodynamic properties of liquid alkali-metal coolants: from the perspective of molecular dynamics	7
Development of ACE file perturbation tool using FRENDY	7
Study on iodine adsorption capacity and adsorption mechanism of AgY	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
Experimental analysis of small sample reactivity measured in the SEG experiment by a deterministic reactor physics code system CBZ	7
High-temperature ex-vessel corium spreading. Part 2: scaling principles for gravity-viscous spreading with slip at the melt–substrate interface	6
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
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates	6
The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment	6
Measurement of the thermal neutron capture-cross section of 191 Ir at ANNRI MLF J-PARC	6
Cross-domain fault diagnosis of rotating machinery in nuclear power plant based on improved domain adaptation method	6
A TOF spectrometer for neutron spectral measurements in a wide energy range base on a fast ionization chamber containing 6Li-235U	6
Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy	6
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	6
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33	5
Development of an integrated non-destructive analysis system, Active-N	5
Improvement of analysis results from the GAGG scintillator Compton camera operated on an unmanned helicopter by selecting stable flight conditions	5
Verification of direct coupling code system using FRENDY version 2 and GENESIS for light water reactor lattices	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
Correction	5
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	5
Investigation on the similarity of turbine cascade with different working fluids	5
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy	5
Improvement of thermal conductivity by adding tungsten and/or copper wire in F82H	5
Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow	5
Irradiation hardening and void swelling behaviors of F82H IEA by using dual-ion irradiation	4
Incineration of trans-uranium elements using chlorides molten salt fast reactors – A proposal of incineration in three steps	4
In-situ TEM observation of migration behavior of helium bubbles in F82H	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
Numerical simulation of bubble hydrodynamics for pool scrubbing	4
Investigation into activation of accelerators at various synchrotron radiation facilities in Japan	4
Recovery and immobilization of cesium from aqueous solution after hydrothermal treatment using functional porous glass	4
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level	4
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environment	4
Experimental techniques for investigating thermal transport in nuclear materials	4
A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries	4
Uranium dissolution and uranyl peroxide formation by immersion of simulated fuel debris in aqueous H 2 O 2 solution	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
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
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): 58 Fe(n,γ) 59 Fe	4
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator	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
Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector	4
Highly promising recycled low-density polyethylene sheet adsorbents for uranium recovery from seawater	4
Study on key technical issues of accident selection in emergency planning zone development for small modular reactors	4
Develop a framework of human reliability analysis to evaluate the human error probability in DMCR of NPPs	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
Ensuring a prudent combination of risk insights and a defense-in-depth philosophy through a reinterpretation of hierarchical safety goals	4
Subcriticality determination methodology during fuel loading of accelerator-driven system	4
Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants	4
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model	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
Measurement and simulations of high-energy neutrons through a various thickness of concrete and steel shields using activation detectors at CHARM and CSBF	4
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions	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
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
Measurement of the water-vapor void fraction in a 4x4 unheated rod bundle	4
Correction of X-ray scattering in energy-resolved computed tomography imaging of 20-cm-diameter phantom	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
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
Activity and weight ratios of cesium, uranium, plutonium, and curium isotopes based on elaborate inventory calculations of Fukushima Dai-ichi NPP units 1 to 3	3
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor	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
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH	3
Bayesian approach to energy dependence of fission product yields of 235 U by data augmentation	3
Thermodynamic analysis and optimization for steam methane reforming hydrogen production system using high temperature gas-cooled reactor pebble-bed module	3
Experiences from the cutting of metallic blocks from simulant Fukushima Daiichi fuel debris	3
Gamma-ray irradiation induced dislocation loops in hexagonal zirconium	3
Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform	3
Measurement of the neutron capture cross section of 185 Re in the keV energy region	3
Solubility of FeSe2(cr) at 318 K in the presence of iron	3
Development of AR-based scanning support system for 3D model reconstruction of work sites	3
Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant	3
Reactor antineutrinos and novel application to real-time remote monitoring of nuclear reactors	3
JENDL-5 benchmarking for fission reactor applications	3
Nuclear data adjustment using a deterministic sampling method with unscented transformation	3
Uncertainty quantification of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly	3
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks	3
Thermophysical properties of molten FeO 1.5 , (FeO 1.5 ) 0.86 –(ZrO 2	3
Development of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithm	3
Computer code analysis of irradiation performance of an annular mixed oxide fuel element	3
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments	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
Research on the powderization treatment of uranium-zirconium solid solution simulated nuclear fuel debris using thermochemical redox reaction	3
The effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatment	3
Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system	3
Integral experiment of 129 I(n, γ) reaction using fast neutron source in the ‘YAYOI’ reactor	3
Status of the 226 Ra nuclear data library and its impact on the production amount of 225 Ac via the 226	3
Phase stability of Cs-Si-O and Cs-Si-Fe-O compounds on stainless steel	3
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (III): 170 Er(n,γ) 171 Er and	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
New variance reduction techniques for Monte-Carlo calculation based on first-collision source method	3
Identification and quantification of a 60 Co radiation source under an intense 137 Cs radiation field using an application-specifi	3
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning	3
Study on corrosion of T-22 alloy under high temperature condition of VHTR	3
Fretting wear behavior test and numerical simulation of Inconel 690 alloy	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
Benchmark study of particle and heavy-ion transport code system using shielding integral benchmark archive and database for accelerator-shielding experiments	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
Integrating DeblurGAN and CNN to improve the accuracy of motion blur X-Ray image classification	3
Experience with valuation methods for the creation of real options enabling diversity of nuclear fuel supply	3
Research on frequency modulation technology and its verifications of superconducting synchrocyclotron for cancer therapy	3
Corrosion behavior of zirconium alloys in the aqueous environment. Phenomenological aspects. Overview	3
Role of solute titanium and oxidation in cesium chemisorption onto stainless steel	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
Hybrid data assimilation methods for nuclear-data-induced uncertainties	2
YouTube-based topic modeling and large language Model sentiment analysis of Japanese online discourse on nuclear energy	2
Degradation of nuclear fuel debris analog by siderophore-releasing microorganisms	2
Nuclear data uncertainty in iterative neutron spectrum unfolding	2
High-efficient removal of tungsten from hafnium by TOA/XAD-7 extraction resin from HCl-HF media	2
The behaviors of dislocation loops punched by helium interstitials accumulation under the temperature gradient field in tungsten	2

Treatment of corner crossing ray-traces in CMFD acceleration of MOC	2
Reactor reactivity calculations with simplified-P3 and perturbation theories	2
Data processing and visualization of X-ray computed tomography images of a JOYO MK-III fuel assembly	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
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
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
Irradiation behavior of HfNbTaTiV in comparison of HfNbTaTiZr and F82H	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
Monte Carlo analyses of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly	2
Enhancing magnetohydrodynamic performance of liquid metal with solid insulating powders for fusion reactor applications	2
Simulation of the self-propagating hydrogen-air premixed flame in a closed-vessel by an open-source CFD code	2
EXFOR-based simultaneous evaluation for fast neutron-induced fission cross section of thorium-232	2
Development of integrated FEPs for safety case scenario development	2
Neutron yield calculation of thin and thick d-D targets by using PHITS with frag data table	2
Establishing an evaluation method for the aging phenomenon by physical force in fuel debris	2
Monte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO 2 and BWR-MOX fuels in the RUBUS program	2
Alteration of fuel debris simulants by Bacillus subtilis	2
Evaluation of beamline subsystem performance during technical commissioning of an superconducting proton therapy facility	2
Observation of nepheline crystallization in the Na 2 O-B 2 O 3 -Al 2	2
Correction	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
Calculations and analysis of n+ 52 Cr reactions below 20 MeV	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
Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV	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 design study on a metal fuel fast reactor core for high efficiency minor actinide transmutation by loading silicon carbide composite material	2
Technical research on rapid source term calculation and prediction technology of nuclear accidents based on Bayesian network	2
Radiation-induced amorphization behavior of thermally-aged M23C6 in F82H-BA12 steel	2
Experimental and analytical investigations on aerosol washout in a large vessel with high spray coverage ratio simulating PWR containment spray	2
Dynamic performance analysis of a new low-temperature nuclear heating system with APROS	2
HHT-based investigation on the two-phase flow regime in the mixer for a nuclear-coupled liquid metal MHD power generation system	2
Experimental and numerical study of a condensing steam jet	2
Simulated performance evaluation of d-Be compact fast neutron source	2
Applicability of the kernel method for macroscopic cross section tabulation to planar MOC-based core transient analysis code	2
A new method of measuring ruthenium activity in ruthenium-containing alloys by using thermogravimetric analysis	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
A membrane, pseudo-vertical p-i-n diamond detector	2
Benchmark specifications of TCA critical experiments for validation of thermal scattering laws of water	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
Tensile properties of irradiated modified 316 stainless steel (PNC316) at slow strain rates	1
Double diffusive dissolution model of UO2 pellet in molten Zr cladding	1
Redistribution of Nb and other alloying elements in Nb-doped Zr alloy under high dose ion irradiation	1
Experimental study on mechanical properties of corroded steel used as containment liner in nuclear power plant	1
Stress relieved Zircaloy-4 recovery and recrystallization during fast anisothermal transients	1
Validation of LWR fuel depletion calculation module of reactor physics code system CBZ	1
Halogenation of used aluminum matrix test reactor fuel – a bench-scale demonstration with surrogate materials	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
Temperature dependence of hydrogen yields from the radiolysis of reprocessing solutions: the dissolved solution of spent nuclear fuel	1
Steady-state thermal-structural analysis of high-temperature heat pipes based on thermal-fluid coupling	1
Human reliability analysis of shared equipment in multi-unit site	1
Evaluation of nanofluids for enhancing critical heat flux for in-vessel retention during sever reactor accidents	1
Meteorological effects on atmospheric radioactive particles: a review of recent research	1
Spectral determination method and its application to γ-ray determination	1
Analysis of work activities involved in clearance verification process of decommissioning Fugen Nuclear Power Plant	1
Consideration on the concrete spalling behavior in high-temperature environments during severe accidents	1
Experimental investigations on flow-induced vibration characteristics of fuel rod with an independent channel for small lead-based reactor	1
Synergism of radiation and steam on mechanical properties of cable insulation removed from a nuclear power plant	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
Request for 35 Cl(n,p) reaction cross-section measurements and re-evaluations from the standpoint of molten chloride salt fast reactor design	1
Optimization of BP neural network for fault parameter prediction in nuclear power plants utilizing the firefly algorithm	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
Decontamination of corrosion oxides in the heat transport system of a pressurized heavy water reactor using chelate-free inorganic acid	1
Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 2	1
Localizing unknown radiation sources by unscented particle filtering based on divide-and-conquer sampling	1
Raman identification and characterization of chemical components included in simulated nuclear fuel debris synthesized from uranium, stainless steel, and zirconium	1
A generalized ternary decision diagram for reliability analysis on fault-tolerant systems in different coverage models	1
Study of magnetic fringe fields and interference effects on beam dynamics for proton facility gantry	1
Double-differential cross sections for charged particle emissions from α particle impinging on Al at 230 MeV/u	1
Predictive accuracy of neutronics of light-water-moderated and graphite-reflected core with low-enriched uranium fuel at UTR-KINKI	1
Numerical simulation method using a Cartesian grid for oxidation of core materials under steam-starved conditions	1
Application of dynamic mode decomposition to Rossi-α method in a critical state using file-by-file moving block bootstrap method	1
Limited linear source approximation with edge detection for convergence stability of method of characteristics	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
Effect of radiation and substitution of Ce4+ at Zr site in Y4Zr3O12 using collision cascades: a molecular dynamics simulation study	1
Numerical simulation of the fluid flow and heat transfer of the supercritical water in the 64-element Canadian SCWR fuel bundle	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
Criticality evaluation considering nonuniformity effect using Monte Carlo perturbation method	1
Deep learning-based anomaly detection in Drift Tube Quadrupole operation for the KOMAC LINAC	1
Rare earth elements and radioactive elements in black sands from the Konkan and Malabar coasts of India	1
Chemical species of iodine during sorption by activated carbon -Effects of original chemical species and fulvic acids	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
Research on rare-earth element reaction processes with fuel cladding materials in FBR	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
Simulation using representative data selection for transboundary radiation effect evaluation by Nuclear Accident Consequence Analysis Code (NACAC)	1
A thermal-hydraulic analysis model of printed circuit heat exchangers for system simulation using Modelica	1
Development of neutron self-indication thermometry at J-PARC	1
Depletion calculation of subcritical system with consideration of spontaneous fission reaction	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
Influence of organic dispersant on nuclear grade anion exchange resin and their interaction behavior	1