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Top Articles

#TitleJournalYearCitations
1JENDL-4.0: A New Library for Nuclear Science and EngineeringJournal of Nuclear Science and Technology20111,716
2Preliminary Estimation of Release Amounts of131I and137Cs Accidentally Discharged from the Fukushima Daiichi Nuclear Power Plant into the AtmosphereJournal of Nuclear Science and Technology2011933
3Features of Particle and Heavy Ion Transport code System (PHITS) version 3.02Journal of Nuclear Science and Technology2018915
4Particle and Heavy Ion Transport code System, PHITS, version 2.52Journal of Nuclear Science and Technology2013700
5Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3Journal of Nuclear Science and Technology2002469
6Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL-3.2Journal of Nuclear Science and Technology1995441
7Development of General-Purpose Particle and Heavy Ion Transport Monte Carlo CodeJournal of Nuclear Science and Technology2002355
8Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL-3.2.Journal of Nuclear Science and Technology1995343
9Preliminary Numerical Experiments on Oceanic Dispersion of131I and137Cs Discharged into the Ocean because of the Fukushima Daiichi Nuclear Power Plant DisasterJournal of Nuclear Science and Technology2011226
10Classification of Two-Phase Flow Instability by Density Wave Oscillation ModelJournal of Nuclear Science and Technology1979207
11Source term estimation of atmospheric release due to the Fukushima Dai-ichi Nuclear Power Plant accident by atmospheric and oceanic dispersion simulationsJournal of Nuclear Science and Technology2013157
12Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I)Journal of Nuclear Science and Technology1997151
13Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase TransformationJournal of Nuclear Science and Technology2002151
14Microstructural Characterization of SCC Crack Tip and Oxide Film for SUS 316 Stainless Steel in Simulated PWR Primary Water at 320°CJournal of Nuclear Science and Technology2005143
15Numerical Analysis of Droplet Breakup Behavior using Particle MethodJournal of Nuclear Science and Technology2001140
16Characterization of High Temperature Creep Properties in Recrystallized 12Cr-ODS Ferritic Steel CladdingsJournal of Nuclear Science and Technology2002140
17Neutronics Design for Lead-Bismuth Cooled Accelerator-Driven System for Transmutation of Minor ActinideJournal of Nuclear Science and Technology2004138
18Effect of Dry Density on Diffusion of Some Radionuclides in Compacted Sodium BentoniteJournal of Nuclear Science and Technology1992136
19Current understanding of radiation-induced degradation in light water reactor structural materialsJournal of Nuclear Science and Technology2013136
20An Experimental Study of Molten Salt Electrorefining of Uranium Using Solid Iron Cathode and Liquid Cadmium Cathode for Development of Pyrometallurgical ReprocessingJournal of Nuclear Science and Technology1997132
21Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water—Effect of Chromium Content in Alloys and Dissolved Hydrogen—Journal of Nuclear Science and Technology2008116
22Mathematica Programs for the Analysis of Three-Dimensional Pore Connectivity and Anisotropic Tortuosity of Porous Rocks using X-ray Computed Tomography Image DataJournal of Nuclear Science and Technology2007115
23Benchmark study of the recent version of the PHITS codeJournal of Nuclear Science and Technology2017115
24Distribution and Fixation of Cesium and Strontium in Zeolite A and ChabaziteJournal of Nuclear Science and Technology1985112
25Validation of a Continuous-Energy Monte Carlo Burn-up Code MVP-BURN and Its Application to Analysis of Post Irradiation ExperimentJournal of Nuclear Science and Technology2000111
26Achievement of Reactor-Outlet Coolant Temperature of 950°C in HTTRJournal of Nuclear Science and Technology2004110
27Fermi-Gas Model Parametrization of Nuclear Level DensityJournal of Nuclear Science and Technology1994109
28Insights from review and analysis of the Fukushima Dai-ichi accidentJournal of Nuclear Science and Technology2012107
29Ionic Diffusion Coefficients of Cs+, Pb2+, Sm3+, Ni2+, SeO2- 4 and TcO− 4 in Free Water Determined from Conductivity MeasurementsJournal of Nuclear Science and Technology1996105
30Advanced Doped UO2Pellets in LWR ApplicationsJournal of Nuclear Science and Technology2006105
31Influence of Dissolved Hydrogen on Structure of Oxide Film on Alloy 600 Formed in Primary Water of Pressurized Water ReactorsJournal of Nuclear Science and Technology2003104
32Flow Behavior and Pressure Drop of Two-Phase Flow through C-Shaped Bend in Vertical Plane, (I)Journal of Nuclear Science and Technology1980103
33Effect of Core Spray Cooling in Transient State after Loss of Coolant AccidentJournal of Nuclear Science and Technology196898
34High Burnup Fuel Cladding Materials R&D for Advanced Nuclear SystemsJournal of Nuclear Science and Technology200798
35Dissolution Rates of Amorphous Silica in Highly Alkaline SolutionJournal of Nuclear Science and Technology200096
36Derivation of Optimum Polar Angle Quadrature Set for the Method of Characteristics Based on Approximation Error for the Bickley FunctionJournal of Nuclear Science and Technology200795
37Neutron-Induced Fission of233U,238U,232Th,239Pu,237Np,natPb and209Bi Relative to235U in the Energy Range 1-200 MeVJournal of Nuclear Science and Technology200294
38Calculation of Gamma-Ray Buildup Factors up to Depths of 100 mfp by the Method of Invariant Embedding, (III)Journal of Nuclear Science and Technology200491
39Monte Carlo Simulation for Particle and γ-Ray Emissions in Statistical Hauser-Feshbach ModelJournal of Nuclear Science and Technology201091
403-D Neutron Transport BenchmarksJournal of Nuclear Science and Technology199190
41Soil-to-Plant Transfer Factors of Stable Elements and Naturally Occurring Radionuclides (1) Upland Field Crops Collected in JapanJournal of Nuclear Science and Technology200789
42A scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retentionJournal of Nuclear Science and Technology201488
43The Direct Contact Condensation of Steam in a Pool at Low Mass FluxJournal of Nuclear Science and Technology200385
44Numerical Analysis of Jet Injection Behavior for Fuel-Coolant Interaction using Particle MethodJournal of Nuclear Science and Technology200184
45Sanex-Btp Process Development StudiesJournal of Nuclear Science and Technology200283
46Proposal of Nondestructive Radionuclide Assay Using a High-Flux Gamma-Ray Source and Nuclear Resonance FluorescenceJournal of Nuclear Science and Technology200883
47Analytical Prediction of CHF by FIDAS Code Based on Three-Fluid and Film-Dryout ModelJournal of Nuclear Science and Technology199082
48Simulation of Bubble Motion under Gravity by Lattice Boltzmann MethodJournal of Nuclear Science and Technology200182
49Crystallography of Zirconium Hydrides in Recrystallized Zircaloy-2 Fuel Cladding by Electron Backscatter DiffractionJournal of Nuclear Science and Technology200481
50Development of a Comprehensive Code for Nuclear Data Evaluation, CCONE, and Validation Using Neutron-Induced Cross Sections for Uranium IsotopesJournal of Nuclear Science and Technology200781