Journal of Nuclear Science and Technology

Title Publication Date Language Citations
JENDL-4.0: A New Library for Nuclear Science and Engineering2011/01/01English1,551
Features of Particle and Heavy Ion Transport code System (PHITS) version 3.022018/01/05English851
Preliminary Estimation of Release Amounts of131I and137Cs Accidentally Discharged from the Fukushima Daiichi Nuclear Power Plant into the Atmosphere2011/07/01English701
Particle and Heavy Ion Transport code System, PHITS, version 2.522013/09/01English578
Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.32002/11/01English389
Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL-3.21995/12/01English388
Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3.2002/01/01English338
Development of General-Purpose Particle and Heavy Ion Transport Monte Carlo Code2002/11/01English207
Preliminary Numerical Experiments on Oceanic Dispersion of131I and137Cs Discharged into the Ocean because of the Fukushima Daiichi Nuclear Power Plant Disaster2011/11/01English176
Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL-3.2.1995/01/01English172
Development of General-Purpose Particle and Heavy Ion Transport Monte Carlo Code.2002/01/01English158
Classification of Two-Phase Flow Instability by Density Wave Oscillation Model1979/02/01English143
Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I)1997/03/01English141
Microstructural Characterization of SCC Crack Tip and Oxide Film for SUS 316 Stainless Steel in Simulated PWR Primary Water at 320°C2005/02/01English133
Characterization of High Temperature Creep Properties in Recrystallized 12Cr-ODS Ferritic Steel Claddings2002/08/01English132
Source term estimation of atmospheric release due to the Fukushima Dai-ichi Nuclear Power Plant accident by atmospheric and oceanic dispersion simulations2013/03/01English131
Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase Transformation2002/07/01English127
Current understanding of radiation-induced degradation in light water reactor structural materials2013/03/01English121
Insights from review and analysis of the Fukushima Dai-ichi accident2012/01/01English117
An Experimental Study of Molten Salt Electrorefining of Uranium Using Solid Iron Cathode and Liquid Cadmium Cathode for Development of Pyrometallurgical Reprocessing1997/04/01English116
Neutronics Design for Lead-Bismuth Cooled Accelerator-Driven System for Transmutation of Minor Actinide2004/01/01English110
Benchmark study of the recent version of the PHITS code2017/03/20English108
Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water—Effect of Chromium Content in Alloys and Dissolved Hydrogen—2008/10/01English106
Effect of Dry Density on Diffusion of Some Radionuclides in Compacted Sodium Bentonite1992/09/01English105
Fermi-Gas Model Parametrization of Nuclear Level Density1994/02/01English104
Japanese evaluated nuclear data library version 5: JENDL-52023/01/02English98
Validation of a Continuous-Energy Monte Carlo Burn-up Code MVP-BURN and Its Application to Analysis of Post Irradiation Experiment2000/02/01English96
Numerical Analysis of Droplet Breakup Behavior using Particle Method2001/12/01English93
Advanced Doped UO2Pellets in LWR Applications2006/09/01English92
Influence of Dissolved Hydrogen on Structure of Oxide Film on Alloy 600 Formed in Primary Water of Pressurized Water Reactors2003/07/01English90