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Publications by Denis V. Grishko
Calculation Methodology of Fast Fission Factor in a Thermal Reactor
MATEC Web of Conferences
Materials Science
Engineering
Chemistry
Related publications
Use of Neutron Filters for Fast Reactor Fuel Irradiations in a Thermal Reactor Core.
Thermal-Hydraulically Calculation for the Dalat Nuclear Research Reactor
Vietnam Journal of Mechanics
Behavior of Fission Products Zirconium and Barium in Fast Reactor Fuel Irradiated to High Burnup
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor
Science and Technology of Nuclear Installations
Engineering
Nuclear Energy
Application of FORSS Sensitivity and Uncertainty Methodology to Fast Reactor Benchmark Analysis
Fission-Produced 99 Mo Without a Nuclear Reactor
Journal of Nuclear Medicine
Medicine
Nuclear Medicine
Radiology
Imaging
Fast Reactor Fuel Assembly Thermal Hydraulic Development Program: Sodium Heat Transfer.
JENDL-4.0 Benchmarking for Fission Reactor Applications
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Relative Hazard Calculation Methodology
