Discover open access scientific publications

Search, annotate, share and cite publications

Publications by M.Y. Ternovykh

Modeling of Analytical-Experimental Benchmark on Irradiation of Nitride Fuel in BN-600 Reactor in the SCALE6 Code

KnE Engineering

English

Related publications

Irradiation Performance of Experimental Fast Reactor "JOYO" MK-I Driver Fuel Assemblies.

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan

English

Nitride Fuel Modeling Recommendation for Nitride Fuel Material Property Measurement Priority

English

Irradiation Test in Experimental Fast Reactor "Joyo"

Bulletin of the Japan Institute of Metals

English

Uranium Nitride--Sodium Paste Fuel for Fast-Reactor Blankets.

English

Manufacture of Fuel Plates for the Experimental Boiling Water Reactor

English

Transient Overpower Irradiation of Axially-Restrained, Zero-Burnup, Fast Reactor Fuel Specimens.

English

Development of Input Data to Energy Code for Analysis of Reactor Fuel Bundles

English

Reactor Physics and Criticality Benchmark Evaluations for Advanced Nuclear Fuel - Final Technical Report

English

Experimental and Computational Study of Thermal Treatment of Particulate Fuel in a Fluidized Bed Reactor

English