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Nuclear Safety Institute | Researchclopedia

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Nuclear Safety Institute

Moscowfacility

1,738

Works

28,242

Citations

70

h-index

Top Research Topics

Nuclear reactor physics and engineering Nuclear Materials and Properties Nuclear Engineering Thermal-Hydraulics

Top Researchers

Yoshio Yamaoka Mie University Hospital

1,237 works50,002 citationsh-index: 107

Recent Research

A 2D approach for thermal analysis in the fuel rod performance code BERKUT-U

A.P. Dolgodvorov,E.G. Belendryasova,et al.

20260 citations

Graphite, nuclear technology, radiation studies

Nuclear and radioactivity studies

Radioactive contamination and transfer

Differential Equations and Numerical Methods

Advanced Numerical Methods in Computational Mathematics

Black Holes and Theoretical Physics

Cosmology and Gravitation Theories

Computational Fluid Dynamics and Aerodynamics

Advanced Mathematical Modeling in Engineering

V.I. Belousov Kurchatov Institute

47 works24,246 citationsh-index: 8

Leonid Zaslavsky National Institutes of Health

48 works19,217 citationsh-index: 14

Akira Nakamura Cross Compass (Japan)

845 works15,706 citationsh-index: 62

Friedrich W. Hehl University of Cologne

302 works12,772 citationsh-index: 53

Masanori Kikuchi National Institute for Materials Science

974 works10,499 citationsh-index: 48

Assessment of the Explosiveness of Dried Residues from Nitric Acid Solutions Containing Organic Reductants for Reprocessing of (U, Pu)N Spent Nuclear Fuel

M. A. Arkhipova,K. N. Dvoeglazov,et al.

20260 citations

Effect of ballistic re-solution on the nucleation kinetics of precipitates in diluted binary alloys under irradiation. Part 2: Cr-rich alpha' precipitates in Fe-Cr alloys

M. S. Veshchunov

20260 citations

80 years of nuclear industry and the role of radiation hygiene

L. A. Bolshov,I. I. Linge,et al.

20260 citations

Effect of Ballistic Re-Solution on the Nucleation Kinetics of Precipitates in Diluted Binary Alloys under Irradiation. Part 2: Cr-Rich Alpha′ Precipitates in Fe-Cr Alloys

Mikhail S. Veshchunov

20260 citations

Models and validation results of the SAFR module of the integral code EUCLID/V2 for calculating thermal destruction of fuel pins with nitride fuel

E.V. Usov,VD Ozrin,et al.

20250 citations