Personal Information
Entreprise/Lieu de travail
Kaluga Region, Russian Federation Russian Federation
Profession
Department Head. Reactor Development & Design Department.
Secteur d’activité
Education
Site Web
http://www.samokhin.ucoz.ru/
À propos
• Calculates self-shielded multigroup cross sections from different evaluated nuclear data libraries and produce multigroup libraries in traditional MATXS format using the NJOY code.
• Calculate shielded multigroup cross sections using TRANSX code.
• Also we can produce MCNP libraries in ACE-format using the NJOY code, generate input MCNP files and perform calculations.
• Besides this we have our own code for isotope kinetics, which uses reaction rates generated by MCNP and very interested in its testing on special benchmarks.
• The feature of this code is to obtain assessments of nuclear concentration uncertainties in isotope kinetics calculations by interval calculation method a
Mots-clés
the safety assessment
nuclear power plant
reliability
nuclear fuel
security
neutrons
fissioning nucleus
macroscopic cross-section
nuclear reactor
Tout plus
Présentations
(14)Personal Information
Entreprise/Lieu de travail
Kaluga Region, Russian Federation Russian Federation
Profession
Department Head. Reactor Development & Design Department.
Secteur d’activité
Education
Site Web
http://www.samokhin.ucoz.ru/
À propos
• Calculates self-shielded multigroup cross sections from different evaluated nuclear data libraries and produce multigroup libraries in traditional MATXS format using the NJOY code.
• Calculate shielded multigroup cross sections using TRANSX code.
• Also we can produce MCNP libraries in ACE-format using the NJOY code, generate input MCNP files and perform calculations.
• Besides this we have our own code for isotope kinetics, which uses reaction rates generated by MCNP and very interested in its testing on special benchmarks.
• The feature of this code is to obtain assessments of nuclear concentration uncertainties in isotope kinetics calculations by interval calculation method a
Mots-clés
the safety assessment
nuclear power plant
reliability
nuclear fuel
security
neutrons
fissioning nucleus
macroscopic cross-section
nuclear reactor
Tout plus