Ушбу иш иқтибос қилган ишлар

2 та иш

Иш: Neutron-physical and thermohydraulic calculations of VVR-SM with high-and low-enrichment uranium fuel assemblies

1. MCNP-A General Monte Carlo N-Particle Transport Code

   Judith F. Briesmeister

   Мақола19933 иқтибос

   ABIABI:AkademIndex/openalex/2026.other.396949

2. Operation of VVR-SM with 36% Enrichment Uranium-Dioxide Fuel

   B. S. Yuldashev, У. С. Салихбаев, A. A. Dosimbaev +3

   МақолаNuclear reactor physics and engineeringAtomic Energy20051 иқтибос

   ABIABI:AkademIndex/openalex/2026.other.396948