WWER-440 Fuel And Control Assemblies’, Reflector Models Descriptions, RT_BNL-09-01_T3_001, 2010
Software and methodology for neutron cross-section calculation, RT_BNL-09-01_T2_001, 2010
Database of nuclear fuel characteristics for cross-sections calculations, RT_BNL-09-01_T1_001, 2010
Development of VVER-440 reactor fuel cross-sections library, NRSC-A110-T2.2-001, 2010
Processing of technological condition evaluation instructions for the personnel of ANRA emergency response center, Emergency procedure EP-RS-01: Definition of an initial condition and integrity of the primary coolant system, Emergency procedure EP-RS-02: Definition of reactor core integrity, Emergency procedure EP-RS-03: Definition of release conditions, #09111002 (rus.), March 2010
Classification of emergency situations and accidents at ANPP МА.АТД.СЧС-002 document revision report, ANPP-EPR-09-09 ver. 01 (rus.), February 2010
Small break thermohydraulic analysis taking into account a reconstruction of gradual starting document revision report, NRSC-ANRA-COP-02-09 (rus.), February 2010
Investigation of ANPP confinement response to DBA (LOCA DN100) taking into account hydrogen safety, NRSC-GRS-03-09-A2,3-R2, February 2010
