JNE | Free Full-Text | Simulation of VVER-1000 Guillotine Large Break Loss of Coolant Accident Using RELAP5/SCDAPSIM/MOD3.5
Design of nuclear plants
Design of nuclear plants
Analytical assessment of VVER-1000 fuel assembly deformation in loss of coolant accident - ScienceDirect
Design of nuclear plants
Status report 93 - VVER–1000 (V-466B) (VVER–1000 (V-466B))
Evaluation of advanced accumulator in a VVER-1000 reactor in loss of coolant accident - ScienceDirect
VVER - Wikipedia
Status report 93 - VVER–1000 (V-466B) (VVER–1000 (V-466B))
Thermal-hydraulic modeling for deterministic safety analysis of portable equipment application in the VVER-1000 nuclear reactor during loss of ultimate heat sink accident using RELAP5/MOD3.2 code - ScienceDirect
Thermal-hydraulic analysis of VVER-1000 residual heat removal system using RELAP5 code, an evaluation at the boundary of reactor repair mode - ScienceDirect
Status report 93 - VVER–1000 (V-466B) (VVER–1000 (V-466B))
Design of nuclear plants
JNE | Free Full-Text | Simulation of VVER-1000 Guillotine Large Break Loss of Coolant Accident Using RELAP5/SCDAPSIM/MOD3.5
JNE | Free Full-Text | Simulation of VVER-1000 Guillotine Large Break Loss of Coolant Accident Using RELAP5/SCDAPSIM/MOD3.5
JNE | Free Full-Text | Simulation of VVER-1000 Guillotine Large Break Loss of Coolant Accident Using RELAP5/SCDAPSIM/MOD3.5
JNE | Free Full-Text | Simulation of VVER-1000 Guillotine Large Break Loss of Coolant Accident Using RELAP5/SCDAPSIM/MOD3.5
ÉLESBEN AZ ENERGIAHATÉKONYSÁGRÓL
Design of nuclear plants
Primer és szekunder köri főberendezések
Severe accident simulation for VVER-1000 reactor using ASTEC-V2.1.1.3
Status report 107 - VVER-1200 (V-392M) (VVER-1200 (V-392M))
Status report 93 - VVER–1000 (V-466B) (VVER–1000 (V-466B))
JNE | Free Full-Text | Simulation of VVER-1000 Guillotine Large Break Loss of Coolant Accident Using RELAP5/SCDAPSIM/MOD3.5
The technology of VVER-440/213 (Legend: PR-pressurizer, MV-main valve,... | Download Scientific Diagram
