Despite similarity between VVER-1000/V320 and PWR, accounting of specificities of Russian reactor designs is still required. Part of it is the simulation of core decay heat rate after the shutdown. MELCOR 1.8.4 distinguishes fifteen classes. Each of them contains chemical elements with similar ...
This paper presents the results of thermal-hydraulic calculation of “Steam Line Break” analysis at full power reactor for VVER-1000/V320 units at Kozloduy Nuclear Power Plant (KNPP), done during the development of symptom based emergency operating procedures (SB EOPs) for this plant. The RELAP...
For this purpose, a VVER-1000/V320 thermal hydraulic model for TRACEV5P5 code has been modified to include the HA-2 system. By analysing the results, it is found that the single performance of this passive safety system along with the accumulators, without considering any other management ...
SUMMARY This summary presents generic results and insights from preliminary calculations performed with the RELAP5-3D code1 for Main-Steam-Line-Break (MSLB) accidents at the Balakovo-4 plant, a VVER-1000 V320 plant located in Russia. The VVER-1000 core model contains three Lead Test Assemblies...
A RELAP5/MOD3.2 model of the VVER-1000/MODEL V320 nuclear power plant was modified and a large-break loss-of-coolant accident (LBLOCA) in the cold leg was simulated. In this analysis, the core consisted of 162 UOassemblies and 1 mixed-oxide assembly. The results from the simulation were...
L.Sabotinov, A.Srivastava, "Large Break Loss of Coolant Accident Analysis of VVER- 1000 reactor using CATHARE Code.", Proc. of ICAPP'08, Anaheim, CA USA, June 8- 12, 2008 , Journal Nuclear Technology Vol.170,April 2010L.Sabotinov "Total Loss of SG Feed Water for a VVER-1000/V320...
VVER-1000 V320 reactorSevere accident analysis of a reactor is an important aspect for evaluation of source term. This in turn helps in emergency planning and severe accident management (SAM). Analyses have been carried out for VVER-1000 (V320) reactor following LOCA along with station blackout...
and Hadjiev, V. (2007) Systematic Approach for the Analytical Validation of Kozloduy NPP, VVER-1000/V320 Symptom Based Emergency Operating Procedures. Progress in Nuclear Energy, 50, 27-32. http://dx.doi.org/10.1016/j.pnucene.2007.10.002...
The ASTECv2.0r3 severe accident computer code was used to simulate Large Break LOCA (2脳850mm) with full Station blackout (SBO) in VVER-1000/v320 reactor model. The external water cooling of the vessel bottom head during the accident was also simulated by the code. The results from four ...
Borisov, E., Grigorov, D. and Mancheva, K. (2013) Study of Long-Term Loss of All AC Power Supply Sources for VVER-1000/V320 in Connection with Application of New Engineering Safety Features for SAMG. Annals of Nuclear Energy, 59, 204-210....