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 ...
Steam Line Break investigation at full power reactor for VVER-1000V320 文档格式: .pdf 文档大小: 2.61M 文档页数: 10页 顶/踩数: 0/0 收藏人数: 0 评论次数: 0 文档热度: 文档分类: 论文--大学论文 文档标签: SteamLineBreakinvestigationatfullpowerreactorforVVER-1000V320 ...
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...
Similar model is prepared with MCNP6 for comparison between deterministic (Pn spherical-harmonics method used in PARCS) and the stochastic (Monte Carlo) approach (used in MCNP6). Such comparison will serve as a demonstration of the capability of the PARCS code for VVER1000/V320 analyses. 展开 ...
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 ...
thermal-hydraulics relap5/mod3.2 nuclear power plant safety wer low power and cold condition critical safety functionThis paper presents the results of thermal–hydraulic calculation of accident scenarios that involve the loss of critical safety function (CSF) "Core cooling" for VVER-1000/V320 units...
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....
Andreeva M., Groudev P., Pavlova M., "Analytical validation of operator actions in case of primary to secondary leakage for VVER-1000/V320, Nuclear Engineering and Design 295 (2015), 479-488.Andreeva, M., Groudev, P. and Pavlova, M. (2015) Analytical Validation of Operator Actions in...
VVER-1000/V320 unitsthermal-hydraulic computer codescritical safety functionscore damageThis paper presents the development and application of methodology used in analytical validation of emergency operating procedures (EOPs) for Kozloduy Nuclear Power Plant (KNPP), VVER-1000/V320 units. EOPs provide ...
Initiation of SAMG for VVER-1000 is considered at two core exit temperatures viz. 650 掳C as a desirable entry temperature and 980 掳C as a backup action. Analyses have been carried out for VVER-1000 (V320) for verification of some of the strategies namely water injection in primary and ...