model for VVER-1000/V320 NPP are included: reactor vessel; core region represented by three channels; pressurizer system includ- ing heaters, spray and relief valves; safety system–low pressure injection pumps. In the model also is presented a make up/drain ...
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 RELAP5...
俄罗斯VVER-1000/V428堆型是在总结VVER-1000/V320型机组的设计、建造和运行经验基础上,集精确自动控制,非能动安全先进技术和西方第三代反应堆控制系统为一体的改进型堆型。田湾核电站3、4 号机组为VVER-1000/V428堆型,采用“自主调试”的模式,即由田湾核电站营运单位—江苏核电有限公司全面负责3、4 号机组的调试...
It is used primarily for the simulation of PWR and BWR types of reactors as there exists an internal database, suitable for modeling of their core inventory. Despite similarity between VVER-1000/V320 and PWR, accounting of specificities of Russian reactor designs is still required. Part of it ...
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...
An analysis has been carried out for VVER-1000 (V320) reactor following Large Break LOCA along with Station Blackout (SBO). Computer code ASTEC, jointly developed by IRSN, France, and GRS, Germany) is used for analyzing the transient. This integral code has been designed to be used as...
The reference power plant for this analysis is a VVER-1000/V320 (e.g. Units 5&6 at Kozloduy NPP). A preliminary comparison with MELCOR and RELAP-SCDAP severe accident codes will be discussed. This investigation has been performed in the framework of the SARNET project (under the Euratom ...
Analyses have been carried out for VVER-1000 (V320) reactor following LOCA along with Station Blackout (SBO). Computer code ASTEC, (jointly developed by IRSN, France, and GRS, Germany) is used for analyzing the transient. This integral code has been designed to be used as reference code ...
Analyses have been carried out for WER-1000 (V320) reactor following LOCA along with Station Blackout (SBO). Computer code ASTEC, (jointly developed by IRSN, France, and GRS, Germany) is used for analyzing the transient. This integral code has been designed to be used as reference code ...
Severe accident studies for very low frequency events for WER-1000 (V320) are carried out to estimate in-vessel damage progression under steam-rich and sta... B.,Chatterjee,D.,... - 《Nuclear Engineering & Design》 被引量: 6发表: 2009年 VVER-1000 Coolant Transient Benchmark: Phase 1 (...