GROUDEV, "RELAP5/MOD3.2 blackout investigation for validation of EOPs for KNPP VVER-1000/V320", Progress in Nuclear Energy 49 (2007) 409-427Andreeva M., M. Pavlova, P. Groudev (2007) RELAP5/MOD3.2 blackout in- vestigation for validation of EOPs for KNPP VVER-1000/V320, Progress in...
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...
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...
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...
RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel 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 ... YA Hassan,C Fu - 《Nuclear Technology》 被引...
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...
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 ...
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...