Assessment of passive safety system performance under gravity driven cooling system drain line break accident

2014 ◽  
Vol 74 ◽  
pp. 136-142 ◽  
Author(s):  
J. Lim ◽  
J. Yang ◽  
S.W. Choi ◽  
D.Y. Lee ◽  
S. Rassame ◽  
...  
Keyword(s):  
System Performance ◽  
Cooling System ◽  
Safety System ◽  
Passive Safety ◽  
Passive Safety System ◽  
Gravity Driven

ESBWR passive safety system performance under loss of coolant accidents

2017 ◽  
Vol 96 ◽  
pp. 1-17 ◽  
Author(s):  
Somboon Rassame ◽  
Takashi Hibiki ◽  
Mamoru Ishii
Keyword(s):  
System Performance ◽  
Safety System ◽  
Passive Safety ◽  
Passive Safety System ◽  
Loss Of Coolant

Assessment of passive safety system performance under main steam line break accident

2014 ◽  
Vol 64 ◽  
pp. 287-294 ◽  
Author(s):  
J. Lim ◽  
S.W. Choi ◽  
J. Yang ◽  
D.Y. Lee ◽  
S. Rassame ◽  
...  
Keyword(s):  
System Performance ◽  
Steam Line ◽  
Safety System ◽  
Passive Safety ◽  
Passive Safety System ◽  
Main Steam Line ◽  
Main Steam

Preliminary Large Break LOCA and SGTR Accident Analysis of the Compact Small Reactor

2017 ◽  
Author(s):  
Mian Xing ◽  
Linsen Li ◽  
Feng Shen ◽  
Xiao Hu ◽  
Zhan Liu ◽  
...  
Keyword(s):  
Cooling System ◽  
Thermal Power ◽  
Reactor Core ◽  
Safety System ◽  
Passive Safety ◽  
Primary System ◽  
The Core ◽  
Passive Safety System ◽  
Safety Margins ◽  
Guideline Values

This paper gives a brief introduction of the Compact Small Reactor (CSR). It is a simplified two-loop reactor with thermal power of 660MW and with compact primary system and passive safety feature. Preliminary safety analysis of the CSR is conducted to evaluate and further optimize the design of passive safety system, especially the passive core cooling system. Large Break Loss Of Coolant Accident (LBLOCA) and Steam Generator Tube Rupture (SGTR) are selected as two reference accidental scenarios. Each scenario is modeled and computed by RELAP5/MOD3.4. For the LBLOCA analysis, a guillotine break happens in the cold leg of the loop containing the core makeup tanks balance lines. The results show certain safety margins from the guideline values, and the passive safety system could supply enough cooling of the core. For the SGTR analysis, the results show the robustness of the design from the safety perspective. It is concluded that the safety systems are capable of mitigating the accidents and protecting the reactor core from severe damage.

The Comparative Advantages of CAP1400 Nuclear Power Plant Passive Safety System

2017 ◽  
Author(s):  
Ye Cheng ◽  
Wang Minglu ◽  
Qiu Zhongming ◽  
Wang Yong
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Cooling System ◽  
Assessment Method ◽  
Safety System ◽  
Passive Safety ◽  
Passive Safety System ◽  
First Choice ◽  
Comparative Advantages

With the demand for nuclear power increasing, the first choice of almost all countries who want to build a new nuclear power plant is to use generation III technology, primarily because the safety of generation III technology is greatly improved compared with that of generation II and II + technology. The passive safety technology was introduced by the AP1000 and is one of the best applications of generation III technologies. In this study, the representative passive containment cooling system of the CAP1400 (developed based on AP1000) and the containment spray system of a generation II nuclear power plant are compared and analyzed using the Probabilistic Safety Assessment method. The reasons why a passive safety system has comparative advantages are determined by concrete calculations.

scholarly journals Testing of Passive Safety System Performance for Higher Power Advanced Reactors

2004 ◽  
Author(s):  
brian G. Woods ◽  
Jr. Jose Reyes ◽  
John Woods ◽  
John Groome ◽  
Richard Wright
Keyword(s):  
System Performance ◽  
Safety System ◽  
Passive Safety ◽  
Passive Safety System ◽  
Higher Power

Survey of Research Activities for Passive Safety System of AC600

1999 ◽  
Author(s):  
Bingde Chen ◽  
Zhumao Yang ◽  
Fuyun Ji
Keyword(s):  
Cooling System ◽  
Program Planning ◽  
Experimental Studies ◽  
Heat Removal ◽  
Safety System ◽  
Injection System ◽  
Passive Safety ◽  
Design Modification ◽  
Research Activities ◽  
Passive Safety System

Abstract The use of passive safety system in AC600, the Chinese advanced 600 MWe PWR proposed by NPIC, together with other improvements, such as simplification and advanced I&C etc., makes the plant more safe, economic and reliable. The core damage frequency (CDF) decreases from less than 10−4 of conventional PWR to less than 10−5 to 10−6 and the plant available factor increases to ∼90%. The passive safety system of AC600 consists of three complete independent systems. They are passive containment cooling system (passive CC system), passive core residual heat removal system (passive CRHR system) and passive safety injection system (CMT). To verify and demonstrate the AC600’s innovative passive safety features and to obtain an experimental database for system design modification and optimizing, and for computer code development and assessment, the experimental studies on these systems were finished in NPIC during the eighth national Five Year period under the national support. In this paper, the experimental research activities on passive containment cooling system, passive CRHR system and CMT injection system, including test rigs and main results are summarized. These experiments proved the design of all these passive systems are feasible and reliable and can meet basically the required safety functions. Some undesired thermal hydraulic phenomena, for example, “water hammer”, which may have bad impacts on its safety functions and to which high attention should be given, was found and identified in these studies. All data obtained have already been used in the design improvement and next R&D program planning.

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