scholarly journals Onshore Nuclear Power Plant Concept with Enhanced Passive Safety System

2019 ◽  
Vol 4 (6) ◽  
pp. 155-159
Author(s):  
A.H.M. Iftekharul Ferdous ◽  
T. H. M Sumon Rashid ◽  
Md Asaduzzaman Shobug ◽  
Tanveer Ahmed ◽  
Nitol Kumar Dutta
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Water Source ◽  
Passive Safety ◽  
Electric Power Supply ◽  
Passive Safety Systems ◽  
Passive Safety System ◽  
Safety Systems

Bangladesh is a developing country and it’s increasing economy can be maintained by providing sufficient amount of electric power supply. Therefore government is initiating Rooppur nuclear power project is one of them which is needed to be sited beside a vast amount of water source, lowest populated area and away from the locality to reduce the damage caused by any nuclear accidents. In this thesis paper we have shown that, the the dangers of residing errors of Rooppur nuclear power plant and give a proposal to go for onshore nuclear power plant in Bangladesh with two proposed designs of passive safety systems PSS-I & PSS-II. These systems will give safety to the power plants in the case of plant blackout during accidents.

The NuScale Advanced Passive Safety Design

2011 ◽  
Author(s):  
Jose´ N. Reyes ◽  
Eric Young
Keyword(s):  
Heat Transfer ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Radiation Heat Transfer ◽  
Normal Operation ◽  
Passive Safety ◽  
Decay Heat ◽  
Passive Safety Systems ◽  
Safety Systems

NuScale Power is designing an advanced passive nuclear power plant that does not rely on any external sources of power or coolant for safety. Accordingly, the NuScale design inherently prevents the types of issues which led to fuel damage at the Fukushima Daiichi facility. This paper presents an overview of the advanced passive safety systems implemented in the NuScale nuclear power plant. During normal operation, each NuScale containment is fully immersed in a water-filled stainless steel lined concrete pool that resides underground. The pool, housed in a Seismic Category I building, is large enough to provide 30 days of core and containment cooling without adding additional water. After 30 days, the decay heat generation is sufficiently small that natural convection heat transfer to air on the outside surface of the containment coupled with thermal radiation heat transfer is completely adequate to remove core decay heat for an indefinite period of time. These passive safety systems can perform their function without requiring an external supply of water, power, or generators.

scholarly journals Experiment for Justification the Reliability of Passive Safety System in NPP

2018 ◽  
Vol 3 (3) ◽  
pp. 1
Author(s):  
D.S. Samokhin ◽  
Mohammad Alslman ◽  
A. D. Vostrilova ◽  
O.Yu. Kochnov
Keyword(s):  
Power Systems ◽  
Nuclear Power ◽  
Critical Issue ◽  
Nuclear Industry ◽  
Passive Safety ◽  
Mathematical Methods ◽  
Mean Time Between Failures ◽  
Passive Safety Systems ◽  
Passive Safety System ◽  
Safety Systems

This article gives an overview of the formation of the global nuclear industry, highlighted a critical issue of ensuring safe operation of nuclear power systems in modern projects. Considering the use of passive safety systems in the design of a nuclear power plant, and discussed the different mathematical methods for assessing the reliability of passive systems. Also it considers the possibility of finding the mean time between failures, using these methods to assess the reliability of passive safety systems.

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.

AP1000™ Breaking the Dependence on Site Characteristics: Electrical Grid and Cooling Water

2009 ◽  
Author(s):  
Richard G. Anderson ◽  
Terry L. Schulz ◽  
Daniel T. McLaughlin
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Cooling Water ◽  
Passive Safety ◽  
Small Contribution ◽  
Passive Safety Systems ◽  
Design Basis ◽  
Site Characteristics ◽  
Diesel Generators ◽  
Safety Systems

The AP1000™ has been developed to use passive safety systems to address design basis and beyond design basis accidents to minimize impact on calculated plant Core Damage Frequency (CDF) and Large Release Frequency (LRF). Passive safety cases are supplemented with accident mitigation strategy using highly reliable non-safety grade systems. AP1000™ non-safety systems that resemble the safety systems of conventional plants are designed to mitigate accidents, when available. In addition, a number of mitigation schemes make use of non-safety systems together with select passive system features. This design approach has resulted in a small dependence on site characteristics and has minimized their contribution to CDF and LRF. Conventional nuclear power plants are designed to use motor driven safety grade equipment to address design basis accidents. Safety grade diesel generators are used to provide power to safety grade equipment in the event of a loss of offsite power. The contribution to CDF and LRF from Loss of Offsite Power (LOSP) or loss of cooling water events is significantly lower for the AP1000™ than that for conventional plants. The AP1000™ uses passive safety systems in conjunction with non-safety systems to reduce plant CDF and LRF sensitivity to site specific characteristics. Non-safety systems used for accident mitigation make use of high grade commercial components and are provided power from non-safety grade diesel generators upon LOSP. These components are well maintained to increase system reliability and to increase availability for accident mitigation. The effect of the non-safety systems is further enhanced by partial use of features of the passive safety systems for accident mitigation. In this way, events with initiating event frequencies often driven by site characteristics are mitigated with small contribution to CDF or LRF, often without the need to activate any, or some of the passive plant features.

The Analysis of Effectiveness of BWR/6 URG Strategies

2017 ◽  
Vol 865 ◽  
pp. 701-706
Author(s):  
Ting Yi Wang ◽  
Yu Ting Hsu ◽  
Shao Wen Chen ◽  
Jong Rong Wang ◽  
Chun Kuan Shih ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Water Injection ◽  
Water Source ◽  
Injection Rate ◽  
Power Company ◽  
Pressure Water ◽  
Station Blackout

After the Fukushima Daichii accidents, Taiwan Power Company developed a strategy to cope with such extended SBO (Station Blackout) cases at nuclear power plants, which called URG. The MAAP and PCTRAN were used to perform the study for Kuosheng BWR/6 nuclear power plant (NPP) ultimate response guideline (URG). The main actions of URG are the depressurization and low pressure water injection of the reactor and the venting of the containment. This study focuses to confirm the URG efficiency. The analysis results depict that following the URG, the fuel can be covered by the coolant, no exposure. It can also prevent the radiation release and the large evacuation. It indicated that Kuosheng NPP was at the safe situation. It shows that the two-step depressurizations can extend the time of the preparation of alternate water source. The minimum injection rate to prevent the fuel to expose is 192 gpm in MAAP.

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