Results 131 to 140 of about 21,387 (164)
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Chemical Engineering Science, 2010
In nuclear safety operations, condensing heat transfer area is placed in a large pool of liquid to accommodate passive thermal decay. Such systems are subject to pool boiling and thermal stratification. Velocity and temperature measurements were carried out in a 300 mm i.d. vessel with a central tube as the heat transfer area.
Arijit A. Ganguli +4 more
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In nuclear safety operations, condensing heat transfer area is placed in a large pool of liquid to accommodate passive thermal decay. Such systems are subject to pool boiling and thermal stratification. Velocity and temperature measurements were carried out in a 300 mm i.d. vessel with a central tube as the heat transfer area.
Arijit A. Ganguli +4 more
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Nuclear Technology, 2002
The passive emergency decay heat removal during severe cooling accidents in Pb/Bi-cooled 80- and 250-MW(thermal) accelerator-driven system (ADS) designs was investigated with the computational fluid dynamics code STAR-CD. For the 80-MW(thermal) design, the calculations show that no structural problems occur as long as the accelerator proton beam is ...
Johan Carlsson, Hartmut Wider
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The passive emergency decay heat removal during severe cooling accidents in Pb/Bi-cooled 80- and 250-MW(thermal) accelerator-driven system (ADS) designs was investigated with the computational fluid dynamics code STAR-CD. For the 80-MW(thermal) design, the calculations show that no structural problems occur as long as the accelerator proton beam is ...
Johan Carlsson, Hartmut Wider
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Numerical modeling of FBR safety grade decay heat removal system and its validation
International Journal of Advances in Engineering Sciences and Applied Mathematics, 2018A numerical code has been developed for simulating natural circulation based decay heat removal system of a typical pool type sodium cooled fast reactor. The code consists of one-dimensional numerical models of a sodium–sodium shell and tube heat exchanger (DHX) dipped in a pool of sodium, finned tube type sodium to air heat exchanger (AHX ...
U. Partha Sarathy +3 more
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Markov analysis for time dependent success criteria of passive decay heat removal system
Annals of Nuclear Energy, 2014Abstract Safety systems deployed in nuclear industry are generally required to operate for a particular mission time. Most of such systems employ redundancy to ensure their high availability over the stipulated mission time. However, availability of a system with redundant configuration depends upon success criteria and is application-specific.
Varun Hassija +2 more
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A CFD-based design optimization of air-cooled passive decay heat removal system
Nuclear Engineering and Design, 2018Abstract The concept of the APDHR (Air-cooled Passive Decay Heat Removal) system was suggested to preserve the safety of a nuclear reactor during accidents. Until 3 days after the reactor shutdown caused by non-LOCA accident, water in the Passive Condensate Cooling Tank (PCCT) was used to condense the steam in secondary side.
Do Yun Kim, Hee Cheon No
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INNOVATIVE RADIATION-BASED DECAY HEAT REMOVAL SYSTEM
2012One of the main issues, regarding the development of Generation IV nuclear power plants, is the safety. In order to design nuclear systems characterized by enhanced safety features, an innovative and passive system, aimed at decay heat removal, especially suitable for sodium cooled fast reactors, has been developed. The attention is here mainly focused
DE SANTIS, ANDREA +4 more
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System Analysis for Decay Heat Removal in Lead-Bismuth-Cooled Natural-Circulation Reactors
Nuclear Technology, 2004Decay heat removal analyses for lead-bismuth cooled natural circulation reactors are described in this paper. A combined multi-dimensional plant dynamics code (MSG-COPD) has been developed to conduct the system analysis for the natural circulation reactors.
Takaaki Sakai +2 more
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A passive decay-heat removal system for an ABWR based on air cooling
Nuclear Engineering and Design, 2017Abstract This paper describes the capability of an air cooling system (ACS) operated under natural convection conditions to remove decay heat from the core of an Advanced Boiling Water Reactor (ABWR). The motivation of the present research is the Fukushima Severe Accident (SA).
Hiroyasu Mochizuki, Takahiro Yano
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Nuclear Engineering and Design, 2006
Increased reliance on passive emergency cooling using natural circulation of gas at elevated pressure is one of the major goals for the Gas-cooled Fast Reactor (GFR). Since GFR cores have high power density and low thermal inertia, the decay heat removal (DHR) in depressurization accidents is a key challenge.
Lee, JI Lee, JeongIk +3 more
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Increased reliance on passive emergency cooling using natural circulation of gas at elevated pressure is one of the major goals for the Gas-cooled Fast Reactor (GFR). Since GFR cores have high power density and low thermal inertia, the decay heat removal (DHR) in depressurization accidents is a key challenge.
Lee, JI Lee, JeongIk +3 more
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Application of heat pipes to decay heat removal systems in next generation reactors
Proceeding of Heat Pipe Technology: Volume 1. Fundamentals and Experimental Studies, 2023Ichiro Sugawara, Yoshiro Asahi
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