NUMERICAL AND EXPERIMENTAL INVESTIGATION OF PASSIVE HEAT REMOVAL FROM POROUS BED IN PATH FACILITY

2018 ◽  
Author(s):  
Anil Kumar Sharma ◽  
Venkateswarlu S ◽  
E Hemanth Rao ◽  
B Malarvizhi ◽  
S S Murthy ◽  
...  
2016 ◽  
Vol 14 (4) ◽  
pp. 442-448 ◽  
Author(s):  
C. S. Malvi ◽  
Arpit Gupta ◽  
M. K. Gaur ◽  
R. Crook ◽  
D. W. Dixon-Hardy

Author(s):  
Aranyak Chakravarty ◽  
Nirmalendu Biswas ◽  
Koushik Ghosh ◽  
Nirmal K. Manna ◽  
Achintya Mukhopadhyay ◽  
...  

Author(s):  
Sumit V. Prasad ◽  
A. K. Nayak

After the Fukushima accident, the public has expressed concern regarding the safety of nuclear power plants. This accident has strengthened the necessity for further improvement of safety in the design of existing and future nuclear power plants. Pressurized heavy water reactors (PHWRs) have a high level of defense-in-depth (DiD) philosophy to achieve the safety goal. It is necessary for designers to demonstrate the capability of decay heat removal and integrity of containment in a PHWR reactor for prolonged station blackout to avoid any release of radioactivity in public domain. As the design of PHWRs is distinct, its calandria vessel (CV) and vault cooling water offer passive heat sinks for such accident scenarios and submerged calandria vessel offers inherent in-calandria retention (ICR) features. Study shows that, in case of severe accident in PHWR, ICR is the only option to contain the corium inside the calandria vessel by cooling it from outside using the calandria vault water to avoid the release of radioactivity to public domain. There are critical issues on ICR of corium that have to be resolved for successful demonstration of ICR strategy and regulatory acceptance. This paper tries to investigate some of the critical issues of ICR of corium. The present study focuses on experimental investigation of the coolability of molten corium with and without simulated decay heat and thermal behavior of calandria vessel performed in scaled facilities of an Indian PHWR.


Author(s):  
Avadhesh K. Sharma ◽  
Mayank Modak ◽  
Santosh K. Sahu

Impinging jet surface cooling is being used in many industrial and engineering applications due to their higher heat removal rate. Jet impingement is one of the methods to cool hot surfaces, especially in textile, metal and electronic industries. Due to high heat removal rate the jet impingement cooling of the hot surfaces is being used in nuclear industries. During the loss of coolant accidents (LOCA) in nuclear power plant, an emergency core cooling system (ECCS) cool the cluster of clad tubes using consisting of fuel rods. The usual water flow within a reactor core is bottom to top, parallel to the fuel rods. When a hot surface quenched at very high temperature using a jet of cold fluid, during the quenching the initial heat transfer is limited by film boiling. The effective cooling takes place only after the surface temperature is below the leidenfrost temperature. In the present work an experimental investigation has been carried out to analyze the rewetting phenomenon of a hot vertical stainless steel foil by circular impinging jets of pure water and Al2O3–water nanofluids. The rewetting time and rewetting velocity in the form of dimensionless number (Peclet number) obtained from the thermal images obtained from infrared thermal imaging camera (A655sc, FLIR System). Experiments are performed for different Reynolds number (Re = 5000, 8000), and Al2O3–water nanofluids concentration (Φ = 0.15%, 0.6%)


2017 ◽  
Vol 7 (1) ◽  
Author(s):  
Wanghua Sui ◽  
Yankun Liang ◽  
Xinjia Zhang ◽  
Ravi Jain ◽  
Tao Zhu

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