National Journal, Tri Dasa Mega Vol. 3 October, 2010
HEAT FLUX CALCULATION FOR BOILING CURVE DURING QUENCHING EXPERIMENT USING HEATED HOLLOW CYLINDER
Mulya Juarsa1,2, Raldi Artono Koestor1, Nandy Setiadi Djaya Putra1 Anhar Riza Antariksawan2, Cukup Mulyana3, Riska Khalisa3
1Departemen Teknik Mesin, Fakultas Teknik, University of Indonesia, Depok 16424
Tel : (021) 7270011 ext 51. Fax : (021) 7270077 E-mail : email@example.com
2Badan Tenaga Nuklir Nasional (BATAN), PUSPIPTEK Serpong, Tangerang Selatan 15310, Tel : (021) 7560912 Fax : (021) 7560913 E-mail : firstname.lastname@example.org
3KBK Fisika Energi, Jurusan Fisika FMIPA, Universitas Padjadjaran Jl. Raya Bandung – Sumedang Km.21 Sumedang 45363 Tel: (022) 7796014 Fax: (022) 7792435
HEAT FLUX CALCULATION FOR BOILING CURVE DURING QUENCHING EXPERIMENT USING HEATED HOLLOW CYLINDER. One of the safety management aspects in the operation of nuclear reactors are thermal management. The basic concept of thermal management is to control the excess heat during an accident. The understanding and investigation of boiling phenomena become important research stage. Experimental study of boiling heat transfer was conducted by cooling the hollow cylinder into the water with saturation temperature. Quenching process is an important part during the occurrence of sudden cooling on heated object. A Hollow cylindrical geometry is a simulation of debris on the vertical form was used as a heated object. Cooling method is naturally hollow cylinder quenching with various initial temperatures between 300oC until 800oC into saturation temperature of water. The results as transient data was used to calculate heat flux. Film boiling regime was beginning on the temperature of the hollow cylinder reaches 300oC. The phenomenon of pool boiling was mapped in boiling curve. Whereas a pictures of the results captured by high speed camera (HSC).
Keywords: quenching, cylinder, boiling, heat flux
International Conference on Cooling and Heating Technologies (ICCHT 2010)
Boiling Mapping for Cooling Process in Annulus Narrow Gap Based on Initial Temperature Variation As a Simulation of Debris Cooling
Mulya Juarsa1,2, Raldi A. Koestoer1, Nandy Putra1, Anhar R. Antariksawan2, Indarto3, Bambang Riyono4
1Mechanical Engineering Department, Faculty of Engineering, Indonesia University, Depok, Indonesia, email@example.com
2Thermal-Hydraulics Experimental Laboratory, Center for Reactor Technology and Nuclear Safety, National Nuclear Energy Agency (BATAN),Tangerang, Indonesia, firstname.lastname@example.org
3Mechanical Engineering and Industry Department,Faculty of Engineering Gadjah Mada University, Yogyakarta, Indonesia,4Indonesia-Nuclear Energy Regulatory Agency (BAPETEN), Jakarta, Indonesia
An experimental set-up which used a specific of the length of heated rod including the thermocouples for instantaneous measurement of surface temperature, was designed, constructed and used to study boiling phenomena in annulus narrow gap. Experimental was aimed to make boiling mapping during cooling process which involving heat flux. The experiments were conducted using heated rod with 700 mm length as a debris simulation and quartz glass tube to visualization purposes, the gap size between outer heated rod and inner quartz glass tube is 1.0 mm. Water with temperature of 98oC was poured into heated gap with initial variation of heated rod, respectively 1500C, 2500C, 3500C, 4500C, 5500C, and 6500C. Visualization process was conducted using high speed camera with 1000 fps. Transient temperature data was used to calculate heat flux versus wall superheat. Rewetting velocity is affected by initial temperature changes. The analysis showed the restriction from initial temperature increasing become longer, rewetting velocity in respectively 0.0072 m/s, 0.0042 m/s, 0.0015 m/s, 0.0013 m/s, 0.0010 m/s and 0.0009 m/s. The value of critical heat flux (CHF) from boiling mapping divided into two categories, lower-wall superheat for initial temperature 150oC and 250oC with CHF in respectively around 100 kW/m2 and 200 kW/m2. High-wall superheat for initial temperature 350oC, 450oC, 550oC, and 650oC by the average value of CHF around 400 kW/m2.
Keywords: boiling, CHF, rewetting, narrow gap
First Winner on The Best Paper Award of Atom Indonesia Int. Journal in 2010
EXPERIMENTAL STUDY ON THE EFFECT OF INITIAL TEMPERATURE ON CHF IN A VERTICAL NARROW CHANNEL WITH BILATERAL HEATED
Mulya Juarsa1,2, Raldi A. Koestoer1, Nandy Putra1, Shinta Habsari4,Indarto3
1Departemen of Mechanical Engineering, Faculty of Engineering, Indonesia University,
EXPERIMENTAL STUDY ON THE EFFECT OF INITIAL TEMPERATURE ON CHF IN A VERTICAL NARROW CHANNEL WITH BILATERAL HEATED. Study to reach the understanding of the complexities of boiling in the narrow channel which was occured in a severe accident on nuclear power plant has been carried out experimentally in order to achieve the safety management ability, CHF is one important parameter to control heat during transient accident. The methodology of research is an experiment using HeaTiNG-01 test section with modifications in the outside pipe using stainless steel material as the reactor vessel wall simulation. Experiments were conducted by heating the heated rod as a simulation of debris until the desired initial temperature by bilateral heated. Then water with a saturation temperature in atmospheric was poured gravitationally into the narrow channel. Data acquisition system recorded temperature changes in transient during the cooling process. The transient temperature profile in double heating surface and rewetting point (rewet fronts) was characterized. Experiment was conducted at three initial temperature variations i.e. 650oC, 750oC and 850oC and using channel width 1 mm. Experiment data was used to calculate heat flux then to fitting CHF form boiling curve. The results showed that CHF in outer pipe is higher than heated rod, these conditions explain that more heat is released through the outer pipe, so that the heat control can be done from outside the system to reduce the temperature quickly. In respectively base on initial temperature increase. The average value of CHF for each vertical position 100 mm and 400 mm at outer pipe are 380 kW/m2 and 733 kW/m2, and then at the heated rod are 250 kW/m2 and 497 kW/m2.
Keywords: CHF, temperature, boiling curve, bilateral
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