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Title: Temperature modeling for analysis and design of the sintering furnance in HTR fuel type of ball

One of the factors that determine the safety of the operation of the sintering furnace fuel HTR ball is the temperature distribution in the ceramic tube furnace. The temperature distribution must be determined at design stage. The tube has a temperature of 1600 °C at one end and about 40 °C at the other end. The outside of the tube was cooled by air through natural convection. The tube is a furnace ceramic tube which its geometry are 0.08, 0.09 and 0.5 m correspondingly for the inner tube diameter, outer tube diameter and tube length. The temperature distribution of the tube is determined by the natural convection coefficient (NCF), which is difficult to be calculated manually. The determination of NCF includes the Grasshoff, Prandtl, and Nusselt numbers which is a function of the temperature difference between the surrounding air with the ceramic tube. If the temperature vary along the tube, the complexity of the calculations increases. Thus the proposed modeling was performed to determine the temperature distribution along the tube and heat transfer coefficient using a self-developed software which permit the design process easier.
Authors:
 [1] ;  [2]
  1. Computational Division, Centre for Nuclear Informatic Development, National Nuclear Energy Agency, Serpong 15310 (Indonesia)
  2. PTAPB - National Nuclear Energy Agency, Yogyakarta 1008 (Indonesia)
Publication Date:
OSTI Identifier:
22218068
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1554; Journal Issue: 1; Conference: PIPS-2013: Padjadjaran international physics symposium 2013: Contribution of physics on environmental and energy conservations, Padjadjaran (Indonesia), 7-9 May 2013; Other Information: (c) 2013 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CERAMICS; COMPUTER CODES; DESIGN; FURNACES; GAS COOLED REACTORS; HTR REACTOR; NATURAL CONVECTION; NUCLEAR FUELS; REACTOR OPERATION; REACTOR SAFETY; SINTERING; TEMPERATURE DISTRIBUTION