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Title: Sensitivity and uncertainty analyses for thermo-hydraulic calculation of research reactor

The sensitivity and uncertainty analysis of input parameters on thermohydraulic calculations for a research reactor has successfully done in this research. The uncertainty analysis was carried out on input parameters for thermohydraulic calculation of sub-channel analysis using Code COOLOD-N. The input parameters include radial peaking factor, the increase bulk coolant temperature, heat flux factor and the increase temperature cladding and fuel meat at research reactor utilizing plate fuel element. The input uncertainty of 1% - 4% were used in nominal power calculation. The bubble detachment parameters were computed for S ratio (the safety margin against the onset of flow instability ratio) which were used to determine safety level in line with the design of 'Reactor Serba Guna-G. A. Siwabessy' (RSG-GA Siwabessy). It was concluded from the calculation results that using the uncertainty input more than 3% was beyond the safety margin of reactor operation.
Authors:
;  [1] ;  [2]
  1. Center for Development of Nuclear Informatics - National Nuclear Energy Agency PUSPIPTEK, Serpong, Tangerang, Banten (Indonesia)
  2. Center for Reactor Technology and Nuclear Safety- National Nuclear Energy Agency PUSPIPTEK, Serpong, Tangerang, Banten (Indonesia)
Publication Date:
OSTI Identifier:
22218071
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; CLADDING; COOLANTS; DESIGN; FISSION; FUEL PLATES; HEAT FLUX; NUCLEAR FUELS; REACTOR COOLING SYSTEMS; REACTOR OPERATION; REACTOR SAFETY; RESEARCH REACTORS; SAFETY MARGINS; SENSITIVITY