A methodology for CHF prediction in VVER rod bundles

The critical heat flux (CHF) is an important thermal-hydraulic parameter that must be determined during the design of water-cooled reactors to ensure safety operation. In this paper, a methodology proposed predict CHF in VVER rod bundles. A whole-reactor model VVER-1000 implemented RELAP-SCDAPSIM, and, based on bundle-average approach, parameters hot channel are used assess four predictors (i.e., 2006 Groeneveld look-up table (LUT), and Bowring, W-3, Biasi, OKB-Gidropress correlations) upon comparison with 2011 Bobkov LUT. brief critique given correction factors for both LUTs. effects diameter non-uniform axial predicted values subcooled conditions also studied. performance time complexity standard Bourke trilinear interpolation algorithms assessed use LUTs codes. It has been concluded does not affect factor exponent gives better predictability bundles over Tanase Wong correlations. Additionally, LUT found nearly reproduces when conjunction heated length factor. Values MDNBR equal 1.83 1.96 can as thermal limits at 12\% overpower Bowring W-3 correlations, respectively, conditions. exhibit same average CPU time. algorithm, however, less affected by noise. Further research needed smoothness derive reactor type-dependent formulas