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Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutions

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Authors
Hursin, Mathieu; Downar, Thomas J.; Yoon, Joo Il; Joo, Han Gyu
Issue Date
2016
Publisher
Elsevier
Citation
Annals of Nuclear Energy, vol.87, pp. 356-365
Keywords
Neutron transportTransientReactivity initiated accident
Abstract
The impact of the approximations in the two-steps procedure used in the current generation of nodal simulators for core transient calculations is assessed by using a higher order solution obtained from a direct, whole core, transient transport calculation. A control rod ejection accident in an idealized minicore is analyzed with PARCS, which uses the two-steps procedure and DeCART which provides the higher order solution. DeCART is used as lattice code to provide the homogenized cross sections and kinetics parameters to PARCS. The approximations made by using (1) the homogenized few-group cross sections and kinetic parameters generated at the assembly level, (2) an effective delayed neutrons fraction, (3) an effective fuel temperature and (4) the few-group formulation are investigated in terms of global and local core power behavior. The results presented in the paper show that the current two-steps procedure produces sufficiently accurate transient results with respect to the direct whole core calculation solution, provided that its parameters are carefully generated using the prescriptions described in the present article.
Language
English
URI
https://hdl.handle.net/10371/95475
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College of Engineering/Engineering Practice School (공과대학/대학원)Dept. of Energy Systems Engineering (에너지시스템공학부)Journal Papers (저널논문_에너지시스템공학부)
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