Title of article :
TRAC-BF1/NEM Modeling and results of OECD/NEA BWR core transient benchmarks
Author/Authors :
Fu، نويسنده , , Haoying; Solis-Rodarte، نويسنده , , Jorge; Ivanov، نويسنده , , Kostadin N ، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2000
Pages :
8
From page :
1051
To page :
1058
Abstract :
TRAC-BF1/NEM is a coupled neutronics-thermal hydraulics code for BWR transient and accident analysis developed at the Penn State University. Research has been carried out at Penn State to further verify this coupled code by using the (OECD/NEA) 3-D BWR core transient benchmarks. These benchmarks provide an opportunity to compare TRAC-BF1/ NEM predictions with the results of many other coupled codes as well as to establish a well- de®ned set of test problems for future TRAC-BF1/NEM modi®cations and code distribu- tions. The paper gives a description of the developed neutronics and thermal-hydraulic mod- els and presents a comparison and discussion of the obtained steady-state results as well as the transient results for the inlet sub-cooling transient.
Journal title :
Annals of Nuclear Energy
Serial Year :
2000
Journal title :
Annals of Nuclear Energy
Record number :
405453
Link To Document :
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