TY - GEN
T1 - Validation of trace using the void fraction tests of the nupec BFBT faciltity
AU - Thieme, Marc
AU - Tietsch, Wolfgang
AU - Macian, Rafael
AU - Espinoza, Victor Hugo Sanchez
PY - 2009
Y1 - 2009
N2 - The present work contributes to the validation of the heat transfer models of the CHAN component in TRACE. For this purpose, 392 performed void fraction steady state tests and one transient test of the BFBT (BWR Full-Size Fine-Mesh Bundle Tests) facility were analysed with TRACE Version 5 RC 2. Therefore, a TRACE model of the BFBT test section was developed for the post-test calculation of the referenced void fraction experiments. TRACE predicts quite well the steady state void fraction results of the BFBT tests at the bundle outlet. However, it tends to underpredict the measured data at the middle bundle elevations. In addition, therefore an uncertainty analysis according to the Benchmark recommendations was performed in which the influence of inlet sub-cooling, outlet quality, mass flow and outlet pressure regarding to the void fraction prediction at the bundle outlet was investigated. This analysis shows a small sensitivity for the inlet sub-cooling but a big sensitivity of the outlet quality of the steam-water mixture. In this paper, a comparison of predicted results with measured data will be presented and discussed in detail.
AB - The present work contributes to the validation of the heat transfer models of the CHAN component in TRACE. For this purpose, 392 performed void fraction steady state tests and one transient test of the BFBT (BWR Full-Size Fine-Mesh Bundle Tests) facility were analysed with TRACE Version 5 RC 2. Therefore, a TRACE model of the BFBT test section was developed for the post-test calculation of the referenced void fraction experiments. TRACE predicts quite well the steady state void fraction results of the BFBT tests at the bundle outlet. However, it tends to underpredict the measured data at the middle bundle elevations. In addition, therefore an uncertainty analysis according to the Benchmark recommendations was performed in which the influence of inlet sub-cooling, outlet quality, mass flow and outlet pressure regarding to the void fraction prediction at the bundle outlet was investigated. This analysis shows a small sensitivity for the inlet sub-cooling but a big sensitivity of the outlet quality of the steam-water mixture. In this paper, a comparison of predicted results with measured data will be presented and discussed in detail.
UR - http://www.scopus.com/inward/record.url?scp=84908003842&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:84908003842
T3 - International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
SP - 1692
EP - 1705
BT - International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
PB - Atomic Energy Society of Japan
T2 - International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
Y2 - 10 May 2009 through 14 May 2009
ER -