TY - GEN
T1 - Three-dimensional modellings for the VENUS-2 mox core
AU - Na, Byung Chan
AU - Messaoudi, Nadia
AU - Roh, Gyu Hong
N1 - Publisher Copyright:
© PHYSOR 2002.All right reserved.
PY - 2002
Y1 - 2002
N2 - Based on the VENUS-2 experimental results released by SCK•CEN, Mol, Belgium, the OECD/NEA launched a two-dimensional VENUS-2 MOX core benchmark in 1999. This was the first experiment-based benchmark and was completed in 2000. Overall, the results were very encouraging and confirmed that present methods using the latest nuclear data sets can adequately calculate MOX-fuelled systems. However, the calculation overestimated fission rates of MOX pins and slightly underestimated those of UO2 pins. This was reflected in all combinations of computer codes and data. Therefore, a three-dimensional VENUS-2 MOX core benchmark was launched in 2001 for a more thorough investigation into the calculation methods used for MOX-fuelled systems. This paper presents the summary of results obtained from the Monte Carlo code MCNP-4B and the deterministic code TORT calculations. Three different nuclear data sets, namely ENDF/B-VI, JENDL-3.2 and JEF-2.2 are mainly investigated. The calculated multiplication factors keff and axial pin power distributions using combinations of different data and methods are compared with the experimental results. The results obtained with different numbers of particle histories and different libraries used in MCNP-4B calculations are analysed and a comparison between the MCNP-4B and the deterministic TORT calculations is also presented. The results show that all combinations of calculation methods and nuclear data can adequately calculate the VENUS-2 MOX core in 3-D geometry, producing reasonably accurate axial pin power distributions.
AB - Based on the VENUS-2 experimental results released by SCK•CEN, Mol, Belgium, the OECD/NEA launched a two-dimensional VENUS-2 MOX core benchmark in 1999. This was the first experiment-based benchmark and was completed in 2000. Overall, the results were very encouraging and confirmed that present methods using the latest nuclear data sets can adequately calculate MOX-fuelled systems. However, the calculation overestimated fission rates of MOX pins and slightly underestimated those of UO2 pins. This was reflected in all combinations of computer codes and data. Therefore, a three-dimensional VENUS-2 MOX core benchmark was launched in 2001 for a more thorough investigation into the calculation methods used for MOX-fuelled systems. This paper presents the summary of results obtained from the Monte Carlo code MCNP-4B and the deterministic code TORT calculations. Three different nuclear data sets, namely ENDF/B-VI, JENDL-3.2 and JEF-2.2 are mainly investigated. The calculated multiplication factors keff and axial pin power distributions using combinations of different data and methods are compared with the experimental results. The results obtained with different numbers of particle histories and different libraries used in MCNP-4B calculations are analysed and a comparison between the MCNP-4B and the deterministic TORT calculations is also presented. The results show that all combinations of calculation methods and nuclear data can adequately calculate the VENUS-2 MOX core in 3-D geometry, producing reasonably accurate axial pin power distributions.
UR - http://www.scopus.com/inward/record.url?scp=84899830888&partnerID=8YFLogxK
M3 - In-proceedings paper
AN - SCOPUS:84899830888
T3 - Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting
BT - Proceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology
PB - American Nuclear Society
T2 - 2002 International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002
Y2 - 7 October 2002 through 10 October 2002
ER -