Authors: S.M. Shauddin
Addresses: Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, Dhaka 1349, Bangladesh
Abstract: The paper presents outcomes obtained by reproducing a VVER-440 lattice physics benchmark using the MCNPX code. A whole study is performed using different radial and axial regions within the whole core. Neutronics and thermal-hydraulics core design basis limits for the first-cycle are studied herein. The infinite multiplication factor behaviour of a fuel assembly with/without the presence of soluble boron in the moderator/coolant at different Full Power Days (FPD) is studied. Assembly wise normalised Radial Power Distribution (RPD) at different FPD is performed and compared with the measured data. Core Critical Boron Concentration (CBC) and average Axial Power Distribution (APD) for different FPD are calculated and discussed. In the CBC calculation, the results were found to stay closer to the measured value up to 51.3 FPD. In the RPD and APD calculation, the results were found to lie within the 10% deviation from the measured and benchmark average values respectively.
Keywords: axial power distribution; critical boron concentration; critical heat flux; depletion calculation; DNBR; hot assembly; MCNPX; radial power distribution; VVER-440; W-3 correlation.
International Journal of Nuclear Energy Science and Technology, 2020 Vol.14 No.3, pp.206 - 222
Received: 05 Jul 2020
Accepted: 11 Dec 2020
Published online: 05 Jul 2021 *