VVER-440 fresh core depletion benchmark analysis using MCNPX Online publication date: Mon, 05-Jul-2021
by S.M. Shauddin
International Journal of Nuclear Energy Science and Technology (IJNEST), Vol. 14, No. 3, 2020
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.
Online publication date: Mon, 05-Jul-2021
If you are not a subscriber and you just want to read the full contents of this article, buy online access here.Complimentary Subscribers, Editors or Members of the Editorial Board of the International Journal of Nuclear Energy Science and Technology (IJNEST):
Login with your Inderscience username and password:
Want to subscribe?
A subscription gives you complete access to all articles in the current issue, as well as to all articles in the previous three years (where applicable). See our Orders page to subscribe.
If you still need assistance, please email firstname.lastname@example.org