Abstract
The PWR benchmark problem was intended to draw some conclusions about the accuracy of the different neutronic calculation codes used in the routine deterministic reactor calculation. The objective of this paper is to test the MCNP code against previously obtained solutions to provide new reference solutions to the IAEA benchmark with Monte Carlo method. The effective multiplication factor, radial and axial assembly power distributions and zone average group flux were calculated using Monte Carlo code (MCNP). The MCNP results are compared with the results of deterministic solutions in two and three dimensions. Good estimates of effective multiplication factor values and power distributionvalues in two and three dimensions were showed. To assess the MCNP results, the collective percent error measures were investigated. The results of AVG, MRE and RMS error measures were less than 1 % error. So all results presented here are considered an accurate reference solution and can using as Monte Carlo reference for IAEA PWR benchmark problem.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
