A computational set of tools developed for fluence calculation as support for BWR's surveillance programme Online publication date: Tue, 17-Jun-2014
by Armando Gómez-Torres; Vicente Xolocostli-Munguía
International Journal of Nuclear Energy Science and Technology (IJNEST), Vol. 8, No. 3, 2014
Abstract: The determination of a neutron source for the RPV fluence calculation is a key factor to detect and prevent degradation of safety-related structures of a NPP. A 3D neutron fluence calculation can be very challenging if all the source details are considered. Several options are possible in order to address the problem, being the most direct the use of 3D transport codes; however, strategies that reduce calculation times are sometimes the preferred. A fast methodology has been developed in order to simplify the calculations without losing accuracy. The methodology relies on the use of DORT together with the synthesis method for having a 3D neutron flux distribution. A set of auxiliary modules for the calculations of the fixed source distribution has been developed. Comparisons of the calculated neutron fluxes against the measurements from the surveillance capsules of the NPP Laguna Verde show maximum relative differences up to 6.81% by far within the 20% difference required by regulation.
Online publication date: Tue, 17-Jun-2014
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