Verification of a Triga Mark III MCNP model for neutron flux calculations Online publication date: Sun, 03-Jul-2016
by Arturo Delfín Loya; Samuel Vargas-Escamilla; Armando Miguel Gómez-Torres; Edmundo Del Valle Gallegos
International Journal of Nuclear Energy Science and Technology (IJNEST), Vol. 10, No. 2, 2016
Abstract: One of the concerns of any fuel configuration change in a research reactor is the ability to produce the same neutron flux. For assessing the impact of fuel changes in the Triga Mark III Mexican research reactor, a detailed model was developed with MCNP-5. The verification was done comparing the fluxes obtained with the ones of the manufacturer. Relative errors in the order of 1% were found in the irradiation core facilities. Using the same model but with the 17th core configuration, the neutron flux was calculated. Neutron flux differences between the initial and the 17th configuration are presented and discussed. Total flux calculated at the irradiation facilities was fitted into correlations providing a valuable way to predict neutron flux as function of height. The developed model can be used to evaluate further changes like the one done in 2012 in which the HEU fuel was replaced with LEU.
Existing subscribers:
Go to Inderscience Online Journals to access the Full Text of this article.
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 subs@inderscience.com
Our Blog 
Follow us on Twitter 
Visit us on Facebook