Neutronics of a liquid salt cooled - Very high temperature reactor
2007 (English)In: 13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007, 2007, 423-430 p.Conference paper (Refereed)
In the present studies, we have utilized the Monte Carlo MCNP code to investigate the neutronic and the safety parameters of the Liquid Salt cooled - Very High Temperature Reactor (LS-VHTR). More precisely, we focused on he void, fuel and moderator temperature reactivity coefficients for two fuel types, enriched uranium and spent LWR fuel, and five different molten salts, NaF, BeF2, LiF, ZrF4, Li2Be4F. The results show that the total void worth coefficient can be set negative provided that the fuel to moderator ratio is optimized and the moderating ratio of the coolant is sufficiently large; whereas the fuel and moderator temperature reactivity coefficients are negative at any fuel to moderator ratio.
Place, publisher, year, edition, pages
2007. 423-430 p.
Fuels, Fused salts, High temperature gas reactors, Liquids, Moderators, Nuclear energy, Uranium
IdentifiersURN: urn:nbn:se:kth:diva-154976ScopusID: 2-s2.0-79959500769ISBN: 978-161782476-0OAI: oai:DiVA.org:kth-154976DiVA: diva2:760276
13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007, 3 June 2007 through 8 June 2007, Istanbul, Turkey
QC 201411032014-11-032014-10-292014-11-03Bibliographically approved