Optimization of the neutronics of the advanced high temperature reactor
2006 (English)In: Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06, 2006, 294-301 p.Conference paper (Refereed)
In these studies, we have investigated the neutronic and safety performance of the Advanced High Temperature Reactor (AHTR) for plutonium and uranium fuels and we extended the analysis to five different coolants. The AHTR is a graphite-mode rated and molten salt-cooled high temperature reactor, which takes advantage of the TRISO particles technology for the fuel utilization. The conceptual design of the core, proposed at the Oak Ridge National Laboratory, aims to provide an alternative to helium as coolant of high-temperature reactors for industrial applications like hydrogen production. We evaluated the influence of the radial reflector on the criticality of the core for the uranium and plutonium fuels and we focused on the void coefficient of 5 different molten salts; since the safety of the reactor is enhanced also by the large and negative coefficient of temperature, we completed our investigation by observing the keff changes when the graphite temperature varies from 300 to 1800 K.
Place, publisher, year, edition, pages
2006. 294-301 p.
, Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06, 2006
Accident prevention, Coolants, Graphite, Optimization, Plutonium, Uranium, Molten salts, Neutronics, Plutonium fuels, Radial reflector, Void coefficient, High temperature reactors
Atom and Molecular Physics and Optics
IdentifiersURN: urn:nbn:se:kth:diva-155848ScopusID: 2-s2.0-33845798799ISBN: 0894486985ISBN: 9780894486982OAI: oai:DiVA.org:kth-155848DiVA: diva2:765048
American Nuclear Society Embedded Topical Meeting - 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06, 4 June 2006 through 8 June 2006, Reno, NV
QC 201411212014-11-212014-11-132014-11-21Bibliographically approved