Molten Salt–Fueled Nuclear Reactor Model for Licensing and Safeguards Investigations

Scott Greenwood
Oak Ridge National Laboratory, Oak Ridge, TN, USA

Ladda ner artikelhttp://dx.doi.org/10.3384/ecp1815427

Ingår i: Proceedings of The American Modelica Conference 2018, October 9-10, Somberg Conference Center, Cambridge MA, USA

Linköping Electronic Conference Proceedings 154:3, s. 27-36

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Publicerad: 2019-02-26

ISBN: 978-91-7685-148-7

ISSN: 1650-3686 (tryckt), 1650-3740 (online)


Fluid-fueled nuclear reactors, particularly molten salt reactors (MSRs), have recently gained significant interest. As with all reactors, modeling and simulation are key factors for advanced reactor design and licensing and will be required for the deployment of MSRs. However, there are significant gaps between simulation capabilities and system behavior for MSRs. This paper presents the system model of an MSR that is based on the Molten Salt Demonstration Reactor. The model includes important physics specific to MSRs, such as fission product and tritium transport and reactivity feedback.


molten salt reactors, salt-fueled, nuclear


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