Published July 1, 2019 | Version v1
Report

Dynamic System Models for Informing Licensing and Safeguards Investigations of Molten Salt Reactors (Revision 1)

  • 1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Description

Fluid-fueled molten salt nuclear 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 a system model of an MSR based on the Molten Salt Demonstration Reactor. The model includes important physics specific to MSRs, such as fission product and tritium transport, as well as reactivity feedback.

Availability note (English)

Available from https://www.osti.gov/servlets/purl/1566973; https://www.osti.gov/biblio/1566973; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo period

Additional details

Publishing Information

Imprint Pagination
78 p.
Report number
ORNL-TM--2018/876-Rev.1

Optional Information

Contract/Grant/Project number
AC05-00OR22725
Funding organization
USDOE (United States)
Secondary number(s)
OSTIID--1566973