Parametric study of natural circulation flow in molten salt fuel in molten salt reactor
- School of Mechanical, Aerospace, and Civil Engineering (MACE), University of Manchester, Oxford Road, M13 9PL Manchester (United Kingdom)
The Molten Salt Reactor (MSR) is one of the most promising system proposed by Generation IV Forum (GIF) for future nuclear reactor systems. Advantages of the MSR are significantly larger compared to other reactor system, and is mainly achieved from its liquid nature of fuel and coolant. Further improvement to this system, which is a natural circulating molten fuel salt inside its tube in the reactor core is proposed, to achieve advantages of reducing and simplifying the MSR design proposed by GIF. Thermal hydraulic analysis on the proposed system was completed using a commercial computation fluid dynamics (CFD) software called FLUENT by ANSYS Inc. An understanding on theory behind this unique natural circulation flow inside the tube caused by fission heat generated in molten fuel salt and tube cooling was briefly introduced. Currently, no commercial CFD software could perfectly simulate natural circulation flow, hence, modeling this flow problem in FLUENT is introduced and analyzed to obtain best simulation results. Results obtained demonstrate the existence of periodical transient nature of flow problem, hence improvements in tube design is proposed based on the analysis on temperature and velocity profile. Results show that the proposed system could operate at up to 750MW core power, given that turbulence are enhanced throughout flow region, and precise molten fuel salt physical properties could be defined. At the request of the authors and the Proceedings Editor the name of the co-author Andrea Cioncolini was corrected from Andrea Coincolini. The same name correction was made in the Acknowledgement section on page 030004-10 and in reference number 4. The updated article was published on 11 May 2015.
- OSTI ID:
- 22391620
- Journal Information:
- AIP Conference Proceedings, Vol. 1659, Issue 1; Conference: NuSTEC2014: Nuclear Science, Technology, and Engineering Conference 2014, Skudai, Johor (Malaysia), 11-13 Nov 2014; Other Information: (c) 2015 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
GENERAL PHYSICS
A CODES
CALCULATION METHODS
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
COOLANTS
DESIGN
F CODES
FISSION
HEAT
MOLTEN SALT FUELS
MOLTEN SALT REACTORS
NATURAL CONVECTION
PARAMETRIC ANALYSIS
REACTOR CORES
SALTS
THERMAL HYDRAULICS
TRANSIENTS
TUBES
TURBULENCE