Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor

TY - GEN

T1 - Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor

AU - Pauzi, Anas Muhamad

AU - Cioncolini, Andrea

AU - Iacovides, Hector

N1 - Publisher Copyright: © 2015 AIP Publishing LLC.

PY - 2015/4/29

Y1 - 2015/4/29

N2 - 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.

AB - 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.

KW - Computational fluid dynamics (CFD)

KW - Molten Salt Reactor (MSR)

KW - Molten fuel salt

UR - http://www.scopus.com/inward/record.url?scp=84997286470&partnerID=8YFLogxK

U2 - 10.1063/1.4916852

DO - 10.1063/1.4916852

M3 - 会议稿件

AN - SCOPUS:84997286470

T3 - AIP Conference Proceedings

BT - Advancing of Nuclear Science and Energy for National Development

A2 - Hamzah, Khaidzir

A2 - Idris, Faridah Mohamad

A2 - Hasan, Abu Bakar

A2 - Mohamed, Abdul Aziz

PB - American Institute of Physics Inc.

T2 - Nuclear Science, Technology, and Engineering Conference 2014: Advancing of Nuclear Science and Energy for National Development, NuSTEC 2014

Y2 - 11 November 2014 through 13 November 2014

ER -