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

Anas Muhamad Pauzi, Andrea Cioncolini, Hector Iacovides

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Citation (Scopus)

Abstract

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.

Original languageEnglish
Title of host publicationAdvancing of Nuclear Science and Energy for National Development
Subtitle of host publicationProceedings of the Nuclear Science, Technology, and Engineering Conference 2014, NuSTEC 2014
EditorsKhaidzir Hamzah, Faridah Mohamad Idris, Abu Bakar Hasan, Abdul Aziz Mohamed
PublisherAmerican Institute of Physics Inc.
ISBN (Electronic)9780735413016
DOIs
Publication statusPublished - 29 Apr 2015
EventNuclear Science, Technology, and Engineering Conference 2014: Advancing of Nuclear Science and Energy for National Development, NuSTEC 2014 - Skudai, Johor, Malaysia
Duration: 11 Nov 201413 Nov 2014

Publication series

NameAIP Conference Proceedings
Volume1659
ISSN (Print)0094-243X
ISSN (Electronic)1551-7616

Other

OtherNuclear Science, Technology, and Engineering Conference 2014: Advancing of Nuclear Science and Energy for National Development, NuSTEC 2014
CountryMalaysia
CitySkudai, Johor
Period11/11/1413/11/14

Fingerprint

molten salts
reactors
tubes
fluid dynamics
salts
computer programs
reactor design
reactor cores
nuclear reactors
coolants
hydraulics
temperature profiles
fission
velocity distribution
physical properties
turbulence
cooling
heat
liquids
simulation

All Science Journal Classification (ASJC) codes

  • Ecology, Evolution, Behavior and Systematics
  • Ecology
  • Plant Science
  • Physics and Astronomy(all)
  • Nature and Landscape Conservation

Cite this

Muhamad Pauzi, A., Cioncolini, A., & Iacovides, H. (2015). Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor. In K. Hamzah, F. M. Idris, A. B. Hasan, & A. A. Mohamed (Eds.), Advancing of Nuclear Science and Energy for National Development: Proceedings of the Nuclear Science, Technology, and Engineering Conference 2014, NuSTEC 2014 [030004] (AIP Conference Proceedings; Vol. 1659). American Institute of Physics Inc.. https://doi.org/10.1063/1.4916852
Muhamad Pauzi, Anas ; Cioncolini, Andrea ; Iacovides, Hector. / Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor. Advancing of Nuclear Science and Energy for National Development: Proceedings of the Nuclear Science, Technology, and Engineering Conference 2014, NuSTEC 2014. editor / Khaidzir Hamzah ; Faridah Mohamad Idris ; Abu Bakar Hasan ; Abdul Aziz Mohamed. American Institute of Physics Inc., 2015. (AIP Conference Proceedings).
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title = "Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor",
abstract = "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.",
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Muhamad Pauzi, A, Cioncolini, A & Iacovides, H 2015, Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor. in K Hamzah, FM Idris, AB Hasan & AA Mohamed (eds), Advancing of Nuclear Science and Energy for National Development: Proceedings of the Nuclear Science, Technology, and Engineering Conference 2014, NuSTEC 2014., 030004, AIP Conference Proceedings, vol. 1659, American Institute of Physics Inc., Nuclear Science, Technology, and Engineering Conference 2014: Advancing of Nuclear Science and Energy for National Development, NuSTEC 2014, Skudai, Johor, Malaysia, 11/11/14. https://doi.org/10.1063/1.4916852

Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor. / Muhamad Pauzi, Anas; Cioncolini, Andrea; Iacovides, Hector.

Advancing of Nuclear Science and Energy for National Development: Proceedings of the Nuclear Science, Technology, and Engineering Conference 2014, NuSTEC 2014. ed. / Khaidzir Hamzah; Faridah Mohamad Idris; Abu Bakar Hasan; Abdul Aziz Mohamed. American Institute of Physics Inc., 2015. 030004 (AIP Conference Proceedings; Vol. 1659).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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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.

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BT - Advancing of Nuclear Science and Energy for National Development

A2 - Hamzah, Khaidzir

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Muhamad Pauzi A, Cioncolini A, Iacovides H. Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor. In Hamzah K, Idris FM, Hasan AB, Mohamed AA, editors, Advancing of Nuclear Science and Energy for National Development: Proceedings of the Nuclear Science, Technology, and Engineering Conference 2014, NuSTEC 2014. American Institute of Physics Inc. 2015. 030004. (AIP Conference Proceedings). https://doi.org/10.1063/1.4916852