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

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 impr...

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主要な著者: Pauzi A.M., Cioncolini A., Iacovides H.
その他の著者: 55812611200
フォーマット: Conference Paper
出版事項: American Institute of Physics Inc. 2023
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spelling my.uniten.dspace-223512023-05-29T14:00:24Z Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor Pauzi A.M. Cioncolini A. Iacovides H. 55812611200 12753591400 7004880147 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. � 2015 AIP Publishing LLC. Final 2023-05-29T06:00:24Z 2023-05-29T06:00:24Z 2015 Conference Paper 10.1063/1.4916852 2-s2.0-84997286470 https://www.scopus.com/inward/record.uri?eid=2-s2.0-84997286470&doi=10.1063%2f1.4916852&partnerID=40&md5=c71a4f7231a68134541817965791ee40 https://irepository.uniten.edu.my/handle/123456789/22351 1659 30004 American Institute of Physics Inc. Scopus
institution Universiti Tenaga Nasional
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country Malaysia
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description 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. � 2015 AIP Publishing LLC.
author2 55812611200
author_facet 55812611200
Pauzi A.M.
Cioncolini A.
Iacovides H.
format Conference Paper
author Pauzi A.M.
Cioncolini A.
Iacovides H.
spellingShingle Pauzi A.M.
Cioncolini A.
Iacovides H.
Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor
author_sort Pauzi A.M.
title Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor
title_short Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor
title_full Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor
title_fullStr Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor
title_full_unstemmed Parametric study of natural circulation flow in Molten Salt fuel in Molten Salt Reactor
title_sort parametric study of natural circulation flow in molten salt fuel in molten salt reactor
publisher American Institute of Physics Inc.
publishDate 2023
_version_ 1806427763520831488
score 13.251813