RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES

The heat pipe cooled reactor is a solid-state reactor using heat pipes to passively transfer heat generated from the reactor, which is a potential and near-term space nuclear power system. This paper introduces the coupling scheme between the continuous energy Reactor Monte Carlo (RMC) code and the...
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Autor*in:	Ma Yugao [verfasserIn] Liu Minyun [verfasserIn] Chen Erhui [verfasserIn] Xie Biheng [verfasserIn] Chai Xiaoming [verfasserIn] Huang Shanfang [verfasserIn] Wang Kan [verfasserIn] Yu Hongxing [verfasserIn]

Format:	E-Artikel
Sprache:	Englisch

Erschienen:	2021

Schlagwörter:	monte carlo methods finite element method neutronic and thermomechanical (n-t/m) coupling heat pipe reactor

Übergeordnetes Werk:	In: EPJ Web of Conferences - EDP Sciences, 2010, 247, p 06007(2021)
Übergeordnetes Werk:	volume:247, p 06007 ; year:2021

Links:	Link aufrufen Link aufrufen Link aufrufen Journal toc

DOI / URN:	10.1051/epjconf/202124706007

Katalog-ID:	DOAJ061978930

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520			\|a The heat pipe cooled reactor is a solid-state reactor using heat pipes to passively transfer heat generated from the reactor, which is a potential and near-term space nuclear power system. This paper introduces the coupling scheme between the continuous energy Reactor Monte Carlo (RMC) code and the finite element method commercial software ANSYS. Monte Carlo method has the advantages of flexible geometry modeling and continuous-energy nuclear cross sections. ANSYS Parametric Design Language (APDL) is used to determine the detailed temperature distributions and geometric deformation. The on-the-fly temperature treatment of cross sections was adopted in RMC code to solve the memory problems and to speed up simulations. This paper proposed a geometric updating strategy and reactivity feedback methods for the geometric deformation of the solid-state core. The neutronic and thermal-mechanical coupling platform is developed to analyze and further to optimize the heat pipe cooled reactor design. The present coupling codes analyze a 2D central cross-section model for MEGAPOWER heat pipe cooled reactor. The thermal-mechanical feedback reveals that the solid-state reactor has a negative reactivity feedback (~1.5 pcm/K) while it has a deterioration in heat transfer due to the expansion.
650		4	\|a monte carlo methods
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700	0		\|a Chai Xiaoming \|e verfasserin \|4 aut
700	0		\|a Huang Shanfang \|e verfasserin \|4 aut
700	0		\|a Wang Kan \|e verfasserin \|4 aut
700	0		\|a Yu Hongxing \|e verfasserin \|4 aut
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allfields	10.1051/epjconf/202124706007 doi (DE-627)DOAJ061978930 (DE-599)DOAJe8197eee078e4c5fbaacc711c9508336 DE-627 ger DE-627 rakwb eng QC1-999 Ma Yugao verfasserin aut RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The heat pipe cooled reactor is a solid-state reactor using heat pipes to passively transfer heat generated from the reactor, which is a potential and near-term space nuclear power system. This paper introduces the coupling scheme between the continuous energy Reactor Monte Carlo (RMC) code and the finite element method commercial software ANSYS. Monte Carlo method has the advantages of flexible geometry modeling and continuous-energy nuclear cross sections. ANSYS Parametric Design Language (APDL) is used to determine the detailed temperature distributions and geometric deformation. The on-the-fly temperature treatment of cross sections was adopted in RMC code to solve the memory problems and to speed up simulations. This paper proposed a geometric updating strategy and reactivity feedback methods for the geometric deformation of the solid-state core. The neutronic and thermal-mechanical coupling platform is developed to analyze and further to optimize the heat pipe cooled reactor design. The present coupling codes analyze a 2D central cross-section model for MEGAPOWER heat pipe cooled reactor. The thermal-mechanical feedback reveals that the solid-state reactor has a negative reactivity feedback (~1.5 pcm/K) while it has a deterioration in heat transfer due to the expansion. monte carlo methods finite element method neutronic and thermomechanical (n-t/m) coupling heat pipe reactor Physics Liu Minyun verfasserin aut Chen Erhui verfasserin aut Xie Biheng verfasserin aut Chai Xiaoming verfasserin aut Huang Shanfang verfasserin aut Wang Kan verfasserin aut Yu Hongxing verfasserin aut In EPJ Web of Conferences EDP Sciences, 2010 247, p 06007(2021) (DE-627)647306611 (DE-600)2595425-8 2100014X nnns volume:247, p 06007 year:2021 https://doi.org/10.1051/epjconf/202124706007 kostenfrei https://doaj.org/article/e8197eee078e4c5fbaacc711c9508336 kostenfrei https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06007.pdf kostenfrei https://doaj.org/toc/2100-014X Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_206 GBV_ILN_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2005 GBV_ILN_2009 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2055 GBV_ILN_2111 GBV_ILN_4012 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4249 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4700 AR 247, p 06007 2021
spelling	10.1051/epjconf/202124706007 doi (DE-627)DOAJ061978930 (DE-599)DOAJe8197eee078e4c5fbaacc711c9508336 DE-627 ger DE-627 rakwb eng QC1-999 Ma Yugao verfasserin aut RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The heat pipe cooled reactor is a solid-state reactor using heat pipes to passively transfer heat generated from the reactor, which is a potential and near-term space nuclear power system. This paper introduces the coupling scheme between the continuous energy Reactor Monte Carlo (RMC) code and the finite element method commercial software ANSYS. Monte Carlo method has the advantages of flexible geometry modeling and continuous-energy nuclear cross sections. ANSYS Parametric Design Language (APDL) is used to determine the detailed temperature distributions and geometric deformation. The on-the-fly temperature treatment of cross sections was adopted in RMC code to solve the memory problems and to speed up simulations. This paper proposed a geometric updating strategy and reactivity feedback methods for the geometric deformation of the solid-state core. The neutronic and thermal-mechanical coupling platform is developed to analyze and further to optimize the heat pipe cooled reactor design. The present coupling codes analyze a 2D central cross-section model for MEGAPOWER heat pipe cooled reactor. The thermal-mechanical feedback reveals that the solid-state reactor has a negative reactivity feedback (~1.5 pcm/K) while it has a deterioration in heat transfer due to the expansion. monte carlo methods finite element method neutronic and thermomechanical (n-t/m) coupling heat pipe reactor Physics Liu Minyun verfasserin aut Chen Erhui verfasserin aut Xie Biheng verfasserin aut Chai Xiaoming verfasserin aut Huang Shanfang verfasserin aut Wang Kan verfasserin aut Yu Hongxing verfasserin aut In EPJ Web of Conferences EDP Sciences, 2010 247, p 06007(2021) (DE-627)647306611 (DE-600)2595425-8 2100014X nnns volume:247, p 06007 year:2021 https://doi.org/10.1051/epjconf/202124706007 kostenfrei https://doaj.org/article/e8197eee078e4c5fbaacc711c9508336 kostenfrei https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06007.pdf kostenfrei https://doaj.org/toc/2100-014X Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_206 GBV_ILN_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2005 GBV_ILN_2009 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2055 GBV_ILN_2111 GBV_ILN_4012 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4249 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4700 AR 247, p 06007 2021
allfields_unstemmed	10.1051/epjconf/202124706007 doi (DE-627)DOAJ061978930 (DE-599)DOAJe8197eee078e4c5fbaacc711c9508336 DE-627 ger DE-627 rakwb eng QC1-999 Ma Yugao verfasserin aut RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The heat pipe cooled reactor is a solid-state reactor using heat pipes to passively transfer heat generated from the reactor, which is a potential and near-term space nuclear power system. This paper introduces the coupling scheme between the continuous energy Reactor Monte Carlo (RMC) code and the finite element method commercial software ANSYS. Monte Carlo method has the advantages of flexible geometry modeling and continuous-energy nuclear cross sections. ANSYS Parametric Design Language (APDL) is used to determine the detailed temperature distributions and geometric deformation. The on-the-fly temperature treatment of cross sections was adopted in RMC code to solve the memory problems and to speed up simulations. This paper proposed a geometric updating strategy and reactivity feedback methods for the geometric deformation of the solid-state core. The neutronic and thermal-mechanical coupling platform is developed to analyze and further to optimize the heat pipe cooled reactor design. The present coupling codes analyze a 2D central cross-section model for MEGAPOWER heat pipe cooled reactor. The thermal-mechanical feedback reveals that the solid-state reactor has a negative reactivity feedback (~1.5 pcm/K) while it has a deterioration in heat transfer due to the expansion. monte carlo methods finite element method neutronic and thermomechanical (n-t/m) coupling heat pipe reactor Physics Liu Minyun verfasserin aut Chen Erhui verfasserin aut Xie Biheng verfasserin aut Chai Xiaoming verfasserin aut Huang Shanfang verfasserin aut Wang Kan verfasserin aut Yu Hongxing verfasserin aut In EPJ Web of Conferences EDP Sciences, 2010 247, p 06007(2021) (DE-627)647306611 (DE-600)2595425-8 2100014X nnns volume:247, p 06007 year:2021 https://doi.org/10.1051/epjconf/202124706007 kostenfrei https://doaj.org/article/e8197eee078e4c5fbaacc711c9508336 kostenfrei https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06007.pdf kostenfrei https://doaj.org/toc/2100-014X Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_206 GBV_ILN_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2005 GBV_ILN_2009 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2055 GBV_ILN_2111 GBV_ILN_4012 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4249 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4700 AR 247, p 06007 2021
allfieldsGer	10.1051/epjconf/202124706007 doi (DE-627)DOAJ061978930 (DE-599)DOAJe8197eee078e4c5fbaacc711c9508336 DE-627 ger DE-627 rakwb eng QC1-999 Ma Yugao verfasserin aut RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The heat pipe cooled reactor is a solid-state reactor using heat pipes to passively transfer heat generated from the reactor, which is a potential and near-term space nuclear power system. This paper introduces the coupling scheme between the continuous energy Reactor Monte Carlo (RMC) code and the finite element method commercial software ANSYS. Monte Carlo method has the advantages of flexible geometry modeling and continuous-energy nuclear cross sections. ANSYS Parametric Design Language (APDL) is used to determine the detailed temperature distributions and geometric deformation. The on-the-fly temperature treatment of cross sections was adopted in RMC code to solve the memory problems and to speed up simulations. This paper proposed a geometric updating strategy and reactivity feedback methods for the geometric deformation of the solid-state core. The neutronic and thermal-mechanical coupling platform is developed to analyze and further to optimize the heat pipe cooled reactor design. The present coupling codes analyze a 2D central cross-section model for MEGAPOWER heat pipe cooled reactor. The thermal-mechanical feedback reveals that the solid-state reactor has a negative reactivity feedback (~1.5 pcm/K) while it has a deterioration in heat transfer due to the expansion. monte carlo methods finite element method neutronic and thermomechanical (n-t/m) coupling heat pipe reactor Physics Liu Minyun verfasserin aut Chen Erhui verfasserin aut Xie Biheng verfasserin aut Chai Xiaoming verfasserin aut Huang Shanfang verfasserin aut Wang Kan verfasserin aut Yu Hongxing verfasserin aut In EPJ Web of Conferences EDP Sciences, 2010 247, p 06007(2021) (DE-627)647306611 (DE-600)2595425-8 2100014X nnns volume:247, p 06007 year:2021 https://doi.org/10.1051/epjconf/202124706007 kostenfrei https://doaj.org/article/e8197eee078e4c5fbaacc711c9508336 kostenfrei https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06007.pdf kostenfrei https://doaj.org/toc/2100-014X Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_206 GBV_ILN_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2005 GBV_ILN_2009 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2055 GBV_ILN_2111 GBV_ILN_4012 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4249 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4700 AR 247, p 06007 2021
allfieldsSound	10.1051/epjconf/202124706007 doi (DE-627)DOAJ061978930 (DE-599)DOAJe8197eee078e4c5fbaacc711c9508336 DE-627 ger DE-627 rakwb eng QC1-999 Ma Yugao verfasserin aut RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The heat pipe cooled reactor is a solid-state reactor using heat pipes to passively transfer heat generated from the reactor, which is a potential and near-term space nuclear power system. This paper introduces the coupling scheme between the continuous energy Reactor Monte Carlo (RMC) code and the finite element method commercial software ANSYS. Monte Carlo method has the advantages of flexible geometry modeling and continuous-energy nuclear cross sections. ANSYS Parametric Design Language (APDL) is used to determine the detailed temperature distributions and geometric deformation. The on-the-fly temperature treatment of cross sections was adopted in RMC code to solve the memory problems and to speed up simulations. This paper proposed a geometric updating strategy and reactivity feedback methods for the geometric deformation of the solid-state core. The neutronic and thermal-mechanical coupling platform is developed to analyze and further to optimize the heat pipe cooled reactor design. The present coupling codes analyze a 2D central cross-section model for MEGAPOWER heat pipe cooled reactor. The thermal-mechanical feedback reveals that the solid-state reactor has a negative reactivity feedback (~1.5 pcm/K) while it has a deterioration in heat transfer due to the expansion. monte carlo methods finite element method neutronic and thermomechanical (n-t/m) coupling heat pipe reactor Physics Liu Minyun verfasserin aut Chen Erhui verfasserin aut Xie Biheng verfasserin aut Chai Xiaoming verfasserin aut Huang Shanfang verfasserin aut Wang Kan verfasserin aut Yu Hongxing verfasserin aut In EPJ Web of Conferences EDP Sciences, 2010 247, p 06007(2021) (DE-627)647306611 (DE-600)2595425-8 2100014X nnns volume:247, p 06007 year:2021 https://doi.org/10.1051/epjconf/202124706007 kostenfrei https://doaj.org/article/e8197eee078e4c5fbaacc711c9508336 kostenfrei https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06007.pdf kostenfrei https://doaj.org/toc/2100-014X Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_206 GBV_ILN_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2005 GBV_ILN_2009 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2055 GBV_ILN_2111 GBV_ILN_4012 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4249 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4700 AR 247, p 06007 2021
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callnumber-first	Q - Science
author	Ma Yugao
spellingShingle	Ma Yugao misc QC1-999 misc monte carlo methods misc finite element method misc neutronic and thermomechanical (n-t/m) coupling misc heat pipe reactor misc Physics RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES
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topic_title	QC1-999 RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES monte carlo methods finite element method neutronic and thermomechanical (n-t/m) coupling heat pipe reactor
topic	misc QC1-999 misc monte carlo methods misc finite element method misc neutronic and thermomechanical (n-t/m) coupling misc heat pipe reactor misc Physics
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title	RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES
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title_auth	RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES
abstract	The heat pipe cooled reactor is a solid-state reactor using heat pipes to passively transfer heat generated from the reactor, which is a potential and near-term space nuclear power system. This paper introduces the coupling scheme between the continuous energy Reactor Monte Carlo (RMC) code and the finite element method commercial software ANSYS. Monte Carlo method has the advantages of flexible geometry modeling and continuous-energy nuclear cross sections. ANSYS Parametric Design Language (APDL) is used to determine the detailed temperature distributions and geometric deformation. The on-the-fly temperature treatment of cross sections was adopted in RMC code to solve the memory problems and to speed up simulations. This paper proposed a geometric updating strategy and reactivity feedback methods for the geometric deformation of the solid-state core. The neutronic and thermal-mechanical coupling platform is developed to analyze and further to optimize the heat pipe cooled reactor design. The present coupling codes analyze a 2D central cross-section model for MEGAPOWER heat pipe cooled reactor. The thermal-mechanical feedback reveals that the solid-state reactor has a negative reactivity feedback (~1.5 pcm/K) while it has a deterioration in heat transfer due to the expansion.
abstractGer	The heat pipe cooled reactor is a solid-state reactor using heat pipes to passively transfer heat generated from the reactor, which is a potential and near-term space nuclear power system. This paper introduces the coupling scheme between the continuous energy Reactor Monte Carlo (RMC) code and the finite element method commercial software ANSYS. Monte Carlo method has the advantages of flexible geometry modeling and continuous-energy nuclear cross sections. ANSYS Parametric Design Language (APDL) is used to determine the detailed temperature distributions and geometric deformation. The on-the-fly temperature treatment of cross sections was adopted in RMC code to solve the memory problems and to speed up simulations. This paper proposed a geometric updating strategy and reactivity feedback methods for the geometric deformation of the solid-state core. The neutronic and thermal-mechanical coupling platform is developed to analyze and further to optimize the heat pipe cooled reactor design. The present coupling codes analyze a 2D central cross-section model for MEGAPOWER heat pipe cooled reactor. The thermal-mechanical feedback reveals that the solid-state reactor has a negative reactivity feedback (~1.5 pcm/K) while it has a deterioration in heat transfer due to the expansion.
abstract_unstemmed	The heat pipe cooled reactor is a solid-state reactor using heat pipes to passively transfer heat generated from the reactor, which is a potential and near-term space nuclear power system. This paper introduces the coupling scheme between the continuous energy Reactor Monte Carlo (RMC) code and the finite element method commercial software ANSYS. Monte Carlo method has the advantages of flexible geometry modeling and continuous-energy nuclear cross sections. ANSYS Parametric Design Language (APDL) is used to determine the detailed temperature distributions and geometric deformation. The on-the-fly temperature treatment of cross sections was adopted in RMC code to solve the memory problems and to speed up simulations. This paper proposed a geometric updating strategy and reactivity feedback methods for the geometric deformation of the solid-state core. The neutronic and thermal-mechanical coupling platform is developed to analyze and further to optimize the heat pipe cooled reactor design. The present coupling codes analyze a 2D central cross-section model for MEGAPOWER heat pipe cooled reactor. The thermal-mechanical feedback reveals that the solid-state reactor has a negative reactivity feedback (~1.5 pcm/K) while it has a deterioration in heat transfer due to the expansion.
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title_short	RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES
url	https://doi.org/10.1051/epjconf/202124706007 https://doaj.org/article/e8197eee078e4c5fbaacc711c9508336 https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06007.pdf https://doaj.org/toc/2100-014X
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up_date	2024-07-03T23:42:43.246Z
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