Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC

The spatial distribution of neutron flux or reaction rate was calculated by cell or mesh tally in traditional Monte Carlo simulation. However, either cell or mesh tally leads to the increase of memory consumption and simulation time. In this paper, the function expansion tally (FET) method was devel...
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Autor*in:	Zhenyu Wang [verfasserIn] Shichang Liu [verfasserIn] Ding She [verfasserIn] Yang Su [verfasserIn] Yixue Chen [verfasserIn]

Format:	E-Artikel
Sprache:	Englisch

Erschienen:	2021

Schlagwörter:	Monte Carlo Function expansion tally Order selection strategy RMC

Übergeordnetes Werk:	In: Nuclear Engineering and Technology - Elsevier, 2016, 53(2021), 2, Seite 430-438
Übergeordnetes Werk:	volume:53 ; year:2021 ; number:2 ; pages:430-438

Links:	Link aufrufen Link aufrufen Link aufrufen Journal toc

DOI / URN:	10.1016/j.net.2020.07.018

Katalog-ID:	DOAJ051915367

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520			\|a The spatial distribution of neutron flux or reaction rate was calculated by cell or mesh tally in traditional Monte Carlo simulation. However, either cell or mesh tally leads to the increase of memory consumption and simulation time. In this paper, the function expansion tally (FET) method was developed in Reactor Monte Carlo code RMC to solve this problem. The FET method was applied to the tallies of neutron flux distributions of uranium block and PWR fuel rod models. Legendre polynomials were used in the axial direction, while Zernike polynomials were used in the radial direction. The results of flux, calculation time and memory consumption of different expansion orders were investigated, and compared with the mesh tally. Results showed that the continuous distribution of flux can be obtained by FET method. The flux distributions were consistent with that of mesh tally, while the memory consumption and simulation time can be effectively reduced. Finally, the convergence analysis of coefficients of polynomials were performed, and the selection strategy of FET order was proposed based on the statistics uncertainty of the coefficients. The proposed method can help to determine the order of FET, which was meaningful for the efficiency and accuracy of FET method.
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allfields	10.1016/j.net.2020.07.018 doi (DE-627)DOAJ051915367 (DE-599)DOAJ5f1eea49d81947cea273c1c67a3ac7c5 DE-627 ger DE-627 rakwb eng TK9001-9401 Zhenyu Wang verfasserin aut Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The spatial distribution of neutron flux or reaction rate was calculated by cell or mesh tally in traditional Monte Carlo simulation. However, either cell or mesh tally leads to the increase of memory consumption and simulation time. In this paper, the function expansion tally (FET) method was developed in Reactor Monte Carlo code RMC to solve this problem. The FET method was applied to the tallies of neutron flux distributions of uranium block and PWR fuel rod models. Legendre polynomials were used in the axial direction, while Zernike polynomials were used in the radial direction. The results of flux, calculation time and memory consumption of different expansion orders were investigated, and compared with the mesh tally. Results showed that the continuous distribution of flux can be obtained by FET method. The flux distributions were consistent with that of mesh tally, while the memory consumption and simulation time can be effectively reduced. Finally, the convergence analysis of coefficients of polynomials were performed, and the selection strategy of FET order was proposed based on the statistics uncertainty of the coefficients. The proposed method can help to determine the order of FET, which was meaningful for the efficiency and accuracy of FET method. Monte Carlo Function expansion tally Order selection strategy RMC Nuclear engineering. Atomic power Shichang Liu verfasserin aut Ding She verfasserin aut Yang Su verfasserin aut Yixue Chen verfasserin aut In Nuclear Engineering and Technology Elsevier, 2016 53(2021), 2, Seite 430-438 (DE-627)63243855X (DE-600)2566624-1 17385733 nnns volume:53 year:2021 number:2 pages:430-438 https://doi.org/10.1016/j.net.2020.07.018 kostenfrei https://doaj.org/article/5f1eea49d81947cea273c1c67a3ac7c5 kostenfrei http://www.sciencedirect.com/science/article/pii/S1738573320302370 kostenfrei https://doaj.org/toc/1738-5733 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_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2014 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 53 2021 2 430-438
spelling	10.1016/j.net.2020.07.018 doi (DE-627)DOAJ051915367 (DE-599)DOAJ5f1eea49d81947cea273c1c67a3ac7c5 DE-627 ger DE-627 rakwb eng TK9001-9401 Zhenyu Wang verfasserin aut Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The spatial distribution of neutron flux or reaction rate was calculated by cell or mesh tally in traditional Monte Carlo simulation. However, either cell or mesh tally leads to the increase of memory consumption and simulation time. In this paper, the function expansion tally (FET) method was developed in Reactor Monte Carlo code RMC to solve this problem. The FET method was applied to the tallies of neutron flux distributions of uranium block and PWR fuel rod models. Legendre polynomials were used in the axial direction, while Zernike polynomials were used in the radial direction. The results of flux, calculation time and memory consumption of different expansion orders were investigated, and compared with the mesh tally. Results showed that the continuous distribution of flux can be obtained by FET method. The flux distributions were consistent with that of mesh tally, while the memory consumption and simulation time can be effectively reduced. Finally, the convergence analysis of coefficients of polynomials were performed, and the selection strategy of FET order was proposed based on the statistics uncertainty of the coefficients. The proposed method can help to determine the order of FET, which was meaningful for the efficiency and accuracy of FET method. Monte Carlo Function expansion tally Order selection strategy RMC Nuclear engineering. Atomic power Shichang Liu verfasserin aut Ding She verfasserin aut Yang Su verfasserin aut Yixue Chen verfasserin aut In Nuclear Engineering and Technology Elsevier, 2016 53(2021), 2, Seite 430-438 (DE-627)63243855X (DE-600)2566624-1 17385733 nnns volume:53 year:2021 number:2 pages:430-438 https://doi.org/10.1016/j.net.2020.07.018 kostenfrei https://doaj.org/article/5f1eea49d81947cea273c1c67a3ac7c5 kostenfrei http://www.sciencedirect.com/science/article/pii/S1738573320302370 kostenfrei https://doaj.org/toc/1738-5733 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_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2014 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 53 2021 2 430-438
allfields_unstemmed	10.1016/j.net.2020.07.018 doi (DE-627)DOAJ051915367 (DE-599)DOAJ5f1eea49d81947cea273c1c67a3ac7c5 DE-627 ger DE-627 rakwb eng TK9001-9401 Zhenyu Wang verfasserin aut Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The spatial distribution of neutron flux or reaction rate was calculated by cell or mesh tally in traditional Monte Carlo simulation. However, either cell or mesh tally leads to the increase of memory consumption and simulation time. In this paper, the function expansion tally (FET) method was developed in Reactor Monte Carlo code RMC to solve this problem. The FET method was applied to the tallies of neutron flux distributions of uranium block and PWR fuel rod models. Legendre polynomials were used in the axial direction, while Zernike polynomials were used in the radial direction. The results of flux, calculation time and memory consumption of different expansion orders were investigated, and compared with the mesh tally. Results showed that the continuous distribution of flux can be obtained by FET method. The flux distributions were consistent with that of mesh tally, while the memory consumption and simulation time can be effectively reduced. Finally, the convergence analysis of coefficients of polynomials were performed, and the selection strategy of FET order was proposed based on the statistics uncertainty of the coefficients. The proposed method can help to determine the order of FET, which was meaningful for the efficiency and accuracy of FET method. Monte Carlo Function expansion tally Order selection strategy RMC Nuclear engineering. Atomic power Shichang Liu verfasserin aut Ding She verfasserin aut Yang Su verfasserin aut Yixue Chen verfasserin aut In Nuclear Engineering and Technology Elsevier, 2016 53(2021), 2, Seite 430-438 (DE-627)63243855X (DE-600)2566624-1 17385733 nnns volume:53 year:2021 number:2 pages:430-438 https://doi.org/10.1016/j.net.2020.07.018 kostenfrei https://doaj.org/article/5f1eea49d81947cea273c1c67a3ac7c5 kostenfrei http://www.sciencedirect.com/science/article/pii/S1738573320302370 kostenfrei https://doaj.org/toc/1738-5733 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_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2014 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 53 2021 2 430-438
allfieldsGer	10.1016/j.net.2020.07.018 doi (DE-627)DOAJ051915367 (DE-599)DOAJ5f1eea49d81947cea273c1c67a3ac7c5 DE-627 ger DE-627 rakwb eng TK9001-9401 Zhenyu Wang verfasserin aut Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The spatial distribution of neutron flux or reaction rate was calculated by cell or mesh tally in traditional Monte Carlo simulation. However, either cell or mesh tally leads to the increase of memory consumption and simulation time. In this paper, the function expansion tally (FET) method was developed in Reactor Monte Carlo code RMC to solve this problem. The FET method was applied to the tallies of neutron flux distributions of uranium block and PWR fuel rod models. Legendre polynomials were used in the axial direction, while Zernike polynomials were used in the radial direction. The results of flux, calculation time and memory consumption of different expansion orders were investigated, and compared with the mesh tally. Results showed that the continuous distribution of flux can be obtained by FET method. The flux distributions were consistent with that of mesh tally, while the memory consumption and simulation time can be effectively reduced. Finally, the convergence analysis of coefficients of polynomials were performed, and the selection strategy of FET order was proposed based on the statistics uncertainty of the coefficients. The proposed method can help to determine the order of FET, which was meaningful for the efficiency and accuracy of FET method. Monte Carlo Function expansion tally Order selection strategy RMC Nuclear engineering. Atomic power Shichang Liu verfasserin aut Ding She verfasserin aut Yang Su verfasserin aut Yixue Chen verfasserin aut In Nuclear Engineering and Technology Elsevier, 2016 53(2021), 2, Seite 430-438 (DE-627)63243855X (DE-600)2566624-1 17385733 nnns volume:53 year:2021 number:2 pages:430-438 https://doi.org/10.1016/j.net.2020.07.018 kostenfrei https://doaj.org/article/5f1eea49d81947cea273c1c67a3ac7c5 kostenfrei http://www.sciencedirect.com/science/article/pii/S1738573320302370 kostenfrei https://doaj.org/toc/1738-5733 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_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2014 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 53 2021 2 430-438
allfieldsSound	10.1016/j.net.2020.07.018 doi (DE-627)DOAJ051915367 (DE-599)DOAJ5f1eea49d81947cea273c1c67a3ac7c5 DE-627 ger DE-627 rakwb eng TK9001-9401 Zhenyu Wang verfasserin aut Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The spatial distribution of neutron flux or reaction rate was calculated by cell or mesh tally in traditional Monte Carlo simulation. However, either cell or mesh tally leads to the increase of memory consumption and simulation time. In this paper, the function expansion tally (FET) method was developed in Reactor Monte Carlo code RMC to solve this problem. The FET method was applied to the tallies of neutron flux distributions of uranium block and PWR fuel rod models. Legendre polynomials were used in the axial direction, while Zernike polynomials were used in the radial direction. The results of flux, calculation time and memory consumption of different expansion orders were investigated, and compared with the mesh tally. Results showed that the continuous distribution of flux can be obtained by FET method. The flux distributions were consistent with that of mesh tally, while the memory consumption and simulation time can be effectively reduced. Finally, the convergence analysis of coefficients of polynomials were performed, and the selection strategy of FET order was proposed based on the statistics uncertainty of the coefficients. The proposed method can help to determine the order of FET, which was meaningful for the efficiency and accuracy of FET method. Monte Carlo Function expansion tally Order selection strategy RMC Nuclear engineering. Atomic power Shichang Liu verfasserin aut Ding She verfasserin aut Yang Su verfasserin aut Yixue Chen verfasserin aut In Nuclear Engineering and Technology Elsevier, 2016 53(2021), 2, Seite 430-438 (DE-627)63243855X (DE-600)2566624-1 17385733 nnns volume:53 year:2021 number:2 pages:430-438 https://doi.org/10.1016/j.net.2020.07.018 kostenfrei https://doaj.org/article/5f1eea49d81947cea273c1c67a3ac7c5 kostenfrei http://www.sciencedirect.com/science/article/pii/S1738573320302370 kostenfrei https://doaj.org/toc/1738-5733 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_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2014 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 53 2021 2 430-438
language	English
source	In Nuclear Engineering and Technology 53(2021), 2, Seite 430-438 volume:53 year:2021 number:2 pages:430-438
sourceStr	In Nuclear Engineering and Technology 53(2021), 2, Seite 430-438 volume:53 year:2021 number:2 pages:430-438
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callnumber-first	T - Technology
author	Zhenyu Wang
spellingShingle	Zhenyu Wang misc TK9001-9401 misc Monte Carlo misc Function expansion tally misc Order selection strategy misc RMC misc Nuclear engineering. Atomic power Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC
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topic_title	TK9001-9401 Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC Monte Carlo Function expansion tally Order selection strategy RMC
topic	misc TK9001-9401 misc Monte Carlo misc Function expansion tally misc Order selection strategy misc RMC misc Nuclear engineering. Atomic power
topic_unstemmed	misc TK9001-9401 misc Monte Carlo misc Function expansion tally misc Order selection strategy misc RMC misc Nuclear engineering. Atomic power
topic_browse	misc TK9001-9401 misc Monte Carlo misc Function expansion tally misc Order selection strategy misc RMC misc Nuclear engineering. Atomic power
format_facet	Elektronische Aufsätze Aufsätze Elektronische Ressource
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title	Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC
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title_full	Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC
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title_sort	implementation of functional expansion tally method and order selection strategy in monte carlo code rmc
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title_auth	Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC
abstract	The spatial distribution of neutron flux or reaction rate was calculated by cell or mesh tally in traditional Monte Carlo simulation. However, either cell or mesh tally leads to the increase of memory consumption and simulation time. In this paper, the function expansion tally (FET) method was developed in Reactor Monte Carlo code RMC to solve this problem. The FET method was applied to the tallies of neutron flux distributions of uranium block and PWR fuel rod models. Legendre polynomials were used in the axial direction, while Zernike polynomials were used in the radial direction. The results of flux, calculation time and memory consumption of different expansion orders were investigated, and compared with the mesh tally. Results showed that the continuous distribution of flux can be obtained by FET method. The flux distributions were consistent with that of mesh tally, while the memory consumption and simulation time can be effectively reduced. Finally, the convergence analysis of coefficients of polynomials were performed, and the selection strategy of FET order was proposed based on the statistics uncertainty of the coefficients. The proposed method can help to determine the order of FET, which was meaningful for the efficiency and accuracy of FET method.
abstractGer	The spatial distribution of neutron flux or reaction rate was calculated by cell or mesh tally in traditional Monte Carlo simulation. However, either cell or mesh tally leads to the increase of memory consumption and simulation time. In this paper, the function expansion tally (FET) method was developed in Reactor Monte Carlo code RMC to solve this problem. The FET method was applied to the tallies of neutron flux distributions of uranium block and PWR fuel rod models. Legendre polynomials were used in the axial direction, while Zernike polynomials were used in the radial direction. The results of flux, calculation time and memory consumption of different expansion orders were investigated, and compared with the mesh tally. Results showed that the continuous distribution of flux can be obtained by FET method. The flux distributions were consistent with that of mesh tally, while the memory consumption and simulation time can be effectively reduced. Finally, the convergence analysis of coefficients of polynomials were performed, and the selection strategy of FET order was proposed based on the statistics uncertainty of the coefficients. The proposed method can help to determine the order of FET, which was meaningful for the efficiency and accuracy of FET method.
abstract_unstemmed	The spatial distribution of neutron flux or reaction rate was calculated by cell or mesh tally in traditional Monte Carlo simulation. However, either cell or mesh tally leads to the increase of memory consumption and simulation time. In this paper, the function expansion tally (FET) method was developed in Reactor Monte Carlo code RMC to solve this problem. The FET method was applied to the tallies of neutron flux distributions of uranium block and PWR fuel rod models. Legendre polynomials were used in the axial direction, while Zernike polynomials were used in the radial direction. The results of flux, calculation time and memory consumption of different expansion orders were investigated, and compared with the mesh tally. Results showed that the continuous distribution of flux can be obtained by FET method. The flux distributions were consistent with that of mesh tally, while the memory consumption and simulation time can be effectively reduced. Finally, the convergence analysis of coefficients of polynomials were performed, and the selection strategy of FET order was proposed based on the statistics uncertainty of the coefficients. The proposed method can help to determine the order of FET, which was meaningful for the efficiency and accuracy of FET method.
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title_short	Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC
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Implementation of functional expansion tally method and order selection strategy in Monte Carlo code RMC

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