As one of the Generation-IV reactor concepts, lead-alloy-cooled advanced nuclear energy systems (LACANES) have been studied worldwide in order to utilize the advantages of good heat transfer properties, neutron transparency and chemical inertness with air and water. Since the Fukushima accident, the passive safety aspect of the LACANES is increasingly emphasized due to outstanding natural circulation capability. To investigate the thermal-hydraulic capability of LBE, an international cooperation has been performed under OECD/NEA program, under the guidance of the Nuclear Science Committee by a task force named as Lead Alloy Cooled Advanced Nuclear Energy Systems (LACANES) since 2007. This international collaboration had dealt with computational benchmarking of isothermal LBE forced convection tests in the phase I, and the working group published a guideline for using one-dimensional system codes to simulate LBE forced circulation test results from HELIOS loop. The phase II was started after that, to give an additional guideline in the case of natural circulation. NACIE, one of benchmarking targets for the phase II which is a rectangular-shape loop located at ENEA-Brasimone Research Centre, Italy. NACIE test results were benchmarked by each participant using their one-dimensional thermal-hydraulic codes, and they are to follow the guideline from the LACANES phase I for regions where hydraulic loss occurs. Due to the selection of hydraulic loss coefficient relations by users, the cross-comparison results of international participants showed some discrepancies and the estimated mass flow rates had 13% of maximum error. Also, the future R&D areas are identified.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4595-0
PROCEEDINGS PAPER
Cross-Comparison of One-Dimensional Thermal-Hydraulic Codes on Natural Circulation Analysis of NACIE Loop Test for Lead-Alloy Cooled Advanced Nuclear Energy Systems (LACANES)
Yong-Hoon Shin,
Yong-Hoon Shin
Seoul National University, Seoul, Republic of Korea
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Il Soon Hwang,
Il Soon Hwang
Seoul National University, Seoul, Republic of Korea
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Massimiliano Polidori,
Massimiliano Polidori
ENEA, Bologna, Italy
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Vincenzo Casamassima,
Vincenzo Casamassima
Ricerca sul Sistema Energetico (RSE S.p.A), Milano, Italy
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Stephanie Cornet,
Stephanie Cornet
OECD Nuclear Energy Agency, Paris, France
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Luciana Barucca,
Luciana Barucca
Ansaldo Nucleare, Genova, Italy
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Davide Balestri,
Davide Balestri
Politecnico di Milano, Milano, Italy
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Ming Jin,
Ming Jin
Chinese Academy of Sciences, Hefei, Anhui, China
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Mathias Viellieber
Mathias Viellieber
Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany
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Yong-Hoon Shin
Seoul National University, Seoul, Republic of Korea
Il Soon Hwang
Seoul National University, Seoul, Republic of Korea
Massimiliano Polidori
ENEA, Bologna, Italy
Paride Meloni
ENEA, Bologna, Italy
Vincenzo Casamassima
Ricerca sul Sistema Energetico (RSE S.p.A), Milano, Italy
Stephanie Cornet
OECD Nuclear Energy Agency, Paris, France
Luciana Barucca
Ansaldo Nucleare, Genova, Italy
Davide Balestri
Politecnico di Milano, Milano, Italy
Ming Jin
Chinese Academy of Sciences, Hefei, Anhui, China
Mathias Viellieber
Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany
Paper No:
ICONE22-30716, V005T16A007; 7 pages
Published Online:
November 17, 2014
Citation
Shin, Y, Hwang, IS, Polidori, M, Meloni, P, Casamassima, V, Cornet, S, Barucca, L, Balestri, D, Jin, M, & Viellieber, M. "Cross-Comparison of One-Dimensional Thermal-Hydraulic Codes on Natural Circulation Analysis of NACIE Loop Test for Lead-Alloy Cooled Advanced Nuclear Energy Systems (LACANES)." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition. Prague, Czech Republic. July 7–11, 2014. V005T16A007. ASME. https://doi.org/10.1115/ICONE22-30716
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