Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors

G. Bandini; M. Polidori; A. Gerschenfeld; D. Pialla; S. Li; W. M. Ma; P. Kudinov; M. Jeltsov; K. Kööp; K. Huber; X. Cheng; C. Bruzzese; A. G. Class; D. P. Prill; A. Papukchiev; C. Geffray; R. Macian-Juan; L. Maas

doi:10.1016/j.nucengdes.2014.11.003

Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors

G. Bandini, M. Polidori, A. Gerschenfeld, D. Pialla, S. Li, W. M. Ma, P. Kudinov, M. Jeltsov, K. Kööp, K. Huber, X. Cheng, C. Bruzzese, A. G. Class, D. P. Prill, A. Papukchiev, C. Geffray, R. Macian-Juan, L. Maas

Chair of Nuclear Technology

Research output: Contribution to journal › Article › peer-review

41 Scopus citations

Abstract

The THINS project of the 7th Framework EU Program on nuclear fission safety is devoted to the investigation of crosscutting thermal-hydraulic issues for innovative nuclear systems. A significant effort in the project has been dedicated to the qualification and validation of system codes currently employed in thermal-hydraulic transient analysis for nuclear reactors. This assessment is based either on already available experimental data, or on the data provided by test campaigns carried out in the frame of THINS project activities. Data provided by TALL and CIRCE facilities were used in the assessment of system codes for HLM reactors, while the PHENIX ultimate natural circulation test was used as reference for a benchmark exercise among system codes for sodium-cooled reactor applications. In addition, a promising grid-free pool model based on proper orthogonal decomposition is proposed to overcome the limits shown by the thermal-hydraulic system codes in the simulation of pool-type systems. Furthermore, multi-scale system-CFD solutions have been developed and validated for innovative nuclear system applications. For this purpose, data from the PHENIX experiments have been used, and data are provided by the tests conducted with new configuration of the TALL-3D facility, which accommodates a 3D test section within the primary circuit. The TALL-3D measurements are currently used for the validation of the coupling between system and CFD codes.

Original language	English
Pages (from-to)	22-38
Number of pages	17
Journal	Nuclear Engineering and Design
Volume	281
DOIs	https://doi.org/10.1016/j.nucengdes.2014.11.003
State	Published - Jan 2015

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10.1016/j.nucengdes.2014.11.003

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Bandini, G., Polidori, M., Gerschenfeld, A., Pialla, D., Li, S., Ma, W. M., Kudinov, P., Jeltsov, M., Kööp, K., Huber, K., Cheng, X., Bruzzese, C., Class, A. G., Prill, D. P., Papukchiev, A., Geffray, C., Macian-Juan, R., & Maas, L. (2015). Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors. Nuclear Engineering and Design, 281, 22-38. https://doi.org/10.1016/j.nucengdes.2014.11.003

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title = "Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors",

abstract = "The THINS project of the 7th Framework EU Program on nuclear fission safety is devoted to the investigation of crosscutting thermal-hydraulic issues for innovative nuclear systems. A significant effort in the project has been dedicated to the qualification and validation of system codes currently employed in thermal-hydraulic transient analysis for nuclear reactors. This assessment is based either on already available experimental data, or on the data provided by test campaigns carried out in the frame of THINS project activities. Data provided by TALL and CIRCE facilities were used in the assessment of system codes for HLM reactors, while the PHENIX ultimate natural circulation test was used as reference for a benchmark exercise among system codes for sodium-cooled reactor applications. In addition, a promising grid-free pool model based on proper orthogonal decomposition is proposed to overcome the limits shown by the thermal-hydraulic system codes in the simulation of pool-type systems. Furthermore, multi-scale system-CFD solutions have been developed and validated for innovative nuclear system applications. For this purpose, data from the PHENIX experiments have been used, and data are provided by the tests conducted with new configuration of the TALL-3D facility, which accommodates a 3D test section within the primary circuit. The TALL-3D measurements are currently used for the validation of the coupling between system and CFD codes.",

author = "G. Bandini and M. Polidori and A. Gerschenfeld and D. Pialla and S. Li and Ma, {W. M.} and P. Kudinov and M. Jeltsov and K. K{\"o}{\"o}p and K. Huber and X. Cheng and C. Bruzzese and Class, {A. G.} and Prill, {D. P.} and A. Papukchiev and C. Geffray and R. Macian-Juan and L. Maas",

year = "2015",

month = jan,

doi = "10.1016/j.nucengdes.2014.11.003",

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Bandini, G, Polidori, M, Gerschenfeld, A, Pialla, D, Li, S, Ma, WM, Kudinov, P, Jeltsov, M, Kööp, K, Huber, K, Cheng, X, Bruzzese, C, Class, AG, Prill, DP, Papukchiev, A, Geffray, C, Macian-Juan, R & Maas, L 2015, 'Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors', Nuclear Engineering and Design, vol. 281, pp. 22-38. https://doi.org/10.1016/j.nucengdes.2014.11.003

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AU - Gerschenfeld, A.

AU - Pialla, D.

AU - Li, S.

AU - Ma, W. M.

AU - Kudinov, P.

AU - Jeltsov, M.

AU - Kööp, K.

AU - Huber, K.

AU - Cheng, X.

AU - Bruzzese, C.

AU - Class, A. G.

AU - Prill, D. P.

AU - Papukchiev, A.

AU - Geffray, C.

AU - Macian-Juan, R.

AU - Maas, L.

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AB - The THINS project of the 7th Framework EU Program on nuclear fission safety is devoted to the investigation of crosscutting thermal-hydraulic issues for innovative nuclear systems. A significant effort in the project has been dedicated to the qualification and validation of system codes currently employed in thermal-hydraulic transient analysis for nuclear reactors. This assessment is based either on already available experimental data, or on the data provided by test campaigns carried out in the frame of THINS project activities. Data provided by TALL and CIRCE facilities were used in the assessment of system codes for HLM reactors, while the PHENIX ultimate natural circulation test was used as reference for a benchmark exercise among system codes for sodium-cooled reactor applications. In addition, a promising grid-free pool model based on proper orthogonal decomposition is proposed to overcome the limits shown by the thermal-hydraulic system codes in the simulation of pool-type systems. Furthermore, multi-scale system-CFD solutions have been developed and validated for innovative nuclear system applications. For this purpose, data from the PHENIX experiments have been used, and data are provided by the tests conducted with new configuration of the TALL-3D facility, which accommodates a 3D test section within the primary circuit. The TALL-3D measurements are currently used for the validation of the coupling between system and CFD codes.

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Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors

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