Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures
In the last four decades, large efforts have been undertaken to provide reliable thermal-hydraulic system codes for the analyses of transients and accidents in nuclear power plants. Whereas the first system codes, developed at the beginning of the 1970s, utilized the homogenous equilibrium model wi...
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| Format: | Article |
| Language: | English |
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Wiley
2008-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2008/460795 |
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| author | Alessandro Petruzzi Francesco D'Auria |
| author_facet | Alessandro Petruzzi Francesco D'Auria |
| author_sort | Alessandro Petruzzi |
| collection | DOAJ |
| description | In the last four decades, large efforts have been undertaken to provide reliable thermal-hydraulic system codes for the analyses of transients and accidents in nuclear power plants. Whereas the first system codes, developed at the beginning of the 1970s, utilized the homogenous equilibrium model with three balance equations to describe the two-phase flow, nowadays the more advanced system codes are based on the so-called “two-fluid model” with separation of the water and vapor phases, resulting in systems with at least six balance equations. The wide experimental campaign, constituted by the integral and separate effect tests, conducted under the umbrella of the OECD/CSNI was at the basis of the development and validation of the thermal-hydraulic system codes by which they have reached the present high degree of maturity. However, notwithstanding the huge amounts of financial and human resources invested, the results predicted by the code are still affected by errors whose origins can be attributed to several reasons as model deficiencies, approximations in the numerical solution, nodalization effects, and imperfect knowledge of boundary and initial conditions. In this context, the existence of qualified procedures for a consistent application of qualified thermal-hydraulic system code is necessary and implies the drawing up of specific criteria through which the code-user, the nodalization, and finally the transient results are qualified. |
| format | Article |
| id | doaj-art-21d60f054d154c2bb5f44f57f0c52bd4 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2008-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-21d60f054d154c2bb5f44f57f0c52bd42025-02-03T01:10:35ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832008-01-01200810.1155/2008/460795460795Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification ProceduresAlessandro Petruzzi0Francesco D'Auria1DIMNP, University of Pisa, Via Diotisalvi 2, Pisa 56100, ItalyDIMNP, University of Pisa, Via Diotisalvi 2, Pisa 56100, ItalyIn the last four decades, large efforts have been undertaken to provide reliable thermal-hydraulic system codes for the analyses of transients and accidents in nuclear power plants. Whereas the first system codes, developed at the beginning of the 1970s, utilized the homogenous equilibrium model with three balance equations to describe the two-phase flow, nowadays the more advanced system codes are based on the so-called “two-fluid model” with separation of the water and vapor phases, resulting in systems with at least six balance equations. The wide experimental campaign, constituted by the integral and separate effect tests, conducted under the umbrella of the OECD/CSNI was at the basis of the development and validation of the thermal-hydraulic system codes by which they have reached the present high degree of maturity. However, notwithstanding the huge amounts of financial and human resources invested, the results predicted by the code are still affected by errors whose origins can be attributed to several reasons as model deficiencies, approximations in the numerical solution, nodalization effects, and imperfect knowledge of boundary and initial conditions. In this context, the existence of qualified procedures for a consistent application of qualified thermal-hydraulic system code is necessary and implies the drawing up of specific criteria through which the code-user, the nodalization, and finally the transient results are qualified.http://dx.doi.org/10.1155/2008/460795 |
| spellingShingle | Alessandro Petruzzi Francesco D'Auria Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures Science and Technology of Nuclear Installations |
| title | Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures |
| title_full | Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures |
| title_fullStr | Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures |
| title_full_unstemmed | Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures |
| title_short | Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures |
| title_sort | thermal hydraulic system codes in nulcear reactor safety and qualification procedures |
| url | http://dx.doi.org/10.1155/2008/460795 |
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