Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures
Joint Authors
Petruzzi, Alessandro
D'Auria, Francesco
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2008, Issue 2008 (31 Dec. 2008), pp.1-16, 16 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2008-01-22
Country of Publication
Egypt
No. of Pages
16
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
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.
American Psychological Association (APA)
Petruzzi, Alessandro& D'Auria, Francesco. 2008. Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures. Science and Technology of Nuclear Installations،Vol. 2008, no. 2008, pp.1-16.
https://search.emarefa.net/detail/BIM-473332
Modern Language Association (MLA)
Petruzzi, Alessandro& D'Auria, Francesco. Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures. Science and Technology of Nuclear Installations No. 2008 (2008), pp.1-16.
https://search.emarefa.net/detail/BIM-473332
American Medical Association (AMA)
Petruzzi, Alessandro& D'Auria, Francesco. Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures. Science and Technology of Nuclear Installations. 2008. Vol. 2008, no. 2008, pp.1-16.
https://search.emarefa.net/detail/BIM-473332
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-473332