Computer codes in the safety analysis for nuclear power plants. Computational capabilities of thermal-hydraulic tools, using the example of the RELAP5 code
Abstract
During the time of the Nuclear Power Programme introduction in Poland, there appears a question about the safety of the nuclear power plants. To answer this question in exhaustive manner there is a need to investigate the design of the proposed reactor, operation principles and analysis, that are prepared before the reactor start-up (The Pre-Construction Safety Report (PCSR)) and during their operation. In the worldwide community of nuclear there are hundreds of people involved in this complicated and complex process, that are aiming to ensure the safety of the nuclear power plants. Because of the sophistication of the phenomena occurring during the operation and accidents, the number of the analysis is rapidly increasing. The current demand is focused on the use of the computer codes and high computational power for the purposes of safety warranty.References
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[2] Polish Energy Group – PGE EJ1 Sp. z o.o., Świadomie o atomie – energia jądrowa w Polsce, [online]. Available: www.swiadomieoatomie.pl.
[3] A. Strupczewski, Nie bójmy się energetyki jądrowej!, Warsaw, Centralny Ośrodek Szkolenia i Wydawnictw SEP, 2010.
[4] d. A. Vega, Atomistically informed fuel performance codes: a proof of principle using Molecular Dynamics and FRAPCON simulation, Uniwersity of Florida, 2008.
[5] Japan Atomic Energy Agency, Investigation of irradiation behaviour of future FBR fuel. Short-term irradiation behaviour of Am-containing MOX fuel, JAEA, 2009.
[6] M. El-Shanawany, IAEA Safety Standards for safety assessment, Vienna, 2010.
[7] United States Nuclear Regulatory Commission, [online]. Available: www.nrc.gov.
[8] Commissariat à l'énergie atomique et aux énergies alternatives- CEA, [Online]. Available: http://www-cathare.cea.fr/.
[9] GRS - The Gesellschaft für Anlagen- und Reaktorsicherheit, Computer code ATHLET, [Online]. Available: www.grs.de.
[10] Fauske and Associates Llc, [Online]. Available: http://www.fauske.com/.
[11] International Atomic Energy Agency, Safety Standards, Vienna, IAEA, 2000.
Published
2015-01-04
How to Cite
SKRZYPEK, Eleonora; SKRZYPEK, Maciej.
Computer codes in the safety analysis for nuclear power plants. Computational capabilities of thermal-hydraulic tools, using the example of the RELAP5 code.
Journal of Power Technologies, [S.l.], v. 94, n. 5, p. 41--50, jan. 2015.
ISSN 2083-4195.
Available at: <https://papers.itc.pw.edu.pl/index.php/JPT/article/view/592>. Date accessed: 22 dec. 2024.
Section
Nuclear Power
Keywords
Safety analysis; Neutronic analysis; Thermalhydraulic analysis; Severe accident; CFD; RELAP5; MELCOR
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