Computer codes in the safety analysis for nuclear power plants. Computational capabilities of thermal-hydraulic tools, using the example of the RELAP5 code

• Autorzy: Skrzypek E. , Skrzypek M.
• Języki publikacji: EN

Abstrakty

EN

Safety is a paramount concern of the Nuclear Power Program in Poland. To this end there is a need to investigate the design of the proposed reactor and its operation principles and perform multiple analyses both before the reactor start-up (The Pre-Construction Safety Report (PCSR) and during its operational life. In the worldwide nuclear community hundreds of people are involved in this complicated and complex process. Due to the sophistication of the phenomena occurring during operation and accidents, the number of analyses is increasing rapidly. Currently, much interest in this field is focused on the use of computer codes and high computational power.

Słowa kluczowe

EN

safety analysis; neutronic analysis; thermal-hydraulic analysis; severe accident; CFD; RELAP5; MELCOR

PL

analiza bezpieczeństwa; analiza neutronowa; analiza termohydrauliczna; wypadek ciężki; CFD; RELAP5; MELCOR

• Wydawca: Institute of Heat Engineering, Warsaw University of Technology
• Czasopismo: Journal of Power Technologies
• Rocznik: 2014
• Tom: Vol. 94, nr 5
• Strony: 41--50
• Opis fizyczny: Bibliogr. 11 poz., rys., tab.

Twórcy

autor

Skrzypek E.

• Institute of Heat Engineering, Warsaw University of Technology, Nowowiejska 21/25, 00-665, Warsaw, Poland
• National Center for Nuclear Research (NCBJ), A. Sołtana 7, 05-400, Otwock-Swierk, Poland

autor

Skrzypek M.

• Institute of Heat Engineering, Warsaw University of Technology, Nowowiejska 21/25, 00-665, Warsaw, Poland
• National Center for Nuclear Research (NCBJ), A. Sołtana 7, 05-400, Otwock-Swierk, Poland

Bibliografia

• [1] Świadomie o atomie – energia jądrowa w Polsce. URL www.swiadomieoatomie.pl
• [2] A. Strupczewski, Nie bójmy się energetyki jądrowej!, Centralny Ośrodek Szkolenia i Wydawnictw SEP, Warsaw, 2010.
• [3] Japan Atomic Energy Agency, Investigation of irradiation behaviour of future FBR fuel. Short-term irradiation behavior of Am-containing MOX fuel (2009).
• [4] M. El-Shanawany, IAEA Safety Standards for safety assessment, Vienna (2010).
• [5] [link]. URL www.nrc.gov
• [6] [link]. URL http://www-cathare.cea.fr/
• [7] [link]. URL http://www.fauske.com/
• [8] International Atomic Energy Agency, Vienna, Safety Standards (2000).
• [9] D. A. Vega, Atomistically informed fuel performance codes: a proof of principle using molecular dynamics and frapcon simulation, Master’s thesis, Uniwersity of Florida (2008).
• [10] [link]. URL www.cis.gov.pl
• [11] GRS - The Gesellschaft für Anlagen- und Reaktorsicherheit, Computer code ATHLET. URL www.grs.de