A Parametric Study of a Large Break in Reactor Inlet Header of CANDU6 Reactors Using RELAP5 Code
Conference
·
OSTI ID:21016374
- Power Plant Engineering Faculty, Politehnica Univ., 313 Splaiul Independentei, Bucharest (Romania)
- National Commission for Nuclear Activities Control, 14 Libertatii Blvd., Bucharest (Romania)
A large break loss of coolant accident in a CANDU can lead to degraded fuel cooling in a large number of fuel channels due to the apparition of a prolonged flow stagnation period in the downstream core pass. The paper presents a parametric study of a reactor inlet header break. The parametric survey includes: the size of the break, the choked flow model employed, the emergency core cooling (ECC) performance and the core nodalization. The study is performed with RELAP5/SCDAP mod 3.4 and the results are compared with the safety analysis results. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 21016374
- Country of Publication:
- United States
- Language:
- English
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