Published 1997 | Version v1
Miscellaneous

AMADEUS: deterministic calculus support to the probabilistic safety analysis of nuclear power plant Atucha 1

  • 1. Comision Nacional de Energia Atomica, Buenos Aires (Argentina)
  • 2. Comision Nacional de Energia Atomica, San Martin (Argentina)
  • 3. Nucleoeletrica Argentina S.A., Lima (Argentina). Central Nuclear Atucha I

Description

The AMADEUS code, which is a first-principles thermalhydraulic code, is intend to facilitate the comprehension of the transients without loss of coolant dynamics. Being fast and user-friendly, allows to calculate transients with either single or combined failures, and to perform parametric studies. AMADEUS has proven to be very useful to develop event sequences, to postulate success criteria, and to estimate the periods of time in which countermeasures are required. Sequences which resulted in a high failure probability were reevaluated with more sophisticated and internationally accepted codes, such as RELAP, and very good agreement was observed. Some of these transients are presented, showing the complicated physics managed by the code and how it helped analysts to develop accident sequences. 3 refs., 12 figs

Part of:
Proceedings of the 11. ENFIR: Meeting on reactor physics and thermal hydraulics

Additional details

Publishing Information

Imprint Title
Proceedings of the 11. ENFIR: Meeting on reactor physics and thermal hydraulics
Imprint Pagination
838 p.
Journal Page Range
p. 580-585.

Conference

Title
Meeting on reactor physics and thermal hydraulics.
Acronym
11. ENFIR
Dates
18-22 Aug 1997.
Place
Pocos de Caldas, MG (Brazil).

Optional Information

Notes
Imprint:Joint nuclear conference with the 4. ENAN: Brazilian meeting on nuclear applications.