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
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).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 28075543
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- A CODES; ATUCHA REACTOR; COMPUTER CALCULATIONS; COMPUTER CODES; NUCLEAR ENGINEERING; PROBABILISTIC ESTIMATION; PROBABILITY; REACTOR PHYSICS; REACTOR TECHNOLOGY; REACTORS; RISK ASSESSMENT; SAFETY ANALYSIS
- Descriptors DEC
- ENGINEERING; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; THERMAL REACTORS
Optional Information
- Notes
- Imprint:Joint nuclear conference with the 4. ENAN: Brazilian meeting on nuclear applications.