A Coupled Calculation Suite for Atucha II Operational Transients Analysis
Description
While more than a decade ago reactor and thermal hydraulic calculations were tedious and often needed a lot of approximations and simplifications that forced the designers to take a very conservative approach, computational resources available nowadays allow engineers to cope with increasingly complex problems in a reasonable time. The use of best‐estimate calculations provides tools to justify convenient engineering margins, reduces costs, and maximises economic benefits. In this direction, a suite of coupled best‐estimate specific calculation codes was developed to analyse the behaviour of the Atucha II nuclear power plant in Argentina. The developed tool includes three‐dimensional spatial neutron kinetics, a channel‐level model of the core thermal hydraulics with subcooled boiling correlations, a one‐dimensional model of the primary and secondary circuits including pumps, steam generators, heat exchangers, and the turbine with all their associated control loops, and a complete simulation of the reactor control, limitation, and protection system working in closed‐loop conditions as a faithful representation of the real power plant. In the present paper, a description of the coupling scheme between the codes involved is given, and some examples of their application to Atucha II are shown.
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10.1155_2011_785304.pdf
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Additional details
Identifiers
- DOI
- 10.1155/2011/785304;
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations
- Journal Volume
- 2011
- Journal Issue
- 1
- ISSN
- 1687-6075
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- APPROXIMATIONS; ATUCHA-2 REACTOR; COMPUTERIZED SIMULATION; CONTROL SYSTEMS; HEAT EXCHANGERS; HYDRAULICS; NEUTRONS; NUCLEAR POWER PLANTS; POWER DISTRIBUTION; REACTOR CONTROL SYSTEMS; REACTOR KINETICS; REACTOR STABILITY; STEAM GENERATORS; THERMAL HYDRAULICS; TOOLS; TRANSIENTS
- Descriptors DEC
- BARYONS; BOILERS; CALCULATION METHODS; CONTROL SYSTEMS; ELEMENTARY PARTICLES; EQUIPMENT; FERMIONS; FLUID MECHANICS; HADRONS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; HYDRAULICS; KINETICS; MECHANICS; NATURAL URANIUM REACTORS; NUCLEAR FACILITIES; NUCLEONS; PHWR TYPE REACTORS; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SIMULATION; STABILITY; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS
Optional Information
- Copyright
- © Author(s)
- Notes
- Record automatically processed