APROS couplings from core to containment

Eija-Karita Puska, Jukka Ylijoki

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    Abstract

    APROS simulation environment is able to describe the1-D and 3-D neutronics of the reactor core. It is also able to describe the thermal hydraulics of the core and circuits either with 5-equation or 6-equation thermal hydraulics. It can also describe the plant automation and electrical systems, as well as the behaviour of the containment.

    The peculiar feature of APROS in comparison to other coupled systems is that all parts in the coupled system are described with the same code instead of coupling two or three separate codes together with information exchange between the separate codes. The most recent possibility is the coupled calculation of the process and the containment. The more traditional coupling, the coupling of the process containing both the process description and the automation description with more or less detailed description of the 3-D core either for safety analysis or real-time simulation purposes has been discussed in previous work, such as reference [1].

    The paper presents and discusses the capabilities of the code in coupling the plant process and automation description with the plant containment description with two example transient cases. An improved boron concentration solution with second order upwind discretisation has been recently included in APROS. An example on the increased accuracy acquired in the 3-D core model has been included.
    Original languageEnglish
    Title of host publicationMathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications
    PublisherAmerican Nuclear Society (ANS)
    Number of pages12
    Publication statusPublished - 2005
    MoE publication typeA4 Article in a conference publication
    EventMathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting, M&C 2005: 21st biennial topical meeting of the Mathematics and Computation Division of the American Nuclear Society (ANS) - Avignon, France
    Duration: 12 Sept 200515 Sept 2005

    Conference

    ConferenceMathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting, M&C 2005
    Country/TerritoryFrance
    CityAvignon
    Period12/09/0515/09/05

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