Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regu...
Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response
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Publisher
New York: Hindawi
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Language
English
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New York: Hindawi
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Contents
The use of the USNRC codes TRACE and PARCS has been considered for the coupled safety analysis of CANDU reactors. A key element of CANDU simulations is the interactions between thermal-hydraulic and physic phenomena with the CANDU reactor regulating system (RRS). To date, no or limited development has taken place in TRACE-PARCS in this area. In thi...
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Full title
Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response
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TN_cdi_doaj_primary_oai_doaj_org_article_711cff1c79c64027a4aefb99c9ef7fc9
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https://devfeature-collection.sl.nsw.gov.au/record/TN_cdi_doaj_primary_oai_doaj_org_article_711cff1c79c64027a4aefb99c9ef7fc9
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ISSN
1687-6075
E-ISSN
1687-6083
DOI
10.1155/2022/7500629
