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Preliminary transient analysis of the Autonomous Reactivity Control system for fast reactors
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.
2015 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 77, 47-64 p.Article in journal (Refereed) Published
Abstract [en]

A preliminary parametric dynamic response study of the Autonomous Reactivity Control (ARC) system is performed for a large fast reactor core subjected to the following postulated design-extension accident scenarios: unprotected overpower (UTOP), unprotected loss of flow (ULOF) and unprotected loss of heat sink (ULOHS). The results show that the ARC system could prevent fuel and cladding failure as well as coolant boiling during UTOP and can lower transient temperatures during ULOHS. However, in case of ULOF, the design space examined the ARC system did not prevent exceeding permissible cladding temperature and introduced instability. A more thorough analysis is recommended.

Place, publisher, year, edition, pages
2015. Vol. 77, 47-64 p.
Keyword [en]
Sodium fast reactor, Inherent safety, Reactivity feedback, Transient analysis
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Identifiers
URN: urn:nbn:se:kth:diva-161947DOI: 10.1016/j.anucene.2014.11.001ISI: 000349723400005Scopus ID: 2-s2.0-84911461867OAI: oai:DiVA.org:kth-161947DiVA: diva2:801058
Note

QC 20150408

Available from: 2015-04-08 Created: 2015-03-20 Last updated: 2017-12-04Bibliographically approved

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