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The impact of americium on the ULOF and UTOP transients of the European Lead-cooled SYstem (ELSY)
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.ORCID iD: 0000-0002-6082-8913
2012 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 47, 104-109 p.Article in journal (Refereed) Published
Abstract [en]

The Unprotected Loss-of-Flow (ULOF) transient and the Unprotected Transient-Over-Power (UTOP) have been evaluated for the European Lead-cooled SYstem (ELSY) for americium concentrations in the fuel between 0% and 10%. With americium in the core, the ELSY design exceeds the maximum allowed asymptotic temperature limit for fuel during UTOP, except for low Am contents. During ULOF, fuel and clad temperatures stabilize below the asymptotic temperature limits.

Place, publisher, year, edition, pages
2012. Vol. 47, 104-109 p.
Keyword [en]
Asymptotic temperature, ELSY, LFR, ULOF, UTOP
National Category
Other Physics Topics
Identifiers
URN: urn:nbn:se:kth:diva-100193DOI: 10.1016/j.anucene.2012.03.036ISI: 000306448800015Scopus ID: 2-s2.0-84861123057OAI: oai:DiVA.org:kth-100193DiVA: diva2:542969
Note
QC 20120817Available from: 2012-08-06 Created: 2012-08-06 Last updated: 2017-12-07Bibliographically approved
In thesis
1. Science and Technology for Americium Transmutation
Open this publication in new window or tab >>Science and Technology for Americium Transmutation
2012 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

Americium could be seen as the most troublesome element that is presentin nuclear fuel. This thesis offers different points of view on the possibility ofamericium transmutation. The first point of view elaborates simulations ofamericium-bearing facilities, namely nuclear data, a popular computationalcode and modeling techniques. The second point of view is focused on practicalusage of the simulations to examine upper limit of americium in a specificreactor.

Abstract [sv]

Americium är ett av det mest besvärande elementen i använt kärnbränsle.Denna avhandling behandlar olika aspekter av möjligheten att transmuteraamericium i snabba reaktorsystem. I den första varianten utarbetas simuleringaroch beräkningsmodeller för neutrondatamätningar av betydelse föracceleratordrivna system avsedda att transmutera americium. I den senareundersöks mer praktiska tillämpningar, i synnerhet beräknas gränser för hurmycket americium som kan laddas i bränslet för kritiska bykylda reaktorer.

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2012. xii, 62 p.
Series
TRITA-FYS, ISSN 0280-316X ; 2012:21
National Category
Other Physics Topics
Identifiers
urn:nbn:se:kth:diva-100186 (URN)978-91-7501-326-8 (ISBN)
Public defence
2012-08-17, F3, Lindstedtsvägen 26, KTH, Stockholm, 13:00 (English)
Opponent
Supervisors
Note

QC 20120806

Available from: 2012-08-06 Created: 2012-08-06 Last updated: 2017-03-02Bibliographically approved

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Wallenius, Janne

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