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Analytical Models of Critical Reactors in Simple Geometries
KTH, School of Engineering Sciences (SCI).
2010 (English)Independent thesis Basic level (degree of Bachelor), 10 credits / 15 HE creditsStudent thesis
Abstract [en]

This bachelor thesis presents an analytical approach to obtain neutron flux distribution function of a critical nuclear reactor in the multigroup approximation. We start with an overview of some basic reactor concepts and tackle the problem with a simple geometry of an infinite slab reactor, where we assume all neutrons to be monoenergetic. Thereafter, we successively treat a few more realistic cases, introducing a more complex geometry as well as several zones of a reactor. Gradually we arrive at two-group approximation evaluations of neutron flux distribution functions in a spherical reflected reactor.

Abstract [sv]

Detta kandidatarbete presenterar en analytisk ansats för att härleda neutronfördelnings-funktioner i en kritisk reaktor med multigrupp approximationer. Vi börjar med en översikt av några viktiga grundkoncept för kärnreaktorer och angriper problemet för en enkel geometri bestående av en oändlig reaktorskiva. Därefter behandlar vi stegvis några mer realistiska fall med komplexare geometrier och flera zoner i reaktorn. Gradvis kommer vi till en två-grupp approximation av neutronfördelningsfunktioner i fallet för en reflektorkläd reaktor.

Place, publisher, year, edition, pages
Trita-FYS, ISSN 0280-316X
National Category
Physical Sciences
URN: urn:nbn:se:kth:diva-32057ISRN: ISRN KTH/FYS/--10:19--SEOAI: diva2:408841
Educational program
Bachelor of Science in Engineering
Physics, Chemistry, Mathematics
Available from: 2012-04-19 Created: 2011-04-04 Last updated: 2012-04-19Bibliographically approved

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