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LOOP STUDIES ADDRESSING THE HYDRAULIC IMPACT FROM THE PRESENCE OF PART-LENGTH FUEL RODS WITHIN A BWR FUEL ELEMENT, USING WATER AND AIR-WATER MIXTURES AT ROOM TEMPERATURE AND LOW PRESSURE
KTH, School of Engineering Sciences (SCI), Physics, Reactor Technology.
KTH, School of Engineering Sciences (SCI), Physics, Reactor Technology.
2008 (English)In: ICONE16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 3, NEW YORK: AMER SOC MECHANICAL ENGINEERS , 2008, 301-308 p.Conference paper, Published paper (Refereed)
Abstract [en]

There are a number of reactivity incidents which could possibly occur at low pressure in boiling water reactor (BWR) cores, and some of them may cause local boiling entailing reactivity feed-back. Unfortunately, theoretical studies of events of this nature are somewhat hampered by the dearth of knowledge about the thermal-hydraulics involved. The research presented here addresses one particular aspect of this issue: how is BWR core thermal-hydralics - at low pressure - affected in such fuel assemblies where some full-length rods have been replaced by part-length rods?

Place, publisher, year, edition, pages
NEW YORK: AMER SOC MECHANICAL ENGINEERS , 2008. 301-308 p.
National Category
Engineering and Technology
Identifiers
URN: urn:nbn:se:kth:diva-38660DOI: 10.1115/ICONE16-48235ISI: 000260916100034ISBN: 978-0-79184-816-6 (print)OAI: oai:DiVA.org:kth-38660DiVA: diva2:448415
Conference
16th International Conference on Nuclear Engineering, Orlando, FL, MAY 11-15, 2008
Note
QC 20111017Available from: 2011-10-17 Created: 2011-08-31 Last updated: 2011-10-17Bibliographically approved

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