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Analysis of Boiling Water Reactor Design and Operating Conditions Effect on Stability Behaviour
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
2011 (English)Independent thesis Advanced level (degree of Master (Two Years)), 20 credits / 30 HE creditsStudent thesis
Abstract [en]

It is well known that boiling water reactors can experience inadvertent power oscillations. When such instability occurs the core can oscillate in two different modes (in phase mode and out of phase mode). In the late 90’s a stability benchmark was created using the stability data obtained from the experiments at the Swedish nuclear power plant of Ringhals-1. Data was collected from the cycles 14, 15 , 16 and 17. Later on, this data was used to validate the various models and codes with the aim of predicting the instability behavior of the core and understand the triggers of such oscillations. The current trend of increasing reactor power density and relying on natural circulation for core cooling may have consequences for the stability of modern BWR’s designs. The objective of this work is to find the most important parameters affecting the stability of the BWRs and propose alternative stability maps. For this purpose a TRACE/PARCS model of the Ringhals-1 NPP will be used. Afterwards a selection of possible parameters and dimensionless numbers will be made to study its effect on stability. Once those parameters are found they will be included in the stability maps to make them more accurate.

Place, publisher, year, edition, pages
2011. , 38 p.
National Category
Mechanical Engineering Energy Engineering
URN: urn:nbn:se:kth:diva-42599OAI: diva2:447365
Subject / course
Reactor Safety
Educational program
Master of Science in Engineering -Engineering Physics
Available from: 2011-10-12 Created: 2011-10-11 Last updated: 2011-11-09Bibliographically approved

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