One of two project reports: The other part is designated as Part A / <p> A fundamental and important part of nuclear reactor development
and analysis today is the study of neutronics following a breach
in the primary heat transport circuit. In the past, much of this
analysis has concentrated on the calculation of the thermalhydraulic
changes which occur following a loss of coolant accident and the effects
these subsequently have on neutron kinetics. The purpose of this
present study is to examine the influence of neutronic parameters on
the size and shape of power pulses which result from loss of coolant
accidents. The parameters studied are shutdown system delay times,
shutoff rod drop curves, and fuel burnup distribution. </p> / Thesis / Master of Engineering (MEngr)
| Identifer | oai:union.ndltd.org:mcmaster.ca/oai:macsphere.mcmaster.ca:11375/19230 |
| Date | January 1981 |
| Creators | McCormick, T.R. |
| Contributors | Dastur, A. R., Engineering Physics |
| Source Sets | McMaster University |
| Language | English |
| Detected Language | English |
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