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Innovative Analysis Techniques for Canadian SCWR Neutronics

Knowledge of the effects of nuclear data uncertainties and physics approximations is crucial
for the development, design, operation, and accident mitigation, of nuclear power
plants. A framework to create a simulated fuel bundle, based on sensitivities and similarities,
has been developed. The methodology allows safe-to-handle fuel to be manufactured
such that it mimics irradiated fuel and can be used to reduce simulation uncertainties and
better predict an application’s response. In this work, similarity values of ck = 0.967,
E = 0.992, and G = 0.891 were found between between the irradiated fuel, and non-irradiated
simulated fuel. In addition, a set of ZED-2 experiments has been analyzed
that are applicable to an SCWR nuclear data adjustment and simulation bias determination.
This was shown through high sensitivity coverage of many important nuclides,
however, a low completeness value of R=0.24 indicates the set of 39 experiments alone is
not sufficient for an accurate bias determination. Lastly, a technique has been presented
that reduces diffusion calculation errors through the use of novel and practical mean
discontinuity factors. The discontinuity factors have shown to reduce maximum channel
power errors by up to 6.7%, and reactivity errors by 2.6 mk, compared to conventional
analysis techniques. / Thesis / Doctor of Philosophy (PhD) / Use of practical discontinuity factors has shown to reduce channel power predictions significantly. Furthermore, an experimental and numerical technique has been developed to improve neutron transport predictions. Finally, a set of experiments have been modeled and simulated to determine their applicability to the SCWR.

Identiferoai:union.ndltd.org:mcmaster.ca/oai:macsphere.mcmaster.ca:11375/22064
Date11 1900
CreatorsSharpe, Jason
ContributorsBuijs, Adriaan, Engineering Physics
Source SetsMcMaster University
LanguageEnglish
Detected LanguageEnglish
TypeThesis

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