Date of Award

January 2015

Degree Type


Degree Name

Doctor of Philosophy (PhD)


Nuclear Engineering

First Advisor

Mamoru Ishii

Committee Member 1

Takashi Hibiki

Committee Member 2

Martin Lope-de- Bertodano

Committee Member 3

Steven Wereley


The thesis evaluates the safety systems in the next generation boiling water reactor by analyzing the main steam line break loss of coolant accident performed in the Purdue university multi-dimensional test assembly (PUMA). RELAP5 code simulations, both for the PUMA main steam line break (MSLB) case and for the simplified boiling water reactor (SBWR) MSLB case have been utilized to compare with the experiment data. The comparison shows that RELAP5 is capable to perform the safety analysis for SBWR. The comparison also validates the three-level scaling methodology applied to the design of the PUMA facility.