Date of Award
January 2015
Degree Type
Dissertation
Degree Name
Doctor of Philosophy (PhD)
Department
Nuclear Engineering
First Advisor
Mamoru Ishii
Committee Member 1
Takashi Hibiki
Committee Member 2
Martin Lope-de- Bertodano
Committee Member 3
Steven Wereley
Abstract
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.
Recommended Citation
Cheng, Ling, "Evaluation of the Safety Systems in the Next Generation Boiling Water Reactor" (2015). Open Access Dissertations. 1176.
https://docs.lib.purdue.edu/open_access_dissertations/1176