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Showing 1 to 1 of 1 for “"next generation boiling water reactor"”.
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Evaluation of the Safety Systems in the Next Generation Boiling Water Reactor
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) …