Thermal hydraulic limits analysis for the MIT Research Reactor low enrichment uranium core conversion using statistical propagation of parametric uncertainties

Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012. === Cataloged from PDF version of thesis. === Includes bibliographical references. === The MIT Research Reactor (MITR) is evaluating the conversion from highly enriched uranium (HEU) to low enrichme...

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Bibliographic Details
Main Author: Chiang, Keng-Yen
Other Authors: Lin-Wen Hu and Benoit Forget.
Format: Others
Language:English
Published: Massachusetts Institute of Technology 2013
Subjects:
Online Access:http://hdl.handle.net/1721.1/77069