LEU-HEU Mixed Core Conversion Thermal-hydraulic Analysis and Coolant System Upgrade Assessment for the MIT Research Reactor
The MIT Research Reactor (MITR) is in the process of converting from the current 93%-enriched U-235 highly-enriched uranium (HEU) fuel to the low enriched uranium (LEU, <20%-enriched U-235) fuel, as part of the global non-proliferation initiatives. A high-density, monolithic uraniummolybdenum (U-...
Main Author: | Zhao, Yinjie |
---|---|
Other Authors: | Hu, Lin-Wen |
Format: | Thesis |
Published: |
Massachusetts Institute of Technology
2023
|
Online Access: | https://hdl.handle.net/1721.1/147212 |
Similar Items
-
Evaluation of the Thermal-Hydraulic Operating Limits of HEU-LEU Transition Cores for the MIT Research Reactor
by: Wan, Yunzhi, et al.
Published: (2012) -
Evaluation of the thermal-hydraulic operating limits of the HEU-LEU transition cores for the MIT Research Reactor
by: Wang, Yunzhi (Yunzhi Diana)
Published: (2010) -
Thermal hydraulics analysis of the MIT research reactor in support of a low enrichment uranium (LEU) core conversion
by: Ko, Yu-Chih, Ph. D. Massachusetts Institute of Technology
Published: (2009) -
Thermal hydraulic mixing transients in the MIT research reactor core tank
by: Hu, Lin-Wen
Published: (2005) -
Development of a core design optimization tool and analysis in support of the planned LEU conversion of the MIT Research Reactor (MITR-II)
by: Connaway, Heather M. (Heather Moira)
Published: (2013)