Thermal hydraulics analysis of the MIT research reactor in support of a low enrichment uranium (LEU) core conversion
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2008.
Main Author: | Ko, Yu-Chih, Ph. D. Massachusetts Institute of Technology |
---|---|
Other Authors: | Lin-wen Hu and Mujid S. Kazimi. |
Format: | Thesis |
Language: | eng |
Published: |
Massachusetts Institute of Technology
2009
|
Subjects: | |
Online Access: | http://hdl.handle.net/1721.1/44771 |
Similar Items
-
Thermal Hydraulic Analysis of a Low Enrichment Uranium Core for the MIT Research Reactor
by: Ko, Yu-Chih, et al.
Published: (2012) -
LEU-HEU Mixed Core Conversion Thermal-hydraulic Analysis and
Coolant System Upgrade Assessment for the MIT Research Reactor
by: Zhao, Yinjie
Published: (2023) -
Estimate of radiation release from MIT reactor with low enriched uranium (LEU) core during maximum hypothetical accident
by: Plumer, Kevin E. (Kevin Edward)
Published: (2013) -
Estimate of Radiation Release from MIT Reactor with Low Enriched Uranium (LEU) Core During Maximum Hypothetical Accident
by: Plumer, Kevin E., et al.
Published: (2012) -
Evaluation of the Thermal-Hydraulic Operating Limits of HEU-LEU Transition Cores for the MIT Research Reactor
by: Wan, Yunzhi, et al.
Published: (2012)