Evaluation of the Thermal-Hydraulic Operating Limits of HEU-LEU Transition Cores for the MIT Research Reactor

Evaluation of the Thermal-Hydraulic Operating Limits of HEU-LEU Transition Cores for the MIT Research Reactor

The MIT Research Reactor (MITR) is in the process of conducting a design study to convert from High Enrichment Uranium (HEU) fuel to Low Enrichment Uranium (LEU) fuel. The currently selected LEU fuel design contains 18 plates per element, compared to the existing HEU design of 15 plates per eleme...

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Bibliographic Details
Main Authors:	Wan, Yunzhi, Hu, Lin-Wen
Other Authors:	MIT Reactor Redesign Program
Format:	Technical Report
Published:	Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program 2012
Online Access:	http://hdl.handle.net/1721.1/75085

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