DDE-MITR Status Report of Conceptual Design Activities

Woolstenhulme, N.E. ; Nielson, R.B. ; Wiest, J.D. ; Nielsen, J.W. ; Roth, G.A. ; Snow, S.D.

Idaho National Laboratory

关键词: 11 Nuclear Fuel Cycle And Fuel Materials Dde;    Leu;    Rertr;    Dde;   

DOI  :  10.2172/1058074
RP-ID  :  INL/EXT-12-27077
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1058074

美国|英语

来源: UNT Digital Library

【 摘 要 】

The Design Demonstration Experiment for the Massachusetts Institute of Technology Reactor (DDE-MITR) is intended to facilitate Low Enriched Uranium (LEU) conversion of the MITR by demonstrating the performance and fabrication of the LEU fuel element design through an irradiation test in the Advanced Test Reactor center flux trap. At the time this report was prepared the resources for furthering DDE design work were expected to be postponed. As such, the conceptual design effort to date is summarized herein in order to provide the status of key objectives, notable results, and provisions for future design work. These demonstrate that the DDE-MITR design effort is well on the path to producing a suitable irradiation experiment, but also exhibits several challenges for which timely resolution is recommend in order to facilitate success of the irradiation campaign and ultimate conversion of the MITR.