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Title: Massachusetts Institute of Technology Reactor LEU Fuel Element Flow Test Conceptual Design – Hydraulic Reactor Design Parameters

Technical Report ·
DOI:https://doi.org/10.2172/1820376· OSTI ID:1820376

The Massachusetts Institute of Technology Reactor (MITR-II, also referred to as MITR) is one of six U.S. high performance research reactors (USHPRR), including one critical facility, that is actively collaborating with the U.S. National Nuclear Security Administration (NNSA) Material Management and Minimization (M3) Reactor Conversion Program to convert to the use of low-enriched uranium (LEU, < 20 wt% 235U) fuel. The MIT Nuclear Reactor Laboratory has been working with the USHPRR Reactor Conversion (RC) Pillar at Argonne National Laboratory to perform fuel element design and fuel cycle performance analyses, steady-state thermal hydraulics safety analyses, and accident safety analyses in preparation for the conversion of MITR and support a preliminary Safety Analysis Report (SAR) for conversion to LEU fuel.

Research Organization:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Security
DOE Contract Number:
AC02-06CH11357
OSTI ID:
1820376
Report Number(s):
ANL/RTR/TM-21/17; 170828; TRN: US2301601
Country of Publication:
United States
Language:
English