Low Enriched Uranium Core Design for the Massachusetts Institute of Technology Reactor (MITR) with Un-finned 12 mil-thick Clad UMo Monolithic Fuel
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
This report contains the results of reactor fuel element design for conversion of the Massachusetts Institute of Technology Reactor (MITR) from the use of highly enriched uranium (HEU) fuel to the use of low enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL) and the Massachusetts Institute of Technology Nuclear Reactor Laboratory. The core conversion to LEU is being performed with financial support of the U.S. government.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1110489
- Report Number(s):
- ANL/GTRI/TM--13/15
- Country of Publication:
- United States
- Language:
- ENGLISH
Similar Records
Preliminary Accident Analyses for Conversion of the Massachusetts Institute of Technology Reactor (MITR) from Highly Enriched to Low Enriched Uranium
Irradiation Experiment Conceptual Design Parameters for MITR LEU U-Mo Fuel Conversion
Comparison and validation of HEU and LEU modeling results to HEU experimental benchmark data for the Massachusetts Institute of Technology MITR reactor.
Technical Report
·
Mon Sep 30 00:00:00 EDT 2013
·
OSTI ID:1114108
Irradiation Experiment Conceptual Design Parameters for MITR LEU U-Mo Fuel Conversion
Technical Report
·
Sat Jun 01 00:00:00 EDT 2013
·
OSTI ID:1087826
Comparison and validation of HEU and LEU modeling results to HEU experimental benchmark data for the Massachusetts Institute of Technology MITR reactor.
Technical Report
·
Thu Dec 09 23:00:00 EST 2010
·
OSTI ID:1008287