Search
Now showing items 1-7 of 7
Design of a Low Enrichment, Enhanced Fast Flux Core for the MIT Research Reactor
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program, 2009-02-01)
Worldwide, there is limited test reactor capacity to perform the required irradiation
experiments on advanced fast reactor materials and fuel designs. This is particularly true
in the U.S., which no longer has an operating ...
Developing Fuel Management Capabilities Based On Coupled Monte Carlo Depletion in Support of the MIT Research Reactor Conversion
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program, 2009-06-01)
Pursuant to a 1986 NRC ruling, the MIT Reactor (MITR) is planning on converting from
the use of highly enriched uranium (HEU) to low enriched uranium (LEU) for fuel. Prior
studies have shown that the MITR will be able ...
Evaluation of the Thermal-Hydraulic Operating Limits of HEU-LEU Transition Cores for the MIT Research Reactor
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program, 2009-05-01)
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 ...
A Benchmark Study of Computer Codes for System Analysis of the Nuclear Fuel Cycle
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2009-04)
As use of nuclear energy is expected to expand in different parts of the world, several codes that
describe the nuclear fuel cycle system are currently under development, featuring a range of
capabilities and different ...
Impact of Alternative Nuclear Fuel Cycle Options on Infrastructure and Fuel Requirements, Actinide and Waste Inventories, and Economics
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2009-09)
The nuclear fuel once-through cycle (OTC) scheme currently practiced in the U.S. leads
to accumulation of uranium, transuranic (TRU) and fission product inventories in the
spent nuclear fuel. Various separation and ...
UPDATE ON THE COST OF NUCLEAR POWER
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2009-05)
We update the cost of nuclear power as calculated in the MIT (2003) Future of
Nuclear Power study. Our main focus is on the changing cost of construction of new
plants. The MIT (2003) study provided useful data on the ...
Thermal-Hydraulic Analysis of Innovative Fuel Configurations for the Sodium Fast Reactor
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2009-08)
The sodium fast reactor (SFR) is currently being reconsidered as an instrument for
actinide management throughout the world, thanks in part to international programs such
as the Generation-IV and especially the Global ...