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Cross Section Generation Strategy for High Conversion Light Water Reactors
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2011-06)
High conversion water reactors (HCWR), such as the Resource-renewable Boiling Water Reactor
(RBWR), are being designed with axial heterogeneity of alternating fissile and blanket zones to
achieve a conversion ratio of ...
Feasibility of Breeding in Hard Spectrum Boiling Water Reactors with Oxide and Nitride Fuels
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2011-06-01)
This study assesses the neutronic, thermal-hydraulic, and fuel performance aspects of using
nitride fuel in place of oxides in Pu-based high conversion light water reactor designs. Using
the higher density nitride fuel ...
General Analysis of Breed-and-Burn Reactors and Limited-Separations Fuel Cycles
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2011-02)
A new theoretical framework is introduced, the “neutron excess” concept, which is useful
for analyzing breed-and-burn (B&B) reactors and their fuel cycles. Based on this concept, a
set of methods has been developed which ...
Design and Optimization of a High Thermal Flux Research Reactor Via Kriging-Based Algorithm
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program, 2011-06-01)
In response to increasing demands for the services of research reactors, a 5 MW LEUfueled
research reactor core is developed and optimized to provide high thermal flux
within specified limits upon thermal hydraulic ...
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 ...
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 ...
A Generalized Optimization Methodology for Isotope Management
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2010-09)
This research focuses on developing a new approach to studying the nuclear fuel cycle:
instead of employing the trial and error approach currently used in actinide management
studies in which reactors are designed and ...
Estimate of Radiation Release from MIT Reactor with Low Enriched Uranium (LEU) Core During Maximum Hypothetical Accident
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program, 2011-06-01)
In accordance with a 1986 NRC ruling, the MIT Research Reactor (MITR) is planning on
converting from the use of highly enriched uranium (HEU) to low enriched uranium
(LEU) for fuel. A component of the conversion analysis ...