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Analysis Of Flow Instabilities In Supercritical Watercooled Nuclear Reactors
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2004-09)
Near the supercritical thermodynamic point, coolant density is very sensitive to
temperature which gives potential to several instabilities in the supercritical water-cooled
nuclear reactors. The flow stability features ...
Conceptual Design of a Lead-Bismuth Cooled Fast Reactor with In-Vessel Direct-Contact Steam Generation
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2001-03)
The feasibility of a lead-bismuth (Pb-Bi) cooled fast reactor that eliminates the need for steam generators and coolant pumps was explored. The working steam is generated by direct contact vaporization of water and liquid ...
Use of Information Theory Techniques with System Dynamics Models
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2005-09)
Research was done to show how the output distribution of a system with random variables changes as the input distributions and other parameters are changed. Using Information Theory techniques, these different input and ...
Uncertainty And Sensitivity Analysis For Long-Running Computer Codes: A Critical Review
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2010-01)
Thermal Hydraulic and Economic Analysis of Grid-Supported Hydride and Oxide Fueled PWRs
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2006-09)
This report advances the Hydride Fuels Project, a collaborative effort between UC
Berkeley and MIT aimed at investigating the potential benefits of hydride fuel use in
light water reactors (LWRs). This effort involves ...
Feasibility of Partial ZrO[subscript 2] Coatings on Outer Surface of Annular UO[subscript 2] Pellets to Control Gap Conductance
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2005-06)
The viability of depositing a thin porous coating of zirconia on the outer surface of an annular UO[subscript 2] pellet
is investigated experimentally. Such a layer has been proposed to buffer the contact between the fuel ...
MCODE, Version 2.2: An MCNP-ORIGEN DEpletion Program
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2008-12)
MCODE Version 2.2 is a linkage program, which combines the continuous-energy
Monte Carlo code, MCNP-4C, and the one-group depletion code, ORIGEN2, to perform
burnup calculations for nuclear fission reactor systems. MCNP ...
Stability Analysis of Natural Circulation in BWRs at High Pressure Conditions
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2007-10)
At rated conditions, a natural circulation boiling water reactor (NCBWR) depends
completely on buoyancy to remove heat from the reactor core. This raises the issue of
potential unstable flow oscillations. The objective ...
Wire Wrapped Hexagonal Pin Arrays for Hydride Fueled PWRs
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2006-01)
This work contributes to the Hydride Fuels Project, a collaborative effort between UC Berkeley and MIT
aimed at investigating the potential benefits of hydride fuel use in light water reactors (LWRs). Core
design is ...
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 ...