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Selection of Correlations and Look-Up Tables for Critical Heat Flux Prediction in the Generation IV "IRIS" Reactor
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2000-06)
In order to fulfill the goals set forth by the Generation IV International Forum, the current NERI funded
research has focused on the design of a Gas-cooled Fast Reactor (GFR) operating in a Breed and Burn
(B&B) fuel ...
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 ...
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 ...
Vented Inverted Fuel Assembly Design for an SFR
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2011-06)
The goal of this work is to investigate the feasibility of a vented inverted fuel
assembly for a sodium-cooled fast reactor. The inverted geometry has been
previously investigated for application in Gas-cooled Fast ...
Flexible Conversion Ratio Fast Reactor Systems Evaluation Final Report
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2008-06)
Executive Summary:
The goal of this project is to develop the conceptual designs of fast flexible conversion
ratio reactors using lead and liquid salt coolants and to compare the results with a gascooled fast reactor ...
Alternative Fuel Cycle Strategies For Nuclear Power Generation In The 21st Century
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2005-06-01)
The deployment of fuel recycling through either CONFU (COmbined Non-Fertile and UO[subscript 2]
fuel) thermal water-cooled reactors (LWRs) or fast ABR (Actinide Burner Reactor) reactors is
compared to the Once-Through ...
Plant Design and Cost Assessment of Forced Circulation Lead-Bismuth Cooled Reactor with Conventional Power Conversion Cycles
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2001-09)
Cost of electricity is the key factor that determines competitiveness of a power plant. Thus the proper selection, design and optimization of the electric power generating cycle is of main importance. This report makes an ...
FUEL PERFORMANCE ANALYSIS OF EXTENDED OPERATING CYCLES IN EXISTING LWRs
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 1998-01)
An integral part of a technical analysis of a core design, fuel performance is
especially important for extended operating cycles since the consequences of failed fuel
are greater for this operating strategy than for ...