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High Performance Fuel Design for Next Generation PWRs: Final Report
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2006-01)
This summary provides an overview of the results of the U.S. DOE funded NERI
(Nuclear Research Energy Initiative) program on development of the internally and
externally cooled annular fuel for high power density PWRs. ...
High Performance Fuel Design for Next Generation PWRs Appendices B-I to FY-02 Annual Report
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2003-08)
B.1.1 VIPRE modeling of PWR core with annular fuel:
Optimization studies in the first year used an isolated channel and models for MDNBR analyses. These analyses provided sufficient knowledge of potential thermal hydraulic ...
An Alternative to Gasoline: Synthetic Fuels from Nuclear Hydrogen and Captured CO[subscript 2]
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2007-04-01)
The motivation for this study stems from two concerns. The first is that carbon dioxide from
fossil fuel combustion is the largest single human contribution to global warming. The use of
nuclear power to produce hydrogen ...
Plant Design and Cost Estimation of a Natural Circulation Lead-Bismuth Reactor with Steam Power Conversion Cycle
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2000-08)
The analysis of an indirect steam power conversion system with lead-bismuth natural circulation primary system has been performed. The work of this report is focused on 1) identifying the allowable design region for the ...
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 ...
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 ...
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 ...
Plant Design and Cost Estimation of a Natural Circulation Lead-Bismuth Reactor with Helium Power Conversion Cycle
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2000-11)
The analysis of an indirect helium power conversion system with lead-bismuth natural circulation primary system has been performed. The work of this report is focused on 1) identifying the allowable design region for the ...
NEUTRONIC AND THERMAL HYDRAULIC DESIGNS OF ANNULAR FUEL FOR HIGH POWER DENSITY BWRS
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2004-12)
As a promising new fuel for high power density light water reactors, the feasibility of using annular fuel for BWR services is explored from both thermal hydraulic and neutronic points of view. Keeping the bundle size ...