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Now showing items 11-20 of 109
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 ...
Application of the Technology Neutral Framework to Sodium-Cooled Fast Reactors
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2011-09)
Sodium cooled fast reactors (SFRs) are considered as a novel example to exercise the Technology Neutral Framework (TNF) proposed in NUREG-1860. One reason for considering SFRs is that they have historically had a licensing ...
Nuclear Energy for Variable Electricity and Liquid Fuels Production: Integrating Nuclear with Renewables, Fossil Fuels, and Biomass for a Low- Carbon World
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2011-09)
The world faces two energy challenges: (1) the national security and economic challenge of
dependence on foreign oil and (2) the need to reduce carbon dioxide emissions from the burning
of fossil fuels to avoid climate ...
Nuclear Energy for Simultaneous Low-Carbon Heavy-Oil Recovery and Gigawatt-Year Heat Storage for Peak Electricity Production
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2010-12)
In a carbon-constrained world or a world of high natural gas prices, the use of fossil-fueled power
plants to satisfy variable electricity demands may be limited. Nuclear power plants operating at
full capacity with ...
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 ...
Conceptual Design of Nuclear-Geothermal Energy Storage Systems for Variable Electricity Production
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2011-06)
Nuclear plants have high capital costs and low operating costs that favor base-load
operation. This characteristic of nuclear power has been a critical constraint that limits
the portion of nuclear power plants in a grid ...
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 ...
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 ...
Investigation of Pressure-Tube and Calandria-Tube Deformation Following a Single Channel Blockage Event in ACR-700
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2005-11)
The ACR-700 is an advanced pressure-tube (PT) reactor being developed by Atomic Energy of Canada Limited (AECL). As in conventional CANDU reactors, the PTs are horizontal. Each PT is surrounded by a calandria tube (CT), ...
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 ...