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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 ...
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 ...
Hydrogen Production for Steam Electrolysis Using a Supercritical CO[subscript 2]- Cooled Fast Reactor
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Energy and Sustainability Program, 2007-02-01)
Rising natural gas prices and growing concern over CO[subscript 2] emissions have intensified interest in alternative
methods for producing hydrogen. Nuclear energy can be used to produce hydrogen through
thermochemical ...
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 ...
Actinide Minimization Using Pressurized Water Reactors
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2006-06)
Transuranic actinides dominate the long-term radiotoxicity in spent LWR fuel. In an open fuel
cycle, they impose a long-term burden on geologic repositories. Transmuting these materials in
reactor systems is one way to ...
A PWR Self- Contained Actinide Transmutation System
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2006-09)
Elements of the new Global Nuclear Energy Partnership (GNEP) initiative in the US call for the
expansion of domestic use of nuclear power and the minimization of nuclear waste. To achieve
both goals in the short term the ...
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 ...
Innovative Fuel Designs for High Power Density Pressurized Water Reactor
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2005-09)
One of the ways to lower the cost of nuclear energy is to increase the power density of
the reactor core. Features of fuel design that enhance the potential for high power density
are derived based on characteristics of ...
A System Dynamics Study of the Nuclear Fuel Cycle with Recycling: Options and Outcomes for the US and Brazil
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2008-11)
A system dynamics simulation technique is applied to generate a new version of the
CAFCA code to study mass flows in the nuclear fuel cycle, and the impact of different
options for advanced reactors and fuel recycling ...