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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 ...
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 ...
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 ...
A Super Critical Carbon Dioxide Cycle for Next Generation Nuclear Reactors
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2004-03)
A systematic, detailed major component and system design evaluation and multiple-parameter optimization under practical constraints has been performed of the family of supercritical CO[subscript 2] Brayton power cycles for ...
Design of Compact Intermediate Heat Exchangers for Gas Cooled Fast Reactors
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2004-05)
Two aspects of an intermediate heat exchanger (IHX) for GFR service have been
investigated: (1) the intrinsic characteristics of the proposed compact printed circuit heat
exchanger (PCHE); and (2) a specific design ...
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 ...