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Analysis and Utilization of Operating Experience for Organizational Learning
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2001-06)
The objective of this report is to clarify the ways that organizational factors influence
nuclear power plant performance in order to improve performance. Therefore, this report
studied the nuclear power plant organizational ...
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. ...
CATILaC: Computer-Aided Technique for Identifying Latent Conditions User's Manual, Version 1.2
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2000-04)
A System Dynamics Model of the Energy Policymaking Process
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2002-08)
Electric energy is a fundamental commodity for any aspects of the modern world. However,
there are many uncertainties in the sources of electricity that are going to be used in the future. Some of these uncertainties are ...
A System Dynamics Model of the Energy Policymaking Process
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2002-08-01)
Electric energy is a fundamental commodity for any aspects of the modern world. However,
there are many uncertainties in the sources of electricity that are going to be used in the future. Some
of these uncertainties are ...
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 ...
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 ...
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 ...
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 ...