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Use of Response Surface for Evaluation of Functional Failure of Passive Safety System
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2010-03)
Passive safety systems are more vulnerable to their environment and initial condition due to
the typical low driving forces, e.g., that of the natural circulation. We investigate the merits
of different methods for ...
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 ...
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 ...
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 ...
General Analysis of Breed-and-Burn Reactors and Limited-Separations Fuel Cycles
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2011-02)
A new theoretical framework is introduced, the “neutron excess” concept, which is useful
for analyzing breed-and-burn (B&B) reactors and their fuel cycles. Based on this concept, a
set of methods has been developed which ...
Vented Inverted Fuel Assembly Design for an SFR
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2011-06)
The goal of this work is to investigate the feasibility of a vented inverted fuel
assembly for a sodium-cooled fast reactor. The inverted geometry has been
previously investigated for application in Gas-cooled Fast ...
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 ...