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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 ...
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 ...
Effects of Surface Parameters on Boiling Heat Transfer Phenomena
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2011-06)
Nanofluids, engineered colloidal dispersions of nanoparticles in fluid, have been shown
to enhance pool and flow boiling CHF. The CHF enhancement was due to nanoparticle
deposited on the heater surface, which was verified ...
Conceptual Design of an Annular-Fueled Superheat Boiling Water Reactor
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2010-10)
The conceptual design of an annular-fueled superheat boiling water reactor (ASBWR) is
outlined. The proposed design, ASBWR, combines the boiler and superheater regions into
one fuel assembly. This ensures good neutron ...
Design of a Functionally Graded Composite for Service in High Temperature Lead and Lead-Bismuth Cooled Nuclear Reactors
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2010-10)
A material that resists lead-bismuth eutectic (LBE) attack and retains its strength at 700°C
would be an enabling technology for LBE-cooled reactors. No single alloy currently exists
that can economically meet the required ...
Comparison Between Air and Helium for Use as Working Fluids in the Energy-Conversion Cycle of the MPBR
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Advanced Nuclear Power Program, 2011-02)
A comparison between air and helium for use as working fluids in the energy-conversion cycle of the MPBR is presented. To date, helium has been selected in the MPBR indirect-cycle working reference design. Air open- and ...