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Now showing items 11-19 of 19
A Unified Risk-Informed Framework to Assess the Proliferation Risk and License the Proliferation Performace of Nuclear Energy
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2011-09)
In order to strengthen the current non-proliferation regime it is necessary to guarantee high standards of security for the sites that use, store, produce, or reprocess special nuclear materials (SNM). The current surge ...
PWR Cores with Silicon Carbide Cladding
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2011-04)
The use in present generation PWRs of fuel clad with silicon carbide rather than Zircaloy
has been evaluated as an aid to reaching higher discharge burnups and to operation at higher
reactor power levels. A preliminary ...
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 ...
A Drop-In Concept for Deep Borehole Canister Emplacement
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2011-06)
Disposal of high-level nuclear waste in deep boreholes drilled into crystalline bedrock (i.e.,
“granite”) is an interesting repository alternative of long standing. Work at MIT over the past
two decades, and more recently ...
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 ...
Estimate of Radiation Release from MIT Reactor with Low Enriched Uranium (LEU) Core During Maximum Hypothetical Accident
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program, 2011-06-01)
In accordance with a 1986 NRC ruling, the MIT Research Reactor (MITR) is planning on
converting from the use of highly enriched uranium (HEU) to low enriched uranium
(LEU) for fuel. A component of the conversion analysis ...
Feasibility of Very Deep Borehole Disposal of US Nuclear Defense Wastes
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program, 2011-06)
This report analyzes the feasibility of emplacing DOE-owned defense nuclear waste from
weapons production into a permanent borehole repository drilled ~4 km into granite
basement rock. Two canister options were analyzed ...
Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Light Water Reactor Environments
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program, 2011-09)
Stress corrosion cracking (SCC) susceptibility of Inconel Alloy X-750 in the HTH condition has been evaluated in high purity water at 93 and 288°C under Boiling Water Reactor Normal Water Chemistry (NWC) and Hydrogen Water ...
Conceptual Design of Molten Salt Loop Experiment for MIT Research Reactor
(Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. MIT Reactor Redesign Program, 2011-08-01)
Molten salt is a promising coolant candidate for Advanced High Temperature Reactor (AHTR) Gen-IV designs. The low neutron absorption, high thermal capacity, chemical inertness, and high boiling point at low pressure of ...