High Flux Resistance Heating Rod

Case ID:
OSU-19-12
Web Published:
11/22/2019
Description:

Technology Description

This technology provides for improved simulation of nuclear reactor fuel rod pulsation for research and testing purposes. The device is a resistive heating filament capable of producing 2.5 MW/m2 of energy in a matter of tens of milliseconds with an outer diameter of less than a centimeter (0.9525 cm). This responsive heating element has minimal internal ceramic support structure which allows for rapid changes in thermal flux at the surface of the heating element.

Features & Benefits

  • Small diameter size (<1cm)
  • Rapid thermal energy creation (2.5 MW/m2)

Applications

  • Reactor testing and simulation
  • Where rapid changes in thermal flux are required

Background of Invention

With the renewed emphasis on the development of advanced reactor technologies, there is an interest in assessing the performance of materials under both normal operating conditions and during hypothesized incident scenarios. Use of nuclear test facilities can be prohibitively expensive and difficult to schedule. The ability to stress materials in a dynamic facility, with operating conditions similar to those of a nuclear reactor, without radiological concerns, is of great benefit to the entire nuclear community. Vendors who can produce necessarily small-sized (by diameter) cartridge heaters for this testing purpose struggle to provide power densities above 15 W/cm2 at a small form factor There is, therefore, a need within the nuclear fuels community for a tool that can produce appropriate power densities representative of an actual rod in an active fuel assembly.

Status

Patent pending. Seeking commercial partners.

   

Revised OSU prototype for heater rod, reduced scale

Patent Information:
For Information, Contact:
David Dickson
IP & Licensing Manager
Oregon State University
541-737-3450
david.dickson@oregonstate.edu
Inventors:
Daniel LaBrier
Wade Marcum
Jim Nylander
Aaron Weiss
Salem Sharaf
Keywords:
boiling
critical heat flux
nuclear
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