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MARVEL team shares lessons learned through microreactor development
On June 1 at the American Nuclear Society’s Annual Conference in Denver, Colo., a team from Idaho National Laboratory presented a session titled “Lessons Learned from MARVEL Reactor Fabrication.” The presentation highlighted challenges that arose as they moved from design to manufacturing and assembly, with a focus on reactor part fabrication, Stirling engine implementation, and reactivity control system development.
Calvin C. Oliver, Edward T. Dugan
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 161-169
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33627
Articles are hosted by Taylor and Francis Online.
Thermodynamic and transport property predictions for UF6-He gas mixtures are presented covering the operating range of conceptual, circulating gas core nuclear systems. The gas mixtures of interest contain 10 to 20% helium by mass, which corresponds to helium mole fractions of 0.9 and higher. For UF6 partial pressure <10 atm and temperatures in the range of 500 to 2000 K, mixture density can be determined from the ideal gas equation of state with an uncertainty of <10%. Compared to pure UF6, the thermal conductivity of the mixtures is an order of magnitude greater; specific heat is doubled while viscosity is changed very little. For identical systems, it is shown that heat transfer rates for UF6-He mixtures are five to six times greater than for pure UF6.