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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.
Juan M. Cajigas
Nuclear Technology | Volume 90 | Number 3 | June 1990 | Pages 316-325
Technical Paper | RELAP/MOD2 / Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34397
Articles are hosted by Taylor and Francis Online.
A version of the RELAP/MOD2 code has been developed to allow the direct calculation of hydrodynamic piping load histories. The code allows the calculation of piping forcing functions within the same computer run used to evaluate the transient thermofluid conditions. A description of this code, RELAP5-FORCE MOD2 is provided. The accuracy and validity of RELAP5-FORCE MOD2 are demonstrated by comparisons to benchmark test data.
