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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.
Sandra M. Sloan, Yassin A. Hassan
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 177-182
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34344
Articles are hosted by Taylor and Francis Online.
The results generated from the IBM version of RELAP5/MOD2 are compared with the experimental data of an International Atomic Energy Agency standard problem exercise. The standard problem exercise data were that of a 7.4% break loss-of-coolant accident conducted at a test facility in Hungary. The United States did not formally participate in this exercise, whose aim was to assess the capabilities of computer codes and modeling techniques and in which a total of 17 organizations from 12 countries participated. The results obtained by execution of RELAP5/MOD2 on the IBM-3090 computer for upper plenum pressure, core inlet and outlet coolant temperature, and secondary-side pressure differed slightly during the latter part of the transient, but in general compared favorably to the experimental data. The magnitude of the cold-leg mass flow rate was underpredicted by the code.