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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.
Yassin A. Hassan
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 388-392
Technical Note | Fission Reactor | doi.org/10.13182/NT85-A33620
Articles are hosted by Taylor and Francis Online.
Comparisons of the predictions of the best-estimate pressurized water reactor TRAC-PF1/MOD1 computer code to data of the General Electric level swell tests were performed. Various time-step sizes and nodalization schemes were employed. With appropriate time-step size, void fraction distributions predicted by TRAC compared favorably with the void fractions inferred from the measured data. Nonphysical oscillations in spatial void profiles were observed when a large time step was used. Comparisons of TRAC predictions with results obtained using three codes of the RELAP family were performed.