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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.
M. P. Paulsen, B. E. Griebenow, L. R. Feinauer, J. H. McFadden, Peter J. Jensen
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 274-288
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34141
Articles are hosted by Taylor and Francis Online.
The RETRAN-02 transient thermal-hydraulic analysis program has found wide acceptance by the nuclear utility industry for performing analyses of operational transients and small-break loss-of-coolant accidents. There are, however, known limitations with RETRAN-02 and the Electric Power Research Institute has sponsored the development of RETRAN-03 to address these limitations. The major objectives of the development program are (a) to extend the range of analyses that can be performed with RETRAN, (b) to make the code more dependable and faster running, and (c) to have a more transportable code. Summaries of the RETRAN-02 models that have been modified for RETRAN-03, new models that have been added, and the new semi-implicit steady-state and dynamic solution methods are presented. The primary development task associated with improving the transportability of the code dealt with implementing the IBM and CDC environmental libraries (assembly language) using a common FORTRAN 77 source. The salient results of this work are discussed.