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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.
Martin E. Nelson, Dean A. Miller, Peter F. Wiggins, Gordon Riel, Thomas D. Strickler
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 512-519
Technical Paper | Technique | doi.org/10.13182/NT85-A33703
Articles are hosted by Taylor and Francis Online.
A new approach is described in the use of NE-213 detectors to perform neutron spectra measurements, which have been developed jointly by the U.S. Naval Academy and the Naval Surface Weapons Center. The approach is based on collecting a three-dimensional matrix of neutron and gamma-ray data. The dimensional plots of the collected data, which are computer generated, are used to ensure proper separation of the neutrons from gamma rays. After separation, the spectra are calibrated, binned, renormalized, and finally unfolded. In this manner neutron energy spectra and kerma are obtained. Linear attenuation coefficients for 14-MeV neutrons were determined by placing iron, lead, aluminum, polyester, and polyethylene-based materials between the neutron source and the NE-213 detector.