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Zeyun NMN Wu, Robert E. Williams, J. Michael Rowe, Thomas Henderson Newton, Sean O'Kelly
This paper presents the neutronics and thermal-hydraulics safety analysis results for an LEU-fueled research reactor concept being designed and studied at NIST
A new method is described for thermodynamic calculations of a two-phase thermosyphon loop based on a one-dimensional finite element division, where each time
Robert E. Williams, Michael Middleton, Paul Kopetka, J. Michael Rowe, Paul C. Brand
The NBSR is a 20 MW research reactor operated by the NIST Center for Neutron Researcher (NCNR) as a neutron source providing beams of thermal and cold neutrons
Preliminary design basis accident analyses have been performed on the proposed split core to examine the thermal-hydraulics (T/H) safety characteristics of the