Papers

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Recent Developments in the OpenMC Monte Carlo Particle Transport Code

Paul K. Romano (ANL), Patrick C. Shriwise (ANL), Sterling M. Harper (TerraPower), Andrew E. Johnson (Ultra Safe Nuclear Corp.), Amanda L. Lund (ANL), Jingang Liang (Tsinghua Univ.), John R. Tramm (ANL), Andrew Davis (Culham Centre for Fusion Energy), Daniel Short (Culham Centre for Fusion Energy), Younghui Park (Univ. Wisconsin, Madison)

Automatic Conversion of MCNP Geometries to TRIPOLI-4®

Davide Mancusi (CEA)

Verification of OpenMC Neutronic Code for Transuranic Waste Incineration in Reduced Moderation Boiling Water Reactor

Sivakorn Sansawas (King Mongkut's Univ. Technology Thonburi), Saksorn Ruangtanusak (King Mongkut's Univ. Technology Thonburi), Yanin Sukjai (King Mongkut's Univ. Technology Thonburi)

Pre-Release Validation Database for the Multi-Dimensional Fuel Performance Code OFFBEAT

A. Scolaro (École Polytechnique Fédérale de Lausanne), C. Fiorina (École Polytechnique Fédérale de Lausanne), I. Clifford (Paul Scherrer Institute), E. Brunetto (École polytechnique fédérale de Lausanne), A. Pautz (Paul Scherrer Institute)


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