Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
8068307 | Annals of Nuclear Energy | 2015 | 13 Pages |
Abstract
The approach is demonstrated by performing an eigenvalue and power distribution calculation of a typical three-dimensional 17Â ÃÂ 17 assembly with thermal-hydraulic and fuel temperature feedback. All neutronics aspects of the problem (cross-section calculation, neutron transport, power release) are solved using the Insilico code suite and are fully coupled to a thermal-hydraulic analysis calculated by the Cobra-TF (CTF) code. The single-executable coupled-code (Insilico-CTF) simulation tool is created using several VERA tools, including LIME (Lightweight Integrating Multiphysics Environment for coupling codes), DTK (Data Transfer Kit), Trilinos, and TriBITS. Parallel calculations are performed on the Titan supercomputer at Oak Ridge National Laboratory using 1156 cores, and a synopsis of the solution results and code performance is presented. Ongoing development of this approach is also briefly described.
Keywords
Consortium for Advanced Simulation of Light Water Reactorst/hASCIIJFNKCTFCASLBWRORNLPWRXSLTVERA-CSOak Ridge National LaboratoryXMLCRUDCFDComputational fluid dynamicsBoiling water reactorGraphical user interfaceGUIPressurized Water Reactorextensible markup languageThermal–hydraulicVeraMultiphysicsAmerican standard code for information interchange
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
Rodney Schmidt, Kenneth Belcourt, Russell Hooper, Roger Pawlowski, Kevin Clarno, Srdjan Simunovic, Stuart Slattery, John Turner, Scott Palmtag,