TY - GEN
T1 - Coupling the core analysis program decart to the fuel performance application bison
AU - Gleicher, Frederick N.
AU - Spencer, Benjamin
AU - Novascone, Stephen
AU - Williamson, Richard
AU - Martineau, Richard C.
AU - Rose, Michael
AU - Downar, Thomas J.
AU - Collins, Benjamin
PY - 2013
Y1 - 2013
N2 - The 3D neutron transport and core analysis program DeCART was coupled to the fuels performance application BISON to provide a higher fidelity tool for fuel performance simulation. This project is motivated by the desire to couple a high fidelity core analysis program (based on the method of characteristics) to a high fidelity fuel performance program, both of which can simulate 3D problems. DeCART provides sub-pin level resolution of the multigroup neutron flux, with resonance treatment, during burnup or a fast transient. BISON implicitly solves coupled thermomechanical equations for the fuel on a sub-milimeter level finite element mesh. A method was developed for mapping the fission rate density and fast neutron flux from DeCART to BISON. Multiple depletion cases were run with one-way data transfer from DeCART to BISON. The one-way data transfer of fission rate density is shown to agree with the fission rate density obtained from an internal Lassman-style model in BISON. One-way data transfer was also demonstrated in a 3D case in which azimuthal asymmetry was induced in the fission rate density profile of a fuel rod modeled in DeCART. Two-way data transfer was established by mapping the temperature distribution from BISON to DeCART. A Picard iterative algorithm was developed for the loose coupling with two-way data transfer.
AB - The 3D neutron transport and core analysis program DeCART was coupled to the fuels performance application BISON to provide a higher fidelity tool for fuel performance simulation. This project is motivated by the desire to couple a high fidelity core analysis program (based on the method of characteristics) to a high fidelity fuel performance program, both of which can simulate 3D problems. DeCART provides sub-pin level resolution of the multigroup neutron flux, with resonance treatment, during burnup or a fast transient. BISON implicitly solves coupled thermomechanical equations for the fuel on a sub-milimeter level finite element mesh. A method was developed for mapping the fission rate density and fast neutron flux from DeCART to BISON. Multiple depletion cases were run with one-way data transfer from DeCART to BISON. The one-way data transfer of fission rate density is shown to agree with the fission rate density obtained from an internal Lassman-style model in BISON. One-way data transfer was also demonstrated in a 3D case in which azimuthal asymmetry was induced in the fission rate density profile of a fuel rod modeled in DeCART. Two-way data transfer was established by mapping the temperature distribution from BISON to DeCART. A Picard iterative algorithm was developed for the loose coupling with two-way data transfer.
KW - BISON
KW - DeCART
KW - Method of characteristics
KW - Multiphysics
KW - Nuclear fuel performance
UR - http://www.scopus.com/inward/record.url?scp=84883372598&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:84883372598
SN - 9781627486439
T3 - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013
SP - 1234
EP - 1246
BT - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013
T2 - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013
Y2 - 5 May 2013 through 9 May 2013
ER -