TY - GEN
T1 - APEX
T2 - 2025 Advances in Nuclear Fuel Management, ANFM 2025
AU - Kropaczek, Dave
AU - Godfrey, Andrew
AU - Collins, Benjamin
AU - Graham, Aaron
N1 - Publisher Copyright:
© Proceedings of Advances in Nuclear Fuel Management, ANFM 2025. All rights reserved.
PY - 2025
Y1 - 2025
N2 - Veracity Nuclear has developed an efficient, fast-running three-dimensional simulator for multicycle fuel and core analysis. APEX is a physics-based surrogate model for the high-fidelity VERA core simulator, accurately representing objective functions and constraints for fuel cycle optimization problems. APEX utilizes QPANDA methods for the neutronics solution, ANTS for the subchannel thermal-hydraulics solution, and MPACT-based lattice cross sections. VERA-based discontinuity factors are also used in regions such as the reflector interface. The APEX nodal solution is robust for core analysis problems in full, half, quarter, and eighth core geometries, as well as four-node-per-assembly, one-node-per-assembly, and pin-by-pin geometries.
AB - Veracity Nuclear has developed an efficient, fast-running three-dimensional simulator for multicycle fuel and core analysis. APEX is a physics-based surrogate model for the high-fidelity VERA core simulator, accurately representing objective functions and constraints for fuel cycle optimization problems. APEX utilizes QPANDA methods for the neutronics solution, ANTS for the subchannel thermal-hydraulics solution, and MPACT-based lattice cross sections. VERA-based discontinuity factors are also used in regions such as the reflector interface. The APEX nodal solution is robust for core analysis problems in full, half, quarter, and eighth core geometries, as well as four-node-per-assembly, one-node-per-assembly, and pin-by-pin geometries.
KW - APEX
KW - Nodal
KW - Simulator
KW - VERA
KW - Watts Bar
UR - https://www.scopus.com/pages/publications/105022182678
U2 - 10.13182/ANFM25-47207
DO - 10.13182/ANFM25-47207
M3 - Conference contribution
AN - SCOPUS:105022182678
T3 - Proceedings of Advances in Nuclear Fuel Management, ANFM 2025
SP - 944
EP - 953
BT - Proceedings of Advances in Nuclear Fuel Management, ANFM 2025
PB - American Nuclear Society
Y2 - 20 July 2025 through 23 July 2025
ER -