TY - GEN
T1 - DEVELOPMENT OF A THERMAL HYDRAULIC MODEL FOR THE VERSATILE TEST REACTOR USING THE CTF SUBCHANNEL CODE
AU - Takasugi, Cole
AU - Martin, Nicolas
AU - Yoon, Su Jong
AU - Bays, Samuel
AU - Avramova, Maria
AU - Ivanov, Kostadin
N1 - Publisher Copyright:
Copyright © 2021 AMERICAN NUCLEAR SOCIETY, INCORPORATED, LA GRANGE PARK, ILLINOIS 60526.All rights reserved.
PY - 2021
Y1 - 2021
N2 - The Versatile Test Reactor (VTR) program, supported by the United States Department of Energy, is a 300 MWth sodium-cooled fast reactor (SFR) design currently in the conceptual phase. Recent developments in the subchannel thermal hydraulic analysis code CTF have been made in order to extend its modeling capabilities to include SFRs. In order to test these capabilities, a comparison is made between coolant temperature profiles resulting from CTF, the code SE2-ANL, and the computational fluid dynamics (CFD) code STAR-CCM+ for VTR fuel driver bundles. Results show good agreement between CTF and SE2-ANL calculations and provide some insight into the differences in these correlation-based models from CFD calculations with STAR-CCM+. Additional steps have been carried out in order to generate and run parallelized, full-core VTR models in CTF. This work demonstrates the first use of CTF for large SFR geometries.
AB - The Versatile Test Reactor (VTR) program, supported by the United States Department of Energy, is a 300 MWth sodium-cooled fast reactor (SFR) design currently in the conceptual phase. Recent developments in the subchannel thermal hydraulic analysis code CTF have been made in order to extend its modeling capabilities to include SFRs. In order to test these capabilities, a comparison is made between coolant temperature profiles resulting from CTF, the code SE2-ANL, and the computational fluid dynamics (CFD) code STAR-CCM+ for VTR fuel driver bundles. Results show good agreement between CTF and SE2-ANL calculations and provide some insight into the differences in these correlation-based models from CFD calculations with STAR-CCM+. Additional steps have been carried out in order to generate and run parallelized, full-core VTR models in CTF. This work demonstrates the first use of CTF for large SFR geometries.
KW - CTF
KW - SFR
KW - VTR
UR - https://www.scopus.com/pages/publications/85183599374
U2 - 10.13182/M&C21-33783
DO - 10.13182/M&C21-33783
M3 - Conference contribution
AN - SCOPUS:85183599374
T3 - Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021
SP - 2274
EP - 2283
BT - Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021
PB - American Nuclear Society
T2 - 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021
Y2 - 3 October 2021 through 7 October 2021
ER -