TY - JOUR
T1 - CTF
T2 - A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pressurized water reactors
AU - Salko, Robert
AU - Wysocki, Aaron
AU - Blyth, Taylor
AU - Toptan, Aysenur
AU - Hu, Jianwei
AU - Kumar, Vineet
AU - Dances, Chris
AU - Dawn, William
AU - Sung, Yixing
AU - Kucukboyaci, Vefa
AU - Gurecky, William
AU - Lange, Travis
AU - Zhao, Xingang
AU - Rader, Jordan
AU - Jernigan, Caleb
AU - Collins, Benjamin
AU - Avramova, Maria
AU - Magedanz, Jeffrey
AU - Palmtag, Scott
AU - Clarno, Kevin
AU - Kropaczek, Dave
AU - Hizoum, Belgacem
AU - Godfrey, Andrew
AU - Pointer, Dave
AU - Turner, John
AU - Sankaran, Ramanan
AU - Schmidt, Rod
AU - Hooper, Russell
AU - Bartlett, Roscoe
AU - Baird, Mark
AU - Pilch, Martin
N1 - Funding Information:
This research made use of the resources of the High Performance Computing Center at Idaho National Laboratory, which is supported by the Office of Nuclear Energy, USA of the U.S. Department of Energy and the Nuclear Science User Facilities, USA under Contract No. DE-AC07-05ID14517 .
Funding Information:
This research is supported by and performed in conjunction with the Consortium for Advanced Simulation of Light Water Reactors ( http://www.casl.gov ), an Energy Innovation Hub ( http://www.energy.gov/hubs ) for Modeling and Simulation of Nuclear Reactors under US Department of Energy, USA Contract No. DE-AC05-00OR22725 .
Funding Information:
This manuscript has been authored by UT-Battelle LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).This research is supported by and performed in conjunction with the Consortium for Advanced Simulation of Light Water Reactors (http://www.casl.gov), an Energy Innovation Hub (http://www.energy.gov/hubs) for Modeling and Simulation of Nuclear Reactors under US Department of Energy, USA Contract No. DE-AC05-00OR22725. This research made use of the resources of the High Performance Computing Center at Idaho National Laboratory, which is supported by the Office of Nuclear Energy, USA of the U.S. Department of Energy and the Nuclear Science User Facilities, USA under Contract No. DE-AC07-05ID14517.
Funding Information:
This manuscript has been authored by UT-Battelle LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ).
Publisher Copyright:
© 2022
PY - 2022/10
Y1 - 2022/10
N2 - CTF is a thermal hydraulic (T/H) subchannel tool that has been extensively developed over the past ten years as part of the Consortium for Advanced Simulation of Light Water Reactors (CASL) program. The code was selected early in the CASL program for support of high-impact challenge problems that were found to be relevant to the nuclear industry and its currently operating fleet of pressurized water reactors (PWRs), including issues such as departure from nucleate boiling (DNB), crud-induced power shifts (CIPSs), and reactivity-insertion accidents (RIAs). By incorporating CTF into the multiphysics Virtual Environment for Reactor Application (VERA) core simulator software developed by CASL, CTF has become the primary means of providing fluid and fuel thermal feedback, as well as T/H figure-of-merits (FOMs) in large-scale reactor simulations. With the goal of solving industry challenge problems, CASL placed great emphasis on developing high-quality, high-performance, validated software tools that offer higher fidelity than what is currently possible with current industry methods. In support of this effort, CTF was developed from a research tool into an nuclear quality assurance (NQA-1)–compliant, production-level software tool that is capable of addressing the stated challenge problems and goals of CASL. This paper presents a review of the major technological achievements that were realized in developing CTF over the past decade of the CASL program and presents an overview of the code solution approach and closure models.
AB - CTF is a thermal hydraulic (T/H) subchannel tool that has been extensively developed over the past ten years as part of the Consortium for Advanced Simulation of Light Water Reactors (CASL) program. The code was selected early in the CASL program for support of high-impact challenge problems that were found to be relevant to the nuclear industry and its currently operating fleet of pressurized water reactors (PWRs), including issues such as departure from nucleate boiling (DNB), crud-induced power shifts (CIPSs), and reactivity-insertion accidents (RIAs). By incorporating CTF into the multiphysics Virtual Environment for Reactor Application (VERA) core simulator software developed by CASL, CTF has become the primary means of providing fluid and fuel thermal feedback, as well as T/H figure-of-merits (FOMs) in large-scale reactor simulations. With the goal of solving industry challenge problems, CASL placed great emphasis on developing high-quality, high-performance, validated software tools that offer higher fidelity than what is currently possible with current industry methods. In support of this effort, CTF was developed from a research tool into an nuclear quality assurance (NQA-1)–compliant, production-level software tool that is capable of addressing the stated challenge problems and goals of CASL. This paper presents a review of the major technological achievements that were realized in developing CTF over the past decade of the CASL program and presents an overview of the code solution approach and closure models.
KW - CTF
KW - LWR
KW - Subchannel
KW - VERA
UR - http://www.scopus.com/inward/record.url?scp=85137156205&partnerID=8YFLogxK
UR - https://www.mendeley.com/catalogue/f9aa7d46-8979-3676-9668-54e3e7276aa9/
U2 - 10.1016/j.nucengdes.2022.111927
DO - 10.1016/j.nucengdes.2022.111927
M3 - Article
AN - SCOPUS:85137156205
SN - 0029-5493
VL - 397
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
M1 - 111927
ER -