skip to main content
DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

This content will become publicly available on April 13, 2020

Title: CTF-R: A novel residual-based thermal hydraulic solver

Abstract

The traditional scientific process has been revolutionized by the advent of computational modeling, but the nuclear industry generally uses "legacy codes," which were developed early in the evolution of computers. One example of a legacy code, the thermal hydraulic subchannel code CTF, is modernized in this work through the development of a novel residual-based version, CTF-R. Unlike its predecessor, CTF-R is not limited by the strict computational limitations of the early 1980's, and can therefore be designed such that it is inherently flexible and easy to use. A case study is examined to demonstrate how the flexibility of the code can be used to improve simulation results. In this example, the coupling between the solid and liquid fields is examined. Traditionally, this coupling is modeled explicitly, which imposes numerical stability limits on the time step size. These limits are derived and it is shown that they are removed when the coupling is made implicit. Further, the development of CTF-R will enable future improvements in next generation reactor modeling, numerical methods, and coupling to other codes. Through the further development of CTF-R and other residual-based codes, state-of-the-art simulation is possible.

Authors:
 [1];  [1];  [2]
  1. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  2. North Carolina State Univ., Raleigh, NC (United States)
Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1507403
Alternate Identifier(s):
OSTI ID: 1507748
Report Number(s):
SAND2019-3952J; SAND2019-1095J
Journal ID: ISSN 0029-5493; 674519
Grant/Contract Number:  
AC04-94AL85000
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Engineering and Design
Additional Journal Information:
Journal Volume: 348; Journal Issue: C; Journal ID: ISSN 0029-5493
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING

Citation Formats

Porter, N. W., Mousseau, V. A., and Avramova, M. N.. CTF-R: A novel residual-based thermal hydraulic solver. United States: N. p., 2019. Web. doi:10.1016/j.nucengdes.2019.04.006.
Porter, N. W., Mousseau, V. A., & Avramova, M. N.. CTF-R: A novel residual-based thermal hydraulic solver. United States. doi:10.1016/j.nucengdes.2019.04.006.
Porter, N. W., Mousseau, V. A., and Avramova, M. N.. Sat . "CTF-R: A novel residual-based thermal hydraulic solver". United States. doi:10.1016/j.nucengdes.2019.04.006.
@article{osti_1507403,
title = {CTF-R: A novel residual-based thermal hydraulic solver},
author = {Porter, N. W. and Mousseau, V. A. and Avramova, M. N.},
abstractNote = {The traditional scientific process has been revolutionized by the advent of computational modeling, but the nuclear industry generally uses "legacy codes," which were developed early in the evolution of computers. One example of a legacy code, the thermal hydraulic subchannel code CTF, is modernized in this work through the development of a novel residual-based version, CTF-R. Unlike its predecessor, CTF-R is not limited by the strict computational limitations of the early 1980's, and can therefore be designed such that it is inherently flexible and easy to use. A case study is examined to demonstrate how the flexibility of the code can be used to improve simulation results. In this example, the coupling between the solid and liquid fields is examined. Traditionally, this coupling is modeled explicitly, which imposes numerical stability limits on the time step size. These limits are derived and it is shown that they are removed when the coupling is made implicit. Further, the development of CTF-R will enable future improvements in next generation reactor modeling, numerical methods, and coupling to other codes. Through the further development of CTF-R and other residual-based codes, state-of-the-art simulation is possible.},
doi = {10.1016/j.nucengdes.2019.04.006},
journal = {Nuclear Engineering and Design},
number = C,
volume = 348,
place = {United States},
year = {2019},
month = {4}
}

Journal Article:
Free Publicly Available Full Text
This content will become publicly available on April 13, 2020
Publisher's Version of Record

Save / Share: