There is a newer version of the record available.

Published June 2021 | Version v1
Journal article

Code validation of SAM using natural-circulation experimental data from the compact integral effects test (CIET) facility

  • 1. Argonne National Laboratory (United States)

Description

Highlights: • SAM system analysis code validation using integral effect test data. • Analytical solution derivation for natural circulation test. • Code-to-code comparison with RELAP5. The primary objective of this study is to validate the system analysis code, SAM, using experimental data from the Compact Integral Effects Test (CIET) experimental loop. SAM is a modern system analysis code being developed at Argonne National Laboratory for safety analysis of designs for advanced non-light water reactors (non-LWRs), such as sodium-cooled fast reactors, high-temperature gas-cooled reactors, and fluoride salt-cooled high-temperature reactors (FHRs). To support SAM code development for the wide range of non-LWR applications, it is of paramount importance to validate the code against experiments highly relevant to these reactor concepts. The CIET facility, which was designed to reproduce the thermal-hydraulics response of FHRs under both forced- and natural-circulation conditions, has been identified and selected as one of the benchmark test facilities for SAM code validation. In this study, two sets of available CIET tests were selected for SAM code validation purposes, namely, forced convection cooling transient test and steady-state natural-circulation tests. For all selected tests, SAM-predicted results show very good agreement with experimental data. The successful validation of SAM against these selected CIET experiments demonstrates that the computer code is well suited for thermal-hydraulics analysis of FHR designs.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2021.111144

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2021.111144;
PII
S0029549321000960;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
377
Journal Page Range
vp.
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2021 Elsevier B.V. All rights reserved.