Code validation of SAM using natural-circulation experimental data from the compact integral effects test (CIET) facility
Creators
- 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.2021.111144Additional 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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54014749
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Descriptors DEI
- ANALYTICAL SOLUTION; BENCHMARKS; COMPUTER CODES; FORCED CONVECTION; NATURAL CONVECTION; REACTOR DESIGN; SAFETY ANALYSIS; SODIUM COOLED REACTORS; STEADY-STATE CONDITIONS; SYSTEMS ANALYSIS; TEST FACILITIES; THERMAL HYDRAULICS; TRANSIENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- CONVECTION; DESIGN; ENERGY TRANSFER; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; LIQUID METAL COOLED REACTORS; MASS TRANSFER; MATHEMATICAL SOLUTIONS; MECHANICS; REACTOR LIFE CYCLE; REACTORS
Optional Information
- Copyright
- Copyright (c) 2021 Elsevier B.V. All rights reserved.