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Title: Benchmark Simulation of Natural Circulation Cooling System with Salt Working Fluid Using SAM

Abstract

Liquid salt-cooled reactors, such as the Fluoride Salt-Cooled High-Temperature Reactor (FHR), offer passive decay heat removal through natural circulation using Direct Reactor Auxiliary Cooling System (DRACS) loops. The behavior of such systems should be well-understood through performance analysis. The advanced system thermal-hydraulics tool System Analysis Module (SAM) from Argonne National Laboratory has been selected for this purpose. The work presented here is part of a larger study in which SAM modeling capabilities are being enhanced for the system analyses of FHR or Molten Salt Reactors (MSR). Liquid salt thermophysical properties have been implemented in SAM, as well as properties of Dowtherm A, which is used as a simulant fluid for scaled experiments, for future code validation studies. Additional physics modules to represent phenomena specific to salt-cooled reactors, such as freezing of coolant, are being implemented in SAM. This study presents a useful first benchmark for the applicability of SAM to liquid salt-cooled reactors: it provides steady-state and transient comparisons for a salt reactor system. A RELAP5-3D model of the Mark-1 Pebble-Bed FHR (Mk1 PB-FHR), and in particular its DRACS loop for emergency heat removal, provides steady state and transient results for flow rates and temperatures in the system that aremore » used here for code-to-code comparison with SAM. The transient studied is a loss of forced circulation with SCRAM event. To the knowledge of the authors, this is the first application of SAM to FHR or any other molten salt reactors. While building these models in SAM, any gaps in the code’s capability to simulate such systems are identified and addressed immediately, or listed as future improvements to the code.« less

Authors:
; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy - Nuclear Energy University Programs (NEUP)
OSTI Identifier:
1392061
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Conference
Resource Relation:
Conference: 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), 09/03/17 - 09/08/17, Xi'an, Shaanxi, CN
Country of Publication:
United States
Language:
English

Citation Formats

Ahmed, K. K., Scarlat, R. O., and Hu, R. Benchmark Simulation of Natural Circulation Cooling System with Salt Working Fluid Using SAM. United States: N. p., 2017. Web.
Ahmed, K. K., Scarlat, R. O., & Hu, R. Benchmark Simulation of Natural Circulation Cooling System with Salt Working Fluid Using SAM. United States.
Ahmed, K. K., Scarlat, R. O., and Hu, R. Sun . "Benchmark Simulation of Natural Circulation Cooling System with Salt Working Fluid Using SAM". United States. doi:. https://www.osti.gov/servlets/purl/1392061.
@article{osti_1392061,
title = {Benchmark Simulation of Natural Circulation Cooling System with Salt Working Fluid Using SAM},
author = {Ahmed, K. K. and Scarlat, R. O. and Hu, R.},
abstractNote = {Liquid salt-cooled reactors, such as the Fluoride Salt-Cooled High-Temperature Reactor (FHR), offer passive decay heat removal through natural circulation using Direct Reactor Auxiliary Cooling System (DRACS) loops. The behavior of such systems should be well-understood through performance analysis. The advanced system thermal-hydraulics tool System Analysis Module (SAM) from Argonne National Laboratory has been selected for this purpose. The work presented here is part of a larger study in which SAM modeling capabilities are being enhanced for the system analyses of FHR or Molten Salt Reactors (MSR). Liquid salt thermophysical properties have been implemented in SAM, as well as properties of Dowtherm A, which is used as a simulant fluid for scaled experiments, for future code validation studies. Additional physics modules to represent phenomena specific to salt-cooled reactors, such as freezing of coolant, are being implemented in SAM. This study presents a useful first benchmark for the applicability of SAM to liquid salt-cooled reactors: it provides steady-state and transient comparisons for a salt reactor system. A RELAP5-3D model of the Mark-1 Pebble-Bed FHR (Mk1 PB-FHR), and in particular its DRACS loop for emergency heat removal, provides steady state and transient results for flow rates and temperatures in the system that are used here for code-to-code comparison with SAM. The transient studied is a loss of forced circulation with SCRAM event. To the knowledge of the authors, this is the first application of SAM to FHR or any other molten salt reactors. While building these models in SAM, any gaps in the code’s capability to simulate such systems are identified and addressed immediately, or listed as future improvements to the code.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Sep 03 00:00:00 EDT 2017},
month = {Sun Sep 03 00:00:00 EDT 2017}
}

Conference:
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