Demonstration of Pronghorn’s Subchannel Code Modeling of Liquid-Metal Reactors and Validation in Normal Operation Conditions and Blockage Scenarios

Author:

Kyriakopoulos Vasileios1ORCID,Tano Mauricio E.1ORCID,Karahan Aydin2

Affiliation:

1. Idaho National Laboratory, Idaho Falls, ID 83415, USA

2. Argonne National Laboratory, Lemont, IL 60439, USA

Abstract

Pronghorn-SC is a subchannel code within the Multiphysics Object-Oriented Simulation Environment (MOOSE). Initially designed to simulate flows in water-cooled, square lattice, subchannel assemblies, Pronghorn-SC has been expanded to simulate liquid-metal-cooled flows in triangular lattices, hexagonal subchannel assemblies. For this purpose, the algorithm of Pronghorn-SC was adapted to solve the subchannel equations as they are applicable to a hexagonal wire-wrapped sodium-cooled fast reactor. Cheng–Todreas models for pressure drop and cross-flow models were adopted and a coolant heat conduction term was added. To solve these equations, an improved implicit algorithm was developed robust enough to deal with the numerical issues, associated with low flow and recirculation phenomena. To confirm the prediction capability of Pronghorn-SC, calculations and comparisons with available experimental data of 19- and 37-pin assemblies were performed, as well as other subchannel codes. Finally, a flow blockage modeling feature was added. This capability was validated for both water-cooled square sub-assemblies and sodium-cooled hexagonal sub-assemblies, using experimental data of partially and fully blocked cases.

Funder

U.S. Government

Publisher

MDPI AG

Subject

Energy (miscellaneous),Energy Engineering and Power Technology,Renewable Energy, Sustainability and the Environment,Electrical and Electronic Engineering,Control and Optimization,Engineering (miscellaneous),Building and Construction

Reference26 articles.

1. Generation IV nuclear reactors: Current status and future prospects;Locatelli;Energy Policy,2013

2. Basehore, K., and Todreas, N.E. (1980). SUPERENERGY-2: A Multiassembly, Steady-State Computer Code for LMFBR Core Thermal-Hydraulic Analysis, Battelle Pacific Northwest Labs.. Technical Report.

3. A subchannel analysis code MATRA-LMR for wire wrapped LMR subassembly;Kim;Ann. Nucl. Energy,2002

4. Development of a subchannel analysis code MATRA applicable to PWRs and ALWRs;Sohn;J. Korean Nucl. Soc.,1999

5. Gosman, A.D., Herbert, R., Patankor, S.V., Potter, R., and Spalding, D.B. (1973). The SABRE Code for Prediction of Coolant Flows and Temperatures in Pin Assemblies Containing Blockages, HTS.

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