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ARIANT Assessments for CANDU Analysis Using RD-14M Experiments.

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Title: ARIANT Assessments for CANDU Analysis Using RD-14M Experiments.
Authors: Cui, John1 (AUTHOR) john.cui@cnl.ca, Waddington, Geoffrey1 (AUTHOR), Wang, Shujun1 (AUTHOR), Liu, Songyu1 (AUTHOR)
Source: Nuclear Science & Engineering. 2025 Suppl 1, Vol. 199, pS898-S922. 25p.
Subjects: Thermal hydraulics, CANDU reactors, Two-phase flow, Heat transfer, Algorithms, Simulation methods & models, Nuclear reactor accidents, Nuclear reactor safety measures
Abstract: ARIANT (AlgoRIthm for Analysis of Network Thermalhydraulics) is a Canadian Nuclear Laboratories system thermal-hydraulic code for the modeling and analysis of two-phase flow and heat transfer for pressurized heavy water reactors, light water pressurized water reactors, and advanced reactor applications. This paper presents ARIANT models and simulations of RD-14M experiments, including small-break loss-of-coolant accidents, large-break loss-of-coolant accidents, loss-of-flow accidents, station blackout, and natural circulation, that are representative of accident scenarios in a CANDU reactor. ARIANT predictions of pressures, flow rates, temperatures, and void fractions are compared against the steady-state and transient data over the course of the tests. The results show that ARIANT predicted the key parameters with reasonable accuracy, as well as the overall behavior of the five transient events. These assessments support ARIANT's applicability to the corresponding CANDU design-basis accidents and demonstrate ARIANT as an alternative to existing system thermal-hydraulic codes for CANDU safety analysis. [ABSTRACT FROM AUTHOR]
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Database: Engineering Source
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Abstract:ARIANT (AlgoRIthm for Analysis of Network Thermalhydraulics) is a Canadian Nuclear Laboratories system thermal-hydraulic code for the modeling and analysis of two-phase flow and heat transfer for pressurized heavy water reactors, light water pressurized water reactors, and advanced reactor applications. This paper presents ARIANT models and simulations of RD-14M experiments, including small-break loss-of-coolant accidents, large-break loss-of-coolant accidents, loss-of-flow accidents, station blackout, and natural circulation, that are representative of accident scenarios in a CANDU reactor. ARIANT predictions of pressures, flow rates, temperatures, and void fractions are compared against the steady-state and transient data over the course of the tests. The results show that ARIANT predicted the key parameters with reasonable accuracy, as well as the overall behavior of the five transient events. These assessments support ARIANT's applicability to the corresponding CANDU design-basis accidents and demonstrate ARIANT as an alternative to existing system thermal-hydraulic codes for CANDU safety analysis. [ABSTRACT FROM AUTHOR]
ISSN:00295639
DOI:10.1080/00295639.2024.2380628