TY - GEN
T1 - Simulation of Oscillatory Flow Induced by Flashing Instability Using the ASYST System Analysis Code
AU - Zhang, Taiyang
AU - Brooks, Caleb S.
N1 - Publisher Copyright:
© 2023 Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. All rights reserved.
PY - 2023
Y1 - 2023
N2 - Two-phase flow instabilities can lead to continuously evolving long-term behaviors involving various non-negligible phenomena. Prediction of instability consequences is therefore a challenge which requires comprehensive and robust models capturing critical physics consistently beyond steady states. As thermal hydraulic codes for reactor system analysis are typically developed with anticipated capability covering a wide spectrum of reactor transients, validation of these code in capturing flow instability is of practical interest. The current work tests the performance of a code, the Adaptive System Thermal-hydraulics Version 3 (ASYST VER3), in reproducing periodic limit-cycle oscillations induced by flashing instability on a low-pressure natural circulation facility. With prescribed periodic boundary conditions, single-channel simulations are conducted to investigate the code capability in correctly modeling two-phase phenomena. Discrepancies between the simulation and experiment are checked, leading to further analysis of potential modeling defects. In general, this work presents the simulation practices and validation attempts of a thermal hydraulic code, ASYST, against a benchmark dataset composing of periodic flow oscillations from flashing instability.
AB - Two-phase flow instabilities can lead to continuously evolving long-term behaviors involving various non-negligible phenomena. Prediction of instability consequences is therefore a challenge which requires comprehensive and robust models capturing critical physics consistently beyond steady states. As thermal hydraulic codes for reactor system analysis are typically developed with anticipated capability covering a wide spectrum of reactor transients, validation of these code in capturing flow instability is of practical interest. The current work tests the performance of a code, the Adaptive System Thermal-hydraulics Version 3 (ASYST VER3), in reproducing periodic limit-cycle oscillations induced by flashing instability on a low-pressure natural circulation facility. With prescribed periodic boundary conditions, single-channel simulations are conducted to investigate the code capability in correctly modeling two-phase phenomena. Discrepancies between the simulation and experiment are checked, leading to further analysis of potential modeling defects. In general, this work presents the simulation practices and validation attempts of a thermal hydraulic code, ASYST, against a benchmark dataset composing of periodic flow oscillations from flashing instability.
KW - ASYST
KW - flashing instability
KW - transient system analysis
KW - two-phase flow
UR - http://www.scopus.com/inward/record.url?scp=85202974114&partnerID=8YFLogxK
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U2 - 10.13182/NURETH20-40123
DO - 10.13182/NURETH20-40123
M3 - Conference contribution
AN - SCOPUS:85202974114
T3 - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
SP - 5358
EP - 5370
BT - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PB - American Nuclear Society
T2 - 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Y2 - 20 August 2023 through 25 August 2023
ER -