TRACE simulations of IIST cooldown experiments
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H.-T. Lin
Abstract
IIST (Institute of Nuclear Energy Research Integral System Test) facility is a RHRP (Reduced-Height and Reduced-Pressure) facility for the three-loop PWR (Pressurized Water Reactor) NPP (Nuclear Power Plant) Maanshan. This test facility was established in 1992 for safety studies of the Maanshan NPP. TRACE is an advanced thermal hydraulic code which is still developed and updated by U.S. NRC. So, validation of specific models against experiments is still necessary. In this paper, cooldown experiments in IIST facility are used to validate the TRACE models. Additionally, the results of TRACE calculations are compared to results of RELAP5 calculations. This comparison shows that the calculations of TRACE are in good agreement to the data of IIST experiments and to the calculational results of RELAP5. So, TRACE can be used to simulate cooldown transients.
© 2020 by Walter de Gruyter Berlin/Boston
Articles in the same Issue
- Frontmatter
- CALENDAR OF EVENTS · VERANSTALTUNGSKALENDER
- Thermal hydraulic characteristics of two-phase natural circulation for secondary side passive residual heat removal system
- Operating experience feedback from incidental fluctuations of the power measurement channel at ETRR-2
- Benchmark study of OPAL research reactor using MCNP codes
- Method based on directed graph and binary decision diagram to break logic loops
- CFD code-to-code benchmarking on simulation of fire and smoke propagation for nuclear applications
- TRACE simulations of IIST cooldown experiments
- Flow and heat transfer characteristics in rough micro-channels
- Technical Note
- In memoriam
- Note · Imprint
Articles in the same Issue
- Frontmatter
- CALENDAR OF EVENTS · VERANSTALTUNGSKALENDER
- Thermal hydraulic characteristics of two-phase natural circulation for secondary side passive residual heat removal system
- Operating experience feedback from incidental fluctuations of the power measurement channel at ETRR-2
- Benchmark study of OPAL research reactor using MCNP codes
- Method based on directed graph and binary decision diagram to break logic loops
- CFD code-to-code benchmarking on simulation of fire and smoke propagation for nuclear applications
- TRACE simulations of IIST cooldown experiments
- Flow and heat transfer characteristics in rough micro-channels
- Technical Note
- In memoriam
- Note · Imprint
