César Berna-Escriche , David Blanco , José Luis Muñoz-Cobo , Lucas Álvarez-Piñeiro , Alberto Escrivá
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引用次数: 0
Abstract
Scaling methodologies quantitatively assess the behavioral differences between small-scale experimental systems and full-size commercial plants during specific accidental scenarios. These methods guide the design and operation of experimental facilities to reliably replicate larger systems, ensuring safety systems are developed and accident sequences predicted accurately. Early integration of scaling calculations into the experimental design phase allows for reliable extrapolation of results to commercial plants. This study applied Fractional Scaling Analysis (FSA) to compare a scaled LSTF experimental facility and a full-size Siemens-KWU reactor during a Small Break LOCA in the hot leg (ROSA 1.2 test). The transient was divided into five phases, each analyzed for thermal-hydraulic similarity. Despite minor scaling distortions, the results showed strong consistency in pressure and level evolution, confirming good scalability between the facilities for this scenario. FSA demonstrated its versatility, allowing data from one type of facility (e.g., Westinghouse-type) to inform analyses for plants of a different type (e.g., Siemens-KWU). A new method provided a "normalized scalability" metric for the entire transient, with figures of merit for pressure and level reaching ∼0.3 (far below 1), indicating good scalability. Non-conservative distortions were minimal (<0.16), enabling quantitative comparisons across plants and transients for enhanced safety and design validation.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development