Development of an evaluation method for debris bed formation behavior focusing on the agglomeration mechanism observed in the DEFOR-A test using THERMOS/JBREAK–DPCOOL–MSPREAD
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Abstract
When the lower head of a reactor pressure vessel (RPV) is damaged during a severe accident in light water reactors (LWRs), after the jet breakup occurs in the water, the entrained pieces of molten debris (hereafter called droplets) is likely to form nonuniform, poorly coolable agglomerations on the floor. These debris agglomerates can impact the debris bed coolability. The authors are developing THERMOS, an analysis code composed of modules such as JBREAK, DPCOOL, and MSPREAD, to evaluate these behaviors. In the investigation of the new DEFOR-A test series conducted in collaboration with Kungliga Tekniska Högskolan (KTH), it has been identified that the formation of agglomerated debris is influenced not only by the solidification fraction of the droplets but also by crust cracking and melt spreading. To evaluate the formation of agglomerated debris at a wide range of superheat, the authors have developed the special model in JBREAK, one of the THERMOS modules, based on mechanism estimated from the investigation of DEFOR-A test series (A23-27). Additionally, the agglomeration process is affected by several complex phenomena, such as jet breakup, droplet sedimentation, deposition, and melt spreading behavior, so the authors developed an evaluation method that sequentially evaluates these behaviors using the THERMOS/JBREAK–DPCOOL–MSPREAD coupling. This evaluation method successfully simulated jet breakup, agglomeration, and debris bed formation observed in the DEFOR-A tests. The evaluation method has accurately explained the agglomerated debris mass fraction over a wide range of melt superheat levels by modeling droplet crust cracking, melt spreading, and agglomeration resulting from droplet–debris interactions.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.