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

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Wataru Kikuchi , Akitoshi Hotta , Koetsu Ito , Mamoru Shimizu
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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.
基于THERMOS/ JBREAK-DPCOOL-MSPREAD的DEFOR-A试验中观察到的碎屑床形成机理,建立了碎屑床形成行为评价方法
在轻水反应堆(LWRs)发生严重事故时,当反应堆压力容器(RPV)的下压头损坏时,在水中发生射流破裂后,被夹带的熔融碎片(以下称为液滴)很可能在地面上形成不均匀的、不耐冷却的团块。这些碎屑团块会影响碎屑床的冷却性。作者正在开发由JBREAK、DPCOOL、MSPREAD等模块组成的分析代码THERMOS来评估这些行为。在与Kungliga Tekniska Högskolan (KTH)合作进行的新的DEFOR-A试验系列的调查中,已经确定凝聚碎片的形成不仅受到液滴凝固分数的影响,而且受到地壳开裂和熔体扩散的影响。为了评估大范围过热条件下碎屑团聚体的形成,作者基于DEFOR-A试验系列(A23-27)研究估计的机理,在THERMOS模块之一的JBREAK中开发了特殊模型。此外,聚块过程还受到喷射破碎、液滴沉降、沉积和熔体扩散行为等复杂现象的影响,因此作者开发了一种利用THERMOS/ JBREAK-DPCOOL-MSPREAD耦合对这些行为进行顺序评价的评价方法。该评价方法成功地模拟了DEFOR-A试验中观察到的射流破碎、团聚和碎屑床形成。该评价方法通过模拟由液滴-碎屑相互作用引起的液滴地壳破裂、熔体扩散和团聚,准确地解释了在大范围熔体过热水平下的团聚碎屑质量分数。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
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.
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