首页> 外文会议>14th International Conference on Nuclear Engineering(ICONE14) vol.5 >ANALYSES OF HIGH PRESSURE MOLTEN DEBRIS DISPERSION FOR A TYPICAL PWR PLANT
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ANALYSES OF HIGH PRESSURE MOLTEN DEBRIS DISPERSION FOR A TYPICAL PWR PLANT

机译:典型压水厂的高压熔渣分散分析

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In such severe core damage accident, as small LOCAs with no ECCS injection or station blackout, in which the primary reactor system remains pressurized during core melt down, certain modes of vessel failure would lead to a high pressure ejection of molten core material. In case of a local failure of the lower head, the molten materials would initially be ejected into the cavity beneath the pressure vessel may subsequently be swept out from the cavity to the containment atmosphere and it might cause the early containment failure by direct contact of containment steel liner with core debris. When the contribution of a high-pressure scenario in a core damage frequency increases, early conditional containment failure probability may become large.rnIn the present study, the verification analysis of PHOENICS code and the combining analysis with MELCOR and PHEONICS codes were performed to examine the debris dispersion behavior during high pressure melt ejection.rnThe PHOENICS code which can treat thermal hydraulic phenomena, was applied to the verification analysis for melt dispersion experiments conducted by the Purdue university in the United States. A low pressure melt dispersion experiment at initial pressure 1.4MPas used metal woods as a molten material was simulated. The analytical results with molten debris dispersion mostly from the model reactor cavity compartment showed an agreement with the experimental result, but the analysis result of a volumetric median diameter of the airborne debris droplets was estimated about 1.5 times of the experimental result.rnThe injection rates of molten debris and steam after reactor vessel failure for a typical PWR plant were analyzed using the MELCOR code. In addition, PHOENICS was applied to a 3D analysis for debris dispersion with low primary pressure at the reactor vessel failure. The analysis result showed that almost all the molten debris were dispersed from the reactor vessel cavity compartment by about 45 seconds after the start of steam release.
机译:在这种严重的堆芯损坏事故中,如没有ECCS注入或站停电的小型LOCA(在堆芯熔化期间主反应器系统仍处于加压状态),某些容器故障模式将导致熔融堆芯材料的高压喷射。如果下压头发生局部故障,熔融材料将首先喷射到压力容器下方的空腔中,随后可能会从空腔中清除到安全壳大气中,并可能由于安全壳的直接接触而导致早期的安全壳失效。带芯碎屑的钢衬。当高压情景对堆芯破坏频率的贡献增加时,早期条件安全壳破坏的可能性可能会变大。rn在本研究中,对PHOENICS代码进行了验证分析,并与MELCOR和PHEONICS代码进行了组合分析,以检查高压熔体喷射过程中的碎屑弥散行为。rn可以处理热水力现象的PHOENICS代码被用于美国普渡大学进行的熔体弥散实验的验证分析。以金属木材为熔融材料,在初始压力​​为1.4MPas下进行了低压熔体分散实验。熔融碎屑弥散的分析结果主要来自模型反应器腔室,与实验结果基本吻合,但估算的空气中碎屑液滴体积中值直径的分析结果约为实验结果的1.5倍。使用MELCOR代码分析了典型压水堆装置在反应堆容器故障后的熔融碎屑和蒸汽。此外,PHOENICS还用于在反应堆容器故障时以低主压力对碎片分散进行3D分析。分析结果表明,在开始释放蒸汽后约45秒钟,几乎所有熔融碎屑都从反应堆容器腔室中分散了。

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