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Development of rapid atmospheric source term estimation system for AP1000 nuclear power plant

机译:AP1000核电厂大气源快速项估计系统的开发

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The development of rapid atmospheric source term estimation system (RASTES) for AP1000 nuclear power plant (NPP) is described. The system is designed to give rapid estimation of the amount of fission products released to the atmosphere, and to provide necessary input for fission products atmospheric dispersion simulation and public dose calculation, during a nuclear accident. The estimation method in RASTES mainly refers to NUREG-1228. However, some adjustments are made based on an investigation of studies in nuclear emergency response and design features of AP1000 NPP during development of RASTES. These adjustments enable the system to be more flexible and realistic in atmospheric source term estimation, and more applicable to AP1000 NPP. These adjustments include modifications and validations of aerosol removal factors in reactor containment in both natural process and spray process, as well as addition of aerosol removal factors in passive containment cooling process. Besides, three reactor core damage assessment methods are integrated into atmospheric source term estimation. In addition, containment radiation levels for specified fuel damage which are used in core damage assessment are recalculated. The calculation function of RASTES is confirmed through comparison with RASCAL. Atmospheric source terms in different fission product removal processes are also calculated and compared. The result shows that passive containment cooling is able to further reduce aerosol release by about 50% compared with natural process. Development of RASTES will enhance the capability of nuclear emergency response of AP1000 NPP. (C) 2015 Elsevier Ltd. All rights reserved.
机译:描述了用于AP1000核电厂(NPP)的快速大气源项估计系统(RASTES)的开发。该系统旨在快速估算释放到大气中的裂变产物的量,并为核事故期间裂变产物的大气弥散模拟和公共剂量计算提供必要的输入。 RASTES中的估计方法主要参考NUREG-1228。但是,根据对RASTES开发过程中AP1000 NPP的核应急响应和设计特征的研究调查,进行了一些调整。这些调整使系统在大气源项估算方面更加灵活和现实,并且更适用于AP1000 NPP。这些调整包括对自然过程和喷雾过程中反应堆安全壳中气溶胶去除因子的修改和验证,以及在被动安全壳冷却过程中增加气溶胶去除因子。此外,将三种反应堆堆芯损伤评估方法集成到大气源项估算中。此外,将重新计算用于核心损坏评估的特定燃料损坏的密闭辐射水平。通过与RASCAL进行比较,可以确定RASTES的计算功能。还计算并比较了不同裂变产物去除过程中的大气源项。结果表明,与自然过程相比,被动安全壳冷却能够进一步减少约50%的气溶胶释放。 RASTES的发展将增强AP1000核电厂的核应急能力。 (C)2015 Elsevier Ltd.保留所有权利。

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