核电厂主控室可居留性内漏剂量模型的研究

核电厂主控室无过滤渗漏风（内漏）的放射性影响是可居留性评价的重要部分，目前针对该部分的剂量模型过于简化，不符合实际工程设计。本研究结合核电厂实际设计特征，对内漏源项迁移机理进行研究，推导放射性活度微分方程，建立主控室可居留性内漏剂量模型，选取典型设计基准失水事故（LOCA）和发生堆熔的大破口失水事故（LB-LOCA）开展模型应用，并与目前常用的简化模型进行对比。结果表明，采用简化模型在LB-LOCA工况下的剂量结果小于采用本研究模型的结果，简化模型无法包络所有事故情景。经分析，本研究建立的内漏剂量模型更符合实际场景，适用于主控室可居留区域的内漏影响评价，并可用于内漏试验结果的验证以及工程项目设计。 

Study on the Habitable Dose Model of Internal Leakage in Main Control Room of Nuclear Power Plant

The radioactive impact of unfiltered air leakage (internal leakage) in the main control room of a nuclear power plant is an important part of habitability evaluation. At present, the dose model for this part is too simplified and does not accord with the actual engineering design. Combined with the actual design characteristics of a nuclear power plant, this study studies the migration mechanism of internal leakage source terms, deduces the differential equation of radioactivity, establishes the habitable internal leakage dose model of the main control room, selects typical design basis loss of coolant accident (LOCA) and large break loss of coolant accident (LB-LOCA) with reactor melting to carry out the application of the model, and compares it with the commonly used simplified model at present. The results show that the dose result of the simplified model under LB-LOCA condition is smaller than that of this model, and the simplified model can not cover all accident scenarios. After analysis, the internal leakage dose model established in this study is more in line with the actual scenario, suitable for the impact evaluation of internal leakage in the habitable area of the main control room, and can be used for the verification of internal leakage test results and engineering project design.