Study on Radiological Consequence Induced by SGTR Accident with Alternative Source Term
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摘要: 介绍了可选择源项的基本假设和剂量计算的基本方法,采用一体化核电厂安全分析程序以及美国NRC RG 1.183中定义的放射性源项和方法,评估了900 MW级核电厂发生蒸汽发生器传热管破裂(SGTR)事故后的放射性后果,并计算了主控室、非居住区边界和低人口密度区外边界的剂量值。将计算结果与剂量准则进行比较,其结果完全在可接受的范围内。Abstract: By introducing and implementing the alternative source term and accident methodology defined in RG 1.183 and using integral safety analysis code,this paper evaluates the radiological consequence induced by(SGTR) accident for the domestic nuclear power plant of 90 MW.Compared with the dose criteria of RG 1.183,the dose values of the control room,exclusion area boundary and outer boundary of low population zone are acceptable.
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Key words:
- Steam generator tube rupture /
- Alternative source term /
- Radiological consequence /
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