摘要
从 CAP1400核电钢制安全壳和模块整体出厂的构想尚存在诸多不确定因素切入,按照模块整体出厂参数,依据已审批的3000~5000 t 级核电站码头初步设计资料、SG 浮吊卸货运输方案、拟采用18000 t 级半潜船运输构想、重件道路等场内设施初步设计参数,对码头、场内设施等设计方案按照理想状态同比例放大航道、港池、码头、重件道路等参数建立模型,进行模块整体出厂的改造分析。经过对船型参数、航道、港池、码头、场内设施详细的技术与经济对比分析,对模块整体出厂从理论、安全、技术、经济等方面给出了切合实际的建议。
With the idea of CAP1400 containment and CA/CV modules in its entirety released from the fabrication shop,there are some uncertainties in this scheme.Based on the parameters of CA/CV modules,the approved drawings for heavy components wharfs of 3 000 t to 5 000 t nuclear power plant,SG offloading (using a float crane ), transportation schemes, the concept of 18 000 t semisubmersible barge, and the preliminary design parameters of site facilities,the heavy components wharf and site facilities were magnified proportionally according to the design scheme.The parameters of the sea routes,dock basin and wharfs were employed to construct the model to analyze the modification scheme of the entirety module releasing.With the technical and economical comparison and analysis, the advices on the theory, safety, techniques and cost-effectiveness shipping of CAP1400 CA/CV modules in its whole can be given.
出处
《能源研究与信息》
2014年第4期218-223,共6页
Energy Research and Information
基金
国家科技重大专项课题资助项目(2011ZX06001-005)