2007年3月6日，国际种子测量协会主席、荷兰ASTEC GlobM执行总裁Johan Van Asbrouck先生来浙江林学院进行合作洽谈。学校党委书记陈敬佑、副书记汤勇会见了来宾。双方在此前签订合作意向书的基础上，就共建种子技术研究中心，举办学术...2007年3月6日，国际种子测量协会主席、荷兰ASTEC GlobM执行总裁Johan Van Asbrouck先生来浙江林学院进行合作洽谈。学校党委书记陈敬佑、副书记汤勇会见了来宾。双方在此前签订合作意向书的基础上，就共建种子技术研究中心，举办学术研讨会，双方互访等具体事宜进行了商讨。科技处、国际合作与交流处、农学院（筹）等部门和学院负责人参加了会谈。展开更多
ASTEC and ICARE / CATHARE are computer codes allowing analysing severe accidents in LWRs. The applicability of these codes to Russian reactors of VVER type is a clear common IRSN-GRS objective. The current work in col...ASTEC and ICARE / CATHARE are computer codes allowing analysing severe accidents in LWRs. The applicability of these codes to Russian reactors of VVER type is a clear common IRSN-GRS objective. The current work in collaboration between IRSN and RRC K1 （Russia） aims at reaching this objective. This paper is devoted to ASTEC and ICARE / CATHARE simulations of a severe accident scenario on a VVER-1000. A Large Break LOCA （850 mm） sequence accompanied with the station blackout was selected for analysis. ICARE / CATHARE V2.2 successfully predicted main events of the accident： heat-up of the core, core degradation and melt relocation to the lower part of the core. A simulation of a complete accidental sequence was performed with ASTEC V 1.3-rev3 code： core heat-up and melting, melt relocation, reactor vessel rupture, molten corium / concrete interaction, release and distribution of steam, H2, CO, CO2, fission products and aerosols in the RCS and the containment. It must be pointed out that, as concerns the thermalhydraulics front-end phase and the in-vessel degradation phase, the ASTEC simulation exhibited consistent results with respect to the best-estimate ICARE / CATHARE ones.展开更多
文摘2007年3月6日，国际种子测量协会主席、荷兰ASTEC GlobM执行总裁Johan Van Asbrouck先生来浙江林学院进行合作洽谈。学校党委书记陈敬佑、副书记汤勇会见了来宾。双方在此前签订合作意向书的基础上，就共建种子技术研究中心，举办学术研讨会，双方互访等具体事宜进行了商讨。科技处、国际合作与交流处、农学院（筹）等部门和学院负责人参加了会谈。
文摘ASTEC and ICARE / CATHARE are computer codes allowing analysing severe accidents in LWRs. The applicability of these codes to Russian reactors of VVER type is a clear common IRSN-GRS objective. The current work in collaboration between IRSN and RRC K1 （Russia） aims at reaching this objective. This paper is devoted to ASTEC and ICARE / CATHARE simulations of a severe accident scenario on a VVER-1000. A Large Break LOCA （850 mm） sequence accompanied with the station blackout was selected for analysis. ICARE / CATHARE V2.2 successfully predicted main events of the accident： heat-up of the core, core degradation and melt relocation to the lower part of the core. A simulation of a complete accidental sequence was performed with ASTEC V 1.3-rev3 code： core heat-up and melting, melt relocation, reactor vessel rupture, molten corium / concrete interaction, release and distribution of steam, H2, CO, CO2, fission products and aerosols in the RCS and the containment. It must be pointed out that, as concerns the thermalhydraulics front-end phase and the in-vessel degradation phase, the ASTEC simulation exhibited consistent results with respect to the best-estimate ICARE / CATHARE ones.
