The passive containment cooling system (PCCS) is important passive safety systems in the Advanced Pressurized Water Reactor (APWR), which belongs to the generation III of nuclear reactors. In design basis accident (DBA), the steam condenses on the inner surface of the containment shell and the cooling water evaporates from the outer surface of the containment shell. In this process, the heat is transferred from the inside of the containment to the outside. To span the expected range of conditions and provide a proper model for evaluating the inner steam condensation coupled with outer evaporation heat transfer process, the inner steam condensation coupled outer evaporation experimental test (ISCOE) is developed by State Nuclear Power Technology Research & Development Centre (SNPTRD). Several tests have been done on the ISCOE experimental test facility. The influence of different key factors for the capability of the heat transfer of the containment steel shell wall has been researched. Key factors include steam pressure, steam temperature, water film velocity, air velocity, steel shell wall angle, and so on. The result of these tests has an important significance to the research of heat transfer capability of the containment steel shell wall. In this paper, several tests are introduced, including details, results and analysis. The influence of air velocity for the capability of the heat transfer of the containment steel shell wall is also analyzed.
Description of liquid nitrogen experimental test facility