The Status and Prospect of Reactor Thermal-hydraulic Verification Database
The experimental data related to the thermal-hydraulic(TH)performance of nuclear reactors mainly come from the actual operation of nuclear power plants and the test facility simulating the accident transient of reactors.For decades,many reactors TH test facilities have been built,such as LOFT,LOBI,PKL,ROSA,ATLAS,ACME,etc.,and a series of experimental data have been obtained.These data can be used to nuclear power plant design,verification and evaluation of reactor safety,and provide validation data for the development of new TH code.To better preserve and utilize these valuable facility information and experimental data,some databases have been established internationally,such as TIETHYS,STRESA,and SANIS.With the continuous accumulation and improvement of data,the construction of verification database began to be put on agenda.Because of the third-generation reactor technology and the demand of softwareverification,based on the construction and operation of relevant test facilities,China began to build relevant verificationexperimental databases.This paper introduces the main contents and construction framework of the TH verification database of the international large-scale test facility.Taking some other nuclear energy-related databases as reference,the need and development progress of relevant test facility database in China are discussed,and relevant suggestions for the thermal-hydraulic verification database of reactor are put forward.
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万方数据
