Intercomparison and Validation of Computer Codes for Thermohydraulic Safety Analysis of Heavy Water Reactors

Intercomparison and validation of computer codes used in different countries for thermohydraulics safety analysis of heavy water reactors (HWRs) enhances confidence in the predictions made by these codes. A set of reliable experimental data is necessary for conducting such intercomparison and validation exercises. Experimental results from a large loss of coolant accident (LOCA) test simulating HWR LOCA behaviour that was conducted by Atomic Energy of Canada Ltd (AECL) was selected for this validation project. This report provides a comparison of the results obtained from six participating countries, utilizing four different computer codes. General conclusions are reached and recommendations made.