The IAEA organizes International Collaborative Standard Problems (ICSPs) to facilitate the development and validation of computer codes for design and safety analysis of nuclear power plants. The implementation of an ICSP usually includes an experimental investigation of interesting phenomena and simulation of the experiment with computer codes. This publication presents the outcome of an ICSP assessing the capability of system thermohydraulic computer codes for integral reactor system design and safety analysis. It took place at the experimental facility at the Oregon State University in the United States of America. The publication details the ICSP tests and results from all participants, provides a description of the computer codes used and the models developed, and includes some discussion by each participant concerning the results that were achieved during blind and open phases of the calculation for their individual models. The publication concludes with lessons learned and recommendations for the future.
