TUF Version Control and Development Status

Abstract

The TUF (Two-Unequal-Fluid) code has been developed at Ontario Hydro as the main safety analysis tool for primary and secondary heat transport systems of CANDU nuclear reactors. The code has been used extensively for both operational and abnormal transients. The objectives of this paper are (1) to briefly outline the code capabilities, (2) to present the version control logic currently being applied and (3) to report the development status of the TUF code.