Transient analysis of the HEU and LEU benchmark cores using the TRANSV2 code

The TRANSV2 code was originally developed for the analysis of the thermal-hydraulic characteristics of MTR-type research reactors. It has been recently modified to provide a coupled thermal-hydraulic and point kinetics capability with continuous reactivity feedback. The modified version of the code has been used to analyze the transients of the HEU and LEU cores included in the safety-related benchmark problem proposed by the IAEA for an idealized, light-water-moderated, pool-type research reactor to compare calculational methods. The HEU and LEU cores: (1) Slow loss-of-flow transient, (2) Fast loss-of-flow transient, (3) Slow reactivity insertion transient, and (4) Fast reactivity insertion transient. The results obtained with TRANSV2 code are compared with those provided by the contributions of ANL, INTERATOM and JAERI to the IAEA safety-related benchmark problem. (author)