Accumulation and Release of Tritium in Pressurized Water Reactors.

摘要

Two computer codes,TRIT and THKK,each designed to predict tritium concentrations and inventories in light-water-cooled and -pressurized nuclear power plants are described and compared in this report. Mathematical bases,input requirements,sample calculational results and program listings are presented for each code. While the codes are similar in purpose,they differ in that TRIT evaluates tritium concentrations only at the end of reactor power operation and refueling cycles,whereas THKK calculates tritium inventories at any desired day of startup,power operation,hot shutdown,or refueling. Both codes were written for application to the Trojan Nuclear Plant but have general applicability to PWRs of similar design.