Safety related heat exchanger modeling using TRACE code

Najveći dio problema sigurnosti nuklearnih elektrana odnosi se na odvođenje zaostale (ostatne) topline, u čemu važnu ulogu ima sustav za odvođenje ostatne topline. Funkcija sustava bitne servisne vode je hlađenje sigurnosnih sustava nuklearne elektrane. Korištenjem grafičkog korisničkog sučelja SNAP napravljeni su modeli izmjenjivača topline u ovim dvama sustavima i provedene su simulacije programom za termohidrauličke proračune TRACE. TRACE je program kojeg je napravila Američka nuklearna regulatorna komisija i koristi se za simulacije događaja koji nastupaju pri normalnom i izvanrednom stanju nuklearnih elektrana. Rezultati su zatim uspoređeni s rezultatima koje je dao drugi program za provođenje simulacija procesa u nuklearnim elektranama – RELAP5.The major part of the nuclear power plants safety problem is considered to be the removal of decay (residual) heat, in which RHR system plays a very important role. Nuclear power plant safety systems are cooled by component cooling water from which the heat is transfered to the ultimate heat sink by ESW (Essential Service Water) system. Heat exchanger models were made in SNAP graphical user interface and then the simulations were carried out by the TRACE code. TRACE is a system code developed by the U.S. Nuclear Regulatory Commission and is used for simulating accidental and regular operating scenarios in nuclear power plants. The results of the simulations were then compared to results calculated by another code for analyzing nuclear power plant processes – RELAP5