Open AccessMORECA: A computer code for simulating modular high-temperature gas-cooled reactor core heatup accidents
Author(s) -
S.J. Ball
Publication year - 1991
Language(s) - English
Resource type - Reports
DOI - 10.2172/5955421
Subject(s) - cabin pressurization , nuclear engineering , modular design , nuclear fission product , coolant , nuclear reactor core , core (optical fiber) , environmental science , core model , fission products , computer science , engineering , mechanical engineering , telecommunications , operating system , mathematical analysis , mathematics