For conceptual blanket design of fusion reactors, a two-dimensional (2-D) nuclear-thermal-coupled analysis code, DOHEAT, has been developed. A remarkable feature of the code is a user-friendly graphical interface which allows to prepare an appropriate analysis model of a variety of blanket concepts with different materials in a short time. Furthermore, the code has a strong point that it provides the cross-sectional distribution of temperature, neutron/gamma fluxes, nuclear heating and tritium breeding ratio (TBR) inside the blanket after the completion of a single run. Throughout the DEMO design work in JAEA, it has proven that DOHEAT is extremely valuable in guiding the design study toward a wide variety of blanket concepts.
ASJC Scopus subject areas