COMMIX-1A code descriptions

Maekawa, I.*; Takahashi, Minoru; Muramatsu, Toshiharu; *; Ninokata, Hisashi; Aoki, Tadao

PNC TN952 84-11, 101 Pages, 1984/07

PNC-TN952-84-11.pdf:3.13MB

COMMIX-1A is a single phase multi-dimensional analysis code for thermal-hydraulics within components of nuclear power plants. The code was introduced from the Argonne National Laboratory in the U.S. in 1983. It has been extensively used for sodium and water analysis and now its improvement and validation programs are under way at the Reactor Engineering Section of OEC/PNC. This report is written based on the materials distributed at COMMIX-1A Workshop, 15th and 16th in May, 1984 which offered PNC engineers the chance to use the code and to get familiarity with it for the solution of thermal hydraulic problems of their own fields. This report consists of the following contents: (1) outline of COMMIX-1A, (2) capability and limitation of the code, (3) usage experiances of the code, (4) main input data description and (5) sample problems.