Verification of the plant dynamics analytical code CERES using the results of the plant trip test of the prototype fast breeder reactor MONJU. The verification with the steady state and plant trip conditions. Collaboration research report of Central Research Institute of Electric Power Industry - Japan Nuclear Cycle Development Institute

To verify the CERES code, analyses were performed by using the result of the plant trip test from the partial power operation of the prototype fast breeder reactor 'MONJU' that had been executed in December, 1995. The detail of the structure of the 'MONJU' and the results of the test were investigated, and the CERES input data was completed. Following four verification analyses were performed. (1) Analysis concerning the primary/secondary/auxiliary cooing system (the plenum in the reactor vessel (R/V) is modeled in R-Z 2-dimension). (2) Analysis concerning the flow pattern in the plenum of R/V (the plenum is modeled in 3-dimension). (3) Analysis concerning the behavior of the coolant in the middle plenum (the plenum is modeled in R-Z 2-dimension). (4) Analysis concerning the flow pattern inside the intermediate heat exchanger (IHX) (the plenum in the IHX is modeled in 3-dimension). Analytical results by the CERES code showed good agreement with the results of the test of the 'MONJU'. Fundamental abilities of the CERES as a plant dynamics calculation code had been verified through these analyses. Additionally, some characteristic flows in plena of 'MONJU' became clear by these analyses. (author)