The analysis of thermal flow all Triso fuel temperature at RGTT200K core

Reactor RGTT200K is conceptual reactor design cooled by high temperature gas. In line with development of RGTT200K conceptual design, thermal flow parameter analysis on Triso fuel element temperature at RGTT200K core was done. The purpose of this evaluation is to know the effectively of Triso fuel strength on power variable effect, coolant flow rate and pressure against to fuel element temperature at steady state condition, that meet safety requirement. Analysis was done by using THERMIX computer code, by divided reactor core into 50 component to represent position of many different material composition, and to model Triso fuel element become 5 zone. Analysis done base on input data of reactor power variant, coolant flow rate, and pressure in the core at steady state condition. Analysis was done at condition: power of 110 MW 200 MW; flow rate of 100 kg/s - 140 kg/sm and system pressure of 4 - 7 MPa. Also modelling for reactor parameters, core specification, and Triso RGTT200K coated particle data. From the analysis of the effect of variable thermal flow of helium gas, variable inlet pressure and variable power reactor against the temperature distribution of the pebble fuel, it can be concluded that variable power reactors have the greatest influence than other variables. The maximum temperature in the OPyC surface layer of the Triso is 703.5°C. Therefore Triso fuel can effectively restrain all radioactive fission products. (author)