The TINTE Modular Code System for Computational Simulation of Transient Processes in the Primary Circuit of a Pebble-Bed High-Temperature Gas-Cooled Reactor

This paper reports on the TINTE code. It deals with the nuclear and thermal transient behavior of a high-temperature reactor, taking into consideration the mutual feedback in two-dimensional r-z geometry including the following: time-dependent neutron flux calcultion; time-dependent heat source distribution (local and nonlocal fractions); time-dependent heat transport from the fuel to the fuel element surface; time-dependent global temperature distribution; gas glow distribution for a given mass flow or given mass flow or given pressure difference or even under natural circulation conditions; and convesction and its feedback to the circulation. The TINTE code has been tested against transient experiments. It has also been used successfully for other reactor investigations and theremofluid problems including design studies for a small heating reactor.