Abstract
The TINTE code deals with the nuclear and thermal transient behavior of a high-temperature reactor, taking into consideration the mutual feedback effects in two-dimensional r-z geometry, including the following: 1. time-dependent neutron flux calculation2. time-dependent heat source distribution (local and nonlocal fractions)3. time-dependent heat transport from the fuel to the fuel element surface4. time-dependent global temperature distribution5. gas flow distribution for a given mass flow or given pressure difference or even under natural circulation conditions6. convection and its feedback to the circulation. The TINTE code has been tested against transient experiments performed at the Arbeitsgemein-schaft Versuchsreaktor. It has also been used successfully for other reactor investigations and thermofluid problems including design studies for a small heating reactor of the peu à peu loading type.
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