The invention discloses a fused salt reactor
tritium transportation characteristic
coupling calculation method. The method mainly comprises the following steps: 1, obtaining geometric parameters, operation parameters and
program calculation parameters of a fused salt reactor; 2, calculating an adsorption
capacity limit value of
graphite to
tritium; 3, calculating the generation amount of
tritium and the
graphite adsorption amount at the reactor core; 4, calculating the
corrosion amount of tritium to
chromium at the
heat pipe section and the deposition amount of
chromium ions; 5, calcuating thecorrosion amount of tritium to
chromium, the deposition amount of chromium ions and the tritium gas
permeation amount at the
heat exchanger; 6, calculating the
corrosion amount of tritium to chromiumat the cold
pipe section and the deposition amount of chromium ions; And 7, if the
current time is equal to the steady-state
operation time of the
molten salt reactor, outputting a calculation result, otherwise, returning to the step 2, and performing calculation again until the calculation is finished. According to the method, the production of tritium in the
molten salt reactor, transportationcharacteristics such as
graphite adsorption,
corrosion / deposition and
permeation, and the influence of
neutron irradiation on the graphite adsorption capacity are considered, so that the production amount, the adsorption amount and the
permeation amount of tritium in the
molten salt reactor can be obtained, and a reference is provided for
radiation protection of the
molten salt reactor.