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KMID : 0364920080330030113
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Journal of Radiation Protection and Research
2008 Volume.33 No. 3 p.113 ~ p.120
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Prediction of the Tritium Behavior in Very High Temperature Gas Cooled Reactor Using TRITGO
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Park Jong-Hwa
Park Ik-Kyu
Lee Won-Jae
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Abstract
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In this study, The TRITGO code was introduced, which can predict the amount of tritium production, it’s transport, removal, distribution and the level of contamination for the produced hydrogen by the tritium on the VHTR (very high temperature gas cooled reactor). The TRITGO code was improved so that the permeation to the IS Iodine Sulfide) loop for producing the hydrogen can be simulated. The contamination level of the produced hydrogen by the tritium was predicted by the improved code for the VHTR with 600MW thermal power. The contamination level for the produced hydrogen by tritium was predicted as 0.055 Bq/H2-g. This level is three order of lower than the regulation value of 56 Bq/H2-g from Japan. From this study, the following results were obtained. it is important that the fuel coating (SiC layer) should be kept intact to prevent the tritium from releasing. Also it is necessary that the level of impurity such as 3He and Li in the helium coolant and the reflector consisting of the graphite should be kept as low as possible. It was found that the capacity of the purification system for filtering the impurities directly from the coolant will be the important design parameter.
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KEYWORD
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VHTR, TRITIUM, TRITGO, TBEC, IS, GT-MHR 600
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