A tritium transport model for a pool-type sodium cooled fast reactor was developed for estimation of tritium effluents from the Prototype Generation IV Sodium-cooled Fast Reactor (PGSFR). For this purpose, the transport model developed for Experimental Breeder Reactor II and Fast Flux Test Facility was updated and validated. The tritium production rate from ternary fission and activations in PGSFR were calculated by the Argonne Reactor Computation (ARC) code suite for fast reactor analysis, and due to the potential uncertainties in source terms and variations of cold trap performance and material permeability during reactor operation, the tritium distributions and tritium effluents were estimated for several bounding cases. The upper bounding gaseous and liquid tritium release rates from PGSFR are ~ 440.7 Ci/year and 14.7 Ci/year, respectively. The gaseous tritium effluent is about few orders of magnitude smaller than the regulatory constraint of the tritium concentration in the air. The peak tritium concentration in the steam-generator feedwater is ~ 1.1x10^-3 μCi/g, which is required to be diluted prior to releasing as tritiated water. The accumulated tritium in the cold trap after five cycle operations is ~ 52,000 Ci. Because of significant conservatism in these upper bounding estimations, it is expected that the tritium effluent at the nominal case with plausible source terms would be about 2 orders of magnitude smaller than that of the upper bounding case.

建立了池型钠冷快堆的transport运输模型，以估算来自第四代原型钠冷快堆（PGSFR）的of流出物。为此目的，为实验育种反应堆II和快速通量测试设施开发的运输模型已得到更新和验证。通过用于快速反应堆分析的Argonne反应堆计算（ARC）代码套件，计算了PGSFR中三元裂变和活化产生的production的产率，并且由于在反应堆运行过程中源条件以及冷阱性能和材料渗透性的变化存在潜在的不确定性，估算了几种边界情况下的tri分布和tri流出物。从PGSFR释放出的气态和液态release的上限分别约为440.7 Ci /年和14.7 Ci /年。气态tri气流出物比空气中tri浓度的调节约束小几个数量级。蒸汽发生器给水中的tri浓度峰值约为1.1x10^-3其中需要微居里/克，以释放氚化水之前进行稀释。经过五个循环操作后，冷阱中的The累积量约为52,000 Ci。由于这些上限估计中的保守性很强，因此可以预期，在标称情况下使用合理的源术语的than流出量将比上限情况下的排放量小约2个数量级。