Abstract The High-Temperature Gas-cooled Reactor (HTGR) has been selected as one of the next-generation nuclear power plants because of its passive safety features. The Korea Atomic Energy Research Institute (KAERI) has been studying how to utilize HTGR efficiently and safely. The HTGR uses graphite as a moderator and helium as a coolant. Once tritium is produced, it is released into the coolant; once released from the core, tritium travels within the primary loop. Because the coolant is gas phase, it is easy to transport to other systems. While it circulates in the primary loop, tritium is involved in processes that include leakage, purification, and permeation. KAERI has been developing a tritium behavior analysis code named TRitium Overall Phenomena analYsis (TROPY) to analyze tritium transport and predict the amount of tritium in the loop in the HTGR core. In this paper, the functions of the TROPY code are introduced, and the amount of tritium in each loop and the amount released into the product hydrogen from the MHTGR 350-MW(thermal) core are explained.

中文翻译：

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高温气冷堆中氚的传输和分布

摘要 高温气冷堆（HTGR）因其非能动安全特性而被选为下一代核电站之一。韩国原子能研究所 (KAERI) 一直在研究如何高效、安全地利用 HTGR。HTGR 使用石墨作为减速剂，使用氦气作为冷却剂。一旦产生氚，它就会被释放到冷却剂中；一旦从核心中释放出来，氚就会在主循环中传播。因为冷却剂是气相的，所以很容易输送到其他系统。当氚在初级回路中循环时，氚参与了包括泄漏、净化和渗透在内的过程。KAERI 一直在开发一种名为氚整体现象分析 (TROPY) 的氚行为分析代码，用于分析氚传输并预测 HTGR 堆芯中循环中的氚量。本文介绍了TROPY代码的功能，并解释了每个循环中氚的数量以及从MHTGR 350-MW（热）堆芯释放到产品氢中的数量。