Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Using British Advanced Gas-Cooled Reactor (AGR) Refueling Technology and Decay Heat Removal Systems That Prevent Salt Freezing
Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Using British Advanced Gas-Cooled Reactor (AGR) Refueling Technology and Decay Heat Removal Systems That Prevent Salt Freezing
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氟化盐冷却高温反应堆（FHR）采用英国先进气冷反应堆（AGR）换料技术和防止盐冻结的衰变排热系统
DOI：
10.1080/00295450.2019.1586372
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发表时间：
2019
影响因子：
1.5
通讯作者：
Forsberg C
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文献类型：
--
作者：
Forsberg C
氟化盐冷却高温反应堆（FHR）使用石墨基涂层颗粒燃料[与高温气冷反应堆（HTGR）相同]和清洁的液体盐冷却剂。它以 600°C 至 700°C 的温度向工业过程或动力循环输送热量，平均热输送温度高于其他反应器。液体盐冷却剂的熔点高于450°C。较高的最低温度给加油带来了挑战，需要特殊功能来控制温度，避免温度过高和冷却剂冻结，从而影响衰变热冷却系统。本文介绍了一种概念前的 FHR 设计，该设计通过采用英国先进气冷反应堆 (AGR) 和替代衰变热冷却系统的功能来解决其中的许多挑战。描述了具体设计选择的基础。AGR 是二氧化碳冷却和石墨慢化反应堆，使用圆柱形燃料组件，可在 650°C 下垂直换料，满足 FHR 高温换料要求。十四个 AGR 已经运行了几十年。 AGR 使用八个圆柱形燃料组件，每个组件高 1 m，通过金属纵梁轴向连接在一起，形成一个长燃料组件。纵梁组件位于提供中子慢化作用的石墨芯中的垂直通道中。这种几何核心设计与使用石墨基质涂层颗粒燃料的 FHR 兼容。 FHR 使用一次通过式燃料循环。相对于其他 FHR 和 HTGR 设计，该设计最大限度地减少了核燃料使用量。主系统位于辅助液体盐填充罐内，该罐（1）为衰变热提供附加散热器，（2）有助于确保主系统盐不会冻结，（3）有助于确保在超出设计基准的事故中不会发生重大燃料故障。经过修改的 AGR 核心中每个纵梁燃料组件上方的加油立管可在 FHR 中用于加油，并可在主系统和辅助液态盐填充罐之间提供有效的热传递。被动式衰变热排出系统使用在预设温度下打开和关闭的热管，以避免反应堆事故中堆芯过热，并避免反应堆停堆后衰变热减少时冻结盐冷却剂。
The flouride-salt-cooled high-temperature reactor (FHR) uses graphite-matrix coated-particle fuel [the same as high-temperature gas-cooled reactors (HTGRs)] and a clean liquid salt coolant. It delivers heat to the industrial process or the power cycle at temperatures between 600°C and 700°C with average heat delivery temperatures higher than for other reactors. The melting point of the liquid salt coolant is above 450°C. The high minimum temperatures present refueling challenges and require special features to control temperatures, avoiding excessively high temperatures and freezing of the coolant that could impact decay heat cooling systems. This paper describes a preconceptual FHR design that addresses many of these challenges by adopting features from the British advanced gas-cooled reactor (AGR) and alternative decay heat cooling systems. The bases for specific design choices are described.The AGRs are carbon dioxide–cooled and graphite-moderated reactors that use cylindrical fuel subassemblies with vertical refueling at 650°C, which meets the FHR high-temperature refueling requirements. Fourteen AGRs have operated for many decades. The AGR uses eight cylindrical fuel subassemblies, each 1 m tall coupled axially together by a metal stringer to create a long fuel assembly. The stringer assemblies are in vertical channels in a graphite core that provides neutron moderation. This geometric core design is compatible with an FHR using graphite-matrix coated-particle fuel. The FHR uses a once-through fuel cycle. The design minimizes used nuclear fuel volumes relative to other FHR and HTGR designs. The primary system is inside a secondary liquid salt–filled tank that (1) provides an added heat sink for decay heat, (2) helps to ensure no freezing of primary system salt, and (3) helps to ensure no major fuel failures in a beyond-design-basis accident. The refueling standpipes above each stringer fuel assembly in the AGR core with modifications can be used in an FHR for refueling and can provide efficient heat transfer between the primary system and the secondary liquid salt–filled tank. The passive decay heat removal system uses heat pipes that turn on and off at a preset temperature to avoid overheating the core in a reactor accident and to avoid freezing the salt coolant as decay heat decreases after reactor shutdown.
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