“supercritical-water-cooled reactor”的概念、定义、翻译、参考文献-科学参考

单词	supercritical-water-cooled reactor
释义	supercritical-water-cooled reactor Encyclopedia 工学核反应堆分类释 supercritical-water-cooled reactor; SCWR超临界水堆在水的热力学临界点（374℃，22.1兆帕）以上运行的高温高压水冷核反应堆。属于第四代核反应堆。
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