核能產氫的先決條件是必須使用極高溫核反應爐以滿足產氫時化學反應之需求。目前各種第四代核反應爐設計理念中，最可能在近期內達成目標者，當屬極高溫氣冷式核反應器(Very High Temperature Gas-Cooled Reactor, VHTGR)。極高溫氣冷式核反應爐所需使用之材料，尤其是在爐心內部的結構材料，不僅面臨極高溫度(∼1000℃)，而且同時具有高能量及高通量快中子的輻射損傷效應。在長期使用(四十年設計壽命)下其材料性質變化與其微結構之關係密切，尤其在高輻射損傷環境下，石墨會產生能量累積的情形（因材料內部微結構產生缺陷，累積缺陷能），當出現意外事件時，有可能因高溫回火產生大量能量釋出的情形，此時極易因瞬間產生高溫使得石墨材料熔化或氣化，進而造成意外事件會亦發不可預測，對於反應爐安全性形成嚴重挑戰。
本研究之主要目的，是在於了解核能級石墨材料在高溫及高輻射環境下之微結構變化，進而了解其內部缺陷形成之機制，針對其所可能產生之風險深入探討可能的對策，事先設計應對方法。
本實驗是利用離子佈植的方式來模擬長時間下核能級石墨受長時間中子照射所受的輻射損傷，之後使用穿透式電子顯微鏡(TEM)進行試片的微結構分析，並利用二維快速傅立葉轉換技術(FFT techniques)進行 HRTEM影像的定量分析比較，最後用彈性變形累積應變能公式估算可能累積於石墨內部的應變總能和可能造成的最大溫度升高。

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