頁籤選單縮合
題名 | 不飽和聚酯固化BWR 及PWR 蒸發濃縮廢料之研究 |
---|---|
編 次 | 1 |
作者 | 李育德; 張義和; 周齊生; | 書刊名 | Journal of the Chinese Institute of Chemical Engineers |
卷期 | 16:3 1985.07[民74.07] |
頁次 | 頁227-234 |
分類號 | 449.1 |
關鍵詞 | 不飽和; 聚酯固化; 蒸發; 廢料; 濃縮; |
語文 | 中文(Chinese) |
中文摘要 | 輕水式核反應器(LWR)運轉過程中產生含放射核種之蒸發濃縮物,BWR(沸水式反應器)主要成份是硫酸納,PWR(壓水式反應器)主要成份是硼酸,以不飽和聚酯與BWR模擬廢料硫酸納及PWR濃縮廢料之預處理產物硼酸鈣水合物混合,固化後,就其密度、機械性質、抗水性、瀝濾率(Leachability)耐放射性、耐熱性進行評估。結果顯示,模擬廢料硫酸納最高填加量可達75wt%,但以不超過70wt%為宜,硼酸鈣二水合物最高可達58wt%。各種固化體之壓縮強度(硫酸納固化體大於1,200 kg/cm²,硼酸鈣水合物固化體大於1,700 kg/cm²),抗水性及熱安定性佳,瀝濾率低(鈉離子擴散速率10¯³-10¯⁴cm²/day,鈣離子擴散速率10¯[8fb6]cm²/day),密度超過投海標準1.2g/cm²,耐放射性可達10[8ec3] Rad的γ-ray照射劑里以上,而減容效果可達水泥固化的4-9倍。 |
英文摘要 | The operating process of light water reactor (LWR) will produce evaporation condensate containing radioactive waste. The main component in the condensate is Na₂SO₄ for boiling water reactor (BWR) and H₃BO₃ for pressure water reactor (PWR). In this study, the simulating wastes Na₂SO₄ and Ca₃(BO₃)₂.2H₂O were solidified with unsatuated polyesters, and their densities, mechanical properties, water resistances, leachabilities, γ-ray resistances and thermal stabilities were evaluated. Our results showed that the highest amounts of Na₂SO₄ which could be added into the resin was 75% by weight while that of Ca₃(BO₃)₂.2H₂O was 58% by weight. The compression strengths of all unsaturated polyester solified wastes were above 1,200 kg/cm², the leachabilities were low and the water resistances and thermal stabilities were good. The γ-ray resistances could be as high as 10[8ec3] Rad, and the volume reducing effect was 4-9 times better than the cement solidified wastes. |
本系統之摘要資訊系依該期刊論文摘要之資訊為主。