Fundamental study on the separation and solidification of radwaste with hydrous titanium(IV) oxides modified with either silicon or zirconium

硅锆改性水合四氧化钛分离与固化放射性废物的基础研究

• 批准号: 04680222
• 负责人: YAMAZAKI Hiromichi
• 金额: $ 1.15万
• 依托单位: Tohoku University
• 依托单位国家: 日本
• 项目类别: Grant-in-Aid for General Scientific Research (C)
• 财政年份: 1992
• 资助国家: 日本
• 起止时间: 1992 至 1993
• 项目状态: 已结题
• 来源: https://kaken.nii.ac.jp/en/grant/KAKENHI-PROJECT-04680222/
• 关键词: Ion Exchange; Solidification; Hydrous Titanium-Silicon Oxide; Caesium Ion; Strontium Ion; Hydrous Titanium-Zirconium Oxide; Thorium Ion; Uranium Ion; 無機イオン交換体; 浸出率; 含水酸化チタン-ケイ素; 含水酸化チタン-ジルコニウム

Inorganic ion-exchangers are a group of promising materials for the solidification of radioactive liquid waste, since they have high sorption capacity for radioactive species, and can be converted into stable waste forms suitable for disposal by simple thermal treatment. The potentiality of the selective removal and immobilizatin of radioactive Cs^+, Sr^<2+>, Co^<2+>, Eu^<3+>, Th^<4+>, and UO_2^<2+> ions in hydrous Ti^<IV>-Si oxide (TS) and hydrous Ti^<IV>-Zr oxide (TZ) has been studied experimentally : The distribution coefficient and sorption capacity for these ions at various conditions in solutions, the structure and the composition of the exchangers in relevant ionic forms at high temperatures, and the leaching rate from calcined exchangers into water and a 0,01M HNO_3 solution at room temperature.TS uptakes these cations much more than TZ does, but the separation of Th^<4+> and UO_2^<2+> from Cs^+ and Sr^<2+> is performed more completely on TZ than TS.The dissolutions of Sr^<2+>, Co^<2+>, Eu^<3+> and Th^<4+> from calcined TS and TZ exchangers at (〕SY.gtoreq.〔)900ﾟC are very slow due to crystallization of strontium titanium silicate or titanates of Co^<2+>, Eu^<3+> and Th^<4+>. The leaching rate of Cs^+ and UO_2^<2+> from TS significantly decreases with increasing temperature for thermal treatment, while such effect is not observed in TZ due to the formation of soluble Cs_2O and alpha-U_3O_8. In calcined TS exchangers in the Cs^+ and UO_2^<2+> forms, most of the intense X-ray diffraction peaks cannot be assigned to known compounds, indicating the formation of crystallographycally unknown caesium titanium silicate and uranium titanium silicate.Based on these results, TS is superior to TZ in the sorption capacity and fixation capability of various kinds of radionuclides and considered as a promising material for the solidification of radwaste.

无机离子交换剂对放射性核素具有很高的吸附能力，通过简单的热处理可以将其转化为稳定的废物形态，是一种很有前途的放射性废液固化材料。实验研究了水合Ti^ -Si氧化物（TS）和水合Ti^ -Zr氧化物（TZ）对Cs^+、Sr^&lt;2 +&gt;、Co^&lt;2+&gt;、Eu^&lt;3+&gt;、Th^&lt;4+&gt;和UO_2^&lt;2+&gt;离子选择性去除和固定<IV><IV>能力。研究了这些离子在溶液中的分配系数和吸附容量，高温下相应离子形式的交换剂的结构和组成，以及焙烧后的交换剂在室温下对水和0.01M HNO_3溶液的浸出率。TZ对Th^&lt;4+&gt;、UO ^&lt;2+&gt;与Cs^+、Sr^&lt;2+&gt;的分离比TS更彻底。()900由于硅酸锶钛或Co^2+、Eu^3+和Th^4+的钛酸锶钛的结晶，所以MgAlC非常缓慢。TS中Cs^+和UO_2^&lt;2+&gt;的浸出率随热处理温度的升高而显著降低，而TZ中由于生成了可溶的Cs_2O和α-U_3O_8，没有观察到这种影响。在Cs^+和UO_2^2+形式的煅烧TS交换剂中，大多数强X射线衍射峰不能归属于已知化合物，表明形成了晶体学上未知的硅酸铯钛和硅酸铀钛。TS对各种放射性核素的吸附能力和固定能力均上级TZ，被认为是一种很有前途的放射性材料。放射性废物固化。

项目成果

Yasushi Inoue: "Fundamental Study on the Solidification of Cs^+ and Sr^<2+> with Hydrous Ti^<IV> Oxide Modified with Si and Zr" Scientific Basis for Nuclear Waste Management. 16. 117-122 (1993)

Yasushi Inoue：“用Si和Zr改性的水合Ti^<IV>氧化物固化Cs^和Sr^<2>的基础研究”核废料管理的科学基础。

Y.Inoue: "Fundamental Study on the Solldification of Cs^+ and Sr^<2+> with Hydrous Ti^4 Oxide modified with either Sior Zr" Proc.XVl International Symposium on the Scientific Basis for Nuclear Waste Management,Nov.30-Dec.4 1992,Boston,Mass.

Y.Inoue：“用 Sior Zr 改性的水合 Ti^4 氧化物对 Cs^ 和 Sr^<2> 进行固溶的基础研究”Proc.XVl 核废物管理科学基础国际研讨会，11 月 30 日至 12 月

Y.Inoue, H.Yamazaki, and R.Erza: "Fundamental Study on the Solidificarion of Cs^+ and Sr^<2+> with Hydrous Ti^<IV> Oxide Modified with Si and Zr" Scientific Basis for Nuclear Waste Management. XVI. 117-122 (1993)

Y.Inoue、H.Yamazaki 和 R.Erza：“用 Si 和 Zr 改性的水合 Ti^<IV> 氧化物固化 Cs^ 和 Sr^<2> 的基础研究”核废物管理的科学基础。

H.Yamazaki: "Studies of the Hydrous Silcon-Titanium(IV) Oxide Ion Exchanger II.Affinity for Various Cations and Thermal Stability" Bulletin of the Chemical Society of Japan. 63. 2601-2609 (1990)

H.Yamazaki：“水合硅-钛（IV）氧化物离子交换剂的研究 II.各种阳离子的亲和力和热稳定性”日本化学会会刊。

H.Yamazaki: "Ion-Exchange Properties and Thermal Stabilities of Hydrous Titanium(IV)-Zirconim(IV) Oxide Ion Exchangers." Bulletin of the Chemical Society of Japan. 64. 566-575 (1991)

H.Yamazaki：“水合钛 (IV)-锆 (IV) 氧化物离子交换剂的离子交换性能和热稳定性。”