合金 690 在模拟玻璃化条件下暴露于含 P2O5 的硼硅玻璃时的相互作用行为

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2024-10-11 DOI:10.1016/j.pnucene.2024.105480

Mohit Rattanpal , Poulami Chakraborty , Kulwant Singh , Soudamini N , R.K. Mishra , Pranesh Sengupta , R. Tewari

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引用次数: 0

摘要

本研究调查了在核燃料循环（NFC）后端高放射性废物玻璃化过程中遇到的典型玻璃浇注温度下，合金 690 与两种玻璃（原始硼硅酸盐玻璃和含 P2O5 的硼硅酸盐玻璃）之间的相互作用。在合金 690/玻璃的界面上观察到了两种玻璃的部分结晶，在界面上形成了某些结晶相，但并不完全相同。这些结晶相的密度明显高于周围玻璃的密度，这让人担心这些反应产物会沉淀在熔炉底部。这种沉淀可能会阻塞冻结阀，从而停止玻璃化过程。此外，在长期暴露于含 P2O5 的硼硅玻璃中的合金表面上，晶间凹槽会消失。这种现象归因于高碱性和氧化性 P2O5 玻璃的强烈腐蚀作用，导致合金 690 的整个暴露表面剥落。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

Interaction behaviour of alloy 690 upon exposure to P2O5 containing borosilicate glass at simulated vitrification conditions

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Interaction behaviour of alloy 690 upon exposure to P2O5 containing borosilicate glass at simulated vitrification conditions

This study investigates the interaction between alloy 690 and two types of glasses: pristine borosilicate and P₂O₅-containing borosilicate glass, at typical glass pouring temperatures encountered during the vitrification of high-level radioactive waste in the back-end of Nuclear Fuel Cycle (NFC). Partial crystallization of both glasses was observed at the alloy 690/glass interface, with certain, though not entirely identical, crystalline phases forming at the interface. The density of these crystalline phases is significantly higher than that of the surrounding glass, which raises concerns about these reaction products settling at the bottom of the furnace. Such sedimentation could potentially obstruct the freeze valve, thereby halting the vitrification process. Additionally, intergranular grooves on the alloy surface exposed to P₂O₅-containing borosilicate glass were found to disappear with prolonged exposure. This phenomenon is attributed to the strong corrosive action of the highly basic and oxidizing P₂O₅-bearing glass, leading to the peeling away of the entire exposed surface of alloy 690.

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来源期刊

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.