三聚二硅燃料颗粒的腐蚀试验

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY
L. A. Karpyuk, V. I. Kuznetsov, V. V. Novikov, E. N. Mikheev, A. V. Fedotov, A. V. Lysikov, R. B. Sivov, N. M. Rysev, O. A. Bakhteev, M. A. Lutkov
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引用次数: 0

摘要

这项研究旨在确定二硅化三铀颗粒在类似小型核电厂(SNPP)模式条件下的腐蚀稳定性。为此,使用纳博热马弗炉(德国)在压力为 16.2 兆帕斯卡、温度为 331 ± 3 °C、等温暴露时间为 4 小时和 10 小时的条件下,在装有蒸馏水(去离子水)的锆迷你高压釜中与二氧化铀进行了腐蚀对比试验。等温切片的温度由微型高压灭菌器附近的铼钨热电偶校准和控制。暴露 4 小时后,二硅化三钛样品表面轻微氧化,但未被破坏。10 小时后,样品被氧化,细小颗粒轻微脱落。样品质量的增加与细颗粒的剥离合计为 0.5%(25 毫克)。在这些氧化模式下,没有在标准燃料颗粒上检测到二氧化铀。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Corrosion tests of triuran disilicide fuel pellets

Corrosion tests of triuran disilicide fuel pellets

The study aims to determine the corrosion stability of triuranium disilicide pellets under the conditions similar to small-nuclear plant (SNPP) modes. For this, corrosion tests were carried out in comparison with uranium dioxide in zirconium mini-autoclaves with distilled (deionized) water at a pressure of 16.2 MPa using a Nabertherm muffle furnace (Germany) at a temperature of 331 ± 3 °C and isothermal exposure of 4 and 10 h. The temperature of isothermal sections was calibrated and controlled using a rhenium-tungsten thermocouple located near the mini-autoclaves. After a 4h exposure, the surface of the triuranium disilicide sample was slightly oxidized without destruction. After 10 h, it was oxidized with a slight detachment of fine particles. The mass gain of the sample together with exfoliated fine particles comprised 0.5% (25 mg). No uranium dioxide was detected on the standard fuel pellet under these oxidation modes.

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来源期刊
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
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