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Preliminary assessment of the controlled release of radionuclides from waste packages containing borosilicate waste glass.

机译：从含有硼硅酸盐废玻璃的废物包装中控制释放放射性核素的初步评估。

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The purpose of this report is to provide a preliminary assessment of the release-rate for an engineered barriers subsystem (EBS) containing waste packages of defense high-level waste borosilicate glass at geochemical and hydrological conditions similar to ...

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作者
B. P. McGrail D. M. Strachan D. W. Engle M. J. Apted P. W. Eslinger;
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年度 1990
页码 1-100
总页数 100
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Borosilicate Glass; Containment Systems; Corrosion; Diffusion; Dissolution; EDB/052002; Failures; Fission Products; High-Level Radioactive Wastes; Mass Transfer; Mathematical Models; Packaging; Performance; Radioisotopes; Radionuclide Migration; Solubility; Waste Forms;

机译：硼硅酸盐玻璃;遏制系统;腐蚀;扩散;溶解; EDB / 052002;失效;裂变产物;高放射性废物;传质;数学模型;包装;性能;放射性同位素;放射性核素迁移;溶解性;废物形式;

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专利

1. Waste Isolation Pilot Plant Performance Assessment: Radionuclide Release Sensitivity to?Diminished Brine and Gas Flows to/from Transuranic Waste Disposal Areas [J] . Brad A. Day, R.C. Camphouse, Todd R. Zeitler Nuclear engineering and technology . 2017,第2期

机译：废物隔离试验工厂的性能评估：放射性核素释放对盐水和进/出超铀废物处置区的气流减少的敏感性
2. An approach to the assessment of high-level radioactive waste containment - II: radionuclide releases from an engineered barrier system [J] . Sitakanta Mohanty, Richard B. Codell, Tae M. Ahn Nuclear Engineering and Design . 2000,第2a3期

机译：评估高水平放射性废物遏制的一种方法-II：工程屏障系统释放的放射性核素
3. Risk-informed assessment of radionuclide release from dissolution of spent nuclear fuel and high-level waste glass [J] . Ahn Tae M. Nuclear Engineering and Design . 2017,第Juna期

机译：废核燃料和高放废玻璃溶解过程中放射性核素释放的风险评估
4. Preliminary evaluation of waste package releases using drift-scale thermo-hydrological analyes [C] . Jerry A.McNeish, Mark Reeves, Timothy F.Dale, Sixth Annual International Conference on High Level Radioactive Waste Management 1995 Las Vegas, Nevada, April 30-May 5, 1995 . 1995

机译：使用漂移规模的热水文分析对废物包装的释放进行初步评估
5. The Effect of Cesium on the Durability and Hydration Rind Thickness of a Simulated Borosilicate Nuclear Waste Glass. [D] . Svee, Wayne. 1994

机译：铯对模拟硼硅酸盐核废玻璃的耐久性和水合线厚度的影响。
6. An Assessment of Initial Leaching Characteristics of Alkali-Borosilicate Glasses for Nuclear Waste Immobilization [O] . Osama M. Farid, Michael I. Ojovan, A. Massoud, 2019

机译：固定核废料的碱金属硼硅酸盐玻璃的初始浸出特性评估
7. Release of neptunium from neptunium-doped borosilicate waste glass. [O] . Shinichi NAKAYAMA, Tsunetaka BANBA 1989

机译：从Neptunium掺杂的硼硅酸盐废玻璃中释放Neptunium。

Preliminary assessment of the controlled release of radionuclides from waste packages containing borosilicate waste glass.

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