Application of Void-Free Filling Technology for Additional Safety Barriers Creation during Uranium-Graphite Reactors Decommissioning

Abstract

The paper presents the results of the best material selection for additional safety barrier construction during uranium-graphite reactors decommissioning. The research findings show that the best material for safety barriers is clay-containing natural material of various types with counter-migrational and counter-filtrational qualities. We have demonstrated a technology for void-free filling of cavities in the reactor space of under-decommissioning uranium-graphite reactors on the site of JSC Pilot and Demonstration Center for Decommissioning of Uranium-Graphite Nuclear Reactors (PDC UGR). This will make it possible to construct reliable man-made geo-barriers and prevent the release of radionuclides from the repository into the environment for thousands of years.

Experimental Studies on Chemical Activation of Cementitious Materials from Smelting Slag of Copper and Nickel Mine

“…The nonferrous smelting industry has made a great contribution to China’s economic development, but also caused serious environmental problems, like occupation of land, and pollution of the environment and groundwater [6,7,8]. Filling technology was developed rapidly as an effective way to overcome the mining problems in the past 20 years [9,10,11]. On the other hand, fundamental scientific research is very important and urgent to improve the use of filling mineral resources and to solve the stability of current mining filling material and high processing cost [12,13,14].…”

On the Challenge Associated with the Final Stage of Irradiated Graphite Management from Water-Graphite NPP Reactor Units

“…Для изоляции графитовой кладки в реакторном объеме была применена технология заполнения внутренних полостей барьерными смесями на основе природной глины . Подбор материала для создания дополнительных барьеров безопасности был проведен ИФХЭ РАН по следующим критериям [10,11]: низкая водопроницаемость; низкие коэффициенты диффузии; высокая сорбционная способность по отношению к радионуклидам; стабильность свойств на период сохранения потенциальной опасности РАО; отсутствие компонентов, способных повышать мобильность радионуклидов при эксплуатации барьера; стабильность свойств барьера в…”