Abstract

In-Can vitrification of spent mineral sorbents using DEM&MELT technology

In-Can vitrification of spent mineral sorbents using DEM&MELT technology

Caroline Michel1, Jean-François Hollebecque 1, Yann Papin 1, Aliénor Vernay 1, Regis Didierlaurent 2

1 CEA, ISEC, DES, DPME, Univ. Montpellier, Marcoule, France
2 Orano Recyclage, Prisme, 125 avenue de Paris, 92320 Châtillon, France

The numerous constraints associated with the management of highly active nuclear waste lead to the consideration of thermal treatment solutions given that these offer multiple advantages. Thermal treatments such as vitrification processes enable significant volume reduction, chemical waste stabilization and efficient radioelements containment in a glassy or glass-ceramic matrix. Moreover, vitrification processes have proven their adaptability to intermediate and high-level waste and can be flexible enough to accommodate a varied waste stream composition. In this context, Orano, CEA and ECM Technology, with the support of Andra through the French governmental program “Programme d’Investissement d’Avenir” have developed a new full scale In-Can vitrification tool, called DEM&MELT. The DEM&MELT process is an innovative and compact process that can be deployed in the existing premises or nearby. This process benefits from wide experience, coming from more than 40 years of operation at Marcoule first and then at La Hague plant with 6 high level waste vitrification lines currently operating. It has been designed to match the requirements and constraints of waste streams arising from remediation or decommissioning and dismantling operations; it is an easy-to-run process, equipped with a multiple resistive zone furnace and an off gas system designed to obtain high decontamination factors, which is crucial when it comes to the last step of a plant life. It benefits from a modular design, adaptable to nuclear operator needs and its operation takes into account the compositional uncertainties linked to such types of waste. The process allows a significant volume reduction in addition to safe radionuclide containment with moderate investment and operating costs. It can deal with a wide range of nuclear waste, ranging from intermediate to high-level waste, with different compositions and forms such as sludge, liquid or solid, including for the latter, one of the most common dismantling wastes: mineral sorbents, used for the radiological decontamination of effluents, such as zeolites or silicotitanates. This waste must be conditioned in a safe and durable manner and its powdery nature eliminated. This paper presents, through an up-scaling methodology, going from laboratory-scale tests up to full-scale pilot tests, the most significant results obtained, performed for mineral sorbent conditioning. The results are presented, with an emphasis on the process parameters such as temperature, waste loading and glass throughput. A first viscosity domain in which the DEM&MELT process can be applied, is approached. The wasteform properties and the radionuclide volatility are also presented. Perspectives on the evolution of the prototype are discussed.