Author:
Garcia-Serrano J.,Serrano J. A.,Diaz-Arocas P. P.,Quiñones J.,Almazan J. L. R.
Abstract
AbstractSimulated high-bumup nuclear fuel (SIMFUEL) has been leached in synthetic groundwater under oxic conditions. SIMFUEL pellets were ground and sieved to two particle sizes (50–100 and 100–315 μm). An extensive solid characterization of the fragments was carried out by various techniques. Elemental analysis has also been performed prior to the leaching tests.The release of U and the minor components (Mo, Ba and Sr) was monitored during the long term dissolution experiments (350 days). These minor components exhibit a trend similar to uranium, high release at the beginning followed by a plateau. The M/U calculated ratios show different behavior although after a period of time, depending on the particle sizes, constant ratios were observed.SIMHUEL powder was used in order to simulate the physical effect of bum-up on the fuel structure. This fact seems to play an important role on the uranium release. A comparison with the results given in the literature for SIMFUEL pellet leaching tests shows good agreement with the values reported.
Publisher
Springer Science and Business Media LLC
Reference10 articles.
1. [7] Casas I. , Sandino A. , Cececi M. S. , Bruno J. , Ollila K. . SIMFUEL dissolution studies in granitic groundwater. SKB Technical Report 91-34
2. Microstructural features of SIMFUEL — Simulated high-burnup UO2-based nuclear fuel
3. [8] Díaz-Arocas P. P. , Garcia-Serrano J. , Quiñones J. , Geckeis H. and Grambow B. , paper presented at Migration 95, Saint Malo (France), to be published in Radiochimica Acta.
4. The dissolution of unirradiated UO2 fuel pellets under simulated disposal conditions
5. The corrosion of spent UO2 fuel in synthetic groundwater
Cited by
1 articles.
订阅此论文施引文献
订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献