1. K. Kim, D. Lee, C. Kim, I. Kuk, Development of high-loading U–Mo alloy fuel by centrifugal atomization, in: Proceedings of the 19th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Seoul, 1996.
2. G. Hofman, M. Finlay, Y. Kim, Post irradiation analysis of low enriched U–Mo/Al dispersion fuel miniplate tests, RERTR 4&5, in: Proceedings of the 26. International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), 2004.
3. M. Ripert, S. Dubois, P. Boulcourt, S. Naury, P. Lemoine, Iris 3 experiment Status and result of thickness increase, in: Proceedings of the 10th International Topical Meeting on Research Reactor Fuel Management (RRFM), Sofia, 2006.
4. P. Lemoine, J. Snelgrove, N. Arkhangelsky, L. Alvarez, UMo dispersion fuel results and status of qualification programs, in: Proceedings of the 8th International Topical Meeting on Research Reactor Fuel Management (RRFM), Munich, 2004.
5. Irradiation behavior of ground U(Mo) fuel with and without Si added to the matrix