Below is a selection of publications by users of CAMECA Shielded EPMA:
MOX fuel microstructural evolution during the VERDON-3 and 4 tests. C. Le Gall, S. Reboul, L. Fayette, T. Blay, I. Zacharie-Aubrun, I. Félines, K. Hanifi, I. Roure, P. Bienvenu, F. Audubert, Y. Pontillon, J-L Hazemann. Journal of Nuclear Materials. Volume 531, 1 April 2020, 152015. Read full article
Fission product speciation in the VERDON-3 and VERDON-4 MOX fuels samples. C. Le Gall, S. Reboul, L. Fayette, T. Blay, I. Zacharie-Aubrun, I. Félines, K. Hanifi,
I. Roure, P. Bienvenu, F. Audubert, Y. Pontillon, J-L Hazemann. Journal of Nuclear Materials. Volume 530, March 2020, 151948. Read full article
Electron probe microanalysis of irradiated FUTURIX-FTA U-Pu-Zr alloy with added minor actinides. Karen E. Wright, Jason M.Harp and Luca Capriotti. Journal of Nuclear Materials. Volume 526, 1 December 2019, 151745. Read full article
Heat capacity of Bi2UO6. K. Popa, O. Beneš, P. E. Raison, J-C. Griveau, P. Pöml, E. Colineau, R.J.M. Konings, J. Somers. Journal of Nuclear Materials, Vol. 465, p. 653-656, doi:10.1016/j.jnucmat.2015.06.055 (2015)
ECRIX-H Irradiation: Post-Irradiation Examinations and Simulations. S. Béjaoui, J. Lamontagne, E. Esbelin, J.M. Bonnerot, E. Brunon, P. Bourdot, Y. Pontillon. Presentation at FP7 FAIRFUELS Workshop, Stockholm, Sweden, February 2011
Chemical States of Fission Products and Actinides in Irradiated Oxide Fuels Analyzed by Thermodynamic Calculation and Post-Irradiation Examination. K. Kurosaki, K. Tanaka, M. Osaka, Y. Ohishi, H. Muta, M. Uno, S.Yamanaka. Progress in Nuclear Science and Technology, Vol. 2, p.5-8 (2011)
Microstructural evolution and Am migration behavior in Am-containing MOX fuels at the initial stage of irradiation. K. Tanaka, S. Miwa, I. Sato, M. Osaka, T. Hirosawa, H. Obayashi, S. Koyama, H. Yoshimochi, K. Tanaka. Presentation at the 10th OECD Nuclear Energy Agency Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Mito, Japan, October 2008
On the Oxidation State of UO2 Nuclear Fuel at a Burn-Up of Around 100 MWd/kgHM. C.T. Walker, V.V. Rondinella, D. Papaioannou, S. Van Winckel, W. Goll, R. Manzel. Journal of Nuclear Materials, Vol. 345, p. 192–205 (2005)
Analysis of High Radioactive Materials in Irradiated DUPIC SIMFUEL Using EPMA. Jung, Yang Hong; Yoo, Bang Ok; Joo Yong Sun; Kim, Hee Mun; Jung In Ha; Kim, Myung Han. Journal of the Korean Radioactive Waste Society, Vol. 2(2), p. 125-133 (2004)
Multiple voltage electron probe microanalysis of fission gas bubbles in irradiated nuclear fuel. M. Verwerft. Journal of Nuclear Materials, Vol. 282, p. 97-111, doi:10.1016/S0022-3115(00)00421-9 (2000)