[en] This is a report collected on the published items at the 7th Meeting of New Type Nuclear Fuel Materials held on March 14, 1996, as a part of the Yayoi Research Group. This meeting was added with a sub-title called 'Interface effect in the nuclear fission energy system', and contained 14 lectures. They were 1) Research trends on a phenomenon using finer granule in the uranium oxides fuels, 2) Rim region forming mechanism of MOX fuel pellet for the light water reactor, 3) Behavior at the rim region of MOX fuel pellet for the fast reactor, 4) Effect of sintering condition on texture of UO₂ pellet, 5) Experimental analysis of iodine behavior at the severe accident using ART code, 6) The environmental effects on vaporization of fission products (SrUO₃ and BaUO₃) by mass spectrometry, 7) Corrosion characteristics of the fuel pellet in water under high temperature and high pressure, 8) Behavior of high burnup PWR fuel under a condition of reactor accident, 9) Behavior of FP gas emission at a transient time, 10) Corrosion of coated pipes under BWR conditions, 11) Corrosion of the coated pipes under PWR conditions, 12) Fundamental study on radiation damage of zirconium alloy, 13) Adsorption process of the actinides against the minerals, and 14) Interface and colloid phenomena of the actinides. This meeting was held to be positioned for preliminary meeting of the second session of the international workshop, 'Interface effects in quantum energy system' to be held at Mito on August 21-23, 1996. (G.K.)