A possible substitution of UO 2 for research purposes is the cerium dioxide (CeO 2 ) owing to its chemical and physical properties. Neutronic properties are different and fission is absent in the case of CeO 2 ; however, similarities were studied recently to have a possibility to compare the neutronic influence of secondary additives into the matrix. This paper deals with increasing the thermal conductivity of UO 2 nuclear fuel on surrogate material (CeO 2 ); the main focus of the research is given on the sintering behaviour of CeO 2 . The incorporation of highly thermally conductive material (SiC) is the investigated concept of thermal conductivity enhancement. Conventional sintering and spark plasma sintering (SPS) were applied to compare the behaviour of CeO 2 and UO 2 reported in the literature. High temperature thermal conductivity measurements did not confirm the positive influence of SiC additive inside the CeO 2 matrix mainly due to grain boundary disruptions. Similar behaviour was also previously reported for UO 2 pellets with SiC.
In this work we present the results for the investigation of intermediate-mass fragment (IMF) production with the proton-induced reaction at 660 MeV on 238 U and 237 Np target. The data were obtained with the LNR Phasotron U-400M Cyclotron at Joint Institute for Nuclear Research (JINR), Dubna, Russia. A total of 93 isotopes, in the mass range of 30 < A < 200, were unambiguously identified with high precision. The fragment production cross sections were obtained by means of the induced-activation method in an off-line analysis. Mass-yield distributions were derived from the data and compared with the results of the simulation code CRISP for multimodal fission. A discussion of the superasymmetric fragment production mechanism is also given.
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