[en] This proceedings describes the volume reduction of radioactive waste, the radioactive waste treatment technology, the decontamination and decommissioning, and the incineration and solidification of radioactive waste. Twenty two papers are submitted

[en] This paper describes the radioactive laundry waste treatment technology using the activated carbon and ion exchanger. 4 refs., 9 figs

[en] This paper describes the optimizing the fuel cycle, the uranium mining industry, the uranium enrichment industry, and the reprocessing recycling industry in France. 1 tab

[en] This paper describes the leaching fraction for each element after 150 days of leaching test, the comparison of k values in overall model and slope in log-log plot for surrogated strontium, and the comparison of dominant mechanism by overall model and slope in log-log plot for each element and ash content. 12 refs., 6 tabs., 8 figs

[en] This paper describes the introduction to research reactor decommissioning plan at KAERI, the background of technology development and demonstration, and the current status of the system decontamination technology for TRIGA reactors, concrete decontamination and dust treatment technologies, wall ranging robot and graphic simulation of dismantling processes, soil decontamination and restoration technology, recycling or reuse technologies for radioactive metallic wastes, and incineration technology demonstration for combustible wastes. 9 figs

[en] The treatment of wastes arising from BNFL's nuclear fuel cycle operations can be traced through a number of phases. The first was the development of vitrification and cementation for fresh arising and plants are now in operation. To handle the mixed, heterogeneous intermediate level wastes, retrieval, segregation and robust treatment processes are at an advanced stage of development, with all plants to be operational from 2002. BNFL is focusing attention on reducing waste management lifetime costs including reducing waste volumes of source. Technologies aimed at significant reductions are now being developed. The final phase, now in progress, recognizes the need for an integrated approach to advanced fuel cycle processes which incorporates BNFL holistic concept. (author) 6 refs., 1 fig

[en] An alpha-bearing waste incineration technology is being developed from this year, after licensing the β/γ-bearing waste incinerator as a treatment facility for burnable wastes generated from KAERI. Some foreign incineration technologies were reviewed. The alpha-bearing waste generation in Korea and their characteristics were also discussed. 15 refs., 3 tabs., 1 fig

[en] The decontamination of the urban building surfaces, based on the covering of clay suspensions, has been studied. An ammonium ion was effective as an ion exchanger of contaminated radionuclides. But, ammonium ion appears to be a powerful flocculant for clay suspension. We overcomes the phenomena by adding the hectorite as an additive, and developed stable clay decontamination agent which contained 15 times ammonium ion of cation exchange capacity of the natural clay. From the fluid behavior experiments of the developed clay decontamination agent were non-Newtonian and shear thinning fluid. The agents would be effectively sprayed on the contaminated building surfaces with very low spraying energy. Optimum synthetic condition were determined by the experiments of surface contact angle, fluid characteristics and decontamination behaviors. The decontamination performance of the clay decontamination agents on typical urban building construction materials, the flow behaviors of the suspensions, decontamination characteristics on specimen are reported in this paper. (author) 11 refs., 5 figs

[en] This paper describes the modelling of release of fission products from defective fuel elements and the development of computerized the coolant activity analysis program. 8 refs., 1 tab., 6 figs

[en] A graphic simulation program is developed to assimilate the remote dismantling process of research nuclear reactors. This program makes extensive use of a commercial robot graphic instruction program. Firstly, a realistic graphic model of research reactors are built along with various dismantling equipments. Using the graphic instruction languages provided by IGRIP, then, a graphic process simulation program is developed that operates interactively with the user. Consequently, it is made possible for a process designer to visualize an arbitrary dismantling sequence and interactively modify the process. It is expected that the developed system will be utilized as an effective operator aid in both design and execution phases of remote dismantling of research reactor. (author) 7 refs., tabs., 6 figs