참고문헌
- Kim, C.-W., Choi, K.-S., Park, J.-K., Shin S.-W. and Soung, M.-J., "Radioactive waste vitrification," Ceramist, 3(6), 55-66(2000).
- Donald, I. W., "Waste immobilisation in glass and ceramic based hosts: Radioactive, toxic and hazardous wastes," Wiley-Blackwell, p. 526(2010).
-
Ghussn, L., Martinelli, J. R. and Russo, D. O., "Comparison of the corrosion resistance of sintered and monolithic iron phosphate and niobium phosphate glasses containing
$U_3O_8$ ," Glass Technol., 50, 269-272(2009). - Low-and Intermediate-Level radioactive Waste (LILW) incineration standards, Notification No. 2014-60 of the Nuclear Safety and Security Commission (NSSC), enforcement in Nov. 11th(2014).
- Standards on radiation protection, etc., Notification No. 2014-34 of the Nuclear safety and security commission, enforcement in Nov. 11th(2014).
- USA 10 CFR 50 appendix I.
- IAEA, "Design and operation of off-gas cleaning systems at high level liquid waste conditioning facilities," Technical reports series No.291(1988).
- Boing, L. E., "Decontamination Technologies," US DOE report, Argonne National Laboratory Decommissioning Program, p. 10(2011).
- Kim, C. W. et al., "Radioactive wastes vitrification using induction Cold Crucible Melter: Characteristics of vitrified form," J. Korean Ceram. Soc., 39(6), 576-581(2002). https://doi.org/10.4191/KCERS.2002.39.6.576
- Bonnetier, A., Hollebecque, J. F., Lacombe, J., Quang, R. D. and Rivat, P., "Development of an advanced cold crucible for direct induction melting of glass," In Proceedings of the 4th International Conference on Electromagnetic Processing of Materials, Lyon, France(2003).
- Ji, P.-G., Yang G.-H. and Shin, S.-W., "Characteristicson off-gas treatment system of the Low-and Intermediate-Level radioactive Waste (LILW) vitrification facility," Proc. Korean Radioact. Wastes Soc., 5(2), 137-138(2007).
- Quang, R. D., Petitjean, V., Hollebecque, F., Pinet, O., Flament, T. and Prod'homme, A., "Vitrification of HLW produced by uranium/molybdenum fuel reprocessing in COGEMA's Cold Crucible Melter," WM'03 Conference, Tucson, AZ(2003).
- Bonniaud, R., Sombret C., and Rancon, D., "Vitrification of fission products concentrated solutions: Technological studies," Symposium on Treatment and Storage of High-Level Radioactive Waste, IAEA Vienna, Austria(1962).
- Bonniaud, R., Jouan, A. and Sombret, C., "Large scale waste glass production,"high-Level Radioactive Solid Waste Forms (Proc. Conf. Denver, 1978), Rep. NUREG/CP-0005, US Nuclear Regulatory Commission, Washington, DC, pp. 157-197 (1978).
- Chotin, M., Bonniaud, R., Jouan, A. and Rabot, G., "Operational experience of the first industrial HLW vitrification plant," paper presented at Symp. Cincinnati, April-May(1979).
- Allan, B. Barnes, et al., "Feasibility evaluation and retrofit plan for CCIM deployment in the DWPF at SRS-8118," WM'08 Conference, Phoenix, AZ(2008).
- Chapman, C. C., "Experience with a Joule-Heated Ceramic Melter while converting simulated High-Level Waste to glass," BNWL-2071, Pacific Northwest Laboratory, Richland, WA (1976).
- Kessler, J. L. and Randall, C. T., "Performance of a large-scale melter and off-gas system utilizing simulated SRP DWPF waste," Waste Management (Proc. Symp. Tucson, 1984), Arizona Board of Regents, Tucson, AZ(1984).
- Jain, V., "Survey of Waste Solidification Process Technologies," Defense Waste Processing Facility at Savannah River Site, U.S. Nuclear Regulatory Commission, Washington, DC, pp. 17-28(2001).