참고문헌
- KEPRI-94Z-17 A Feasibility Study on the Vitrification of Low-level Radioactive Waste KEPRI-KEPCO
- J. Kor. Ceram. Soc. v.38 no.9 Studies on the Physicochemical Properties of Vitrified Forms of the Low-and Intermediate-level Radioactive Waste(in Kor.) C-W. Kim;B-C. Park;H-M. Kim;T-W. Kim;K. Choi;J-K. Park;S-W. Shin;M-J. Song
- Ceramist v.3 no.6 Vitrification of Radioactive Waste: An Environmentally friendly Treatment Technology C-W. Kim;K. Choi;J-K. Park;S-W. Shin;M-J. Song
- Development of Vitrification Technology Development for Low-and Intermediate-Level Radioactive Waste (Ⅱ), NETEC-KHNP
- INEEL/EXT-98-00269 GlassForm Version 1.1 : An Algorithm for Generating Preliminary Glass Formulations for Waste Streams K. Vinjamuri;S. T. Wood;L. O. Nelson
- J. Am. Ceram. Soc. v.73 no.10 Control of Radioactive Waste Glass Melters: 1, Preliminary General Limits at Savannah River D. F. Bickford;A. Applewhite-Ramsey;C. M. Jantzen;K. G. Brown https://doi.org/10.1111/j.1151-2916.1990.tb06692.x
- Pacific Northwest Laboratory Nuclear Waste Glass Compositional Limitations L. A. Chick;J. L. Swanson;D. S. Goldman
- Viscosity and Electrical Conductivity of Glass Melts as a Function of Waste Composition, Savannah River Laboratory M. J. Poldinec;J. R. Wiley
- TR-105912, Research Project WO3500-29 Vitrification of Low-level Radioactive Waste EPRI
- Federal Register v.55 no.60 Method 1311 Toxicity Characteristic Leaching Procedure US EPA
- WSRC-TR-90-539, Product Consitency Tests(PCT)(Method Version 3.0) C. M. Jantzen;N. E. Bibler
- Scientific Basis for Nuclear Waste Management XIX v.412 Redox State and Transition Metal Concentration Effects on Microstructure of Simulated Simplified Glasses for Waste Immobilization C-W. Kim;I. S. Muller;A. C. Buechele;I. L. Pegg;P. B. Macedo
- Compressive Strength of Cylindrical Concrete Specimens, ASTM C39
- Ph.D. Dissertation, The Catholic University of America Studies of the Properties of Multicomponent Waste Glasses Containing Transition Metal Oxides C-W. Kim
- Principles of Instrumental Analysis D. A. Skoog;J. J. Leary
- TR.A00NJ01.M2001.12 Summary Report on the Long Duration Pilot Plant Test with Simulated Combustible Low-and Intermediate-level Radioactive Waste NETEC-KHNP
- Ph.D. Dissertation, Chungnam National University Leach Study on the Simulated Nuclear Waste Glass for the High-level Radioactive Waste S-S. Kim
- J. Kor. Ceram. Soc. v.38 no.9 Studies on the Physico Chemical Properties of Vitrified Forms of the Low- and Intermediate-level Radioactive Waste(in Kor.) C-W. Kim;B-C. Park;H-M. Kim;T-W. Kim;K. Choi;J-K. Park;S-W. Shin;M-J. Song
- Development of Vitrification Technology Development for Low- and Intermediate-level Radioactive Waste (Ⅱ) NETEC-KHNP
- Technical Position on Waste Form US NRC
- Vitrification Technologies for Treatment of Hazardous and Radioactive Waste US EPA
- Glastech. Ber. v.60 no.12 Sulfur Chemistry in a Borosilicate Melt: Part 1. Redox Equilibrium and Solubility H. D. Schreiber;S. J. Kozak;P. G. Leonhard;K. K. McManus
- Radioactive Waste Forms for the Future W. Lutze;R. C. Ewing(eds.)
- Center for Glass Chemistry Sulfur Chemistry in a Borosilicate Melt, Part I: Redox Equilibria and Solubility H. D. Schreiber
- J. Non-Cryst. Solids v.181 Solvations of Redox Ions in Glass-forming Silicate Melts H. D. Schreiber;M. T. Coolbaugh https://doi.org/10.1016/S0022-3093(94)00516-8
- J. Am. Ceram. Soc. v.70 no.8 Redox Chemistry in Candidate Glasses for Nuclear Waste Immobilization H. D. Schreiber;A. L. Hockman https://doi.org/10.1111/j.1151-2916.1987.tb05712.x
- Ceram. Trans. v.39 Development of the Minimum Additive Waste Stabilization(MAWS) Program for Fernald I. L. Pegg https://doi.org/10.1111/j.1151-2916.1987.tb05712.x
- WebElements bulletin
피인용 문헌
- A Case Study on Operation of Off-Gas Treatment System of Radioactive Waste Vitrification Facility vol.38, pp.5, 2016, https://doi.org/10.4491/KSEE.2016.38.5.249