Disposition of salt waste from pyrochemical nuclear fuel processing

GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems

Volumn , Issue , 2007, Pages 1412-1415

  Vance, E R ^a  

^a AUSTRALIAN NUCLEAR SCIENCE AND TECHNOLOGY ORGANISATION   (Australia)

Author keywords

[No Author keywords available]

Indexed keywords

ALKALI METALS; CANNING; FISSION PRODUCTS; HEALTH; HOT ISOSTATIC PRESSING; HOT PRESSING; IRON; LEACHING; NUCLEAR ENERGY; NUCLEAR ENGINEERING; NUCLEAR FUELS; PIGMENTS; SILICATE MINERALS; STAINLESS STEEL;

ALKALI IONS; HOT-ISOSTATIC PRESSING (HIP); LEACH RESISTANCE; NUCLEAR FUEL PROCESSING; NUCLEAR-FUEL CYCLES; PYROCHEMICAL PROCESSING; SPODIOSITE; STAINLESS STEEL 316; WASTE FORMS;

FUELS;

EID: 45149134229     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (14)

1. T. KOYAMA, C. MATSUBARA, T. SAWA and H. TANAKA, Waste Form Development for Immobilization of Radioactive Halide Salt Generated from Pyrometallurgical Reprocessing,
2. S. M. FRANK, T. L. BARBER, T. DI SANTO, K. M. GOFF, S. G. JOHNSON, J-F JUE, M. NOY, T. P. O'HOLLERAN and W. SINKLER, Alpha-decay Radiation Damage Study of a Glass-bonded Sodalite Ceramic Waste Form, Mat. Res. Soc. Symp. Proc. Vol 713, Materials Research Society, Warrendale, PA, USA, p. 487 (2002).
3. Y. IKEDA, Y. TAKASHIMA, H. KOBAYASHI and H. IGARISHI, Conversion Reactions of Metal Chlorides into Oxide with Boric acid, J. Nucl. Sci. and Tech., 32, 1138 (1995).
4. I.W. DONALD, B. L. METCALFE, S. K. FONG, L. A. GERRARD, D. M. STRACHAN and R. D. SCHEELE, A glass-encapsulated calcium phosphste wasteform for the immobilization of actinide-, fluoride-, and chloride-containing radioactive wastes from the pyrochemical reprocessing of plutonium metal, J. Nucl. Mater., 361, 78 (2007).
5. N. SENAMUND, D. BERNACHE-ASSOLLANT, J. CARPENA and C. PIN, Synthesis and Characterization of Cs-Bearing Apatite, in Scientific Basis for Nuclear Waste Management XXII, Warrendale, PA, USA, p. 93 (1999).
6. G. J. MCCARTHY, High-Level Waste Ceramics: Materials Consideration, Process Simulation and Product Characterization, Nucl. Tech. 32, 92 (1977).
7. O. TERRA, F. AUDUBERT, N. DACHEUX, C. GUY and R. PODOR, Synthesis and characterization of uranium-bearing britholites, J. Nuc. Mater., 366, 70 (2007).
8. A. LAGHZIZIL, S. EL HAJJAJI, A. BOUHAOUSS and M. FERHAT, Ionic Conductivities of lithium fluorapatites, Solid State Ionics, 126, 245 (1999).
9. A. LAGHZIZIL, A. BOUHAOUSS, P. BARBOUX, R. MORINEAU and J. LIVAGE, Mixed ionic conductivities in sodium fluorapatites, Solid State Ionics, 67, 137 (1993).
10. D. S. DUNN, G. A. CRAGOLINO and N. SRIDHAR, Passive dissolution and localized Corrosion of Alloy 22 High-Level Waste Container Weldments, Mat. Res. Soc. Symp. Proc. Vol. 608, p. 89 (2000).
11. Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and Multiphase Glass Ceramics:The Product Consistency Test, ASTM Committee C26 (2000).
12. 3 (M = Li. Na, Cs, Sr), J. Radioanalytical and Nucl, Chem., 268, 617 (2006).
13. H. T. HAWKINS, B. E. SCHEETZ and G. D. GUTHRIE, Jr., Preparation of Monophasic [NZP] Radiophases: Potential Host Matrices for the Immobilization of Reprocessed Conmmercial High-Level wastes, Mat. Res. Soc. Symp. Vol 465, Materials Research Society, Warrendale, PA, USA, p. 387(1997).
14. A. P. MUKHAMET-GALEYEV, L. O. MAGAZINA, K. A. LEVIN, N. D. SAMOTOIN, A. V. ZOTOV and B. I. OMELIANENKO, The Interaction of Na-Al-P-Glass (Cs,Sr-bearing) with Water at elevated temperatures (70-250°C), Scientific Basis for Nuclear Waste Management XVIII, edited by T. Murakami and R. C. Ewing (Materials Research Society, Pittsburgh, PA, USA, 1995) p. 79.