Journal of Inorganic Materials, Volume. 35, Issue 3, 271(2020)
[1] IZUKA M, KINOSHITA K, KOYAMA T. Modeling of anodic dissolution of U-Pu-Zr ternary alloy in the molten LiCl-KCl electrolyte[J]. J. Phys. Chem. Solids, 427-432(2005).
[2] PARK B H, LEE I W, SEO C S. Electrolytic reduction behavior of U3O8 in a molten LiCl-Li2O salt[J]. Chem. Eng. Sci., 3485-3492(2008).
[3] HUR J M, HONG S S, LEE H S. Electrochemical reduction of UO2 to U in a LiCl-KCl-Li2O molten salt[J]. J. Radioanal Nucl. Chem., 851-854(2013).
[4] EBERT W L, SNYDER C T, RILEY B J et al. Designing Advanced Ceramic Waste Forms for Electrochemical Processing Salt Waste[J]. Fuel Cycle Research & Development, Argonne National Laboratory, FCRD-MRWFD-2016-000038(2016).
[5] GOMBERT D R, COUNCE A, COZZI J et al. Global Nuclear Energy Partnership Integrated Waste Management Strategy Waste Treatment Baseline Study Vol. I and Vol. II. DOE report GNEP- WAST-AI-RT-2007-000324[J]. Idaho National Laboratory(2007).
[6] SIMPSON M F, SACHDEV P. Development of electrorefiner waste salt disposal process for the EBR-II spent fuel treatment project[J]. Nucl. Eng. Technol., 175-182(2008).
[7] RICHARDSON J W. Salt-Occluded Zeolite Waste Forms: Crystal Structures and Transformability, Scientific Basis for Nuclear Waste Management XXIII, Symposium, December 2-6,1996[C]. Boston, Massachusetts.
[8] FRANK S M. Alpha Decay Damage Study of a Glass-Bonded Sodalite Ceramic Waste Form.” Scientific Basis for Nuclear Waste Management XXV, Symposium, November 26-29, 2001[C]. Boston, Massachusetts.
[9] MORSS LR, MERTZ C J, KROPF A J et al. Properties of Plutonium- Containing Colloids Released from Glass-Bonded Sodalite Nuclear Waste Form, Scientific Basis for Nuclear Waste Management XXV. Proceedings of the Materials Research Society Symposium, November 26-29,2001[C]. Boston, Massachusetts.
[10] MORSS L R, JOHNSON S G, EBERT W L et al. Corrosion Tests with Uranium- and Plutonium-Loaded Ceramic Waste Forms[J]. Argonne National Laboratory report ANL-02/09..
[11] LI H, VIENNA J D, HRMA P et al. Nepheline Precipitation in High Level Waste Glass: Composition Effects and Impact on Waste Form Acceptability, Scientific Basis for Nuclear Waste Management XX[C]. Materials Research Society Symposium Proceedings, 465, 261-268(1997).
[12] VOLKOVICH V A, GRIFFITHS T R, THIED R C. Formation of lanthanide phosphates in molten salts and evaluation for nuclear waste treatment[J]. Phys. Chem. Chem. Phys., 3053-3060(2003).
[13] EUN H C, KIM J H, CHO Y Z et al. An optimal method for phos- phorylation of rare earth chlorides in LiCl-KCl eutectic based waste salt[J]. J. Nucl. Mater., 175-178(2013).
[14] LIQORNIK M, MARCUS Y. Ion exchange in molten salts.V. potassium zeolite-a as an ion exchanger in nitrate melts[J]. J. Phys. Chem., 75, 2523-2525(1971).
[15] LAMBREGTS M J, FRANK S M. Characterization of cesium containing glass-bonded ceramic waste forms[J]. Micropor. Mesopor. Mat., 1-9(2003).
[16] EBERT W. Testing to Evaluate the Suitability of Waste Forms Developed for Electrometallurgically Treated Spent Sodium-Bonded Nuclear Fuel for Disposal in the Yucca Mountain Repository[J]. Argonne National Laboratory report ANL-05/43(2005).
[17] O’HOLLERAN T P, JOHNSON S G. Ceramic Waste Form Intergranular Glass Composition[J]. ANL-W Memo ENT-NWM-(TPO)- 99-010(1999).
[18] FRANK S, O’HOLLERAN T P. Product Consistency Test and Density Measurement Results from Surrogate CWF Inter-Granular Glass Material[J]. ANL-W Memo ENT-MS-(SMF)-04-005(2004).
[19] EBERT W L, LEWIS M A, JOHNSON S G. The precision of product consistency tests conducted with a glass-bonded ceramic waste form[J]. J. Nucl. Mater., 37-51(2002).
[20] BATEMAN K J, MORRSNA M C, RAPPEYE D S et al. Scale up of ceramic waste forms for electrorefner salts produced during spent fuel treatment[J]. Journal of Nuclear Fuel Cycle and Waste Technology, 55-75(2015).
[21] MORRISON M C, BATEMAN K J, SIMPSON M F. Scale of Ceramic Waste Forms for the EBR-II Spent Fuel Treatment Process[J]. Idaho National Laboratory, INL/CON-10-19439(2010).
[22] RILEY B J, RIECK B T, MCCLOY J S et al. Tellurite glass as a waste form for mixed alkali-chloride waste streams: candidate materials selection and initial testing[J]. J. Nucl. Mater., 29-37(2012).
[23] MCCLOY J S, RILRY B J, LIPTON A S et al. Structure and chemistry in halide lead-tellurite glasses[J]. J. Phys. Chem. C, 3456-3466(2013).
[24] RILEY B J, CRUM J V, MATYAS J et al. Solution-derived, chloride- containing minerals as a waste form for alkali chlorides[J]. J. Am. Ceram. Soc., 3115-3123(2012).
[25] RILEY B J, PIERCE D A, FRANK S M et al. Efficacy of a solution- based approach for making sodalite waste forms for an oxide reduction salt utilized in the reprocessing of used uranium oxide fuel[J]. J. Nucl. Mater., 313-322(2015).
[26] MARRA J, EBERT W. Accounting for a Vitrified Plutonium Waste From in the Yucca Mountain Repository Total System Performance Assessment (TSPA)[J]. Westinghouse Savannah River Company (Ed.), WSRC-TR-2003-00530(2003).
[27] YOUCHAK-BILLINGS A L, CRUM J V, MARRA J C et al. Waste/Storage Form Baseline-Fission Products & Lanthanides[J]. Savannah River National Laboratory, GNEP-WAST-PMO-MI-DV-2008-000151(2008).
[28] B H, PARK H S, KIM H Y et al. Immobilization of radioactive rare earth waste by solid phase sintering[J]. Journal of the Korea Radioactive Waste Society, 49-56(2009).
[29] CHO Y Z, PARK H S, EUN H C et al. Development and characterization of new high-level waste form containing LiCl-KCl eutectic salts for achieving waste minimization from pyroprocessing[J]. Korea Atomic Energy Research Institute, KAERI/RR-3288/2010(2011).
[30] PARK H S, KIM I T, CHO Y Z et al. Stabilization/solidification of radioactive salt waste by using
[31] H S, AHN B G, KIM H et al. Solidification method of radioactive waste accompanying chloride recycling or radioactive iodide removing and the device thereof[J]. Korea patent 1188650, patent pending USA US20120165594,A1, 2012.
[32] PARK H S, CHO I H, EUN H C et al. Characteristics of wasteform composing of phosphate and silicate to immobilize radioactive waste salts[J]. Environ.Sci. Technol., 1932-1939(2011).
[33] FRANK S, EBERT W, RILRY B et al. Waste Stream Treatment and Waste Form Fabrication for Pyroprocessing of Used Nuclear Fuel[J]. Idaho National Laboratory, INL/EXT-14-34014, 2015.
Get Citation
Copy Citation Text
Yalan LIU, Zhifang CHAI, Weiqun SHI.
Category: REVIEW
Received: Oct. 15, 2019
Accepted: --
Published Online: Jan. 27, 2021
The Author Email: Weiqun SHI (shiwq@ihep.ac.cn)