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Garisto F, Garisto NC. A UO2Solubility Function for the Assessment of Used Nuclear Fuel Disposal. NUCL SCI ENG 2017. [DOI: 10.13182/nse85-a17435] [Citation(s) in RCA: 14] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Frank Garisto
- Atomic Energy of Canada Limited, Research Chemistry Branch Whiteshell Nuclear Research Establishment Pinawa, Manitoba, Canada ROE 1L0
| | - N. C. Garisto
- Atomic Energy of Canada Limited, Fuel Waste Technology Branch Whiteshell Nuclear Research Establishment Pinawa, Manitoba, Canada ROE 1L0
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Wang P, Anderko A, Kosinski JJ, Springer RD, Lencka MM. Modeling Speciation and Solubility in Aqueous Systems Containing U(IV, VI), Np(IV, V, VI), Pu(III, IV, V, VI), Am(III), and Cm(III). J SOLUTION CHEM 2017. [DOI: 10.1007/s10953-017-0587-x] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Guzonas D, Qiu L, Livingstone S, Rousseau S. Fission Product Release Under Supercritical Water-Cooled Reactor Conditions. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2016. [DOI: 10.1115/1.4031381] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
Most supercritical water-cooled reactor (SCWR) concepts being considered as part of the Generation IV initiative are direct cycle. In the event of a fuel defect, the coolant will contact the fuel pellet, potentially releasing fission products and actinides into the coolant and transporting them to the turbines. At the high pressure (25 MPa) in an SCWR, the coolant does not undergo a phase change as it passes through the critical temperature in the core, and nongaseous species may be transported out of the core and deposited on out-of-core components, leading to increased worker dose. It is therefore important to identify species with a high risk of release and develop models of their transport and deposition behavior. This paper presents the results of preliminary leaching tests in SCW of U-Th simulated fuel pellets prepared from natural U and Th containing representative concentrations of the (inactive) oxides of fission products corresponding to a fuel burnup of 60 GWd/ton. The results show that Sr and Ba are released at relatively high concentrations at 400°C and 500°C.
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Affiliation(s)
- D. Guzonas
- Canadian Nuclear Laboratories, Chalk River Laboratories, CNL, Chalk River, ON K0J 1J0, Canada e-mail:
| | - L. Qiu
- Canadian Nuclear Laboratories, Chalk River Laboratories, CNL, Chalk River, ON K0J 1J0, Canada e-mail:
| | - S. Livingstone
- Canadian Nuclear Laboratories, Chalk River Laboratories, CNL, Chalk River, ON K0J 1J0, Canada e-mail:
| | - S. Rousseau
- Canadian Nuclear Laboratories, Chalk River Laboratories, CNL, Chalk River, ON K0J 1J0, Canada e-mail:
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Torrero ME, Casas I, Aguilar M, De Pablo J, Gimenez J, Bruno J. The Solubility of Unirradiated UO2 In Both Perchlorate And Chloride Test Solutions. Influence of the Ionic Medium. ACTA ACUST UNITED AC 2011. [DOI: 10.1557/proc-212-229] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/13/2022]
Abstract
ABSTRACTThe solubility of a crystalline unirradiated UO2 (s) has been studied under reducing conditions at 25°C in three different ionic media: 0.008 mol dm–3 NaCIO4, 1 and 5 mol dm-3 NaCl+. The species responsible for the solubility in perchlorate medium are U(OH)3 and U(OH)4, with the stability constants log β13 = -0.4(±0.2) and log β14 = -5.7(±0.1), respectively. The solubility in both1! and 5 M chloride media is explained at pH values higher than 6 by the species U(OH)4 with log β14 = -5.5(±0.2) while at lower pH values an abnormal behaviour is observed, with higher uranium concentrations in solution and a proton independent solubility for pH values lower than 4. The XPS observations of the reacted solids do not show the presence of solid surface phases other than uranium dioxide, with an upper oxidation state of UO2.1.
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Bruno J, Arcos D, Cera E, Duro L, Grivé M. Modelling near- and far-field processes in nuclear waste management. ACTA ACUST UNITED AC 2004. [DOI: 10.1144/gsl.sp.2004.236.01.28] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/04/2022]
Abstract
AbstractIn this chapter we present some of the recent advances concerning process understanding and modelling of radionuclide migration in nuclear waste disposal systems. The present geochemical modelling approaches used to quantify the processes concerning spent fuel dissolution, radionuclide interactions with the canister materials and the bentonite buffer are thoroughly discussed. Finally, some applications to natural analogue studies of spent nuclear fuel disposal, as testing ground for concepts and models developed for waste management systems, are presented.
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Affiliation(s)
- J. Bruno
- Enviros. Passeig de Rubí
Valldoreix, Spain
| | - D. Arcos
- Enviros. Passeig de Rubí
Valldoreix, Spain
| | - E. Cera
- Enviros. Passeig de Rubí
Valldoreix, Spain
| | - L. Duro
- Enviros. Passeig de Rubí
Valldoreix, Spain
| | - M. Grivé
- Enviros. Passeig de Rubí
Valldoreix, Spain
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Moulin C, Beaucaire C, Decambox P, Mauchien P. Determination of uranium in solution at the ng 1−1 level by time-resolved laser-induced spectrofluorimetry: application to geological samples. Anal Chim Acta 1990. [DOI: 10.1016/s0003-2670(00)80550-4] [Citation(s) in RCA: 45] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
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Thomas GF, Till G. The dissolution of unirradiated UO2 fuel pellets under simulated disposal conditions. ACTA ACUST UNITED AC 1984. [DOI: 10.1016/0191-815x(84)90044-5] [Citation(s) in RCA: 31] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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Ryan JL, Rai D. The solubility of uranium(IV) hydrous oxide in sodium hydroxide solutions under reducing conditions. Polyhedron 1983. [DOI: 10.1016/s0277-5387(00)81413-8] [Citation(s) in RCA: 40] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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