Mechanisms of desorption of 134Cs and 85Sr aerosols deposited on urban surfaces

Real, José Sánchez; Persin, F.; Camarasa-Claret, C.

doi:10.1016/s0265-931x(01)00136-9

Cited by 47 publications

(18 citation statements)

References 9 publications

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“…Ammonium chloride was shown to be an effective wash solution for removing cesium from concrete [12] and clay building materials [11,12,21] due to its similar ion exchange properties [21]. More aggressive chemicals may be used to etch the surface and possibly improve the mobilization of cesium from the surfaces, but use of such chemicals may be prohibitive in a wide-area decontamination effort.…”

Section: Concrete Aggregate Batch Testsmentioning

confidence: 99%

“…DeWitt et al [11] found that ammonium concentrations above 0.2M generally improved decontamination factors only marginally for concrete, asphalt and clay tiles. Real et al [12] reported dramatic improvement in the removal of cesium deposited on clay tile and concrete as an aerosol using aqueous ammonium 3 solutions. Drake and MacKinney [13] recently discussed several approaches for decontamination technologies and tools for use after radionuclides, including cesium, are released from a radiological dispersal device.…”

Section: Introductionmentioning

confidence: 99%

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Sorption of radionuclides to building materials and its removal using simple wash solutions

Kaminski

Mertz

Ortega

et al. 2016

Journal of Environmental Chemical Engineering

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Decontamination after a nuclear or radiological release requires a detailed understanding of the materials hosting the contamination, the chemistry of the radionuclide, and the chemical properties of the decontamination agent. Urban contamination via a number of radiological release scenarios may require simple decontamination methods that can be deployed for wide-area decontamination. This paper investigates a number of factors of importance for developing such decontamination methods, focusing on cesium. These factors include the influence on decontamination approaches from the cesium deposition conditions, the urban building material composition and, when washing with an ionic solution that is utilized for decontamination, the composition of the wash solutions. In summary, the sorption chemistry of cesium onto urban building materials and roadways has been studied to develop simple decontamination methods that can be deployed for wide-area decontamination efforts.To improve the understanding of the sorption of cesium onto common urban building materials and roadways the desorption of cesium deposited from solution and as a dry powder was tested. Using ammonium (NH 4 + )salt solutions, we tested the desorption of ionic cesium bound to individual components of concrete and coupons of several common building materials. While the tests on concrete aggregate suggest that a concentration >10 mM NH 4 + does not improve the desorption of cesium, tests on concrete, asphalt, marble, limestone and granite monoliths showed improved decontamination factors when the NH 4 + concentration increased from 0.1 to 0.5 M. We also found that cesium as dry particulate material could be removed quite effectively although the contamination became tenacious upon wetting the surface.

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Section: Concrete Aggregate Batch Testsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Sorption of radionuclides to building materials and its removal using simple wash solutions

Kaminski

Mertz

Ortega

et al. 2016

Journal of Environmental Chemical Engineering

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“…Adsorption of Cs by soil and minerals has been published in the literature [10][11][12][13][14]. Duursma and Eisma [15] reported that Cs enters the interlayers of a mineral such as illite, since its ionic radius matches the interlayer space of the mineral.…”

Section: Introductionmentioning

confidence: 99%

Kinetic and equilibrium studies of cesium adsorption on ceiling tiles from aqueous solutions

Miah

Volchek

Kuang³

et al. 2010

Journal of Hazardous Materials

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“…Bahan bakar U3Si2/Al pasca iradiasi mengandung beberapa hasil fisi seperti isotop 137 Cs, 144 Ba, dan 90 Sr dan unsur bermassa berat diantaranya adalah isotop 238 U, 235 U , 234 U, 236 U, 239 Pu, dan 238 Pu. Isotop 144 Ba adalah isotop hasil fisi yang masih dapat meluruh dan menghasilkan isotop lain sebagai hasil fisi yang lebih stabil yaitu 90 Sr dan 137 Cs [2,3] . Hasil fisi sebagai pemancar radiasi gamma harus dipisahkan dari unsur-unsur bermassa berat sebagai pemancar radiasi sinar alpha.…”

Section: Pendahuluanunclassified

PENGARUH PARAMETER PROSES ELEKTRODEPOSISI TERHADAP PENENTUAN BERAT ISOTOP 235U DALAM PEB U3Si2/Al PASCA IRADIASI

Yanlinastuti

Boybul

Ginting

et al. 2016

urania

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ABSTRAK PENGARUH PARAMETER PROSES ELEKTRODEPOSISI TERHADAP PENENTUAN BERAT ISOTOP 235U DALAM PEB U3Si2/Al PASCA IRADIASI. Parameter proses elektrodiposisi yang sangat mempengaruhi penentuan berat 235 U dalam larutan PEB U3Si2/Al pasca iradiasi adalah kuat arus, waktu proses, volume umpan dan jenis larutan buffer elektrolit iradiasi. Tujuan penelitian adalah untuk mendapatkan parameter proses elektrodeposisi yang optimum dalam menetukan berat isotop 235 U dalam PEB U3Si2/Al pasca iradiasi. Proses elektrodeposisi dilakukan dengan beberapa variasi parameter antara lain kuat arus 1; 1,2; dan1,4 ampere dengan waktu 1; 1,5; 2,0; 2,5 dan 3,0 jam, volume umpan standar U3O8 % mulai dari 100; 300; 500; 700 µL dengan variasi jenis larutan buffer elektrolit NH4Cl, NH4OAc,NH4HSO4dan (NH4)2SO4. Hasil proses elektrodeposisi menunjukkan bahwa kondisi optimum proses elektrodeposisi untuk isotop 235 U diperoleh pada kuat arus1,2 ampere dengan waktu proses selama 2 jam serta jumlah volume umpan sebesar 300 µL dengan buffer elektrolit NH4HSO4 pada pH 3,5. Hasil proses eletrodeposisi diperoleh berat endapan isotop 235 U sebesar 2,314 µg dengan recovery pengendapan sebesar 99,91%.Parameter optimum yang diperoleh selanjutnya digunakan untuk proses elektrodeposisi untuk menentukan berat isotop 235 U yang terkandung di dalam larutan PEB U3Si2/Al pasca iradiasi dengan volume umpan sebesar 300 µL. Hasil pengukuran dan analisis dengan menggunakan spektrometer alpha diperoleh berat isotop 235 U sebesar 0,403 µg dengan recovery pengendapan sebesar 91,80 %. Dari hasil yang diperoleh dapat dinayatakan bahwa metoda elektrodeposisi cukup baik digunakan untuk menentukan berat isotop 235 U di dalam larutan PEB U3Si2/Al pasca iradiasi.Kata kunci: Elektrodeposisi, isotop 235 U, spektrometer alpha, PEB U3Si2/Al pasca iradiasi.

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Mechanisms of desorption of 134Cs and 85Sr aerosols deposited on urban surfaces

Cited by 47 publications

References 9 publications

Sorption of radionuclides to building materials and its removal using simple wash solutions

Sorption of radionuclides to building materials and its removal using simple wash solutions

Kinetic and equilibrium studies of cesium adsorption on ceiling tiles from aqueous solutions

PENGARUH PARAMETER PROSES ELEKTRODEPOSISI TERHADAP PENENTUAN BERAT ISOTOP 235U DALAM PEB U3Si2/Al PASCA IRADIASI

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