Borosilicate glass and synroc R&amp;D for radioactive waste immobilization: An international perspective

Deokattey, Sangeeta; Bhaskar, Nita; Kalyane, V. L.; Kumar, Vijai; Jahagirdar, Pralhad B.

doi:10.1007/s11837-003-0176-x

Cited by 11 publications

(5 citation statements)

References 2 publications

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“…It can be seen in Fig. 7 that the normalized mass loss of Sr 2+ from samples S1S6 gradually decrease, which is Journal of the Ceramic Society of Japan 131 [6] 146-151 2023 JCS-Japan consistent with the intensities of the SrB 2 Si 2 O 8 peaks in Fig. 4.…”

Section: Pct Ion Leaching Text Analysissupporting

confidence: 76%

Sintering of SrB2Si2O8 glass-ceramics and their Sr immobilization

Shao¹,

Wang²,

et al. 2023

J. Ceram. Soc. Japan

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A method of low-temperature liquid-phase sintering was used to prepare SrB 2 Si 2 O 8 glass-ceramics in order to simulate immobilization of 90 Sr, and the SrOB 2 O 3 system as a flux could avoid new impurities to be introduced into the solidified body. The sintering behaviors, mechanical properties and solidification behaviors of SrB 2 Si 2 O 8 were investigated. The crystalline phase of SrB 2 Si 2 O 8 was formed by liquid phase sintering at 1223 K. Additionally, adding Ca 2+ improves the sintering behavior and mechanical properties of samples. The stable mineral phase of SrB 2 Si 2 O 8 is helpful to achieve a perfect effect on the immobilization of Sr. The Sr 2+ leak mainly from the glass phase. Our results suggest that the key to resisting the leaking of Sr 2+ is to form not only stable mineral phases but also stable glass phases.

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Section: Pct Ion Leaching Text Analysissupporting

confidence: 76%

Sintering of SrB2Si2O8 glass-ceramics and their Sr immobilization

Shao¹,

Wang²,

et al. 2023

J. Ceram. Soc. Japan

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“…Because of high melting point, high thermal conductivity, radiation stability, ceramics are regarded as the second generation of HLW forms. Many results showed that ceramic forms have superior chemical durability to glass forms [4,5]. Ceramic incorporation of waste elements is based on the isomorphism of mineralogy.…”

Section: Introductionmentioning

confidence: 99%

Ceramics for high level radioactive waste solidification

Wang¹,

Liang²

2012

J Adv Ceram

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Several countries reprocess their nuclear spent fuel using the Purex process to recover U and Pu as MOX fuel. The high level radioactive waste (HLW) produced during this reprocessing is a complex mixture containing both radioactive (fission products, minor actinides) and non-radioactive elements. Since HLW shows high rate heat release and contains some long half-life and biologically toxic radionuclide, its treatment and disposal technology is complex, difficult and high cost. HLW treatment and disposal become a worldwide challenge and research focus. In order to minimize the potential long-term impact of HLW, studies on enhanced chemical separation processes of long-lived radionuclides are in progress. Two options are then envisaged for these separated radionuclides: (a) transmutation into short-lived or non-radioactive elements, (b) immobilization in highly durable ceramic matrix instead of borosilicate glass. In this paper, we briefly review the composition, structure, processing and product properties of some ceramic candidates for inert matrix fuels (IMF) and the immobilization of high level radioactive waste.

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“…Pb-Fe 3þ phosphates are generally studied due to their application as glasses in the nuclear waste industry (e.g., Reis et al, 2002;Oelkers & Montel, 2008). The family of phosphate glasses, which are based on pyrophosphate groups (P 2 O 7 ), are chemically stable in aqueous solutions and offer an excellent alternative to more conventional glasses such as sodium aluminophosphate glass (e.g., Polyakov et al, 1994) or borosilicate glass (e.g., Deokattey et al, 2003) for the immobilisation of nuclear waste (Karabulut et al, 2000).…”

Section: Introductionmentioning

confidence: 99%

Pb3Fe3+2(PO4)4(H2O), a new octahedral-tetrahedral framework structure with double-strand chains

Mills

Kolitsch

Miyawaki

et al. 2010

ejm

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A new lead iron(III) hydrated phosphate, Pb 3 Fe 2 (PO 4 ) 4 (H 2 O), has been synthesised hydrothermally in Teflon-lined stainless steel autoclaves at 220 C for 7 days, with an initial pH of 1.5. It is the first example of a synthetic hydrous Pb-Fe 3þ phosphate. Crystals are small, colourless to white prisms, uniaxial (þ) and non-pleochroic. The calculated refractive index for white light is n ¼ 1.95. Single-crystal structure determination (R(F) ¼ 0.0457) shows Pb 3 Fe 2 (PO 4 ) 4 (H 2 O) to be tetragonal, space group P4 1 2 1 2 (no. 92), with a ¼ 9.0440(10), c ¼ 16.766(3) A ˚, V ¼ 1371.4(3) A ˚3 and Z ¼ 4. Pb 3 Fe 2 (PO 4 ) 4 (H 2 O) has a structure type which is based on a tetrahedral-octahedral framework of FeO 6 octahedra sharing corners with PO 4 tetrahedra, with Pb atoms and H 2 O molecules occupying voids in the framework. Pb 3 Fe 2 (PO 4 ) 4 (H 2 O) is homeotypic with synthetic Pb 3 Cr 2 (PO 4 ) 4 ; both compounds share the same heteropolyhedral topology and the same space group, but only Pb 3 Fe 2 (PO 4 ) 4 (H 2 O) contains an additional position occupied by a water molecule. The octahedral-tetrahedral chain of Pb 3 Fe 2 (PO 4 ) 4 (H 2 O) is topologically similar to double-strand chains found in the structures of hannayite, galliskiite, kapundaite, PbIn(AsO 4 )(AsO 3 OH) and Na 2.88 Fe(PO 4 ) 2 . Infrared spectroscopy is used to describe the vibrational properties of Pb 3 Fe 2 (PO 4 ) 4 (H 2 O).

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Borosilicate glass and synroc R&D for radioactive waste immobilization: An international perspective

Cited by 11 publications

References 2 publications

Sintering of SrB<sub>2</sub>Si<sub>2</sub>O<sub>8</sub> glass-ceramics and their Sr immobilization

Sintering of SrB<sub>2</sub>Si<sub>2</sub>O<sub>8</sub> glass-ceramics and their Sr immobilization

Ceramics for high level radioactive waste solidification

Pb3Fe3+2(PO4)4(H2O), a new octahedral-tetrahedral framework structure with double-strand chains

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