First-order study of property/composition relationships for Hanford Waste Vitrification Plant glasses

Piepel, G.F.; Hrma, Pavel R.; Bates, S.O.; Schweiger, M.J.; Smith, D.E.

doi:10.2172/10125958

Cited by 4 publications

(7 citation statements)

References 7 publications

(10 reference statements)

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“…The observed effect of the constituents is in agreement with other published work [1][2][3]. The Fe + Ni + Cr group slightly increases the initial alteration rate whereas the fission products, particularly the rareearth elements and zirconium, improve the glass alteration resistance under initial rate conditions.…”

Section: Initial Alteration Ratesupporting

confidence: 91%

“…As previously observed [1][2][3], aluminum favors the rapid development of a protective gel with a significant decrease in the rate during the initial instants of gel formation. The fines, which are rich in molybdenum (a relatively mobile element) and zirconium (a sparingly soluble structural element), have little effect on the glass containment properties.…”

Section: Altered Glass Thickness After 1 Yearsupporting

confidence: 55%

“…The influence of the composition on the initial alteration rate has already been extensively covered in the literature [1][2][3][4], but the influence of the composition on the alteration rate at advanced stages of reaction progress has not often been considered. The second parameter is more representative of disposal conditions, however, and is indicative of the predominant long-term alteration mechanisms.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

The effect of composition on the leaching of three nuclear waste glasses: R7T7, AVM and VRZ

Frugier¹,

Martin²,

Ribet³

et al. 2005

Journal of Nuclear Materials

111

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Section: Initial Alteration Ratesupporting

confidence: 91%

Section: Altered Glass Thickness After 1 Yearsupporting

confidence: 55%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

The effect of composition on the leaching of three nuclear waste glasses: R7T7, AVM and VRZ

Frugier¹,

Martin²,

Ribet³

et al. 2005

Journal of Nuclear Materials

111

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“…The qualitative effect of various constituents on these thermal properties is known in many cases so that the iteration steps to arrive at the correct viscosity and conductivity ranges can be minimized. The HLW programs within EM-30 have developed computer models over some compositional ranges to predict properties (Piepel et al 1993).…”

Section: Methodsmentioning

confidence: 99%

Vitrification development plan for US Department of Energy mixed wastes

Peters

Lucerna²,

Plodinec

1993

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This document is a general plan for conducting vitrification development for application to mixed wastes owned by the U.S. Department of Energy. The emphasis is a description and discussion of the data needs to proceed through various stages of development. These stages are (1) screening at a waste site to determine which streams should be vitrified, (2) waste characterization and analysis, (3) waste form development and treatability studies, (4) process engineering development, (5) flowsheet and technical specifications for treatment processes, and (6) integrated pilot-scale demonstration. Appendices provide sample test plans for various stages of the vitrification development process. This plan is directed at thermal treatments which produce waste glass. However, the study is still applicable to the broader realm of thermal treatment since it deals with issues such as off-gas characterization and waste characterization that are not necessarily specific to vitrification. The purpose is to provide those exploring or considering vitrification with information concerning the kinds of data that are needed, the way the data are obtained, and the way the data are used. This will provide guidance to those who need to prioritize data needs to fit schedules and budgets. Knowledge of data needs also permits managers and planners to estimate resource requirements for vitrification development. Vitrification has already been developed for high-level waste and other types of radioactive and industrial waste. Based on this experience, development for mixed waste should also be feasible. One distinguishing aspect of mixed waste, however, is variability and uncertainty in composition. Production of a glass acceptable for land disposal will require some knowledge of the waste composition so that appropriateglass-forming chemicals can be added where necessary. Process safety will also be a factor when vitrifying unknown waste materials. Another special feature of mixed waste is that it consists of regulated hazardous materials as well as radionuclides. Vitrification development should thus result in equipment systems and process chemistry flowsheets that satisfy regulatory requirements for waste form product consistency, product quality, worker safety, equipment perfo.rmance,and environmental discharges. The required product quality is not yet defined beyond certain minimal limits. Through vitrification development, the glass waste form can be tailored to any desired level of quality.

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“…The canister centerline cooling (CCC) treatment was performed on Series A and B glasses to simulate cooling at the center of the axis of the axis of a stainless steel canister. Glass samples were held at 1150°C for 30 minutes and cooled following the CCC schedule [5]. Crystallinity was evaluated by optical microscopy with image analysis and X-ray diffraction (XRD).…”

Section: Glass Crystallizationmentioning

confidence: 99%

Maximization of waste loading for a vitrified Hanford high-activity simulated waste

Fini

Hrma

1994

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This report was preparedas an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employe_,s,makes any warranty, express or implied, or assumes any legal liability or responsibility for the aec_racy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Referonce herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recom-April 1994 mendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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First-order study of property/composition relationships for Hanford Waste Vitrification Plant glasses

Cited by 4 publications

References 7 publications

The effect of composition on the leaching of three nuclear waste glasses: R7T7, AVM and VRZ

The effect of composition on the leaching of three nuclear waste glasses: R7T7, AVM and VRZ

Vitrification development plan for US Department of Energy mixed wastes

Maximization of waste loading for a vitrified Hanford high-activity simulated waste

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