scholarly journals Effect of aluminum and silicon reactants and process parameters on glass-ceramic waste form characteristics for immobilization of high-level fluorinel-sodium calcined waste

1993 ◽  
Author(s):  
K. Vinjamuri
Keyword(s):  
Process Parameters ◽  
Glass Ceramic ◽  
Waste Form ◽  
Ceramic Waste ◽  
High Level

scholarly journals Characterization of Composite Ceramic High Level Waste Forms

1997 ◽  
Vol 481 ◽  
Author(s):  
S. M. Frank ◽  
K. J. Bateman ◽  
T. DiSanto ◽  
S. G. Johnson ◽  
T. L. Moschetti ◽  
...  
Keyword(s):  
Spent Nuclear Fuel ◽  
Argonne National Laboratory ◽  
Fission Products ◽  
Composite Ceramic ◽  
Waste Form ◽  
High Level Waste ◽  
Ceramic Waste ◽  
Chloride Form ◽  
Physical Measurements ◽  
High Level

ABSTRACTArgonne National Laboratory has developed a composite ceramic waste form for the disposition of high level radioactive waste produced during electrometallurgical conditioning of spent nuclear fuel. The electrorefiner LiCl/KCl eutectic salt, containing fission products and transuranics in the chloride form, is contacted with a zeolite material which removes the fission products from the salt. After salt contact, the zeolite is mixed with a glass binder. The zeolite/glass mixture is then hot isostatic pressed (HIPed) to produce the composite ceramic waste form. The ceramic waste form provides a durable medium that is well suited to incorporate fission products and transuranics in the chloride form. Presented are preliminary results of the process qualification and characterization studies, which include chemical and physical measurements and product durability testing, of the ceramic waste form.

scholarly journals Development of a ceramic waste form for high-level waste disposal

1999 ◽  
Vol 556 ◽  
Author(s):  
D. W. Esh ◽  
K. M. Goff ◽  
K. T. Hirsche ◽  
T. J. Battisti ◽  
M. F. Simpson ◽  
...  
Keyword(s):  
Spent Nuclear Fuel ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Fission Products ◽  
Waste Form ◽  
High Level Waste ◽  
Durability Test ◽  
Ceramic Waste ◽  
High Level ◽  
The Impact

AbstractA ceramic waste form is being developed by Argonne National Laboratory* (ANL) as part of the demonstration of the electrometallurgical treatment of spent nuclear fuel [1]. The halide, alkaline earth, alkali, transuranic, and rare earth fission products are stabilized in zeolite which is combined with glass and processed in a hot isostatic press (HIP) to form a ceramic composite. The mineral sodalite is formed in the HIP from the zeolite precursor. The process, from starting materials to final product, is relatively simple. An overview of the processing operations is given. The metrics that have been developed to measure the success or completion of processing operations are developed and discussed. The impact of variability in processing metrics on the durability of the final product is presented. The process is demonstrated to be robust for the type and range of operation metrics considered and the performance metric (PCT durability test) against which the operation metrics are evaluated.

The Influence of Gamma Irradiation on the Leaching Behavior of a Modified Synroc-B Ceramic Waste Form

1981 ◽  
Vol 6 ◽  
Author(s):  
A. G. Solomah
Keyword(s):  
Waste Form ◽  
Leaching Behavior ◽  
Acid Base ◽  
Γ Irradiation ◽  
Ph Measurements ◽  
Ceramic Waste ◽  
Acid Generation ◽  
Leaching Experiments ◽  
High Level ◽  
Base Formation

ABSTRACTThe leaching behavior of a sintered Modified SYNROC-B ceramic waste form containing l0wt% simulated high level radioactive waste, under the influence of γ-irradiation, has been investigated. Similar leaching experiments have been carried out in the absence of γ-irradiation, and the leach rates of Ba and Cs are presented for comparison studies. Acid/Base formation has been monitored through pH measurements of the leachants. A decrease in pH is found with γ-irradiation due to radiolytic nitric acid generation. Higher initial leach rates with a more pronounced subsequent drop in the case of Ba and Cs were observed with γ-irradiation than without irradiation. The results of the study are presented and discussed.

Synthesis and characterization of oxyapatite [Ca2Nd8(SiO4)6O2] and mixed-alkaline-earth powellite [(Ca,Sr,Ba)MoO4] for a glass-ceramic waste form

2018 ◽  
Vol 510 ◽  
pp. 623-634 ◽  
Author(s):  
Jacob A. Peterson ◽  
Jarrod V. Crum ◽  
Brian J. Riley ◽  
R. Matthew Asmussen ◽  
James J. Neeway
Keyword(s):  
Glass Ceramic ◽  
Alkaline Earth ◽  
Waste Form ◽  
Synthesis And Characterization ◽  
Ceramic Waste

scholarly journals Dilute condition corrosion behavior of glass-ceramic waste form

2016 ◽  
Vol 482 ◽  
pp. 1-11 ◽  
Author(s):  
Jarrod V. Crum ◽  
James J. Neeway ◽  
Brian J. Riley ◽  
Zihua Zhu ◽  
Matthew J. Olszta ◽  
...  
Keyword(s):  
Corrosion Behavior ◽  
Glass Ceramic ◽  
Waste Form ◽  
Ceramic Waste

scholarly journals Synroc development—Past and present applications

2017 ◽  
Vol 4 ◽  
Author(s):  
Eric R. Vance ◽  
Dorji T. Chavara ◽  
Daniel J. Gregg
Keyword(s):  
Glass Ceramic ◽  
Intermediate Level ◽  
Waste Form ◽  
Spent Fuel ◽  
Process Technology ◽  
Technology Platform ◽  
Ceramic Waste ◽  
Waste Forms ◽  
Produce Glass ◽  
Waste Loading

ABSTRACTSynroc has evolved over the last 40 years from the titanate full-ceramics developed in the late 1970s to a technology platform that can be applied to produce glass, glass–ceramic, and ceramic waste forms and where there are distinct advantages in terms of waste loading and suppressing volatile losses.A first of a kind Synroc plant for immobilizing intermediate level waste arising from Mo-99 production is currently in detailed engineering at ANSTO.Since the year 2000, Synroc has evolved from the titanate full-ceramics developed in the late 1970s to a technology platform that can be applied to produce glass, glass–ceramic, and ceramic waste forms and where there are distinct advantages in terms of waste loading and suppressing volatile losses. Furthermore recent efforts have focused strongly on waste form development for plutonium-bearing wastes in the UK, for different options for the immobilization of Idaho calcines and most recently developing an engineered waste form for the intermediate level wastes arising from 99Mo production, for the Australian Nuclear Science and Technology Organisation (ANSTO). A variety of other studies are currently in progress, including engineered waste forms for spent fuel and investigating the proliferation risks for titanate-based waste forms containing highly enriched uranium or plutonium. This paper also attempts to give some perspective on Synroc waste forms and process technology development in the nuclear waste management industry.

Advantages Hot Isostatically Pressed Ceramic and Glass-Ceramic Waste Forms Bring to the Immobilization of Challenging Intermediate- and High-Level Nuclear Wastes

2010 ◽  
Vol 73 ◽  
pp. 130-135 ◽  
Author(s):  
Eric R. Vance ◽  
S. Moricca ◽  
Bruce D. Begg ◽  
M.W.A. Stewart ◽  
Y. Zhang ◽  
...  
Keyword(s):  
Glass Ceramic ◽  
Spent Nuclear Fuel ◽  
Hot Isostatic Pressing ◽  
Batch Process ◽  
Ceramic Waste ◽  
Waste Forms ◽  
Simulated Waste ◽  
Process Line ◽  
The One ◽  
High Level

Hot isostatic pressing (HIP) is a technology with wide applicability in consolidating calcined intermediate-level and high-level nuclear waste, especially with wastes that are not able to be readily processed by vitrification at reasonable waste loadings. The essential process steps during the HIP cycle will be outlined. We have demonstrated the effective consolidation via HIP technology of a wide variety of tailored glass-ceramic and ceramic waste forms, notably simulated ICPP waste calcines, I sorbed upon zeolite beads, Pu-bearing wastes, inactive Cs/Sr/Rb/Ba mixtures, simulated waste pyroprocessing salts from spent nuclear fuel recycling, Tc, U-rich isotope production waste, and simulated K-basin (Hanford, WA, USA) and Magnox sludges (UK). Can-ceramic interactions have been carefully studied. The principal advantages of the HIP technology include: negligible offgas during the high temperature consolidation step, relatively small footprint, and high waste loadings. As a batch process, the wasteform chemistry can be readily adjusted on a given process line, to deliver wastes into different end states (e.g. direct HIP versus chemically tailored). This flexibility allows the treatment of multiple waste streams on the one process line.

Synroc tailored waste forms for actinide immobilization

2017 ◽  
Vol 105 (11) ◽  
Author(s):  
Daniel J. Gregg ◽  
Eric R. Vance
Keyword(s):  
Glass Ceramic ◽  
Waste Treatment ◽  
Waste Form ◽  
Borosilicate Glasses ◽  
Process Technology ◽  
Treatment Technology ◽  
Ceramic Waste ◽  
Waste Forms ◽  
Glass Matrices ◽  
Key Aspects

AbstractSince the end of the 1970s, Synroc at the Australian Nuclear Science and Technology Organisation (ANSTO) has evolved from a focus on titanate ceramics directed at PUREX waste to a platform waste treatment technology to fabricate tailored glass–ceramic and ceramic waste forms for different types of actinide, high- and intermediate level wastes. The particular emphasis for Synroc is on wastes which are problematic for glass matrices or existing vitrification process technologies. In particular, nuclear wastes containing actinides, notably plutonium, pose a unique set of requirements for a waste form, which Synroc ceramic and glass-ceramic waste forms can be tailored to meet. Key aspects to waste form design include maximising the waste loading, producing a chemically durable product, maintaining flexibility to accommodate waste variations, a proliferation resistance to prevent theft and diversion, and appropriate process technology to produce waste forms that meet requirements for actinide waste streams. Synroc waste forms incorporate the actinides within mineral phases, producing products which are much more durable in water than baseline borosilicate glasses. Further, Synroc waste forms can incorporate neutron absorbers and

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