Results of intermediate-scale hot isostatic press can experiments

Nelson, Lee O.; Vinjamuri, K.

doi:10.2172/119414

Cited by 2 publications

(1 citation statement)

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“…Approximately, 4,400 m 3 of calcine is stored at INTEC (Patterson and Prather 2004). (Nelson and Vinjamuri 1995).…”

Section: Introductionmentioning

confidence: 99%

Summary of Calcine Disposal Development Using Hot Isostatic Pressing

Bateman¹,

Wahlquist²,

Hart³

et al. 2015

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Battelle Energy Alliance, LLC, has demonstrated the effectiveness of the hot isostatic press (HIP) process for treatment of hazardous high-level waste known as calcine that is stored at the Idaho Nuclear Technology and Engineering Center (INTEC) at Idaho National Laboratory. HIP trials performed with simulated calcines at Idaho National Laboratory's Materials and Fuels Complex and an Australian Nuclear Science and Technology Organization facility from 2007 to 2010 produced a dense, monolithic waste form with increased chemical durability and effective (storage) volume reductions of ~10 to ~70% compared to granular calcine forms. In December 2009, the U.S. Department of Energy signed an amended Record of Decision selecting HIP technology as the treatment method for the 4,400 m 3 of granular zirconia and alumina calcine stored at INTEC. Testing showed that HIP treatment reduces the risks associated with radioactive and hazardous constituent release, post-production handling, and long-term (repository) storage of calcines and would result in estimated storage cost savings in the billions of dollars. Battelle Energy Alliance has the ability to complete pilot-scale HIP processing of INTEC calcine, which is the next necessary step in implementing HIP processing as a calcine treatment method.

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“…Approximately, 4,400 m 3 of calcine is stored at INTEC (Patterson and Prather 2004). (Nelson and Vinjamuri 1995).…”

Section: Introductionmentioning

confidence: 99%

Summary of Calcine Disposal Development Using Hot Isostatic Pressing

Bateman¹,

Wahlquist²,

Hart³

et al. 2015

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show abstract

Vitrification of High-Level Radioactive Waste by Sintering Under Pressure

et al. 1997

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Sintered silicate glass waste forms with a continuous glass phase and embedded but not completely dissolved waste particles were prepared by powder technology. We used a typical defense waste compositions, containing 38 wt.% of ZrO2 and prepared sinter glass samples with 30, 35, and 40 wt.% waste loading at 830°C and 27.6 MPa, by hot isostatic pressing. The glass former was amorphous silica powder. Simulated waste was added as calcine. Samples were characterized using scanning and transmission electron microscopy. The results show that extensive sintering took place, particularly with the 40 wt.% samples. Waste components, such as Na2O, CaO, MnO2, La203, Fe2O3, NiO, Cr2O3, and P2O5, dissolved completely in the continuous glass phase. ZrO2 was partly dissolved and occurred as aggregates of tiny baddeleyite crystals. The porosity of the samples was 2-3%, indicating that the optimum sintering conditions have not been met to reach porosities <1%.Chemical durability tests were carried out with sintered glass with 35 wt.% waste loading in deionized water at 90°C under static conditions, showing that the glass is at least as chemically durable as a borosilicate glass with 31 wt.% melted at 1350°C.

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Results of intermediate-scale hot isostatic press can experiments

Cited by 2 publications

References 1 publication

Summary of Calcine Disposal Development Using Hot Isostatic Pressing

Summary of Calcine Disposal Development Using Hot Isostatic Pressing

Vitrification of High-Level Radioactive Waste by Sintering Under Pressure

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