Zinc-in-titania waste form for immobilizing lanthanide fission products from electrochemical reprocessing

Riley, Brian J.; Park, Hwan-Seo; Choi, Jonghyun; Lee, Ki-Rak; Ebert, W. L.; Canfield, Nathan L.

doi:10.1016/j.jnucmat.2020.152313

Cited by 8 publications

(13 citation statements)

References 26 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…In follow-up work to this original study, a joint study between the KAERI and US National Laboratories showed that the ZIT wasteform could be fabricated with double the REO x loading (40 mass%) from that in the original study. This product had a higher density at 4.7 × 10 3 kg m –3 and reduced chemical durability.…”

Section: Wasteform Optionsmentioning

confidence: 92%

“…Here, the wasteform volume based on starting mass of RE ( V wf,RE ) can be calculated, where the mass of RE in a given salt ( m RE ) and the fraction of RE in the wasteform ( f RE,wf ) are used in place of m s and f sf,wf in eq , respectively. Data from these comparisons are shown in Figure with data from Table . ,,,,, From this comparison plot, it is immediately apparent that some options are much more aggressive at improving upon the volumetric loading of RE within the wasteform ( V wf,RE ) compared to the baseline GBS wasteform. The data in Figure are split into different regions where the LABS glass and ZIT glass ceramic are entirely separated (right side) from the other wasteforms due to high-REO x loadings, the intermediate (middle) RE-loaded samples include Pb-Te-O and Fe-P-O wasteforms with RECl 3 or REOCl, and then the low RE-loaded wasteforms are on the left (i.e., those made with the full salt). …”

Section: Wasteform Comparisonsmentioning

confidence: 99%

“…Data from these comparisons are shown in Figure 10 with data from Table 4. 13,20,21,24,34,53 From this comparison plot, it is immediately apparent that some options are much more aggressive at improving upon the volumetric loading of RE within the wasteform (V wf,RE ) compared to the baseline GBS wasteform. The data in Figure 10 Comparison of the final wasteform volume required to immobilize 100 g of starting salt cations [i.e., V wf,s −see eq 9] as a function of salt cation loading (m sc ) for GBS, 53 Pb-Te-O glass, 20 Fe-P-O glass, 13 and consolidated USHYZ 25 wasteforms; see Table 3 for data.…”

Section: Wasteform Comparisonsmentioning

confidence: 99%

“…Additional discussion will be provided to describe where research gaps exist that could be used to (1) further improve the waste loading within an existing wasteform option or (2) remove salt constituents that do not require immobilization (e.g., only immobilizing fission products). The primary wasteforms that will be compared within the context of this paper include glass-bonded sodalite (GBS) ceramic wasteforms (CWF), lead tellurite (Pb-Te-O) glasses, , lanthanide (alumino)borosilicate (LABS) glasses, − and iron phosphate (Fe-P-O) glasses. ,, Others that will not be discussed in as much detail include dehalogenation processes for salt waste streams including one utilizing an ultrastable H-Y zeolite (USHYZ) where the dehalogenated product is immobilized by a cold-press-and-sinter process or in a low-melting glass, − a silica aluminophosphate (SAP; or upgraded SAP, U-SAP) process, − and a zinc-in-titania (Zn-Ti-O or ZIT) process. , …”

Section: Introductionmentioning

confidence: 99%

“…12,13,24 Others that will not be discussed in as much detail include dehalogenation processes for salt waste streams including one utilizing an ultrastable H-Y zeolite (USHYZ) where the dehalogenated product is immobilized by a cold-press-andsinter process or in a low-melting glass, 25−27 a silica aluminophosphate (SAP; or upgraded SAP, U-SAP) process, 28−32 and a zinc-in-titania (Zn-Ti-O or ZIT) process. 33,34 2. SALT PARTITIONING OPTIONS Partitioning options are summarized in the following subsections.…”

Section: Introductionmentioning

confidence: 99%

See 4 more Smart Citations

Electrochemical Salt Wasteform Development: A Review of Salt Treatment and Immobilization Options

Riley

2020

Ind. Eng. Chem. Res.

Self Cite

View full text Add to dashboard Cite

Electrochemical reprocessing, also referred to as pyroprocessing, is a technique for recycling actinides from used nuclear fuel (UNF) to produce fuel for future reactors. Here, UNF is dissolved in a molten salt (e.g., LiCl-KCl eutectic) within an electrorefiner. After UNF dissolution, fission products are released into the electrolyte salt and converted to chlorides. This paper discusses wasteform options for processing the base electrolyte salt with the fission product salts as well as only the rare-earth (RE) fission products (as RECl3, REOCl, or REO x ) with the intent of finding optimal methods for reducing total waste salt volumes by partitioning the salt for alternate wasteform options. Two of the more detailed partitioning options discussed herein include halide removal from the salt (dehalogenation), which accounts for more than half of the salt on a molar basis, and RE fission product removal for wasteforms with high-RE loadings. Wasteform properties are compared with emphasis on wasteform volume starting from a given amount of (1) total salt cations or (2) RE cations. Comparisons are also made of wasteform chemical durabilities, with the data available from like testing methods. A main conclusion from this work is the justification of subsequent salt processing after electrorefiner operations for achieving significant wasteform volume reduction.

show abstract

Section: Wasteform Optionsmentioning

confidence: 92%