Evaluation of disposal stability of cement waste forms mixed with concentrated liquid waste for efficient treatment of AUC process waste

The uranium reconversion process is performed to convert concentrated UF 6 into UO 2 . Ca(OH) 2 is used to neutralize liquid waste generated during the uranium reconversion process, and all waste generated during this process is then collectively named lime waste. The present study aimed to improve...

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Published inJournal of radioanalytical and nuclear chemistry Vol. 331; no. 10; pp. 4335 - 4345
Main Authors Shon, Jong-Sik, Lee, Hyun-Kyu, Kim, Gi-Yong, Kim, Tack-Jin, Ju, June-Sik
Format Journal Article
LanguageEnglish
Published Cham Springer International Publishing 01.10.2022
Springer
Springer Nature B.V
Subjects
Acceptance criteria
Analysis
Cementation
Chemistry
Chemistry and Materials Science
Diagnostic Radiology
Effectiveness
Hadrons
Heavy Ions
Inorganic Chemistry
Leaching
Liquid wastes
Nuclear Chemistry
Nuclear energy
Nuclear Physics
Physical Chemistry
Refuse and refuse disposal
Slaked lime
Stability analysis
Structural stability
Uranium
Uranium dioxide
Waste disposal
Waste management
Waste treatment
WAC
Lime waste
Cementation
AUC
Operating conditions
Online AccessGet full text
ISSN0236-5731
1588-2780
DOI10.1007/s10967-022-08495-8

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Abstract The uranium reconversion process is performed to convert concentrated UF 6 into UO 2 . Ca(OH) 2 is used to neutralize liquid waste generated during the uranium reconversion process, and all waste generated during this process is then collectively named lime waste. The present study aimed to improve cost-effectiveness and efficiency in lime waste treatment by replacing water, required in the cementation process, with concentrated liquid waste. The concentrate/cement ratio in the cementation process was set to range from 1.90 to 2.30, and the content of waste (lime + salt) ranged from 73.4 to 73.5 wt%. The optimum concentrate/cement ratio was determined to be 1.91, considering cost-effectiveness and safety. The structural stability of cement waste forms generated under the optimum operating conditions was evaluated according to the waste acceptance criteria (WAC). The feasibility of waste disposal was demonstrated by the evaluation of the leaching index of Cs, Sr, and Co.
AbstractList The uranium reconversion process is performed to convert concentrated UF.sub.6 into UO.sub.2. Ca(OH).sub.2 is used to neutralize liquid waste generated during the uranium reconversion process, and all waste generated during this process is then collectively named lime waste. The present study aimed to improve cost-effectiveness and efficiency in lime waste treatment by replacing water, required in the cementation process, with concentrated liquid waste. The concentrate/cement ratio in the cementation process was set to range from 1.90 to 2.30, and the content of waste (lime + salt) ranged from 73.4 to 73.5 wt%. The optimum concentrate/cement ratio was determined to be 1.91, considering cost-effectiveness and safety. The structural stability of cement waste forms generated under the optimum operating conditions was evaluated according to the waste acceptance criteria (WAC). The feasibility of waste disposal was demonstrated by the evaluation of the leaching index of Cs, Sr, and Co.
The uranium reconversion process is performed to convert concentrated UF 6 into UO 2 . Ca(OH) 2 is used to neutralize liquid waste generated during the uranium reconversion process, and all waste generated during this process is then collectively named lime waste. The present study aimed to improve cost-effectiveness and efficiency in lime waste treatment by replacing water, required in the cementation process, with concentrated liquid waste. The concentrate/cement ratio in the cementation process was set to range from 1.90 to 2.30, and the content of waste (lime + salt) ranged from 73.4 to 73.5 wt%. The optimum concentrate/cement ratio was determined to be 1.91, considering cost-effectiveness and safety. The structural stability of cement waste forms generated under the optimum operating conditions was evaluated according to the waste acceptance criteria (WAC). The feasibility of waste disposal was demonstrated by the evaluation of the leaching index of Cs, Sr, and Co.
The uranium reconversion process is performed to convert concentrated UF6 into UO2. Ca(OH)2 is used to neutralize liquid waste generated during the uranium reconversion process, and all waste generated during this process is then collectively named lime waste. The present study aimed to improve cost-effectiveness and efficiency in lime waste treatment by replacing water, required in the cementation process, with concentrated liquid waste. The concentrate/cement ratio in the cementation process was set to range from 1.90 to 2.30, and the content of waste (lime + salt) ranged from 73.4 to 73.5 wt%. The optimum concentrate/cement ratio was determined to be 1.91, considering cost-effectiveness and safety. The structural stability of cement waste forms generated under the optimum operating conditions was evaluated according to the waste acceptance criteria (WAC). The feasibility of waste disposal was demonstrated by the evaluation of the leaching index of Cs, Sr, and Co.
Audience Academic
Author Lee, Hyun-Kyu
Shon, Jong-Sik
Kim, Gi-Yong
Kim, Tack-Jin
Ju, June-Sik
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CitedBy_id crossref_primary_10_1016_j_jclepro_2023_138682
Cites_doi 10.1002/9781118511992
10.1016/j.pnucene.2021.103957
10.1016/j.conbuildmat.2022.126471
10.1007/978-3-319-52287-6
10.15392/bjrs.v9i1A.1283
10.1016/j.net.2017.07.019
10.1016/j.conbuildmat.2019.117975
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10.1016/j.hydromet.2021.105747
10.1007/s10967-020-07471-4
10.1023/b:jrnc.0000027105.83084.c7
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Lime waste
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AUC
Operating conditions
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Snippet The uranium reconversion process is performed to convert concentrated UF 6 into UO 2 . Ca(OH) 2 is used to neutralize liquid waste generated during the uranium...
The uranium reconversion process is performed to convert concentrated UF.sub.6 into UO.sub.2. Ca(OH).sub.2 is used to neutralize liquid waste generated during...
The uranium reconversion process is performed to convert concentrated UF6 into UO2. Ca(OH)2 is used to neutralize liquid waste generated during the uranium...
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SubjectTerms Acceptance criteria
Analysis
Cementation
Chemistry
Chemistry and Materials Science
Diagnostic Radiology
Effectiveness
Hadrons
Heavy Ions
Inorganic Chemistry
Leaching
Liquid wastes
Nuclear Chemistry
Nuclear energy
Nuclear Physics
Physical Chemistry
Refuse and refuse disposal
Slaked lime
Stability analysis
Structural stability
Uranium
Uranium dioxide
Waste disposal
Waste management
Waste treatment
Title Evaluation of disposal stability of cement waste forms mixed with concentrated liquid waste for efficient treatment of AUC process waste
URI https://link.springer.com/article/10.1007/s10967-022-08495-8
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Volume 331
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