Thermodynamic study on the separation of strontium and barium from LWR spent fuel
The separation of high heat load fission products, such as alkaline earth metals, from nuclear spent fuel can significantly reduce the burden of spent fuel disposal. This study investigates the feasibility of separating strontium and barium from light water reactor spent fuel through non-aqueous pro...
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| Format: | Article |
| Language: | English |
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Elsevier
2025-02-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573324004297 |
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| author | Jin-Mok Hur Jungho Hur Yung-Zun Cho Chang Hwa Lee |
| author_facet | Jin-Mok Hur Jungho Hur Yung-Zun Cho Chang Hwa Lee |
| author_sort | Jin-Mok Hur |
| collection | DOAJ |
| description | The separation of high heat load fission products, such as alkaline earth metals, from nuclear spent fuel can significantly reduce the burden of spent fuel disposal. This study investigates the feasibility of separating strontium and barium from light water reactor spent fuel through non-aqueous processes. Process flows were developed for treating spent nuclear fuel by heating it at high temperatures to remove volatile nuclides, followed by chlorination with a chlorinating agent. The chlorinated products were then treated with a precipitating agent in LiCl-KCl molten salt for further separation. The remaining liquid was distilled to recover strontium and barium. Thermodynamic equilibrium calculations were conducted for the process flows. Under the conditions of the process flows, the chlorinating agents MgCl2 and NH4Cl both converted SrO and BaO entirely into SrCl2 and BaCl2, respectively. The precipitating agent Li2CO3 exhibited superior separation effectiveness compared to Li3PO4. Thermodynamic calculations indicate that strontium and barium recovered by MgCl2 chlorination, Li2CO3 precipitation, and distillation will contain 0.18 %, 1.06 %, and 0.32 % impurities in terms of mass, radioactivity, and decay heat, respectively. |
| format | Article |
| id | doaj-art-88393f7a593141daa47f70214b05f7e0 |
| institution | Kabale University |
| issn | 1738-5733 |
| language | English |
| publishDate | 2025-02-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj-art-88393f7a593141daa47f70214b05f7e02025-01-31T05:11:01ZengElsevierNuclear Engineering and Technology1738-57332025-02-01572103181Thermodynamic study on the separation of strontium and barium from LWR spent fuelJin-Mok Hur0Jungho Hur1Yung-Zun Cho2Chang Hwa Lee3Corresponding author. Korea Atomic Energy Research Institute, Daejeon, 34057, Republic of Korea.; Korea Atomic Energy Research Institute, Republic of KoreaKorea Atomic Energy Research Institute, Republic of KoreaKorea Atomic Energy Research Institute, Republic of KoreaKorea Atomic Energy Research Institute, Republic of KoreaThe separation of high heat load fission products, such as alkaline earth metals, from nuclear spent fuel can significantly reduce the burden of spent fuel disposal. This study investigates the feasibility of separating strontium and barium from light water reactor spent fuel through non-aqueous processes. Process flows were developed for treating spent nuclear fuel by heating it at high temperatures to remove volatile nuclides, followed by chlorination with a chlorinating agent. The chlorinated products were then treated with a precipitating agent in LiCl-KCl molten salt for further separation. The remaining liquid was distilled to recover strontium and barium. Thermodynamic equilibrium calculations were conducted for the process flows. Under the conditions of the process flows, the chlorinating agents MgCl2 and NH4Cl both converted SrO and BaO entirely into SrCl2 and BaCl2, respectively. The precipitating agent Li2CO3 exhibited superior separation effectiveness compared to Li3PO4. Thermodynamic calculations indicate that strontium and barium recovered by MgCl2 chlorination, Li2CO3 precipitation, and distillation will contain 0.18 %, 1.06 %, and 0.32 % impurities in terms of mass, radioactivity, and decay heat, respectively.http://www.sciencedirect.com/science/article/pii/S1738573324004297Thermodynamic studySeparationStrontiumBariumLWR spent fuel |
| spellingShingle | Jin-Mok Hur Jungho Hur Yung-Zun Cho Chang Hwa Lee Thermodynamic study on the separation of strontium and barium from LWR spent fuel Nuclear Engineering and Technology Thermodynamic study Separation Strontium Barium LWR spent fuel |
| title | Thermodynamic study on the separation of strontium and barium from LWR spent fuel |
| title_full | Thermodynamic study on the separation of strontium and barium from LWR spent fuel |
| title_fullStr | Thermodynamic study on the separation of strontium and barium from LWR spent fuel |
| title_full_unstemmed | Thermodynamic study on the separation of strontium and barium from LWR spent fuel |
| title_short | Thermodynamic study on the separation of strontium and barium from LWR spent fuel |
| title_sort | thermodynamic study on the separation of strontium and barium from lwr spent fuel |
| topic | Thermodynamic study Separation Strontium Barium LWR spent fuel |
| url | http://www.sciencedirect.com/science/article/pii/S1738573324004297 |
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