Characterization of Cs deposits formed by the interaction of simulated fission product CsOH in the gas phase and concrete at 200°C
Cs distribution is crucial for decommissioning Fukushima Daiichi Nuclear Power Station (1F). Several experimental studies confirmed Cs retention on stainless steels by performing chemical reactions at high temperatures (typically > 800°C), but the Cs retention on concrete, used in large quant...
| Main Authors: | , |
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| Format: | Article |
| Language: | English |
| Published: |
The Japan Society of Mechanical Engineers
2024-02-01
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| Series: | Mechanical Engineering Journal |
| Subjects: | |
| Online Access: | https://www.jstage.jst.go.jp/article/mej/11/2/11_23-00446/_pdf/-char/en |
| _version_ | 1797206045435625472 |
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| author | Nhut Vu LUU Kunihisa NAKAJIMA |
| author_facet | Nhut Vu LUU Kunihisa NAKAJIMA |
| author_sort | Nhut Vu LUU |
| collection | DOAJ |
| description | Cs distribution is crucial for decommissioning Fukushima Daiichi Nuclear Power Station (1F). Several experimental studies confirmed Cs retention on stainless steels by performing chemical reactions at high temperatures (typically > 800°C), but the Cs retention on concrete, used in large quantities in light water reactors, is not fully understood. This study demonstrated that Cs might have been deposited and retained on concrete structures where the temperature was not so high during the 1F accident. Results showed that the CsOH/concrete interaction at ~200°C occurred in water-insoluble Cs–(Al, Fe)–Si–O deposits and water-soluble phases, i.e., Cs carbonate hydrate and possibly Cs2SiO3 if Al and Fe are absent. CsOH might be trapped on concrete by chemical reaction with CaCO3 to form Cs2CO3 hydrate and with aluminosilicate and SiO2 (quartz) to form Cs–Al–Si–O and Cs–Si–O deposits, respectively. This output could help elucidate the trapping mechanism that caused extremely high radioactivity on concrete shield plugs at 1F and develop an effective decommissioning practice for concrete structures. |
| first_indexed | 2024-04-24T09:00:46Z |
| format | Article |
| id | doaj.art-6e28b3353198419ab1c576a69acd7946 |
| institution | Directory Open Access Journal |
| issn | 2187-9745 |
| language | English |
| last_indexed | 2024-04-24T09:00:46Z |
| publishDate | 2024-02-01 |
| publisher | The Japan Society of Mechanical Engineers |
| record_format | Article |
| series | Mechanical Engineering Journal |
| spelling | doaj.art-6e28b3353198419ab1c576a69acd79462024-04-16T01:29:36ZengThe Japan Society of Mechanical EngineersMechanical Engineering Journal2187-97452024-02-0111223-0044623-0044610.1299/mej.23-00446mejCharacterization of Cs deposits formed by the interaction of simulated fission product CsOH in the gas phase and concrete at 200°CNhut Vu LUU0Kunihisa NAKAJIMA1Nuclear Science and Engineering Center, Japan Atomic Energy AgencyNuclear Science and Engineering Center, Japan Atomic Energy AgencyCs distribution is crucial for decommissioning Fukushima Daiichi Nuclear Power Station (1F). Several experimental studies confirmed Cs retention on stainless steels by performing chemical reactions at high temperatures (typically > 800°C), but the Cs retention on concrete, used in large quantities in light water reactors, is not fully understood. This study demonstrated that Cs might have been deposited and retained on concrete structures where the temperature was not so high during the 1F accident. Results showed that the CsOH/concrete interaction at ~200°C occurred in water-insoluble Cs–(Al, Fe)–Si–O deposits and water-soluble phases, i.e., Cs carbonate hydrate and possibly Cs2SiO3 if Al and Fe are absent. CsOH might be trapped on concrete by chemical reaction with CaCO3 to form Cs2CO3 hydrate and with aluminosilicate and SiO2 (quartz) to form Cs–Al–Si–O and Cs–Si–O deposits, respectively. This output could help elucidate the trapping mechanism that caused extremely high radioactivity on concrete shield plugs at 1F and develop an effective decommissioning practice for concrete structures.https://www.jstage.jst.go.jp/article/mej/11/2/11_23-00446/_pdf/-char/encsohcesium aluminosilicatechemisorptionshield plugfukushima accidentconcrete |
| spellingShingle | Nhut Vu LUU Kunihisa NAKAJIMA Characterization of Cs deposits formed by the interaction of simulated fission product CsOH in the gas phase and concrete at 200°C Mechanical Engineering Journal csoh cesium aluminosilicate chemisorption shield plug fukushima accident concrete |
| title | Characterization of Cs deposits formed by the interaction of simulated fission product CsOH in the gas phase and concrete at 200°C |
| title_full | Characterization of Cs deposits formed by the interaction of simulated fission product CsOH in the gas phase and concrete at 200°C |
| title_fullStr | Characterization of Cs deposits formed by the interaction of simulated fission product CsOH in the gas phase and concrete at 200°C |
| title_full_unstemmed | Characterization of Cs deposits formed by the interaction of simulated fission product CsOH in the gas phase and concrete at 200°C |
| title_short | Characterization of Cs deposits formed by the interaction of simulated fission product CsOH in the gas phase and concrete at 200°C |
| title_sort | characterization of cs deposits formed by the interaction of simulated fission product csoh in the gas phase and concrete at 200°c |
| topic | csoh cesium aluminosilicate chemisorption shield plug fukushima accident concrete |
| url | https://www.jstage.jst.go.jp/article/mej/11/2/11_23-00446/_pdf/-char/en |
| work_keys_str_mv | AT nhutvuluu characterizationofcsdepositsformedbytheinteractionofsimulatedfissionproductcsohinthegasphaseandconcreteat200c AT kunihisanakajima characterizationofcsdepositsformedbytheinteractionofsimulatedfissionproductcsohinthegasphaseandconcreteat200c |