Karine Ferrand, Pieter Schroeders, Sébastien Caes, Karel Lemmens
{"title":"热等静压固定化有机废物的溶解实验","authors":"Karine Ferrand, Pieter Schroeders, Sébastien Caes, Karel Lemmens","doi":"10.1016/j.nucengdes.2025.114533","DOIUrl":null,"url":null,"abstract":"<div><div>The presence of organic compounds in radioactive wastes might be incompatible with long-term waste management options. Consequently, as part of the H2020-PREDIS project, different thermal treatment routes and conditioning techniques were first used to process surrogates of solid organic wastes. Then, the chemical durability of the conditioned wastes was investigated performing dissolution experiments in a synthetic cementitious water at pH<!--> <!-->12.7, 22 °C and in diluted conditions. These tests were conducted with a glass–ceramic, produced by hot isostatic pressing using a mixture of ashes and sodium tetraborate (95/5 wt%). The results showed that glass–ceramic dissolution was incongruent and controlled by diffusion. SEM–EDX analysis showed the presence of an altered zone of about 45 <!--> <!-->µm after 730 <!--> <!-->days of alteration, with amorphous and crystalline phases (spinel and chlorapatite), and containing voids due to the dissolution of the glass matrix. The average diffusion coefficients were in the range of (4.26 ± 1.36) × 10<sup>−15</sup> <!-->–<!--> <!-->(2.88 ± 0.59) × 10<sup>−13</sup> <!-->m<sup>2</sup>/s, with the lowest and highest values for Zn and B, respectively. This corresponds to leachability indexes in the range of 10.40 ± 0.14 and 8.54 ± 0.07. The maximum dissolution rate of the glass matrix based on the B release between the start of the tests and 28 <!--> <!-->days was similar to that found when borosilicate glass was corroded by a KOH solution at pH<!--> <!-->12.5. Hot isostatic pressing was thus successfully used to immobilize ashes, and the resulting glass–ceramic exhibited good chemical durability under alkaline conditions.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114533"},"PeriodicalIF":2.1000,"publicationDate":"2025-10-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Dissolution experiments with surrogate treated organic wastes immobilized by hot isostatic pressing\",\"authors\":\"Karine Ferrand, Pieter Schroeders, Sébastien Caes, Karel Lemmens\",\"doi\":\"10.1016/j.nucengdes.2025.114533\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The presence of organic compounds in radioactive wastes might be incompatible with long-term waste management options. Consequently, as part of the H2020-PREDIS project, different thermal treatment routes and conditioning techniques were first used to process surrogates of solid organic wastes. Then, the chemical durability of the conditioned wastes was investigated performing dissolution experiments in a synthetic cementitious water at pH<!--> <!-->12.7, 22 °C and in diluted conditions. These tests were conducted with a glass–ceramic, produced by hot isostatic pressing using a mixture of ashes and sodium tetraborate (95/5 wt%). The results showed that glass–ceramic dissolution was incongruent and controlled by diffusion. SEM–EDX analysis showed the presence of an altered zone of about 45 <!--> <!-->µm after 730 <!--> <!-->days of alteration, with amorphous and crystalline phases (spinel and chlorapatite), and containing voids due to the dissolution of the glass matrix. The average diffusion coefficients were in the range of (4.26 ± 1.36) × 10<sup>−15</sup> <!-->–<!--> <!-->(2.88 ± 0.59) × 10<sup>−13</sup> <!-->m<sup>2</sup>/s, with the lowest and highest values for Zn and B, respectively. This corresponds to leachability indexes in the range of 10.40 ± 0.14 and 8.54 ± 0.07. The maximum dissolution rate of the glass matrix based on the B release between the start of the tests and 28 <!--> <!-->days was similar to that found when borosilicate glass was corroded by a KOH solution at pH<!--> <!-->12.5. Hot isostatic pressing was thus successfully used to immobilize ashes, and the resulting glass–ceramic exhibited good chemical durability under alkaline conditions.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"445 \",\"pages\":\"Article 114533\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-10-10\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0029549325007101\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325007101","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Dissolution experiments with surrogate treated organic wastes immobilized by hot isostatic pressing
The presence of organic compounds in radioactive wastes might be incompatible with long-term waste management options. Consequently, as part of the H2020-PREDIS project, different thermal treatment routes and conditioning techniques were first used to process surrogates of solid organic wastes. Then, the chemical durability of the conditioned wastes was investigated performing dissolution experiments in a synthetic cementitious water at pH 12.7, 22 °C and in diluted conditions. These tests were conducted with a glass–ceramic, produced by hot isostatic pressing using a mixture of ashes and sodium tetraborate (95/5 wt%). The results showed that glass–ceramic dissolution was incongruent and controlled by diffusion. SEM–EDX analysis showed the presence of an altered zone of about 45 µm after 730 days of alteration, with amorphous and crystalline phases (spinel and chlorapatite), and containing voids due to the dissolution of the glass matrix. The average diffusion coefficients were in the range of (4.26 ± 1.36) × 10−15 – (2.88 ± 0.59) × 10−13 m2/s, with the lowest and highest values for Zn and B, respectively. This corresponds to leachability indexes in the range of 10.40 ± 0.14 and 8.54 ± 0.07. The maximum dissolution rate of the glass matrix based on the B release between the start of the tests and 28 days was similar to that found when borosilicate glass was corroded by a KOH solution at pH 12.5. Hot isostatic pressing was thus successfully used to immobilize ashes, and the resulting glass–ceramic exhibited good chemical durability under alkaline conditions.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.