S. S. Poglyad, O. S. Dmitrieva, E. A. Bezdnyakova, O. V. Romanova
{"title":"评估基于膨润土的陶瓷在固定乏核燃料热化学处理过程中产生的放射性废物方面的适用性","authors":"S. S. Poglyad, O. S. Dmitrieva, E. A. Bezdnyakova, O. V. Romanova","doi":"10.1134/S1066362223070135","DOIUrl":null,"url":null,"abstract":"<p>The applicability of bentonite clay-based ceramics for immobilization of waste from pyrochemical reprocessing of spent nuclear fuel–spent electrolyte, which consists of alkali metal chlorides, was studied. Main matrix characteristics such as the phase composition, mechanical durability, leaching rate and microstructure were studied. The results obtained were compared to the requirements to the cement compound, formulated in NP-019-15 document. The matrix was considered to be suitable for the radioactive waste disposal.</p>","PeriodicalId":747,"journal":{"name":"Radiochemistry","volume":"65 1 supplement","pages":"S160 - S166"},"PeriodicalIF":0.9000,"publicationDate":"2024-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Assessment of Applicability of Bentonite Clay-Based Ceramics for Immobilization of Radioactive Waste from Pyrochemical Processing of Spent Nuclear Fuel\",\"authors\":\"S. S. Poglyad, O. S. Dmitrieva, E. A. Bezdnyakova, O. V. Romanova\",\"doi\":\"10.1134/S1066362223070135\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<p>The applicability of bentonite clay-based ceramics for immobilization of waste from pyrochemical reprocessing of spent nuclear fuel–spent electrolyte, which consists of alkali metal chlorides, was studied. Main matrix characteristics such as the phase composition, mechanical durability, leaching rate and microstructure were studied. The results obtained were compared to the requirements to the cement compound, formulated in NP-019-15 document. The matrix was considered to be suitable for the radioactive waste disposal.</p>\",\"PeriodicalId\":747,\"journal\":{\"name\":\"Radiochemistry\",\"volume\":\"65 1 supplement\",\"pages\":\"S160 - S166\"},\"PeriodicalIF\":0.9000,\"publicationDate\":\"2024-03-12\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Radiochemistry\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://link.springer.com/article/10.1134/S1066362223070135\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q4\",\"JCRName\":\"CHEMISTRY, INORGANIC & NUCLEAR\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Radiochemistry","FirstCategoryId":"1085","ListUrlMain":"https://link.springer.com/article/10.1134/S1066362223070135","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"CHEMISTRY, INORGANIC & NUCLEAR","Score":null,"Total":0}
Assessment of Applicability of Bentonite Clay-Based Ceramics for Immobilization of Radioactive Waste from Pyrochemical Processing of Spent Nuclear Fuel
The applicability of bentonite clay-based ceramics for immobilization of waste from pyrochemical reprocessing of spent nuclear fuel–spent electrolyte, which consists of alkali metal chlorides, was studied. Main matrix characteristics such as the phase composition, mechanical durability, leaching rate and microstructure were studied. The results obtained were compared to the requirements to the cement compound, formulated in NP-019-15 document. The matrix was considered to be suitable for the radioactive waste disposal.
期刊介绍:
Radiochemistry is a journal that covers the theoretical and applied aspects of radiochemistry, including basic nuclear physical properties of radionuclides; chemistry of radioactive elements and their compounds; the occurrence and behavior of natural and artificial radionuclides in the environment; nuclear fuel cycle; radiochemical analysis methods and devices; production and isolation of radionuclides, synthesis of labeled compounds, new applications of radioactive tracers; radiochemical aspects of nuclear medicine; radiation chemistry and after-effects of nuclear transformations.