PROPERTIES OF THE FINAL PRODUCT OF THERMOCHEMICAL REPROCESSING OF IRRADIATED REACTOR GRAPHITE WASTES IN THE Al-TiO_2-C SYSTEM

O. K. Karlina; G. Yu. Pavlova; Y. L. Klimov; S. A. Dmitriev

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PROPERTIES OF THE FINAL PRODUCT OF THERMOCHEMICAL REPROCESSING OF IRRADIATED REACTOR GRAPHITE WASTES IN THE Al-TiO_2-C SYSTEM

机译：Al-TiO_2-C体系中辐照反应器石墨废料热化学重整的最终产物性质

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Laboratory investigations of the strength and chemical resistance of the final product of thermochemical reprocessing of reactor graphite wastes in the Al-TiO_2-C system are presented. The ~(137)Cs and ~(90)Sr leaching rate, which is determined for samples synthesized from a charge with real irradiated graphite from an AM research reactor, does not exceed 10~(-6) g/(cm~2·day) at the 28th day.

机译：实验室对反应堆石墨废料在Al-TiO_2-C系统中进行热化学处理的最终产品的强度和耐化学性进行了实验室研究。由AM研究反应堆中带有真实辐照石墨的装药合成的样品测定的〜（137）Cs和〜（90）Sr浸出速率不超过10〜（-6）g /（cm〜2·天）在第28天。

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《Atomic Energy》 |2008年第4期|p.295-298|共4页
作者
O. K. Karlina; G. Yu. Pavlova; Y. L. Klimov; S. A. Dmitriev;
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收录信息美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
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正文语种 eng
中图分类原子能技术;
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入库时间 2022-08-18 00:40:41

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1. CHARACTERISTICS OF THERMOCHEMICAL PROCESSES IN THE SYSTEM C-Al-TiO_2 DURING REPROCESSING OF REACTOR GRAPHITE [J] . O. K. Karlina, V. L. Klimov, G. Yu. Pavlova, Atomic Energy . 2006,第5期

机译：反应器石墨再处理过程中C-Al-TiO_2体系热化学过程的特征
2. Radionuclides in Irradiated Graphite of Industrial Uranium–Graphite Reactors: Effect of Irradiation and Thermochemical Treatment on the Graphite Structure [J] . A. A. Shiryaev, A. G. Volkova, E. V. Zakharova, Radiochemistry . 2018,第6期

机译：辐照核酸核核酸石墨 - 石墨反应器的辐射核素：辐照和热化学处理对石墨结构的影响
3. Radionuclides in Irradiated Graphite of Uranium–Graphite Reactors: Decontamination by Thermochemical Methods [J] . A. G. Volkova, E. V. Zakharova, N. I. Rodygina, Radiochemistry . 2018,第6期

机译：铀 - 石墨反应器辐照石墨中的放射性核素：通过热化学方法去污
4. THERMOCHEMICAL CONDITIONING OF RADIOACTIVE WASTE: STRUCTURE AND PROPERTIES OF FINAL PROCESSED PRODUCT [C] . Olga K. Karlina, Galina A.Varlakova, Sergei A. Dmitriev, 9th International Conference on Environmental Remediation and Radioactive Waste Management . 2003

机译：放射性废料的热化学条件：最终加工产品的结构和性质
5. ICP-MS analysis of fission product diffusion in graphite for High-Temperature Gas-Cooled Reactors. [D] . Carter, Lukas M. 2015

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6. Sustainable conversion of coffee and other crop wastes to biofuels and bioproducts using coupled biochemical and thermochemical processes in a multi-stage biorefinery concept [O] . Stephen R. Hughes, Juan Carlos López-Núñez, Marjorie A. Jones, -1

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7. Boronated-graphite irradiation studies : final report of irradiation experiments conducted in a Hanford reactor / [O] . Davidson, J. M., Gates, L. O., U.S. Atomic Energy Commission., 1965

机译：硼化石墨辐照研究：汉福德反应堆辐照实验的最终报告/

PROPERTIES OF THE FINAL PRODUCT OF THERMOCHEMICAL REPROCESSING OF IRRADIATED REACTOR GRAPHITE WASTES IN THE Al-TiO_2-C SYSTEM

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