快中子反应堆钠主冷却剂固定化和反应堆运行过程中产生的放射性废液处理的创新技术

IF 0.4 4区工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY

Atomic Energy Pub Date : 2025-03-03 DOI:10.1007/s10512-025-01186-z

K. G. Legkikh, V. B. Smykov

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引用次数: 0

摘要

本文研究了氮化硼反应堆碱性液态金属废冷却剂的处理问题。详细介绍了BR-10研究堆处理冷却剂及其残余物的方法。给出了固化产物的机械强度、铯-137浸出率等主要参数。将所得数据与放射性钠在10%碱溶液中溶解得到的水泥胶凝物固定化指标进行了比较。对三种改性斜沸石净化反应堆退役过程中产生的高盐放射性废液的效率进行了比较。简要介绍了一种处理放射性液体废物浓缩物的方法。BN-350反应堆目前的状态被认为表明需要处理积累的放射性废物，以便进一步退役。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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Innovative technologies for immobilizing the sodium primary coolant of fast neutron reactors and processing liquid radioactive waste generated during reactor operation

The paper considers the issues of processing spent alkaline liquid metal coolant of BN reactors. Methods used in the BR-10 research reactor for processing coolant and its residues are described in detail. The main parameters of solidified products including mechanical strength and cesium-137 leaching rate are provided. The obtained data are compared with the indicators of cement compounds immobilizing an alkaline solution obtained by dissolving radioactive sodium in 10% alkali. The efficiency of purifying high-salt concentrates of liquid radioactive waste generated during reactor decommissioning is provided for three options of modified clinoptilolite. An approach to processing liquid radioactive waste concentrates is briefly described. The current state of the BN-350 reactor is considered indicating the need for processing accumulated radioactive waste for further decommissioning.

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来源期刊

Atomic Energy 工程技术-核科学技术

CiteScore

1.00

自引率

20.00%

发文量

100

审稿时长

4-8 weeks

期刊介绍： Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.