首页> 外文会议>Proceeding of the 2000 international conference on incineration and thermal treatment technologies (IT3 conference proceedings) >THE STUDY ON PLASMA VITRIFICATION TECHNOLOGY FOR THE TREATMENT OF RADIOACTIVE AND HAZARDOUS WASTES
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THE STUDY ON PLASMA VITRIFICATION TECHNOLOGY FOR THE TREATMENT OF RADIOACTIVE AND HAZARDOUS WASTES

机译:等离子玻璃化技术处理放射性和有害废物的研究

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To evaluate the cost benefit of the treatment of low-level radioactive wastes and hazardous wastes by plasma technology, vitrificationrntests of nuclear surrogates and fly ashes from municipal waste incinerators are studied. The nuclear surrogate wastes suchrnas concentrate, cement solidified wastes, bottom ash from incinerator, resin, thermal insulators, high efficient particulate air filter,rnmetal, contaminated soil etc. were prepared according to the waste stream from one nuclear power plant in Taiwan. Non-radioactiverntracers with an amount of 0.1wt% are added into surrogate wastes to study the volatility of radioactive nuclides such as Cs-134,rnCs-137, Co-60, Co-58 etc. To control the quality of vitreous slag, to reduce the melting temperature and to obtain maximum volumernreduction ratio in each vitrification testing, no additional glass-formers were added and the strategy that one waste surrogaternwas mixed with another was used. Several tens of vitrification tests under the temperatures between 900℃ and 1650℃ are performedrnto screen out the proper waste mixtures which produce high-quality slag with satisfied volume reduction ratios. The evaluationrnof plasma vitrification treatment for the low level radioactive wastes of the nuclear power plant in Taiwan by using binaryrnwaste mixing strategy shows that the gross volume reduction ratio is greater than 2.8, which implies that the final disposal cost is tornbe greatly reduced. Vitrification tests of fly ashes and bottom ashes from two incinerators show that ash residues can be easilyrnprocessed without additives at 1500℃, and glassy slag with high compressive strength and low leaching rate has great potential tornbe reused as construction materials.
机译:为了评估通过等离子体技术处理低放射性废物和危险废物的成本效益,研究了市政废物焚化炉产生的核替代物和飞灰的玻璃化测试。根据台湾一台核电站的废物流,制备了核替代废物浓缩物,水泥固化废物,焚烧炉底灰,树脂,绝热材料,高效颗粒空气过滤器,金属,污染的土壤等。将0.1wt%的非放射性示踪剂添加到替代废物中,以研究放射性核素(例如Cs-134,rnCs-137,Co-60,Co-58等)的挥发性。为了控制玻璃渣的质量,为了降低熔化温度并在每次玻璃化测试中获得最大的体积减少率,不添加其他玻璃形成剂,而是采用了一种将废旧替代物与另一种替代替代物混合的策略。在900℃至1650℃的温度下进行了数十次玻璃化试验,以筛选出合适的废物混合物,产生高质量炉渣的体积缩小率。采用二元废物混合策略对台湾核电站低放射性废物进行等离子体玻璃化处理的评估表明,总体积减少率大于2.8,这意味着最终处置成本将大大降低。两台焚烧炉的粉煤灰和底灰的玻璃化试验表明,在没有添加剂的情况下,灰渣可以在1500℃下容易地进行处理,具有高抗压强度和低浸出率的玻璃状渣具有被重新用作建筑材料的巨大潜力。

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