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In situ vitrification demonstration for the stabilization of buried wastes at the Oak Ridge National Laboratory 橡树岭国家实验室埋藏废物稳定的原位玻璃化演示
Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90051-4
Gary K. Jacobs, Brian P. Spalding, J.Gary. Carter, Sydney S. Koegler

A demonstration of In Situ Vitrification (ISV) technology for the stabilization of radioactively contaminated soil sites at the Oak Ridge National Laboratory (ORNL) was successfully completed during July 1987. This demonstration is the first application of the ISV process not performed at the Hanford Site, where the technology was developed and patented for the U.S. Department of Energy by Pacific Northwest Laboratory (PNL). The joint ORNL-PNL pilot-scale demonstration was performed on a 3/8-scale trench (2 m deep × 1 m wide × 10 m long) that was constructed to simulate a typical seepage trench used for liquid low-level radioactive waste disposal at ORNL from 1951 to 1966. In the ISV process, electrodes are inserted around a volume of contaminated soil, power is applied to the electrodes, and the entire mass is melted from the surface of the soil down through the contaminated zone, thus making a glassy-to-microcrystalline waste form that incorporates the contaminants. Gases produced during the melting are collected, treated, monitored, and released through an off-gas process trailer. In the ORNL demonstration, a 25,000-kg mass of melted rock approximately 1.2 m thick × 2.1 m wide × 4.9 m long was formed during 110 h of operation that consumed approximately 29 MWh of power. Data obtained on the operational performance of the test and waste-form durability will be used to assess the feasibility of applying the ISV technology to an actual waste trench.

1987年7月,橡树岭国家实验室(ORNL)成功地完成了原位玻璃化(ISV)技术稳定放射性污染土壤场址的示范。这次演示是ISV过程的第一次应用,不是在汉福德现场进行的,该技术是在那里开发的,并由太平洋西北实验室(PNL)为美国能源部获得专利。为了模拟1951 - 1966年ORNL用于低放射性液体废物处理的典型渗水沟,在3/8比例尺(2 m深× 1 m宽× 10 m长)上进行了ORNL- pnl联合中试示范。在ISV过程中,电极被插入到污染土壤的周围,对电极施加电力,整个土壤从土壤表面向下通过污染区域熔化,从而形成含有污染物的玻璃状到微晶状的废物形式。熔化过程中产生的气体被收集、处理、监测,并通过废气处理拖车释放。在ORNL的演示中,在110小时的运行期间,形成了一个25000公斤的熔化岩石,大约1.2米厚× 2.1米宽× 4.9米长,消耗了大约29兆瓦时的电力。有关测试的操作性能和废物形式耐久性的数据将用于评估将独立系统技术应用于实际废物沟渠的可行性。
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引用次数: 13
Automated monitoring of fissile and fertile materials in large waste containers 自动监测大型废物容器中的易裂变和可再生材料
Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90065-4
Frederick Schoenig, Sharon G. Glendinning, Timothy Schick, Samuel Untermyer
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引用次数: 0
4683711 Thread monitoring device 4683711螺纹监控装置
Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90044-7
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引用次数: 0
4689121 Recovery of phosphorus from sludge 4689121污泥中磷的回收
Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90086-1
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引用次数: 0
Editorial: Software survey section 编辑:软件调查部分
Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90066-6
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引用次数: 0
Process and equipment, in particular for the conditioning of waste water sludges 工艺和设备,特别是废水污泥的调理
Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90061-7
Helmut E. Siekmann, Jurgen Bassler, Winfried Liebig
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引用次数: 0
Waste not 不浪费
Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90067-8
Dixy Lee Ray
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引用次数: 0
4681706 Nuclear waste packaging facility 4681706核废料包装设施
Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90036-8
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引用次数: 0
4683542 Vibration monitoring apparatus 4683542振动监测装置
Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90043-5
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引用次数: 0
4681729 Monitoring temperature within a vessel 4681729监测容器内温度
Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90037-X
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引用次数: 0
期刊
Nuclear and Chemical Waste Management
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