Nuclear and Chemical Waste Management最新文献

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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

Nuclear and Chemical Waste Management

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

Nuclear and Chemical Waste Management

Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90065-4

Frederick Schoenig, Sharon G. Glendinning, Timothy Schick, Samuel Untermyer

引用次数: 0

4683711 Thread monitoring device 4683711螺纹监控装置

Nuclear and Chemical Waste Management

Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90044-7

引用次数: 0

4689121 Recovery of phosphorus from sludge 4689121污泥中磷的回收

Nuclear and Chemical Waste Management

Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90086-1

引用次数: 0

Editorial: Software survey section 编辑:软件调查部分

Nuclear and Chemical Waste Management

Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90066-6

引用次数: 0

Waste not 不浪费

Nuclear and Chemical Waste Management

Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90067-8

Dixy Lee Ray

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

Nuclear and Chemical Waste Management

Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90061-7

Helmut E. Siekmann, Jurgen Bassler, Winfried Liebig

引用次数: 0

The distribution of trace water around brine leaks in the avery island salt mine: Implications for the natural migration of water in salt 艾弗里岛盐矿卤水泄漏周围微量水的分布:对水在盐中的自然运移的启示

Nuclear and Chemical Waste Management

Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90026-5

Anthony J. Tesoriero , L.Paul Knauth

The natural distribution of water in the Avery Island domal salt has been investigated by performing trace water content analysis on 64 samples collected systematically at the 210 and 270 meter levels of the International Salt Compan mine. Specific attention was given to salt near an internal shear zone which is the apparent source of several mine leaks. No discernible migration of brine into the adjacent salt was observed from the meteoric leak at the 210 m level. Extensive water enrichment (>1000 mg/kg) was limited to 30 meters from the formation water leak at the 270 m level. The water contents of coexisting samples near the formation water leak are highly variable. If water is moving from; this leak into the adjacent normal salt it is not doing so by way of a uniform diffusion process. Petrographic examination of polished salt samples reveals that fluid inclusions occur mainly in healed fractures. The water content of a sample depends on the density of such fractures. Natural movement of water in the salt appears to occur mainly through microfractures and possibly along crystal boundaries rather than by the diffusion of brine through crystals. One possible zone of enhanced water content may occur along a possible bedding plane which intersects a mine leak. This suggests that any natural movement of fluid not associated with fractured salt may occur preferentially along bedding planes. The method of brine migration under natural conditions, the occurrence of fluid inclusions (i.e., fracture vs. nonfracture-fill inclusions), and the water content of salt will be helpful in evaluating the migration of brine in response to the thermal and/or pressure gradient which will be created by the emplacement of radioactive waste.

通过对国际盐业公司在210米和270米高度系统收集的64个样品进行痕量水含量分析，研究了艾弗里岛丘状盐中水的自然分布。特别注意了内部剪切带附近的盐，这是几个矿井泄漏的明显来源。在210 m高度的大气泄漏中，没有观测到盐水向邻近盐的明显迁移。广泛的水富集(>1000 mg/kg)被限制在距离地层水泄漏处270 m的30米处。地层漏水附近共存样品的含水量变化很大。如果水从;这种泄漏进入邻近的普通盐，它不是通过均匀扩散过程这样做的。抛光盐样品的岩石学检查表明，流体包裹体主要出现在愈合的裂缝中。样品的含水量取决于这种裂缝的密度。水在盐中的自然运动似乎主要是通过微裂缝进行的，可能沿着晶体边界进行，而不是通过盐水在晶体中的扩散。沿着与矿井泄漏点相交的可能的层理平面可能出现一个可能的含水率增加的区域。这表明任何与裂缝性盐无关的流体的自然运动都可能优先沿层理面发生。在自然条件下的盐水迁移方法、流体包裹体(即裂缝与非裂缝充填包裹体)的发生情况以及盐的含水量将有助于评估放射性废物安置将产生的热梯度和/或压力梯度对盐水迁移的影响。

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引用次数: 1

4681729 Monitoring temperature within a vessel 4681729监测容器内温度

Nuclear and Chemical Waste Management

Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90037-X

引用次数: 0

4681706 Nuclear waste packaging facility 4681706核废料包装设施

Nuclear and Chemical Waste Management

Pub Date : 1988-01-01 DOI: 10.1016/0191-815X(88)90036-8

引用次数: 0

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