无GGH湿法脱硫工艺的“石膏雨”防治设计与运行优化

为了解决火力发电厂无GGH湿法脱硫工艺出现的“石膏雨”问题,神华万州发电厂从脱硫吸收塔内部流场调整、结构设置、烟气流速、边界条件设定、烟囱结构优化等方面进行设计和优化运行,在很大程度上减少了湿法脱硫的“石膏雨”现象的发生。     

扬州市城区内河优化换水方案研究

通过分析扬州市城区内河各河段的流量关系和水质关系,建立城区内河水系优化换水数学模型,合理分配各内河的换水量,使得各内河出水口水质有所改善且相当,实现扬州市城区内河换水方案的优化.开发的开放性可视化优化换水软件,方便用户随时更新河道参数和水质参数,计算不同情况下的换水方案.     

优化混凝处理低温低浊黄河水及对余铝的控制

考察了4种混凝剂,高效聚合氯化铝（HPAC）,聚合氯化铝（PACl）,硫酸铝（Al2（SO4）3）,混合PACl和氯化铁（FeCl3）,对低温低浊黄河原水的混凝效果与沉后水残留铝含量的关系。结果表明,当采用Al2（SO4）3或PACl做混凝剂时,在取得较好浊度去除的投药量下,水中余铝浓度会超过国家标准（0．2131g／L）。而采用HPAC或FeCl3和PACl复配药剂,在取得与Al2（SO4）3或PACl类似的浊度去除效果的同时,也能较好地控制水中的余铝含量。当HPAC投加量为21mg／L时,沉后水浊度降至1．3NTU,残留铝含量为0．147mg／L。复配投加PACl 15mg／L和FeCl3 12mg／L后,沉后水浊度为1．18NTU,残留铝含量为0．074mg／L。PACl和氯化铁的复配比例需要精确的调控,否则容易导致出水余铁余铝含量增加。而HPAC投加量小于21mtg／L时出水余铝浓度均低于国家标准。因此,在这4种混凝剂中,就混凝效果及余铝控制而言,HPAC更适合充当低温低浊水源水的混凝处理药剂。     

改进隔板絮凝池的数值模拟和实验

通过在廊道中增加了V型穿孔挡板,对传统往复式隔板絮凝池进行了改进,利用数值模拟和实验方法,探讨了改进絮凝池中流态、湍动能（κ）、耗散率（ε）分布情况以及这些参数对絮凝效果的影响。对多种方案进行了优化计算和实验,结果表明,在隔板絮凝池第1个廊道进口1/3和2/3处设置2个120°多孔V型挡板在各种方案中絮凝效果最好,能有效地增加水体紊动,提高絮凝效果,增设V型穿孔挡板后可以适当减少隔板絮凝池长度。     

新型微生物菌剂对垃圾渗滤液的除臭效果

利用从食材中筛选纯化的特定微生物制成新型复合菌剂,以不同浓度梯度处理垃圾渗滤液,测定其在自然条件下的嗅阈值,监测NH3和H2S即时挥发浓度的变化,评价菌剂的综合除臭效果,设计三因素三水平实验并采用响应面优化法对反应适宜的实验参数进行了优化。研究结果表明,新型复合菌剂的投加会使垃圾渗滤液嗅阈值明显下降;响应面优化模型分析表明,反应时间2.5 d时和0.5%的菌剂投加对抑制NH3的挥发效果最好,而反应时间2.5 d和0.2%的投入量对抑制H2S的挥发效果最好,氧气的供应情况对两者的挥发抑制效果影响不显著。     

海南火山岩滤料曝气生物滤池工艺优化研究

本研究基于上向流曝气生物滤池污水处理系统,研究了该工艺不同气水比、不同水力停留时间、不同滤料高度层、反冲洗强度对污染物的处理效能的影响。结果表明,气水比为4∶1、水力停留时间2 h时,BAF出水中COD、NH+4-N和SS指标达到最佳;沿程污染物去除率随着滤料层高度的增加逐渐增大,当滤料高度大于1.6 m时趋于稳定,COD、NH+4-N和SS平均去除率分别达到80%、99%和80.3%。建议曝气生物滤池的反冲洗推荐程序为:先气冲(18 L/(m2·s)),单独气洗2~3 min;再气冲(18 L/(m2·s))加水冲(5 L/(m2·s)),联合反冲洗3~5 min;最后水冲(5 L/(m2·s)),漂洗5~8 min。     

基于多枢纽城际应急管理网络资源调度鲁棒优化

为了降低由于应急突发事件随机性带来的应急资源需求不确定性,在对基于Multi-HUB(多枢纽)城际应急管理网络机制研究的基础上,分析基于Multi-HUB城际应急管理网络信息传递和资源调度方式,建立以时间最小为目标的资源优化调度模型并鲁棒性地选择一级HUB点,通过Matlab7.0对优化调度模型及一级HUB点鲁棒性选择进行了数值仿真。研究表明:对Multi-HUB城际应急管理网络中的一级HUB点进行鲁棒性选择,能很好地对"都市圈"内应急资源进行优化调度,降低需求不确定性所带来的"都市圈"内资源无法有效整合的风险,从而有效地提高城市应急资源利用效率。     

Assessment of the efficiency and economic viability of various methods of treatment of sanitary landfill leachate

This study assesses the efficiency of various physico-chemical, biological and other tertiary methods for treating leachate. An evaluation study on the treatability of the leachate from methane phase bed (MPB) reactor indicated that at an optimum hydraulic retention time of 6 days, the efficiency of the reactor in terms of biological oxygen demand (BOD) and chemical oxygen demand (COD) removal was 91.29 and 82.69%, respectively. Recycling of the treated leachate through the municipal solid waste layers in the leachate recycling unit (LRU) resulted in a significant increase in the biodegradation of organics present in the leachate. Optimum BOD and COD removal efficiencies were achieved at the third recycle; additional recycling of the leachate did not produce any significant improvement. Physico-chemical treatment of the leachate demonstrated that alum and lime (Option 2) were more economical than coagulants lime and MgCO₃. A cost analysis of the economics of the various treatments revealed that the alternative treatment consisting of a MPB bed followed by a LRU and aerated lagoon is the most cost-effective treatment. However, the alternative consisting of a MPB followed by the LRU and a soil column, which is slightly more costly, would be the most appropriate treatment when adequate land is readily available.     

Assessing field-scale migration of radionuclides at the Nevada Test Site: “mobile” species

Many long-lived radionuclides are present in groundwater at the Nevada Test Site (NTS) as a result of 828 underground nuclear weapons tests conducted between 1951 and 1992. In conjunction with a comprehensive geochemical review of radionuclides (³H, ¹⁴C, ³⁶Cl, ⁹⁹Tc and ¹²⁹I) that are presumably mobile in the subsurface, we synthesized a body of radionuclide activity data measured from groundwater samples collected at 18 monitoring wells, to qualitatively assess their migration at the NTS over distances of hundreds of meters and over timescales of decades. Tritium and ³⁶Cl showed little evidence of retardation, while the transport of ¹⁴C may have been retarded by its isotopic exchange with carbonate minerals in the aquifer. Observed local reducing conditions (either natural or test-induced) will impact the mobility of certain redox-sensitive radionuclides (especially ⁹⁹Tc) that were otherwise soluble and readily transported under oxidizing conditions. Conversely, strongly oxidizing conditions may impact the mobility of ¹²⁹I which is mobile under reducing conditions. The effect of iodine speciation on its transport deserves further attention. Indication of delayed transport of some “mobile” radionuclides (especially ⁹⁹Tc) in the groundwater at the NTS suggested the importance of redox conditions of the natural system in controlling the fate and transport of radionuclides, which has implications in the enhanced performance of the potential Yucca Mountain repository, located adjacent to the NTS, to store high-level nuclear wastes as well as management of radionuclide contamination in legacy nuclear operations facilities.