兰州某垃圾填埋场场地岩土工程条件评价及防渗处理方案建议

通过对垃圾填埋场场地岩土工程条件的分析,对垃圾填埋场拟采用的防渗方案进行了比选,提出了粘土铺盖加HDPE（高密度聚乙稀）防渗膜的综合防渗方案,对同类工程防渗设计具有参考意义。     

Role of mass transfer in overall substrate removal rate in a sequential aerobic sludge blanket reactor treating a non-inhibitory substrate

A laboratory study was undertaken to explore the role of mass transfer in overall substrate removal rate and the subsequent kinetic behavior in a glucose-fed sequential aerobic sludge blanket (SASB) reactor. At the organic loading rates (OLRs) of 2-8 kg chemical oxygen demand (COD)/m³-d, the SASB reactor removed over 98% of COD from wastewater. With an increase in OLR, the average granule diameter (d_p = 1.1-1.9 mm) and the specific oxygen utilization rate increased; whereas biomass density of granules and solids retention time decreased (13-32 d). The intrinsic and apparent kinetic parameters were evaluated using break-up and intact granules, respectively. The calculated COD removal efficiencies using the kinetic model (incorporating intrinsic kinetics) and empirical model (incorporating apparent kinetics) agreed well with the experimental results, implying that both models can properly describe the overall substrate removal rate in the SASB reactor. By applying the validated kinetic model, the calculated mass transfer parameter values and the simulated substrate concentration profiles in the granule showed that the overall substrate removal rate is intra-granular diffusion controlled. By varying different d_p within a range of 0.1-3.5 mm, the simulated COD removal efficiencies disclosed that the optimal granular size could be no greater than 2.5 mm.     

余割平方波束雷达支援干扰的建模与效能分析

建立了支援干扰模型,给出了现代雷达压制系数计算方法,并针对余割平方波束,分别在方位平面和俯仰平面构建了方向图模型。然后,分析了支援干扰对余割平方波束雷达的干扰效能,提取了干扰扇面作为干扰效能评估的核心指标,并建立了计算模型,定量研究了干扰扇面与掩护距离、干扰距离、飞行高度等效能指标间的内在关系。最后,得出了影响支援干扰作战效能的定性结论。     

土坝粘土铺盖裂缝淤填过程中渗透系数的变化规律

针对水库粘土铺盖渗漏问题，在“土坝粘土铺盖裂缝淤填自愈”模型试验的基础上，对裂缝淤填过程中渗透系数的变化规律进行分析，进一步说明“淤填自愈”的先进性与可行性。     

Aspirating vs. nonaspirating nozzles for making fire fighting foams — Evaluation of a nonaspirating nozzle

The use of nonaspirating nozzles for effective application of aqueous film-forming foam is almost a controversial topic. Fire tests on gasoline compared several commercial nozzles (aspirating and nonaspirating), revealing significant difference in the extinguishment of large fires. A new variable stream nonaspirating nozzle was tested, and by comparison found to be marginally acceptable. Consequences of choosing the wrong equipment for use with various foams and their use on a variety of flammable liquids are discussed. Mobil Research and Development Corporation Reference: L. R. DiMaio, R. F. Lange, and F. J. Cone, “Aspirating vs. Nonaspirating Nozzles for Making Fire Fighting Foams — Evaluation of a Nonaspirating Nozzle,” Fire Technology, Vol. 20, No. 1, February 1984, p. 5.     

The TFTR Lithium Blanket Module program

The Lithium Blanket Module (LBM) is an approximately 80×80×80 cm cubic module, representative of a helium-cooled lithium oxide fusion reactor blanket module, that will be installed on the TFTR (Tokamak Fusion Test Reactor) in late 1986. The principal objective of the LBM Program is to perform a series of neutron transport and tritium-breeding measurements throughout the LBM when it is exposed to the TFTR toroidal fusion neutron source, and to compare these data with the predictions of Monte Carlo (MCNP) neutronics codes. The LBM consists of 920 2.5-cm diameter breeder rods constructed of lithium oxide (Li₂O) pellets housed in thin-walled stainless steel tubes. Procedures for mass-producing 25,000 Li₂O pellets with satisfactory reproducibility were developed using purified Li₂O powder, and fabrication of all the breeder rods was completed in early 1985. Tritium assay methods were investigated experimentally using both small lithium metal samples and LBM-type pellets. This work demonstrated that the thermal extraction method will be satisfactory for accurate evaluation of the minute concentrations of tritium expected in the LBM pellets (0.1–1 nCi/g).     

Treatment of coking wastewater by a UBF‐BAF combined process

BACKGROUND: Coking wastewater is a major pollutant, produced in large quantities in many countries worldwide. This study investigates the performance of a combined system for treating coking wastewater. The system is based on an upflow blanket filter (UBF) with a biological aerated filter (BAF). Efficiency is assessed according to organic pollutants and nitrogen removal. RESULTS: It was found that hydraulic retention time (HRT) had a greater influence on the removal efficiency of NH₃‐N than chemical oxygen demand (COD). The BAF facilitated simultaneous carbonaceous removal and nitrification, depending on the reactor height. The system removed 81.5% of COD and 96.4% of NH₃‐N when the total HRT was 46.7 h (15.4 h for UBF and 31.3 h for BAF). Gas chromatography/mass spectrometry analysis indicated that the main components of the coking wastewater were phenols and nitrogenous heterocyclic compounds. Certain refractory compounds decomposed in the anaerobic section, resulting in the production of intermediates. Although most organics present in the influent were absent from the final effluent, a few residual contaminants could not be fully eliminated by the system. CONCLUSION: The experimental results show that the present system is feasible for the treatment of coking wastewater. Copyright © 2007 Society of Chemical Industry     

Characterization of the effects of continuous salt processing on the performance of molten salt fusion breeder blankets

Several continuous salt processing options are available for use in molten salt fusion breeder blanket designs: fluorination only, fluorination plus reductive extraction, and fluorination, plus reductive extraction, plus metal transfer. The effects of processing on blanket performance have been assessed for these three levels of processing and various equilibrium uranium concentrations in the salt. A one-dimensional model of the blanket was used in the neutronics analysis, which incorporated transport calculations with time-dependent isotope generation and depletion calculations. The method of salt processing was found to have little affect on the level of radioactivity, toxicity, or the thermal behavior of the salt during operation of the reactor. The processing rates necessary to maintain the desired uranium concentrations in the suppressed-fission environment were quite low, which permitted only long-lived species to be removed from the salt. The effects of the processing therefore became apparent only after the radioactivity due to the short-lived species diminished. The effects of the additional processing (reductive extraction and metal transfer) could be seen after approximately 1 year of decay, but were not significant at times closer to shutdown. The reduced radioactivity and corresponding heat deposition were thus of no consequence in accident or maintenance situations. Net fissile production in the Be/MS blanket concept at a fusion power level of 3000 MW at 70% capacity ranged from 5100 kg/year to 5170 kg/year for uranium concentrations of 0.11% and 1.0%²³³U in thorium, respectively, with fluorination-only processing. The addition of processing by reductive extraction resulted in 5125 kg/year for the 0.11%²³³U case and 5225 kg/year for the 1.0%²³³U case.     

Nuclear analysis of a laser fusion reactor,SENRI-I

A neutronic analysis of the laser-driven inertial-confinement fusion reactor SENRI-I is presented. Three-dimensional Monte Carlo calculations were performed to examine the effects of laser beam ports on the flux distribution, tritium breeding ratio, thermal energy deposition in the blanket, and radiation streaming. A Monte Carlo code was also used for the time-dependent radiation-damage analysis accounting for the time of the flight spread of neutrons and the results are compared to the analysis for the HIBALL design. Induced radioactivity was estimated, based on the one-dimensional transport calculation and depletion analysis. The calculated results reveal the advantages of the SENRI-I design with a thick Li layer compared to other reactor systems employing a dry-wall scheme.     

Neutronics optimization study for D-D fusion reactor blanket/shield

Position-dependent optimization calculations have been carried out on a D-D fusion reactor blanket/shield to maximize the energy gain in the blanket and to minimize the atomic displacement rate of the copper stabilizer in the superconducting magnet. The results obtained by using the optimization code SWAN indicate (1) the advantage of D₂O coolant over H₂O coolant with respect to increasing the energy gain, and (2) the difference in the optimal shield distributions between D-T and D-D neutron sources. The possibility of improving both the energy gain and radiation shielding characteristics is also discussed.