Dehydration Behavior of Aluminum Sulfate Hydrates

An exothermic transition is observed near 400°CC on thermal dehydration of highly crystalline AI₂(SO₄)3.16H₂O, Al₂(S0₄)₃ 14H₂O, and Al₂(S0₄)₃ 9H₂O when the early stages of heating are carried out in vacuum. Amorphous or partially crystalline hydrates do not show the exotherm. No systematic relation is apparent between the decomposition behavior and the pore volume distribution of the various anhydrous A1₂(SO₄)₃ products.     

急性放射损伤小鼠血清蛋白质组分析

为寻找急性放射病早期诊断指标和新的治疗靶点，探讨辐射损伤的发病机理，采用蛋白质组学的双向电泳和蛋白质氨基酸序列分析技术研究了8Gy γ射线照射后24h小鼠血清蛋白质的变化，鉴定有差异的蛋白质，并用蛋白质印迹(Western blotting)方法进行验证。结果显示，双向电泳发现8Gy照射后24h小鼠血清有一显著变化蛋白点，分子量约为15ku，经氨基酸序列分析发现为结合珠蛋白(Haptoglobin，Hp)的α亚单位。Western blotting方法进一步验证了双向电泳的结果。结果表明，经8Gy γ射线照射后24h小鼠血清中结合珠蛋白发生显著增加，可能在辐射损伤中发挥着一定的作用，此结果为探索急性放射损伤的发病机理提供了新的线索。     

用时域连续有限冲激响应滤波器进行过零测频的方法

根据时域连续有限冲激响应滤波器的原理设计了短窗窄带带通连续滤波器。该滤波器通过处理输入离散采样信号获得连续信号并抑制谐波噪声,改进了过零测频方法。对含有40%低频和高频谐波的500 kV线路的故障电压进行仿真,试验结果表明当采样数据的窗长为4个工频周期时,该方法的测频误差小于0.05 Hz,且延时仅为2个工频周期,其抗谐波、抗噪声和动态响应特性优于傅氏测频法,能够满足电子式互感器应用环境下实时测频的要求。     

一种新的基于复指数函数映射的盲均衡算法

定义了一个新的复指数函数将典型的16-QAM非常模信号的实部和虚部分别映射至单位圆上.然后利用映射后星座坐标的实部和虚部之间的关系建立代价函数,从而提出了一种新的盲均衡算法.新算法克服了著名的恒模盲均衡算法及其典型的改进算法在对非常模信号均衡时稳态误差大的缺点.通过理论证明验证了新算法在无噪声环境下稳态均方误差为0;通过仿真实验验证了新算法在有噪环境下比恒模及其改进算法具有更低的稳态均方误差.     

ECRH Launcher for Four-Beam Injection on HL-2A Tokamak

An Electron Cyclotron Resonance Heating (ECRH) launcher for four-beam injection has been installed on the HL-2A tokamak and used in plasma heating experiments. By the launcher, four EC wave beams can be injected into the tokamak through a φ350 mm port, which are generated from 2 sets of 68 GHz/1 s and 2 sets of 68 GHz/1.5 s gyrotron tubes manufactured by GYCOM, with maximum output power of 500 kW for each. In this paper, the properties of the EC beam in the launcher and plasma are presented: at the centre of the cross section of the tokamak, the beam radius is 31.7 mm; thermal analysis of a 3D model indicates that the peak temperature increase would be only 30 o C at the mirror surface for a 500 kW/1 s pulse; ray-tracing calculation predicts satisfactory power deposition. In the plasma experiment, six beams including four beams from this launcher and two from another launcher have been injected simultaneously. Besides, obtaining ELM-y H-mode discharges, the ECRH system shows reliability and stability of the launcher functions.     

中国实验快堆核反应率分布测量试验研究

核反应率相对分布是中国实验快堆(CEFR)的重要参数,也是获取运行许可证的必要试验数据之一。利用专用试验组件,在CEFR首炉堆芯内特定的径向或轴向位置装入同种材料的探测箔片,经辐照后测量各箔片的感生放射性活度,计算其单核反应率,经归一化计算后得到CEFR堆芯的反应率相对分布曲线,此分布曲线与理论计算值比较,结果符合较好。     

Experimental Studies on the Self-Shielding Effect in Fissile Fuel Breeding Measurement in Thorium Oxide Pellets Irradiated with 14 MeV Neutrons

The 14 MeV neutrons produced in the D-T fusion reactions have the potential of breeding Uranium-233 fissile fuel from fertile material Thorium-232. In order to estimate the amount of U-233 produced, experiments are carried out by irradiating thorium dioxide pellets with neutrons produced from a 14 MeV neutron generator. The objective of the present work is to measure the reaction rates of 232 Th + 1 n → 233 Th → 233 Pa → 233 U in different pellet thicknesses to study the self-shielding effects and adopt a procedure for correction. An appropriate assembly consisting of high-density polyethylene is designed and fabricated to slow down the high-energy neutrons, in which Thorium pellets are irradiated. The amount of fissile fuel ( 233 U) produced is estimated by measuring the 312 keV gammas emitted by Protactinium-233 (half-life of 27 days). A calibrated High Purity Germanium (HPGe) detector is used to measure the gamma ray spectrum. The amount of 233 U produced by Th 232 (n, γ) is calculated using MCNP code. The self-shielding effect is evaluated by calculating the reaction rates for different foil thickness. MCNP calculation results are compared with the experimental values and appropriate correction factors are estimated for self-shielding of neutrons and absorption of gamma rays.     

模糊鲁棒控制方法在核反应堆功率控制中的应用

为了对核反应堆功率进行实时控制,以适应电网负荷的变化需求,基于T-S模糊模型设计了核反应堆功率模糊鲁棒控制器。首先使用状态反馈设计了局部控制器,然后应用并行补偿方法设计全局控制器。线性矩阵不等式的求解证明所设计的控制器是稳定的。仿真结果表明,对于3种典型工况变化,所设计的控制器对反应堆的功率变化能进行很好的控制。     

Instrumental neutron activation analysis of beachrock samples of South East Coast of Tamilnadu, India

Element profiles of some beach rock samples collected from South East Coast of Tamilnadu, India have been determined using single comparator method of INAA. The geo-chemical behavior of the elements in the region is discussed. The irradiations were done at thermal neutron flux of ~ 1011 cm-2·s-1 at 20kW power using Kalpakkam Mini Reactor (KAMINI), IGCAR, Kalpakkam, Tamilnadu, India. Around 19 elements have been determined from 15 samples by high-resolution gamma spectrometry. The accuracy and precision were evaluated by assaying the irradiated Standard Reference Material (SRM 1646a Estuarine sediment) and were found to be in good agreement with certified values.     

基于储能装置的柔性直流输电技术提高大规模风电系统稳定运行能力的研究

大规模风电集中接入电网对直流输电技术提出了更高的要求。为此,提出了基于储能装置的柔性直流输电并网传输系统拓扑结构。根据dq同步旋转坐标系下VSC-HVDC(Voltage Source Converter HVDC)系统的数学模型,设计了相应的换流器直接电流控制策略。其中送端换流站解耦控制器实现了风电场输出有功功率和无功功率的独立控制,受端换流站采用将储能装置充放电功率偏差值作为直流电压控制器附加信号的控制策略。最后,以配备双馈风电机组的风电场经柔性直流输电系统接入电网进行仿真分析,针对风电场在噪声风引起的输电功率波动、受端换流站侧交流系统短路故障等情况进行仿真验证,结果表明该控制方案有效可行。