氧化镁中子过滤器研究

核电厂反应堆乏燃料水池格架材料在生产和使用过程中需要对其中子吸收性能进行监测和检测,针对这两方面需求,研制了乏燃料水池格架B₄C＿Al材料的中子吸收性能检测设备。为了降低检测过程中超热中子本底的影响,考虑采用氧化镁超热中子过滤器滤除超热中子。对10和5 cm氧化镁单晶的中子透射率与宏观总截面进行了理论计算,对慢化体表面中子成分进行蒙特卡罗模拟计算并开展实验测量。实验结果表明,10 cm氧化镁对采用8 cm聚乙烯慢化后的²⁵²Cf中子源的中子透射率为60.16%,相对镉比值比未加10 cm氧化镁时提高了93.85%,证明常温下采用氧化镁单晶做B₄C＿Al检测装置的超热中子过滤器是可行的。     

（n,xnγ）反应截面测量的实验本底改进研究

瞬发γ射线法测量（n,xnγ）反应截面实验中,在线的实验本底对测量结果影响显著,是影响测量结果的关键因素。为了达到降低在线实验本底一个量级的目标,通过蒙特卡罗模拟程序给出了屏蔽体和准直器的改进方案,最终选取的屏蔽方案:在原有屏蔽体上加厚30 cm（C₂H₄）n+9 cmPb,原屏蔽墙加厚54 cm重混凝土,再在屏蔽体和屏蔽墙上共同加厚2 cm厚的铅（Pb）;准直孔开孔形状在圆柱形、圆锥形和对称双锥形这三种方案中准直效果和能量单一性方面对称双锥形准直孔最好。在屏蔽体改造完成后,利用尺寸为φ5.08cm×5.08 cm型液体闪烁体探测器（BC501）测量了改造后距准直孔右方径向距离70 cm处透射出来的中子和γ射线的相对强度,在扣除无束流天然本底后,有束流的中子本底降低了7.75倍,γ本底降低了38.5倍,改造效果达到了测量要求。In the experiment of measuring (n,xnγ) reaction cross section with prompt γ ray method, the experiment background has a significant influence on the result and is the key factor. In order to achieve the goal of reducing a certain amount of the experiment background, the improvement scheme of shield and collimator was given through Monte Carlo method and the shielding scheme was finally selected: add 30 cm(C₂H₄)n+9 cm Pb on the original shield, 54 cm heavy concrete on the original shield wall and then 2 cm thick lead(Pb) on the shield and shield wall. The collimation effect and energy uniformity of symmetrical double cone collimation hole are the best among cylindrical, conical, and symmetrical double cone. After the completion of the transformation of shield, the relative intensities of the transmitted neutron and γ rays from the 70 cm in right radial of the transformed collimation hole were measured with ?5.08 cm×5.08 cm type liquid scintillator detector(BC501). After deducting the natural background of no beam current, the neutron background of the beam current is reduced by 7.75 times and the γ background is reduced by 38.5 times, which meets the requirement.     

小波分析及神经网络方法在核物理及核工程中的应用

介绍了小波分析和神经网络方法在核物理及核工程领域的应用现状。 分别对小波分析及神经网络方法的基本原理进行了介绍, 详细讨论了小波变换中的多分辨分析方法在γ能谱平滑以及核电站设备监测等方面的应用, 讨论了连续小波变换在γ能谱分析、 粒子种类鉴别以及核反应堆安全监测等领域的应用。 同时, 还详细介绍了神经网络方法在以上各领域的发展现状。 最后, 展望了两种方法在核安全检测、 核辐射防护以及核电站实时监控等领域的发展趋势。 Applications of wavelet analysis and neutral networks in the field of nuclear physics and engineering are reviewed. The principle of these two methods are introduced briefly, and then the applications of multiresolution analysis technique in the smoothing of γ ray spectroscopy, and in nuclear power plant monitoring are discussed in detail. Applications of the continuous wavelet analysis method in γ ray spectroscopy analysis, in particle identification , and in nuclear reactor safety monitoring are also talked over. In addition, the applications of neutral networks in above fields are introduced. Finally, the trends of the future development for these two methods are prospected.     

B4C_Al材料中子吸收性能检测技术研究

核电厂反应堆乏燃料水池的安全性是核电厂十分重要的安全性问题。其中,中子吸收材料的性能关系到乏燃料水池的安全性。在乏燃料水池中放入同种中子吸收材料的挂片,通过定期检查挂片的性能可以对乏燃料水池中子吸收材料的可靠性进行评估。我们开展的B₄C Al合金挂片检测设备的研制工作,有望在评估核电厂反应堆乏燃料水池的安全性方面发挥重要作用。该套检测设备首先通过采用面密度已知的标准板制定标准曲线,再以此为标准,根据中子透射率检测挂片的面密度,从而反映出乏燃料水池贮存格架材料的中子吸收能力,为反应堆乏燃料水池的安全性检测提供了技术手段。该设备是国内首台硼铝合金挂片检测设备,该设备的研制为以后开展国产含硼中子吸收材料的无损检测研究奠定了实验基础。     

B4C_Al材料中子吸收性能检测设备研制

当前基于燃耗信任制的乏燃料密集贮存方式,对乏燃料水池格架中子吸收材料的可靠性和有效性,都提出了更高的要求。在格架材料生产和使用过程中需要对其中子吸收性能(硼含量)进行无损检测和监测,针对这两个方面的需求,我们研制了核电厂乏燃料水池格架B₄C_Al中子吸收材料检测设备。该检测设备主要由中子源(3枚252Cf放射源)、中子探测器(10个锂玻璃组成的探测阵列)、中子屏蔽准直和慢化系统等组成,通过测量中子透射率来推算待测样板上各个测量点的10B面密度,从而达到对于乏燃料水池贮存格架材料B₄C_Al合金硼含量的无损检测。使用该套设备进行了两种B₄C_Al合金20 cm×30 cm悬挂样片的检测,结果可靠。该B₄C_Al材料中子吸收性能检测设备为国内首创,推动了我国含硼中子吸收材料的无损检测研究,能为核电厂乏燃料水池的临界安全监测提供有力保障。     

NaI探测器对23.8 MeVγ射线的效率刻度方法

低能D(d,γ)4He辐射俘获反应截面的研究在聚变领域和天体物理等领域中起到非常重要的作用。由于受到标准γ源能量的制约,在研究D(d,γ)4He反应高能γ射线产额实验过程中不能用标准源进行效率刻度。采用实验测量与计算相结合的方法实现NaI探测器对23.8 MeV γ射线的效率刻度,先对6.13MeVγ射线效率进行实验刻度,然后用蒙卡程序MCNP－4C模拟计算出NaI探测器的效率曲线,再用实验数据与模拟结果进行对比校正,计算出NaI探测器在23.8MeV能量点对γ射线的探测效率。该方法对高能γ射线效率刻度给出了一种参考依据。In the study of D(d,γ)4He radiative capture reactions research, which is very important for fusion and astrophysics, the efficiency calibration of the detector is necessary. Due to the restriction on energy of the standard gamma source, the efficiency calibration of high-energy gamma-rays can not be calibrated by a standard source. In this paper, the method combining the experimental measurements and calculations for the efficiency calibrations of high energy gamma rays is given in the experiment of 6.13MeV gamma rays efficiency calibration using NaI detector, the efficiency curve of which is calculated by MCNP-4C and corrected experimentally. In this case, the detection efficiency of 23.8MeV gamma ray is known. The method provides a reference to high energy gamma ray efficiency calibration.