分压电流对7.62 cm光电倍增管性能的影响

7.62 cm(3英寸)光电倍增管(Photomultiplier Tube,PMT)是江门中微子实验(Jiangmen Underground Neutrino Observatory,JUNO)巨型探测器的重要组成部分,以此构成的一套独立探测系统,承担着独立物理测量、与50.8 cm(20英寸)PMT探测系统相互检验等重要任务。为提高探测系统的可靠性,使每个7.62 cm PMT供电高压的单通道电流不超过10?A,研究了不同高压电流对7.62 cm PMT探测性能的影响。采用三种高压电流的分压器,对海南展创生产的型号为XP72B20(样管编号为70069)的7.62 cm PMT的性能进行实验测试,包括增益、能量分辨率、峰谷比和阳极输出信号的非线性。结果表明:不同分压电流对7.62 cm PMT性能的影响较小。这个结果为该7.62 cm PMT在JUNO探测器中使用小分压电流的方案提供了重要的实验依据。     

EAST在不同加热模式下的辐射响应研究

利用EAST(Experimental Advanced Superconducting Tokamak)上的在线辐射剂量监测系统,对氘氘等离子体实验期间各种加热模式下装置主机厅内中子、γ剂量进行测量。对比分析了欧姆加热、低杂波加热、中性束注入加热,以及中性束与射频波协同加热实验时的中子、γ辐射强度随时间演化的规律。结果显示:在纯欧姆加热模式,辐射剂量主要来源于逃逸电子轫致辐射产生的高能γ(X)射线和光中子;低杂波辅助加热时,通常会出现环电压下降的现象,离子温度和聚变反应率提高有限,而逃逸电子产生的韧致辐射却被有效抑制,使得总体辐射剂量水平反而低于纯欧姆加热模式;中性束注入加热时,束靶反应使得中子产额提高2～3个数量级,聚变中子以及中子与周围物质核反应产生的γ射线成为辐射剂量的主要来源。通过统计归纳得到在中性束注入加热时,中子周围剂量当量与γ周围剂量当量存在近似的线性关系。该线性关系对于中性束与各种射频波协同加热实验时,中子、γ射线来源于多种途径的情形并不完全适用。     

Application of local Monte Carlo method in neutronics calculation of EAST radial neutron camera

The Local Monte Carlo (LMC) method is used to solve the problems of deep penetration and long time in the neutronics calculation of the radial neutron camera (RNC) diagnostic system on the experimental advanced superconducting tokamak (EAST), and the radiation distribution of the RNC and the neutron flux at the detector positions of each channel are obtained. Compared with the results calculated by the global variance reduction method, it is shown that the LMC calculation is reliable within the reasonable error range. The calculation process of LMC is analyzed in detail, and the transport process of radiation particles is simulated in two steps. In the first step, an integrated neutronics model considering the complex window environment and a neutron source model based on EAST plasma shape are used to support the calculation. The particle information on the equivalent surface is analyzed to evaluate the rationality of settings of equivalent surface source and boundary. Based on the characteristic that only a local geometric model is needed in the second step, it is shown that the LMC is an advantageous calculation method for the nuclear shielding design of tokamak diagnostic systems.