集成式多球中子谱仪球球干扰影响

模拟计算了集成式多球中子谱仪7路测量通道同时工作与每路测量通道独立测量时的能量响应函数。两种测量模式的能响比值结果显示,球球干扰的影响随着慢化球尺寸增大而减小;对小尺寸慢化球球球干扰随着中子能量增大而增大。     

多球谱仪测量BNCT医院中子照射器中子束能谱

用于硼中子俘获治疗（BNCT）的医院中子照射器（IHNI-Ⅰ）已由北京凯佰特技术有限公司建设完成,为获得空气中自由中子束的能谱,建立了一套改进的主动式多球谱仪,并开展了相关实验方法研究。该谱仪包含14个探测单元,中心探测器为球形³He正比计数器。为改善谱仪在超热能区的分辨率,在常规多球谱仪的基础上增加了4个包裹不同厚度硼壳的探测单元。通过MCNP程序计算谱仪的响应函数,并利用标准²⁵²Cf和²⁴¹Am-Be中子源进行了校准和验证。测量在距离照射器孔道口110 cm处进行,再采用反迭代方法将能谱修正到孔道口处,结果显示,测量的中子能谱与理论模拟结果略有差异。因而利用ROSPEC谱仪和金箔对中子能谱和PMMA体模内中子通量密度的深度曲线进行了测量,结果验证了多球谱仪测量结果的可靠性。     

闪烁法测量伴随~3He粒子的中子飞行时间谱仪

在D(d,n)~3He反应中,目前常采用Si(Au)面垒型半导体探测器测量伴随粒子。半导体探测器的能量分辨率高,是这种方法的优点,但由于~3He粒子能量低,电荷灵敏前置放大器所给出的~3He信号幅度小,容易受到噪声以及干扰信号的影响,因而谱仪的时间分辨性能不容易做得很好。比如Ohio大学的中子飞行时间谱仪,出射~3He粒子的能量为650     

基于扩展型多球中子谱仪的中子能谱测量

为了有效地测量加速器辐射场的中子能谱,论文通过FLUKA模拟的辐射场中子能谱和探测器能量响应选择出合适的扩展型多球中子谱仪、利用基于少道解谱理论的解谱程序来得到实验能谱以及积分注量统计。并通过计算与实验计数率的对比证明了该方法测量中子能谱的可行性,同时分析了实验的不足并给出了改进的建议。     

MC法模拟单球中子谱仪响应函数及其能谱解析

利用MCNP5模拟分析了不同直径下基于锂玻璃闪烁体的单球中子谱仪的响应函数,能量范围从热能至20 MeV;模拟了实验室²⁴¹ Am-Be中子源辐射场、载荷舱内空间辐射场内单球中子谱仪的响应函数;采用UMG少道解谱程序进行了解谱计算。结果显示,入射中子能量低于20 MeV时,直径为30 cm的单球中子谱仪通过UMG解谱可得到较好的中子能谱解谱结果;载荷舱辐射环境下,含氢量大的舱壁材料对接近单球表面探测器的热中子能区的响应函数影响最大,对其影响做出修正后可得到一个较好的解谱结果。     

利用BF_3多柱谱仪测量临界装置中子能谱

研发了一种中子能谱测量装置——BF_3多柱谱仪。对BF_3多柱谱仪的工作原理、结构与性能,以及该探测系统的使用方法进行研究,并分析其可满足的实验要求。应用BF_3多柱谱仪在临界装置上进行了中子能谱测量的实验,将实验测量结果与MCNP程序的理论计算结果进行了比较,两者符合较好,验证了该中子探测系统的性能。该BF_3多柱谱仪可适用于低中子通量密度能谱测量、屏蔽实验、环境监督测量、实验大厅内部及周围环境中子场测量等多种工况。     

Bonner球谱仪对Pu-Be源中子能谱的测量

Bonner球谱仪是开展中子能谱测量的重要仪器,本文利用自行研制的Bonner球谱仪对已知源强的Pu-Be中子源进行能谱测量,以验证谱仪测量方法和中子能谱解谱方法的准确性。首先制作出由8个球组成的Bonner球谱仪,再根据谱仪的测量读数,采用最大熵法获得中子能谱信息,与国际原子能机构公布的数据基本符合,进一步计算得到所测Pu-Be中子源的中子周围剂量当量转换系数为0.37nSv.cm2,与目前已经公布的数值0.36nSv.cm2基本一致,表明求解出的能谱测量数据基本符合物理事实,测量所使用的Bonner谱仪和解谱方法的准确可靠性。     

~3He半导体夹心谱仪解谱方法理论探讨

通过介绍~3He半导体夹心谱仪探测器结构、工作原理及电子学系统组成,给出谱仪测量信号的两大来源反应,并与多箔活化法相比较,提出基于SAND-Ⅱ算法的解谱方法;最后进行了数值校验,证实了该方法的理论可行性.     

GRNN算法多球中子谱仪解谱软件设计

为更加准确的求解中子辐照环境中的中子能谱,编写了基于GRNN算法的多球解谱程序,设计了基于MATLAB的图形用户界面,开发了通用性强、计算准确、人机交互性能好的解谱软件.模拟计算以及实验测试的结果表明,该解谱软件实现了设计的功能,并且解谱结果与标准能谱相似度很高.     

Simulation and calibration of the response function of multi-sphere neutron spectrometer

In order to realize the on-line real-time measurement of neutron specmnn of ITER fusion, this paper presents a multi-sphere spectrometer system which consists of eight thermal neutron detectors, namely SP9 3He proportional counter, embedded in eight different diameter polyethylene spheres. The response function of eight polyethylene spheres of rnulti-sphere neutron spectrometer was calculated after the simulation of the neutron transport processes in multi-sphere spectrometer by adopting software Geant4. The peak of the response function is in the low energy region for smaller diameter polyethylene sphere. As the polyethylene sphere diameter increased, the peak of the response function moves to the high energy region. The experimental calibration adopts 241Am-Be neutron source. The relative error between normalized data of experiment 47t solid angle counts and normalized data of simulated detection efficiency of 4in to 8in polyethylene sphere is from 1.152% to 12.222%.The experimental results verify the response function of the simulation. All these results provide a theoretical and experimental basis for solving the on-line real-time neutron spectrum of ITER fusion.     

3He半导体夹心中子能谱仪

介绍了3He半导体夹心谱仪的探头组件和电子学系统,开展了热中子调试,获得快中子临界装置上0.1-1.3 MeV的能谱数据.测量结果与6Li夹心谱仪在0.3-1.3 MeV范围非常符合,证明该谱仪用于测量快中子临界装置泄漏谱是可行的.     

单球中子谱仪的能量响应模拟及解谱方法研究

本文阐述了单球中子谱仪的原理,介绍了基于单慢化球和19对⁶Li-⁷Li闪烁体探测器构成的单球中子谱仪的结构及解谱方法,使用蒙特卡罗中子输运程序模拟了单球中子谱仪的中子响应函数。计算结果表明,该谱仪具有较好的空间对称性,能根据谱仪中各探测器的计数对源的大致方位进行判断;模拟了单球谱仪在²⁴¹Am-Be源照射下各探测器的计数,使用Unfolding with Maxed and Gravel (UMG)解谱程序在不同解谱算法以及初始谱的情况下对模拟数据进行解谱计算,在使用最大熵散发以及与源项相同的预置谱的情况下,解谱结果最为准确,验证了响应函数的准确性。     

Express estimate of the reliability of3He neutron counters

Translated from Atomnaya Énergiya, Vol. 66, No. 2, pp. 139–140, February, 1989.     

Ideal response function of a 3He proportional counter to thermal neutrons determined by different length counters

The gas multiplication distributions along the anode wires of ³He proportional counters with different sensitive lengths of 10, 15 and 20 cm were measured using a collimated thermal neutron beam at the Kyoto University Reactor facility. The ideal response function excluding the effect of electric field distortion near the boundaries of the anode wire was derived by taking into account the difference between pulse height spectra measured by two different length counters. The pulse height spectrum calculated by the NRESPG Monte Carlo code assuming the ideal gas multiplication region showed relatively good agreement with the response function derived from the measurements. Both the energy resolution of the full energy peak at 764 keV and the peak ratio to the entire pulse height spectrum were improved markedly.     

基于球谱仪的中子剂量率仪设计

研制了一套基于球谱仪的中子剂量率仪。采用单个慢化球及位置灵敏计数器的探测结构,通过单次测量即可计算出中子剂量等信息。在基于电荷分配法的读出电路中,通过对电荷灵敏放大器及滤波成型电路的参数进行优化,使探测器系统的平均位置分辨达到6 mm。利用硬件寻峰等数字信号处理技术,使数据获取系统的最高计数率达到200 k·s-1,满足剂量率仪实时性的要求。     

Verification of a fusion neutron diagnostic Bonner sphere spectrometer on measurement of a ~(241)Am–Be neutron source

A Bonner sphere spectrometer(BSS) was developed for neutron diagnostic on HL_2A Tokamak.It contains eight polyethylene spheres embedded with SP9~3 He proportional counter.Before setting up on the Tokamak experimental hall,a verification experiment was arranged on a~(241)Am–Be neutron source to test its spectrometry capability.The neutron response functions were calculated by Monte Carlo code Geant4 to simulate the real measurement environments.By least square method,the neutron spectrum was finally unfolded on log domain from0.1 e V to 11 Me V.It has a remarkable consistency to the ISO 8529-1 standard~(241)Am–Be neutron spectrum.This shows that the BSS is effective and reliable for neutron spectrum determination.     

多探测器快中子飞行时间谱仪

描述了一台串列加速器HI-13上的多探测器快中子飞行时间谱仪,并与国际上同类谱仪进行了比较。本谱仪主要用于能量大于8 MeV的快中子散射实验、次级中子双微分截面及带电粒子引起的出射中子能谱的测量。简要介绍了谱仪各主要部分(包括零信号拾取筒、氘气体靶、探测器、电子学等)的结构和特性及其在快中子实验中的应用。     

Portable spectroscopic fast neutron probe and 3He detector dead-time measurements

This paper presents dead-time calculations for the Portable Spectroscopic Fast Neutron Probe (N-Probe) using a combination of the attenuation law, MCNP (Monte Carlo N-particle Code) simulations and the assumption of ideal paralyzing and non-paralyzing dead-time models. The N-Probe contains an NE-213 liquid scintillator detector and a spherical ³He detector. For the fast neutron probe, non-paralyzing dead-time values were higher than paralyzing dead-time values, as expected. Paralyzing dead-time was calculated to be 37.6 μs and non-paralyzing dead-time was calculated to be 43.7 μs for the N-Probe liquid scintillator detector. Dead-time value for Canberra ³He neutron detector (0.5NH1/1K) was also estimated using a combination of subcritical assembly measurements and MCNP simulations. The paralyzing dead-time was estimated to be 14.5 μs, and the non-paralyzing dead-time was estimated to be 16.4 μs for ³He gas filled detector. These results are consistent with the dead-time values reported for helium detectors.