国产Am-Be中子源4.438MeVγ射线与中子强度比值测量

本工作涉及准确测量国产Am-Be中子源发射的4.438MeVγ射线与中子强度比值R＝S_γ/S_n的实验方法。中子源的中子发射率用锰浴法进行比对测量。用Φ75mm×75mmNaI（Tl）探测器测量中子源的γ能谱;用MCNP程序模拟计算中子引起的γ本底和探头的源峰探测效率。实验与理论计算得到的R值符合得很好。综合评价已发表的R实验值,给出了R推荐值为0.575（1±4.8%）。结果表明,R值可认为是Am-Be源的一标志性特征量。     

混合压片型241AmO2-Be中子源物理特性研究

Am-Be中子源是应用广泛的同位素中子源,国际上为其建立了ISO 8529-1推荐标准。为检验该标准的普适性和各种应用的需求,本文以德国PTB实验室ISO源和北京大学核物理与核技术国家重点实验室的国产同类源为例,对源中子从产生到出射的物理过程进行蒙特卡罗模拟和理论计算。综合评述了源的制作和结构差异等因素对源中子能谱、平均能量、1.5 MeV以下中子的份额、源强、源发射4.438 MeVγ射线与中子的强度比和出射中子的各向异性等源自身物理特性的细致影响。     

ST-401图像转换屏γ射线-中子相对灵敏度测量

介绍了测量图像转换屏对60Coγ射线与DT中子相对灵敏度的实验方法.在中子灵敏度测量中,用脉冲中子源测量了γ射线贡献份额,在γ射线灵敏度标定中,使用与中子实验同一实验设置,钴源与中子源交替标定.给出了不同厚度ST-401闪烁体对1.25MeVγ射线与14.85MeV中子的相对灵敏度及测量不确定度.     

BF3长计数器效率刻度及其应用

利用²³⁸U裂变反应，通过测量裂变碎块的数量，能够较为准确地测量快中子注量。但这种方法在中子能量为1.6MeV以下（裂变道未开或处于裂变截面第1个台阶上升处）和6.0～7.0MeV能区（第2个台阶上升处）由于不确定度过大而不适用。本工作采用4种不同的核反应作中子源，对北京大学4.5MV静电加速器中子实验大厅的BF₃长计数器的相对效率进行了刻度。将²³⁸U(n,f)反应与相对效率已知的BF₃长计数器相结合，解决了在上述能区准确测量中子注量的问题。      

镝活化法测量低产额脉冲中子

设计一个快中子聚乙烯慢化体，用来慢化加速器的d-T和d-D中子，利用¹⁶⁴Dy(n,γ)¹⁶⁵Dy^m在热中子区极高的反应截面，得到半衰期为75s的¹⁶⁵Dy^m，使用HPGe探测器测量¹⁶⁵Dy^m放出的γ射线。由于测得的γ射线与加速器的中子产额成一定比例，故通过这种方法可测量脉冲中子源的中子产额。     

微型中子源反应堆中子谱参数测量

以Au、Zr和Fe为活化探测器,采用裸探测器法测量中国原子能科学研究院微型中子源反应堆的中子谱参数f、α、f_F和φ_th。内辐照座的α、f和f_F分别为－0.007±0.003、20.8±0.4、5.5±0.2。该方法对φ_th的测量结果与4πβ-γ符合法的一致,相对偏差小于2%。与SLOWPOKE相比,微堆有较高的α、f_F值。与已有测量数据的比较表明,微堆中子谱在很长一个时期内是稳定的,利用微堆作为中子源的k₀法中子活化分析不需中子注量率监测器,且比较器一经照射和测量后,可用于其后较长时间内所有分析的计算标准。     

电子直线加速器驱动的光中子源装置的研制

核反应堆的安全运行、新一代反应堆设计以及核废料处理等需要精确的中子核数据。光中子源联用飞行时间谱(Time of Flight,TOF)测量是最精确的中子能量测量技术,在热中子和共振中子能区的截面测量中发挥了非常重要的作用。钍基熔盐堆(Thorium Molten Salt Reactor,TMSR)项目中15 MeV电子加速器驱动的光中子源装置(TMSR Photo-Neutron Source Phase 1,TPNS1)是专为钍-铀循环核数据测量设计和建造的,它位于中国科学院上海应用物理研究所嘉定园区内。第一阶段采用15 MeV电子直线加速器(LINAC)驱动,第二阶段拟建造电子能量约100 MeV(TPNS2)驱动的光中子源。前者建成后可提供飞行路径5 m、通量约104 n·s-1·cm-2的连续能量中子束(白光中子)及约1 MeV低能伽马射线,它们分别用于测量中子反应截面和伽马辐照研究,这是国内首台用于核数据测量的白光中子源。     

α能谱法测定241Am(n,γ)242Amg,m的反应分支比

研究建立了1种利用α能谱测定²⁴¹Am(n,γ)²⁴²Am^g,m的反应分支比K₁和K₂的方法。利用²⁴²Am^m与²⁴²Am^g半衰期差别很大的特点，分两次测量²⁴¹Am辐照样品中的²⁴²Cm含量，分别推算²⁴²Am^g与²⁴²Am^m的生成量，从而得到K₁和K₂。实际分析了某反应堆辐照的样品，测得了该反应堆中子能谱对应的K₁和K₂值。     

厚铍靶9Be(d,n)反应中子产额测量

能量在3MeV以下厚靶D-Be反应的中子产额实验数据至关重要,但较为缺乏。本工作在北京大学4.5MV静电加速器上对氘束轰击厚铍靶的中子产额进行测量。对入射氘核能量在0.35~2MeV之间的若干能量点用长中子计数管进行了0°方向中子产额、中子角分布及中子总产额的测量。与已有的测量结果和经验公式进行了比较,并拟合出氘束轰击厚铍靶中子总产额的经验公式。     

SND-S1型液体闪烁体光输出的能量响应

采用不同能量的γ射线标准源及D-D、D-T核反应的单能中子源分别测定了新型液体闪烁体SND-S1的光输出随粒子能量的变化,采用Monte-Carlo程序Penelope模拟计算了¹³⁷Csγ射线的能量分布谱,最大康普顿电子能量的计算值和实验值相差2.7%。将实验结果与文献值作了比较,能量低于3MeV时,符合较好;能量高于6MeV时,略有差别。结果表明,液体闪烁体的光输出与电子能量呈线性正比关系,而与中子能量呈非线性关系。     

Am-Be中子源辐射场周围剂量当量与吸收剂量的计算

根据最近更新的微观中子核反应截面数据（ENDF/B-Ⅶ库）计算了热中子到20MeV中子能区,H、C、N、O、Ar5种元素以及干燥空气和ICRU四元素组织的中子比释动能系数（kerma因子）。在此基础上,结合MCNP程序对Am-Be源外中子能谱的模拟,计算了Am-Be源中子场的周围剂量当量,单位中子注量下为373.0pSv•cm²。利用本实验室计算国产Am-Be源的中子能谱,算得相应中子场的周围剂量当量为374.0pSv•cm²,距离该源1m处空气对中子和γ射线的吸收剂量率分别为1.457×10^－2和1.580×10^-1μGy/(GBq•h)。     

Measurement of Gamma-Ray Production Cross Sections of Iron for Incident Neutron Energies between 6 and 33 MeV

Measurement of differential γ-ray production cross sections, i.e. (n, x γ) cross sections, of Fe was made for neutron energies from 6 to 33 MeV. Neutrons used in the experiment were white neutrons produced with (p, n) reactions by 35 MeV protons using a thick Be target. The neutron energy was analyzed by the time-of-flight method and bunched into 3 MeV wide energy bins, for each of which the spectrum of secondary γ-rays produced in an Fe sample was measured by a BGO scintillator at an angle of 144° to the neutron beam direction.

The obtained (n, xγ) cross sections agreed well with other data and the evaluated data file of ENDF/B-IV at neutron energies below 15 MeV where data were existing. The JENDL-3 file overestimated the γ-ray spectra at γ-ray energies of 3 to 7 MeV. The present work newly provided the data in the neutron energy range above 20 MeV. The GNASH calculation made by Young reproduced the measured data fairly well even at these higher energies.     

加速器中子源大厅内散射中子分布的模拟

本文针对加速器中子源可在较宽能量区间产生单能中子的特点,采用MCNP5对0.2～20 MeV的源中子在加速器中子源大厅内的散射情况进行模拟计算和分析。结果表明,直射中子通量随离源距离的增大呈平方反比衰减,散射中子通量则随离源距离的增大而几乎保持不变;大厅内的散射中子主要来自墙壁的贡献,离墙壁越近散射率越高。能量为0.4 MeV和1 MeV的源中子散射率最高,10 MeV和15 MeV的源中子散射率最低。用中子的宏观散射截面可较好解释散射率模拟结果,中子的弹性散射截面远大于非弹性散射截面,因此弹性散射起主导作用。中子能量大于1 MeV后,散射截面随中子能量增加而减小直至进入一段坪区,散射率也随之降低并进入坪区。结合待测位置处直射、散射中子通量和不同能量的散射中子份额的计算,能解释能量较高的源中子散射率较低的现象。通过在墙壁表面附上一层中子慢化吸收材料的方法可有效减弱中子散射,如5 cm的含硼聚乙烯（10%B4C）可降低散射率约40%。     

Benchmark Experiment on Vanadium with D-T Neutrons and Validation of Evaluated Nuclear Data Libraries by Analysis of the Experiment

A neutronics benchmark experiment on vanadium, which is a low activation fusion reactor material, was conducted by using the D-T neutron source facility of FNS/JAERI. Neutron spectra, dosimetry reaction rates, γ-ray spectra and γ-ray heating rates were measured in a vanadium experimental assembly. Benchmark tests for four evaluated nuclear data files were performed by analyzing the experiment. As a result, the following problems were pointed out in view of accuracy of fusion reactor designs. (1) JENDL-FF and JENDL-3.2: Total cross section should be reexamined especially at ～2keV. (2) ENDF/B-VI: Double differential cross sections for 14 MeV neutrons should be revised because of the isotropic angular distribution for continuum neutron emission. Gamma-ray production cross sections are too small and discrete γ-ray peaks are not represented clearly. (3) EFF-3: Gamma-ray production cross sections are too large.     

Method of Measuring Boron-10 Depletion in Control Blade

The neutron capture cross sections and capture γ-ray spectra of ^143,145,146Nd were measured in the neutron energy region of 10 to 90 keV and at 550 keV. A neutron time-of-flight method was adopted with a 1.5-ns pulsed neutron source by the ⁷Li(p, n)⁷Be reaction and with a large anti-Compton NaI(Tl) γ-ray spectrometer. A pulse-height weighting technique was applied to observed capture γ-ray pulse-height spectra to derive capture yields. The capture cross sections were obtained with the error of about 5% by using the standard capture cross sections of ¹⁹⁷Au. The evaluated values of JENDL-3.2 and previous measurements were compared with the present results. The capture γ-ray spectra were obtained by unfolding the observed capture γ-ray pulse-height spectra. An anomalous shoulder was observed around 2 MeV in the γ-ray spectra of ^145,146Nd, and the energy position of the shoulder was consistent with the systematics obtained in our previous work.     

0.57、1.0和1.5 MeV中子诱发235U裂变的99Mo产额绝对测量

用HPGe γ能谱法绝对测量了0.57、1.0和1.5 MeV中子诱发²³⁵U裂变产物⁹⁹Mo的产额,使用双裂变室测量了样品辐照过程中的裂变率,应用MCNP ⅣB模拟了铀样品中的中子能谱,并讨论了非主中子的各种来源对产额数据的影响。得到⁹⁹Mo在0.57、1.0和1.5 MeV的产额分别为6.61%、6.62%和6.28%。本工作与美国阿贡实验室的结果有15%以上的相对偏差,主要是由引用的衰变数据不同引起。对阿贡实验室数据进行校正后,本工作与阿贡实验室数据的相对偏差处于实验不确定度范围内。     

Evaluation of Neutron Capture Gamma-Ray Spectra in Hafnium and Tantalum

A method has been developed for evaluation of neutron capture γ-ray spectrum. It couples measured intensities of primary and secondary discrete—-ray with a γ-ray cascade model to calculate the unresolved part of the capture spectrum, and adds the discrete part and the unresolved part to obtain the whole spectrum. The cascade model uses the level density formula proposed by Gilbert & Cameron and the Brink & Axel form of El γ-ray profile function with a modification. This method was applied to thermal neutron capture spectra in six hafnium isotopes and ¹⁸¹Ta and was extended also to non-thermal capture spectra in ¹⁸¹Ta for 0.25 and 0.5 MeV neutrons with empirical assumptions. The calculated results were compared with experiments and agreement was good not only in terms of the gross structure, but also in terms of the fine structure which appears at high and low γ-ray energies.