基于2.5 MeV质子加速器BNCT装置的中子慢化材料性能模拟研究

基于加速器中子源的硼中子俘获治疗(Boron Neutron Capture Therapy, BNCT)是新一代的放射治疗方法,束流整形体(Beam Shaping Assembly, BSA)作为硼中子俘获治疗装置的重要组成部分,其作用是将中子源中的快中子束流慢化至超热中子能区(0.5 eV~10 keV),并尽可能减少快中子、热中子以及$\gamma $射线的成分,使其满足BNCT用于治疗的中子束要求。本工作基于蒙特卡罗软件包Geant4(Geometry and Tracking),以2.5 MeV,10 mA质子流强的7Li(p, n)7Be中子源为对象,研究分析了AlF₃ 、Fluental、Al₂O₃、Al作为慢化体材料时,不同的厚度对束流出口处的超热中子注量率、超热中子注量与热中子注量比值、快中子成分、$ \gamma $成分所产生的影响。计算表明,当选用厚度为25 cm的AlF₃作为慢化体材料时,经过整形慢化后的超热中子束的束流参数,均满足国际原子能机构(International Atomic Energy Agency, IAEA)的中子束流参数推荐值。     

基于加速器的多终端硼中子俘获治疗装置的束流整形组件设计

硼中子俘获治疗(Boron Neutron Capture Therapy,BNCT)是一种新型的精准放射治疗方法,束流整形组件(Beam Shaping Assembly,BSA)作为硼中子俘获治疗装置的重要组成部分,对于产生适用于BNCT的中子束至关重要.通过BSA可以将快中子慢化到适当的能量范围,并且减少其他不需...     

快中子堆n，γ混合场中γ光子注量的测量研究

用热释光探测器对快堆堆外n,γ混合场进行了区分测量，结果表明：该方法可有效的检测出n,γ混合场的γ成分；为了更较精确地测量快堆n，γ混合场γ光子注量，提出了采用新配方的热释光探测器LiFTLD(6LiF,７LiF各占50%)与6LiFTLD成对使用的方法.考虑到LiFTLD对中子吸收剂量的响应存在LET效应，对LiF(Mg,Cu,P)TLD进行了中子响应的LET效应因子RLET的实验测定(RLET≈005)，在此基础上，对６LiF 7LiFTLD的成对使用测量快中子堆的n,γ混合场中光子注量的方法进行了实验研究.实验结果表明，混合场中的中子在7LiF(Mg,Cu,P)中产生的热释光量(TL)占n,γ产生的总TL的81%—171%.实验结果表明该方法是行之有效的.为钝化中子谱的不确定性所致的影响，进一步提高γ光子注量测量结果的精度，提出了采用新配方的LiFTLD(6LiF,7LiF各占50%)与6LiFTLD成对使用测量快堆n,γ混合场γ光子注量的方法.     

活化分析方法的新进展

近几年来,活化分析方法取得了引人注目的进展。在所用活化束流源的种类、辐照和测量条件的最佳化、数据获取和分析结果可靠性的提高以及应用范围的展宽等方面,都进行了卓有成效的探索。本文将简要评述在放射化学中子活化分析(RNAA)、仪器中子活化分析(INAA)、瞬发γ中子活化分析(PGNAA)、超热中子活化分析(ENAA)、快中子活化分析(FNAA)、仪器光子活化分析(IPAA)和带电粒予沂化分析(CPAA)中的最新进展。     

用于位置灵敏型中子探测器的6LiF/ZnS（Ag）闪烁体性能研究

研究了掺杂6LiF的ZnS(Ag)闪烁体对中子、γ射线的发光特性和EJ426闪烁体样品的热中子探测效率、出射光产额和γ灵敏度。EJ426的热中子探测效率为32.4%,出射光产额为8.01×103光子/中子,70 mV阈值时的γ灵敏度小于10-7,表明EJ426是较理想的闪烁体型位置灵敏中子探测器材料。     

基于紧凑型D-D中子发生器的热中子照相慢化准直器设计

热中子照相是一种重要的无损检测技术,是X射线照相技术的重要补充,小型化热中子照相系统有重要研究应用前景。基于紧凑型D-D中子发生器,采用蒙特卡罗程序MCNP-4C,通过中子和γ射线的输运模拟,完成了热中子照相慢化准直器的模拟研究与设计。慢化准直器准直比约为3.58,模拟研究结果显示,在D-D中子发生器中子产额大于5×10⁸ n/s条件下,样品平面内热中子注量率可大于10³ n/(cm²·s),准直中子束中热中子占比可大于74%,在Φ70 mm的照射视野范围内,热中子注量的不均匀度约为7.3%,基本满足热中子照相的成像要求。     

用于BNCT-SPECT的帕维亚TRIGA MARK Ⅱ反应堆热柱优化设计北大核心CSCD

针对坐落于意大利帕维亚大学的TRIGA Mark Ⅱ反应堆热柱结构进行优化设计,从而满足面向硼中子俘获治疗(BNCT)的单光子发射计算机断层成像(SPECT)研究要求。为提高计算效率并减小统计误差,对比分析使用SSW/SSR方法与直接使用反应堆为源项时热柱内照射位置处中子能谱,其结果基本一致,从而验证了SSW/SSR方法的可靠性。为在该反应堆开展BNCT中SPECT实验,热柱中子束需准直为笔形束。对比分析四种热柱优化方案下束流口处及探测器处热中子和光子通量:40cm长石墨(射束口5cm×3cm);0.5cm厚硼包裹40cm长石墨(射束口5cm×3cm);30cm长天然锂聚乙烯(射束口直径4cm);30cm长天然锂聚乙烯(20cm长射束口直径5cm,5cm长射束口直径4cm,5cm长射束口直径2cm)。结果显示,射束口处热中子通量分别为1.05×108,2.52×107,6.08×107和5.10×107#/(cm2·s)。综合考虑中子准直效果及光子污染,方案三具有最优性能。为后续进行BNCT-SPECT理论和实验研究提供了基础,从而有效促进BNCT剂量准确评估方法的研究进程。     

用于BNCT-SPECT的帕维亚TRIGA MARK II反应堆热柱优化设计

针对坐落于意大利帕维亚大学的TRIGA Mark II反应堆热柱结构进行优化设计,从而满足面向硼中子俘获治疗(BNCT)的单光子发射计算机断层成像(SPECT)研究要求。为提高计算效率并减小统计误差,对比分析使用SSW/SSR方法与直接使用反应堆为源项时热柱内照射位置处中子能谱,其结果基本一致,从而验证了SSW/SSR方法的可靠性。为在该反应堆开展BNCT中SPECT实验,热柱中子束需准直为笔形束。对比分析四种热柱优化方案下束流口处及探测器处热中子和光子通量:40 cm长石墨(射束口5 cm3 cm);0.5 cm厚硼包裹40 cm长石墨(射束口5 cm3 cm);30 cm长天然锂聚乙烯(射束口直径4 cm);30 cm长天然锂聚乙烯(20 cm长射束口直径5 cm,5 cm长射束口直径4 cm,5 cm长射束口直径2 cm)。结果显示,射束口处热中子通量分别为1.05108,2.52107,6.08107和5.10 107 #/(cm2s)。综合考虑中子准直效果及光子污染,方案三具有最优性能。为后续进行BNCT-SPECT理论和实验研究提供了基础,从而有效促进BNCT剂量准确评估方法的研究进程。     

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。     

优质热中子束技术

优质热中子束技术是五十年代出现[1]的中子实验测量的有用技术之一,今天仍受到重视并得到引人注目的发展[2].它的特点是,在反应堆孔道外能获得γ射线本底、超热中子和快中子本底都很低的较强热中子束(简称优质热中子束).它是应用研究和基础研究的重要中子源之一. 一、获得优质热中子束的基本方法 归纳起来,获得优质热中子束与中子源、准直器、单晶体过滤器、中子导管以及屏蔽与捕集器等部分的性能有关,其中中子源具有的特点是重要的,它决定其它部分在获得优质热中子束中所起的作用.1.中子源 增加反应堆中子的通量是获得优质热中子束的重要条…     

Neutron fluences and dose equivalents measured with passive detectors on LDEF

Neutron fluences were measured on LDEF in the low energy (< 1 MeV) and high energy (> 1 MeV) ranges. The low energy detectors used the ⁶Li(n,)T reaction with Gd foil absorbers to separate thermal (< 0.2 eV) and resonance (0.2 eV−1 MeV) neutron response. High energy detectors contained sets of fission foils (¹⁸¹Ta, ²⁰⁹Bi, ²³²Th, ²³⁸U) with different neutron energy thresholds. The measured neutron fluences together with predicted spectral shapes were used to estimate neutron dose equivalents. The detectors were located in the A0015 and P0006 experiments at the west and Earth sides of LDEF under shielding varying from 1 to 19 g/cm².

Dose equivalent rates varied from 0.8 to 3.3 μSv/d for the low energy neutrons and from 160 to 390 μSv/d for the high energy neutrons. This compares with TLD measured absorbed dose rates in the range of 1000–3000 μGy/d near these locations and demonstrates that high energy neutrons contribute a significant fraction of the total dose equivalent in LEO.

Comparisons between measurements and calculations were made for high energy neutrons based on fission fragment tracks generated by fission foils at different shielding depths. A simple 1-D slab geometry was used in the calculations. Agreement between measurements and calculations depended on both shielding depth and threshold energy of the fission foils. Differences increased as both shielding and thereshold energy increased. The modeled proton/neutron spectra appeared deficient at high energies. A 3-D model of the experiments is needed to help resolve the differences.     

Determination of slow neutron flux and spatial distribution using LR-115 2B detectors and radiochemical sensors and comparison of the results with Monte Carlo simulations

The fluence and spatial distribution of slow neutrons on the surface of a cylindrical paraffin moderator, surrounding a Pu/Be neutron source was measured using LR-115 2B detectors via ¹⁰B(n,)⁷Li reaction and ¹³⁹La radiochemical sensors. The obtained results were compared with Monte Carlo simulation using MCNP-4B2 code.     

Identification of the Li ground state

The proton-stripping reaction from a ¹¹Be radioactive beam incident on a beryllium target demonstrates that only (7±3)% of the ⁹Li residues in the reaction are in coincidence with the 2.7 MeV γ-ray corresponding to the ⁹Li first excited state. This implies that the previously observed low-energy neutrons from the decay of the unbound nucleus ¹⁰Li represent a direct l=0 transition to the ⁹Li ground state. Consequently, neutron-unbound ¹⁰Li is proven to have the same parity inversion as occurs in the case of ¹¹Be with a  intruder state below the natural parity state.     

A microscopic three-cluster model in the hyperspherical formalism

The hyperspherical formalism is applied in the framework of the microscopic generator-coordinate method. Three-cluster systems are described with a single generator coordinate, the hyperradius. This model is a natural extension of previous microscopic theories, and can be applied to bound states and resonances in a range of nuclei exhibiting a cluster structure. As an illustrative example, the model is applied to ⁶He and ⁶Li. Density distributions and electric dipole transition strengths are calculated, including B(E2;0⁺→2⁺) in ⁶He. The results are consistent with a neutron halo structure for the ground state of ⁶He, and with a proton–neutron halo structure of its isobaric analog state in ⁶Li. No 1⁻ “soft dipole” resonance is found in ⁶He.     

A study of the Li(p,n)Be reaction by the neutron threshold technique

The reaction ⁶Li(p,n)⁶Be has been studied by slow-neutron detection, with particular attention to the ⁶Be ground state threshold. The detector response was calculated by a Monte Carlo technique and verified with a measurement of the ⁷Li(,n)¹⁰B threshold. An analysis of the shape of the ⁶Be threshold indicated that both s- and p-wave neutrons contribute significantly to the reaction. The results depend on what mode of decay is assumed for the ground state of ⁶Be. If a two-stage process is assumed, with either an alpha particle and an unbound diproton or ⁵Li and a proton as intermediate state, the width is found to be 95±28 keV and the Q-value obtained for the ⁶Li(p,n)⁶Be reaction is −5074±13 keV. It was not possible to detertmine which process is predominant. No higher thresholds in the slow neutron yield up to 4 MeV of excitation in ⁶Be were observed. The data above the ground state threshold are consistent with a broad excited state of ⁶Be or with the occurrence of other neutron-producing reactions.     

COULD 7Be BE DESTROYED BY NEUTRON ABSORPTION IN THE SUN? -A NOTE ON THE SOLAR NEUTRINO PUZZLE

A comparison is made between the rate of the ⁷Be(p,y) ⁸B reaction and the rate of the neutron absorption reaction ⁷Be(n,p) ⁷Li which might have been important in. destroying ⁷Be in the solar interior.     

Three-Body Structure of 11Li

A variational calculation for neutron rich nucleus l1 Li is made in the ⁹Li + n + n model. The ⁹Li-neutron and neutron-neutron interactions are chosen to be of the Gaussian potentials with a repulsive core and an attractive tail. The strlicture and interparticle correlations are studied. A direct verification supporting neutron halo structure is found by inspecting the correlated densities.     

Boron determination in tourmaline by neutron induced radiography

The technique of neutron induced radiography has been applied to determine the boron concentration and its spatial distribution in mineral tourmaline collected from Swat Tourmaline Granite, Northern Pakistan. The technique involves the simultaneous irradiation of sample and a standard fixed on a track detector with thermal neutrons and the counting of alpha and ⁷Li tracks produced in the detector from the nuclear reaction ¹⁰B(n,)⁷Li. Boron concentration is determined by comparing the ⁷Li and alpha particle tracks density with that of a standard of known boron concentration. Boron concentration in tourmaline has been found to be (3.40±0.01)% in this study which is on the upper side within the normal range (2.5–3.8)% reported in the world. The presence of somewhat higher concentration of boron in tourmaline indicates that the Swat Tourmaline Granite was generated as a late stage hydrothermal activity during the Himalayan Orogeny.