放射性核束引起反应中轻带电粒子发射的同位旋效应

研究了69MeV/u³⁶Ar轰击Be靶的碎裂产物与Si靶反应引起的前角区轻带电粒子的发射产额与原子核同位旋、原子核序数的关系.发现前角区轻带电粒子发射产额对于丰质子核的结构非常敏感,与同位旋存在一种指数关系.因此可以把前角区轻带电粒子发射产额作为探测丰质子核结构的一种手段,也是一种新的验证一个核是否具有质子晕结构的实验证据.     

17N破裂反应产物的测量

利用RIBLL提供的丰中子放射性束测量了17N在197Au和9Be靶上的破裂反应.用1?4单元阵列探测器测量得到了前角带电粒子产额和关联粒子对的破裂截面,得到了17N在197Au和9Be靶上的带电粒子破裂截面比为4—5倍,结果表明对重靶核除了核破裂机制外还要考虑库仑破裂的贡献.     

17N破裂反应产物的测量

利用RIBLL提供的丰中子放射性束测量了^17N在^197Au和^9Be靶上的破裂反应,用14单元阵列探测器测量得到了前角带电粒子产额和关联粒子对的破裂截面,得到了^17N在^197Au和^9Be靶上的带电粒子破裂截面比为4－5倍,结果表明对重靶核除了核破裂机制外还要考虑库仑破裂的贡献。     

弱束缚原子核引起的熔合反应机制研究

弱束缚原子核引起的熔合反应机制研究是近几十年中实验核物理研究的重要课题之一。相比于放射性核束，加速器提供的稳定弱束缚原子核束流的强度要高几个数量级，利用稳定弱束缚原子核作为弹核进行反应机制的研究，可以在保证统计性和准确性的基础上，深入研究原子核的破裂、转移等反应道对熔合过程的耦合作用。已有很多实验数据表明，在库仑位垒附近，弱束缚原子核引发的熔合反应有很多有趣的现象，例如完全熔合截面的“垒下增强”和“垒上压低”。本文主要回顾近年来弱束缚原子核“垒上压低”的研究结果，并探讨造成“垒上压低”的可能原因。完全熔合截面“垒上压低”的主要原因是弱束缚原子核在进入熔合位垒之前发生破裂，从而降低了完全熔合反应道的入射通量。同时，实验研究表明完全熔合截面压低的程度可能与靶核质量数以及靶核结构相关。目前，在实验上对弱束缚原子核引起的熔合反应研究主要有3种测量方法，分别为$\gamma$射线测量方法、带电粒子测量方法以及带电粒子-$\gamma$射线符合测量的方法。其中，带电粒子-$\gamma$射线符合测量的方法在反应道鉴别方面具有明显的优势。本文对这3种测量方法进行了概要介绍，并就国内外对运用这3种方法开展的研究进行了介绍，包括本研究组在此方面的研究工作。此外，对弱束缚原子核引起的熔合反应近期在理论方面的研究工作也做了些介绍。     

基于HIRFL-CSR测量丰中子重核质量的建议

丰中子重核区有大量原子核质量未知,迫切需要实验测量。我们建议,利用兰州重离子加速器研究装置HIRFL-CSR上的等时性质谱术,高精度测量204Pt等丰中子重核的质量。CSR质量测量实验中,在目标核产额尽可能高的前提下,需要每次注入都有多个离子同时储存到实验环CSRe中,才能针对逐次注入修正磁场晃动的影响,得到高精度测量结果。但在丰中子核区,当目标核产生截面非常低时,每次注入能储存到环中的离子数目太少。为了解决这个问题,我们提出了一种"混合厚度靶"的方法,在不明显改变目标核产额的情况下,显著增加同时储存在CSRe中的离子数,满足实验要求。模拟计算表明,在CSRe测量丰中子重核质量是可行的,并推荐了实验的设置。     

今日国外物理

 1 英、澳学者创原子核形状研究新方法据澳大利亚《实验室新闻》报道,英国尼尔·罗利博士提出用相对简单的实验数据确定原子核形状的可能性,改变入射原子核的能量,测量核合成(聚变)的概率的变化.澳大利亚学者杰克·利博士在其学生简星伟协助下,用韦纳滤波器进行这一实验,发现轰击1平方毫米靶区时,只有百万分之一的入射粒子能够进行合成,大多数被散射掉,散射粒子的强度妨碍检测器的正常工作.他们采用球形氧原子核作为入射原子核,其他一系列原子核作为靶,进行了大量测量,获得十分满意的结果.     

利用GEANT4研究轻带电粒子诱发反应出射中子双微分产额

轻带电粒子诱发反应产生次级中子的研究对于加速器屏蔽设计和优化具有重要意义。利用Geant4程序结合INCL、BIC、BERT物理模型分别计算了33 MeV的d核、65 MeV的3He核和4He核轰击厚的碳、铜和铅靶在轻带电粒子诱发反应产生次级中子的研究对于加速器屏蔽设计和优化具有重要意义。利用Geant4程序结合INCL、BIC、BERT物理模型分别计算了33 MeV的d核、65 MeV的3He核和4He核轰击厚的碳、铜和铅靶在$0^{\circ}$，$15^{\circ}$，$45^{\circ}$，$75^{\circ}$和$135^{\circ}$等方向出射中子的双微分产额，并与实验数据进行了比较。研究表明，对于33 MeV的d核诱发的核反应，INCL模型的计算结果基本上再现了碳靶和铜靶的实验数据，但高估了铅靶直接过程产生的中子。BIC模型和BERT模型的计算结果没有重现弹核削裂过程对应的宽峰。对于65 MeV的3He核诱发的核反应，三个模型的计算结果均未能重现前向角弹核削裂过程产生的中子，但在$15^{\circ}$，$45^{\circ}$，$75^{\circ}$和$135^{\circ}$上三个模型的计算结果与实验数据符合较好。对于65 MeV的4He核诱发的核反应，INCL模型的计算结果与碳靶和铜靶的实验数据符合较好，但低估了铅靶的中子产额。BIC模型和BERT模型的计算结果低估了碳靶的实验数据，且在大角度上略微高估了铅靶的实验数据。     

尼尔斯·玻尔的原子核裂变理论及其发展近况

尼尔斯·玻尔对原子核物理的最直接、最重要的贡献,是他创立了核反应复合核模型与原子核的裂变理论. 原子核裂变是指一个重核自发地或者通过中子或其它带电粒子打进原子核产生的核反应,使这个核分裂成两个质量相差不多的碎片.这一现象是哈恩(Hahn)和斯塔兹曼(Stra-ssmann)于193     

原子核的同位旋对碎裂产物的影响

用同位旋相关的晶格气体模型系统地研究了Z=54的同位素和A=129的同质异位素热发射体的粒子发射的特性,阐述了发射体系的同位旋对中子、质子和带电粒子产额,以及轻粒子的同位素比及同位素对的比的影响.同时,还比较了在同位旋相关作用势下和同位旋不相关作用势下碎片产物特性的差异.发现了不同质量区间(轻粒子、中等质量碎片和重余核)的产物的平均中子质子比,在同位旋相关的或不相关的作用下它们有十分不同的温度依赖性.发现核气态(轻粒子)的要大于核液态(重余核)的,也就是说在液气共存时的气态有 关键词：     

17N+197Au反应中碎片与中子的符合测量

在3?3?.4MeV/u ¹⁷N束轰击¹⁹⁷Au靶产生的反应中,利用放置于不同角度组合的17个中子探测器(4°—83°)和14个半导体望远镜(2.3°—9.0°)对反应产物碎片与中子进行了符合测量.经对所得实验角分布积分得到Z=3—6元素的同位素产额分布.在参加者-旁观者模型框架下,采用¹⁷N原子核内部的不同密度分布计算了同位素产额分布并与实验数据做比较.     

高能质子在散裂靶中的能量沉积计算与实验验证

高能质子在散裂靶中的能量沉积是散裂靶中子学研究的重要内容之一,准确掌握高能质子在散裂靶中引起的能量沉积分布与瞬态变化是开展散裂靶热工流体设计的重要前提.本文采用MCNPX,PHITS与FLUKA三种蒙特卡罗模拟程序,计算并比较了高能质子入射重金属铅靶、钨靶的能量沉积分布及不同粒子对总能量沉积的占比贡献;针对高能质子入射金属钨靶的能量沉积实验数据空白,采用热释光探测器阵列测量了250 MeV质子束入射厚钨靶的能量沉积分布,实验结果表明蒙特卡罗模拟程序在散裂靶中能量沉积的计算结果具有较高的可靠性.     

Ep≤63 GeV 质子入射铅、铋引起的中子产生双微分截面的模拟(英文)

加速器驱动次临界系统(ADS) 液态Pb-Bi 散裂靶的设计中,需要可靠的理论计算工具精确地预言几个GeV 能量范围的质子引起的散裂反应产生的各种粒子和核素。利用蒙特卡罗模拟软件包Geant4 计算研究了800 MeV至3 GeV 质子入射铅、铋材料引起的中子产生双微分截面。比较了Geant4 不同物理模型得到的模拟结果与现有的实验数据。其中,Geant4 的QGSP BERT和QGSP INCL ABLA 物理模型模拟结果很好地再现了实验数据。本工作证实了Geant4 蒙特卡罗模拟软件包适合用于能量高达3 GeV 的质子入射铅、铋引起的中子产生双微分截面的模拟计算。A detailed design of the liquid Pb-Bi spallation target of the Accelerator Driven Systems (ADS) requires powerful and reliable computational tools that can accurately predict particles and nuclides production by the proton induced spallation reactions in the energy range of a few GeV. In this paper, the neutron production double-differential cross sections for Pb and Bi target materials at incident proton kinetic energies between 800 MeV and 3 GeV are studied by calculations with Monte Carlo simulation package Geant4. The simulated results of Geant4 with several physics models are compared with available experimental data. The simulated results generated by QGSP BERT and QGSP INCL ABLA physics models of Geant4 well reproduce the available experimental data. The present results validated that Geant4 Monte Carlo simulation package is suitable for simulations of neutron production double-differential cross sections of proton induced reaction on Pb and Bi targets in the incident energy range up to 3 GeV.     

分层γ扫描技术中点源定位的蒙特卡罗方法

随着核工业发展和放射性同位素的广泛应用,产生大量中、低放射性废物。中、低放射性废物长期贮存前要对放射性废物的核素种类、活度等进行测量。分层扫描(SGS)测量技术是一种无损检测桶装核废物的手段,但是在测量过程中会遇到放射性核素所在的位置变化,则相对衰减距离、效率刻度不对应,导致估计活度结果误差较大。本工作首先将当前层平均分成12份分别进行计数,并通过实验和蒙特卡罗模拟方法,记录以均匀聚乙烯样品填充对废物桶径向不同偏心位置的探测器的计数。由12个位置的探测器计数得到两个最值,并根据射线在样品中衰减规律计算得到放射性核素距桶轴的距离,从而确定放射性核素在当前层的位置。结果表明:此方法可求出放射性核素所在的位置从而估计点源在桶内旋转半径,对应使用该旋转半径下的自吸收校正因子、探测效率和衰减校正效率,提高了SGS估计的精度。     

PHITS—a particle and heavy ion transport code system

The paper presents a summary of the recent development of the multi-purpose Monte Carlo Particle and Heavy Ion Transport code System, PHITS. In particular, we discuss in detail the development of two new models, JAM and JQMD, for high energy particle interactions, incorporated in PHITS, and show comparisons between model calculations and experiments for the validations of these models. The paper presents three applications of the code including spallation neutron source, heavy ion therapy and space radiation. The results and examples shown indicate PHITS has great ability of carrying out the radiation transport analysis of almost all particles including heavy ions within a wide energy range.     

Measurement of neutron-induced proton-production energy spectra with NE213 scintillator

Many benchmark data are required for the improvement of theoretical model implemented in a Monte Carlo code for particle transport. To acquire the benchmark data, we measured energy spectra of protons emitted from graphite, aluminum, and iron targets bombarded with continuous-energy neutrons, which enable simultaneous measurements at the incident energies from 100 to 600 MeV at a time. The neutron flux incident on the target was measured with a ²³⁸U fission ionization chamber. Protons emitted from the target were measured with three ΔE–E detectors consisting of a thin NE102A scintillator and a thick NE213 liquid scintillator. In the analysis, the pulse shape discrimination of the NE213 scintillator enable us to distinguish events for a charged particle stopping in the scintillator from events for a charged particle penetrating the scintillator. Experimental results were compared with calculations by the PHITS code coupled with the JENDL-HE file, the Bertini model implemented in the PHITS code, and the PEANUT model in the FLUKA code.     

Application of Origen2.1 in the decay photon spectrum calculation of spallation products

Origen2.1 is a widely used computer code for calculating the burnup, decay, and processing of radioactive materials. However, the nuclide library of Origen2.1 is used for existing reactors like pressurized water reactors. To calculate the photon spectrum released by the decay of spallation products, we have made specific libraries for the ADS tungsten spallation target, based on the results given by the FLUKA Monte Carlo code. All the data used to make the Origen2.1 libraries are obtained from Nuclear structure & decay Data (NuDat2.6). The accumulated activity of spallation products and the contribution of nuclides to photon emission are given in this paper.     

Applicability of particle and heavy ion transport code PHITS to the shielding design of spacecrafts

Development of HZE particle transport codes is severely required for the shielding design of spacecrafts. One-dimensional deterministic codes are generally adopted in the shielding calculation because of their reasonable computational time, but three-dimensional Monte Carlo codes are also to be employed especially in the final step of the design with fully optimized geometries. We are therefore developing a general-purpose Monte Carlo code PHITS, which can deal with the transports of all kinds of hadrons and heavy ions with energies up to . For the purpose of examining the applicability of PHITS to the shielding design, neutron and charged particle spectra inside the Space Shuttle were calculated for an imaginary vessel whose shielding distribution is fitted to that of the real shuttle. Absorbed doses and dose equivalents were estimated from the spectra by applying fluence to dose conversion coefficients. The agreements between the calculated spectra or doses and the corresponding experimental data were generally satisfactory, especially for the neutron spectra, which have been barely reproduced by other studies. We therefore concluded that PHITS has a great possibility of playing an important role in the design study of spacecrafts.     

Target Residues from the Interaction of Indium with 42MeV/nucleon 12C Ions

The cross section is measured for 65 target residues produced from the interaction of indium with 42MeV/nucleon ¹²C ions using nuclear chemistry techniques.The experimental mass yield distribution gives a satisfactory agreement with that calculated from Monte Carlo code GEMINI based on the statistical binary decay model. According to the systematics of isotope distributions,the possibility of the production of new neutron-deficient nuclides far from β stability is discussed in the intermediate energy heavy ion reaction.     

Monte Carlo simulation of ion-beam doping of a silicon-on-sapphire heterostructure with regard to the dislocation structure

A modification of the well-known TRIM algorithm for the Monte Carlo simulation of accelerated-ion trajectories in targets with a high density of structural defects is proposed. The spatial distributions of dopants and radiation-induced defects in a thin-film silicon-on-sapphire heterostructure are calculated for the boron and phosphorus ions implanted with energies of 30, 60, and 100 keV. It is shown that the influence of the dislocation structure in the target on the concentration profile of implanted atoms taken into account in the proposed model is insignificant, while the concentration of radiation-induced defects at the same distance from the irradiated surface can vary more than twice, depending on the ion type and implantation energy.     

充气反冲核谱仪焦平面探测阵列的GEANT4模拟

充气反冲核谱仪(SHANS)是目前国内合成缺中子锕系新核素、研究重核素α衰变性质的重要实验装置。为进一步提高焦平面探测阵列对重核素α衰变粒子和射线的探测效率,计划对现有探测装置进行升级。本文的主要工作是采用基于蒙特卡罗方法的GEANT4软件对现有的谱仪探测器阵列进行模拟,并与实验测量数据进行比较,以验证程序的准确性。结果表明,新探测系统对α衰变粒子的探测效率可达到88%左右,对能量在1 MeV的$\gamma$射线全能峰的探测效率约为7%。