25MeV/u~(40)Ar+~(115)In反应碎片和轻带电粒子的方位角关联

在２５ＭｅＶ／ｕ４０Ａｒ＋１１５Ｉｎ反应的在平面和出平面大角度关联测量中，提取了碎片和α粒子之间的方位角关联函数和方位角非对称性因子．φ＝９０时，方位角关联函数呈现为最小值，表明在集体类转动效应影响下，反应产生的轻带电粒子和碎片优先在反应平面内发射．随着关联对质量的增加，在平面关联粒子的发射相对于束流轴不对称性逐渐增大．随着关联对质量的增加，相继衰变和粒子末态相互作用对φ＝０的关联粒子对方位角关联函数值的影响逐渐降低并直至消失，同时集体转动效应增强，方位角非对称性增加．

30MeV/u~(40)Ar+~(115)In反应中的IMF能谱

测量了 3 0MeV/u40 Ar束流轰击115 In反应靶时出射的中等质量碎片(IMF)的能谱 .通过比较在不同出射角度发射的同一种IMF的能谱 ,得到了IMF的发射机制随出射角的演化关系 .在假定运动源速度和出射离子库仑位垒不随出射角变化的条件下 ,通过改变发射源的强度和核温度参量完成了对实验测得能谱的运动源拟合 ,并详细讨论了 3个发射源所占份额和源强随出射角的演化关系 .

同位素~(106)Cd金属自支撑靶的制备及废靶的再生利用

用滚压技术制备出同位素１０６Ｃｄ自支撑靶，并成功地利用破靶膜的再生方法。制备出可供使用的靶膜。

25MeV/u~(40)Ar+~(115)In反应中前中角区碎片发射研究

从 2 5MeV/u4 0 Ar+115In反应前中角区出射碎片的能谱、角分布和Z电荷分布出发 ,讨论了碎片发射机制随出射角和核电荷数Z的渐进变化 ;用改进的量子分子动力学 (MQMD)模型研究了碎片角分布及Z电荷分布 ,理论计算和实验值整体上符合较好 ,但在前角区MQMD模型低估了碎片的产额 ,在中角区对于Z接近弹核的碎片 ,理论计算比实验值偏高 ;碎片产物的角分布及Z电荷分布还与统计模型GEMINI进行了比较 ,发现在前角区平衡蒸发的成分所占比例很小 ,中角区所占的比例有所增加 ,但仍然是较小的比例 .随着碎片核电荷数Z的减小 ,平衡核的蒸发成分逐渐减少 ,非平衡的中速成分逐渐占主导地位

25MeV/u ~(40)Ar+~(115)In,~(58)Ni,~(27)Al反应中前中角区碎片角分布和元素Z分布

测量了 ２５ＭｅＶ／ｕ４０　Ａｒ＋１１５　Ｉｎ，５８　Ｎｉ，２７　Ａ１反应前中角区出射碎片的角分布和 元素 Ｚ分布．用改进的量子分子动力学（ＭＱＭＤ）模型研究了碎片的角分布和 Ｚ 分布．理论计算值和实验值整体上符合得很好，但在前角区，ＭＱＭＤ模型低估 了碎片的产额，在中角区对于Ｚ接近弹核的碎片，理论计算值比实验值偏高．碎 片产物的角分布和Ｚ分布还与统计蒸发模型ＧＥＭＩＮＩ进行了比较，结果表明，在 前角区平衡蒸发成份所占的比例很小，中角区所占的比例有所增加，但仍然是较 小的比例．同时发现平衡蒸发成份随着出射碎片核电荷数Ｚ的减小而逐渐减 少．

Production of new superheavy Z=108-114 nuclei with U-238, Pu-244, and Cm-248,Cm-250 targets

Within the framework of the dinuclear system (DNS) model, production cross sections of new superheavy nuclei with charged numbers Z=108-114 are analyzed systematically. Possible combinations based on the actinide nuclides U-238, Pu-244, and Cm-248,Cm-250 with the optimal excitation energies and evaporation channels are pointed out to synthesize new isotopes that lie between the nuclides produced in the cold fusion reactions and the Ca-48-induced fusion reactions experimentally, which are feasible to be constructed experimentally. It is found that the production cross sections of superheavy nuclei decrease drastically with the charged numbers of compound nuclei. Larger mass asymmetries of the entrance channels enhance the cross sections in 2n-5n channels.

Isotopic dependence of production cross sections of superheavy nuclei in hot fusion reactions

The dinuclear system model has been further developed by introducing the barrier distribution function method in the process of heavy-ion capture and fusion to synthesize superheavy nuclei. The capture of two colliding nuclei, formation and de-excitation process of compound nucleus are decribed by using empirical coupled channel model, solving master equation numerically and statistical evaporation model, respectively. Within the framework of the dinuclear system model, the fusion-evaporation excitation functions of the systems Ca-48(Am-243, 3n-5n) (288-286)115 and Ca-48(Cm-248, 3n-5n)(293-291)116 are calculated, which are used for synthesizing new superheavy nuclei at Dubna in recent years. Isotopic dependence of production cross sections with double magic nucleus Ca-48 bombarding actinide targets U, Np, Pu, Am, Cm to synthesize superheavy nuclei with charged numbers Z=112-116 is analyzed systematically. Based on these analysis, the optimal projectile-target combination and the optimal excitation energy are proposed. It is shown that shell correction energy and neutron separation energy will play an important role on the isotopic dependence of production cross sections of superheavy nuclei.

Properties of the superheavy nuclei (288)115 and its alpha-decay chain in a generalized liquid-drop model

The properties of the nuclei belonging to the newly observed nuclei starting from (288)115 have been studied with the generalized liquid drop model connected with WKB approximation. The calculated results have been compared with the results of the DDM3Y theory and the experimental data. The half lives of this new alpha decay chain have been well tested from the consistence of the macroscopic, microscopic and the experimental data.

42 MeV/u~(12)C与~(115)In反应的靶余核

本实验使用放射化学方法测定了42 MeV/u (12)C与~(115)In相互作用靶余核的生成截面。借助高斯电荷分布的假设得到了靶余核的质量分布。将实验得到的质量分布与熔合碎裂模型和级联的两体衰变模型进行了比较。特别值得注意的是，使用统计的两体衰变模型Monte Carlo GEMINI程序计算第一次与实验结果符合得非常满意。同时计算结果也表明：在42MeV/u的轰击能量下，完全熔合对靶余核的产物仍然有很大的贡献。在同样的假设下，得到了靶余核的同位素分布。可以看到，同位素分布的宽度随靶余核原子序数的增加而增加，在此对利用中能重离子反应生成新的远离β稳定线的缺中子核素进行了讨论

46.7 MeV/u~(12)C轰击~(58)Ni、~(115)In、~(197)Au反应中粒子发射研究中子皮及中子分布弥散度对核势的影响

用能量密度公式及小液滴模型给出的费米密度分布，并引入中子皮及中子分布弥散度随中子过剩自由度增加而增加这一因素，计算了重离子反应在相互作用势及熔合位垒。熔合位垒的计算值和实验值符合很好，特别是在中重核区域，改善了以前的计算结果。详细研究了亲近势标度，发现用中子皮及中子分布弥散度的变化能较好地解释中子过剩自由度对新近势标度偏离的影响。本工作对奇异核结构与核反应性质的研究无疑是有用的。我们利用HIRFL提供的46.7MeV/u ~(12)C束轰击~(58)Ni、~(115)In、~(197)Au研究了反应中发射的α粒子角分布和能谱。从速度表象中洛仑兹不变截面等高图中明显看到发射α粒子的三个源。用这三个源的运动模型成功拟合了α粒子能谱，所提取的参数符合费米气体模型计算结果，并讨论了能谱及拟合参数对靶的依赖关系。认为快速源实质上来自弹核碎裂或类弹核碎裂

中能重离子引起的碎裂及转移反应研究

重离子核反应机制的研究一直是人们关注的课题。入射能量较低时，集体效应占主要地位，反应为熔合反应及深部非弹性碰撞，实验可用平均场理论进行解释。当入射能量较高时，平均场效应消失，核子-核子碰撞起主要作用，实验可用参加者-旁观者模型来描述。中能区（10-100 MeV/u）的重离子反应既具有低能下一体耗散的特点，又具有高能下核子-核子碰撞的特征，由于作用时间短，非平衡现象变得很重要。在这一能区，多种反应机制共存并相互竞争。对这一能区的重离子核反应制的研究将有助于我们更清楚地了解原子核的结构。为此，我们在兰州重离子加速器HIRFL上进行了46.7 MeV/u ~(12)C引起的重离子反应中前方向出射产物的测量，着重讨论了周边反应中的弹核碎裂和转移反应以及它们的相互竞争。实验中用46.7 MeV/u ~(12)C束流轰击四种靶核：~(58)Ni、~(64)Ni、~(115)In和~(197)Au。通过对前方向出射的类弹碎片的测量，发现它们的平行动量分布宽度满足Goldhaber关系式，提取的约化平行动量分布宽度σ_0 = 80 ± 10 MeV/c，与相对论情形下的值接近，并且σ_0对于各种反应系统均相同。反应中弹核碎裂产物的最可几能量可用Abrasion图象来解释。对于质量接近弹核的类弹碎片，将碎裂部分和转移部分分开后，提取的转移部分的约化平行动量分布宽度为44 ± 10 MeV/c，这比弹核碎裂部分的宽度要窄，说明转移反应比弹核裂受到相空间中更严格的限制。弹核碎裂和转移反应的几率都随靶核质量增加而增加，并且与被转移结团的结构有关。转移反应主要对弹核附近的类弹碎片有贡献，当类弹碎片质量与弹核质量相差较大时，主要是弹核碎裂的贡献。对反应中的同位素产额分布也进行了分析，结果表明，类弹碎片的同位素分布对靶核有依赖关系，当靶核的N/Z增加时，产物的N/Z也增加，并且低能部分的N/Z比高能部分的N/Z要大。当角度变大时，~7Li/~6Li、~9Be/~7Be、~(11)B/~(10)B等同位素产额比随之变化，低能部分变化缓慢，高能部分则变化明显。产物的同位素产额分布或同位素产额比反映了系统由非平衡向平衡演化的过程。实验中对于BaF_2晶体与半导体组成的望远镜探测器的性能进行了测量。圆柱形BaF_2晶体后配以XP2020Q型光电倍增管，输出信号送入不同的QDC，以获得BaF_2中光输出的快慢成分。ΔE-E方法可以得到较好的元素鉴别，即使对低能的p、d、t也能分开，用快慢成分关联方法可对较高能量的轻带电粒子很好地鉴别。入射离子越重，相同能量的离子在BaF_2晶体中引起的光输出越小。BaF_2对入射离子的响应在较大的能区内是线性的，在低能时存在轻微的非线性。对80 cm大面积位置灵敏电离室与一维位置灵敏塑料闪烁体组成的探测系统首次在中能重离子反应中进行了测试。电离室可以测量较重的低能离子，有较好的粒子鉴别能力，能给出能量信息及两维位置信息。闪烁体则使得该系统可用于较高能量轻带电粒子的测量，它能给出能量吸一维位置信息，与电离室配合可以进行元素鉴别。它将在以后的中能重离子实验中得到广泛的应用

25MeV/A~(40)Ar+~(115)In反应中轻粒子发射研究及大面积位置灵敏闪烁探测器的研制

论文分为两个部分。第一部分：研究在25MeV/u ~(40)Ar+~(115)In反应中轻粒子发射机制。实验中，利用研制的轻粒子探测器测量了发射的P、#alpha#能谱。用三源模型拟合了轻粒子能谱，所提取的参数与费米气体模型的计算结果进行比较，分析了发射源形成和衰变的一些特点。第二部分：研制一种大面积幅度、时间、位置灵敏闪烁探测器。它是HIRFL上建成的第一阶段放射性核束物理实验终端的主要设备之一，在首次放射性核束调试中收到良好的效果。本文的目的是用经典理论研究了热核形成及衰变的一些性质，在即将开展的放射性核束物理研究中， 利用研制的大型探测器对经典理论普适性进行检验

Nafion/PTFE composite membranes for fuel cell applications

Porous polytetrafluoroethylene (PTFE) membranes were used as support material for Nafion((R))/PTFE composite membranes. The composite membranes were synthesized by impregnating porous PTFE membranes with a self-made Nafion solution. The resulting composite membranes were mechanically durable and quite thin relative to traditional perfluorosulfonated ionomer membranes (PFSI); we expect the composite membranes to be of low resistance and cost. In this study, we used three kinds of porous PTFE films to prepare Nafion/PTFE composite membranes of different thickness. Scanning electron micrographs and oxygen permeabilities showed that Nafion resin is distributed uniformly in the composite membrane and completely plug the micropores, there is a continuous thin Nation film present on the PTFE surface. The variation in water content of the composite and Nafion 115 membranes with temperature was determined. At the same temperature, water content of the composite membranes was smaller than that of the Nafion 115. In both dry and wet conditions, maximum strength and break strength of C-325(#) and C-345(#) were larger than those of Nafion 112 due to the reinforcing effect of the porous PTFE films. And the PEMFC performances and the lifetime of the composite membranes were also tested on the self-made apparatus. Results showed that the bigger the porosity of the substrate PTFE films, the better the fuel cell performance; the fuel cell performances of the thin composite membranes were superior to that of Nation 115 membrane; and after 180 h stability test at 500 mA/cm(2), the cell voltage showed no obvious drop. (C) 2002 Published by Elsevier Science B.V.

Structure and oxygen permeability of a dual-phase membrane

The dual-phase membrane of La0.15Sr0.85Ga0.3Fe0.7O3-delta-Ba0.5Sr0.5Fe0.2Co0.8O3-delta (LSGF-BSCF) was prepared successfully. This membrane was characterized with X-ray diffraction (XRD), scanning electron microscopy (SEM) and electron probe micro-analyzer (EPMA). This membrane has a dense dual-phase structure: LSGF being the dense body of this membrane and BSCF as another phase running along the LSGF body. This structure is favorable for the oxygen permeation through the membrane. The oxygen permeation test shows that the oxygen permeation flux of LSGF-BSCF membrane (Jo(2) = 0.45 ml/min cm(2), at 915 degreesC) is much higher than that of LSGF membrane (Jo(2) = 0.05 ml/min cm(2)). Thickness dependence of oxygen permeation indicates that the oxygen permeation is controlled by the bulk diffusion. Compared to pure BSCF the dual-phase membrane of LSGF-BSCF is stable in reducing atmosphere. (C) 2003 Elsevier B.V. All rights reserved.

A 2-kW COIL with a square pipe-array JSOG and nitrogen buffer gas

A 2-kW-class chemical oxygen-iodine laser (COIL) using nitrogen buffer gas has been developed and tested since industrial applications of COIL devices will require the use of nitrogen as the buffer gas. The laser, with a gain length of 11.7 cm, is energized by a square pipe-array jet-type singlet oxygen generator (SPJSOG) and employs a nozzle bank with a designed Mach number of 2.5. The SPJSOG has advantages over the traditional plate-type JSOG in that it has less requirements on basic hydrogen peroxide (BHP) pump, and more important, it has much better operational stability. The SPJSOG without a cold trap and a gas-liquid separator could provide reliable operations for a total gas flow rate up to 450 mmol/s and with a low liquid driving pressure of around 0.7 atm or even lower. The nozzle bank was specially designed for a COIL using nitrogen as the buffer gas. The cavity was designed for a Mach number of 2.5, in order to provide a gas speed and static temperature in the cavity similar to that for a traditional COIL with helium buffer gas and a Mach 2 nozzle. An output power of 2.6 kW was obtained for a chlorine flow rate of 140 mmol/s, corresponding to a chemical efficiency of 20.4%. When the chlorine flow rate was reduced to 115 mmol/s, a higher chemical efficiency of 22.7% was attained. Measurements showed that the SPJSOG during normal operation could provide a singlet oxygen yield Y greater than or equal to 55%, a chlorine utilization U greater than or equal to 85%, and a relative water vapor concentration w = [H2O]/([O-2] + [Cl-2]) less than or equal to 0.1.