辐射白沙液新酒老熟试验的色谱分析法

我国70年代即开始辐射酒的研究,近年来四川省原子核技术应用研究所与金堂县机械化酒厂合作辐射白酒的试验获得成功;1982年,我所与长沙市酒厂合作这项试验,初步结论是辐照使酒质变好,味甜柔和,有回味。从理化分析数据来看,辐射能增加酒中香味成分——总酸、总酯含量,从而使影响酒质的杂醇油明显下降。因此,辐照能提高酒质,缩短使酒陈化的贮藏期。 人们很关心辐照能增加酒中总酯、总酸含量,但对白酒的组分有无不利变化?本文着重报导辐照湖南名酒     

酒的辐射化学Ⅱ.辐照酒形成的2,3-丁二醇光学异构体的分布

本工作主要研究了辐照酒形成的2,3-丁二醇光学异构体的分布,并与商品酒中2,3-丁二醇异构体分布作了比较。结果指出,虽然某些商品酒中2,3-丁二醇含量高于4000 Gy吸收剂量辐照酒样-1时形成的2,3-丁二醇量,但是两者有不同的光学异构体分布。在辐照酒中,2,3-丁二醇以dl(外消旋体)和meso(内消旋体)形式存在;在商品酒中则以1和meso形式存在。辐照酒样-1中d-2,3-丁二醇含量随吸收剂量增加而增加,在吸收剂量为4330 Gy时,d-2,3-丁二醇的量达7.6ppm,因此其卫生安全性是亟待研究的问题。在N_2饱和的乙醇体系中,G_(2,3-丁二醇)=2.23;在缺氧条件下辐照酒样-1时,G_(2,3-丁二醇)=1.46;在溶解氧可得到某种程度补足的条件下辐照酒样-1时,G_(2,3-丁二醇)=0.35,这不仅表明酒中溶解氧抑制2,3-丁二醇生成,而且酒中其它成分还能与乙醇分子竞争水辐解形成的活性粒子并形成新的辐解产物,因此在评估辐照酒的卫生安全性时必须予以注意。     

气相色谱法分析^60Coγ辐照前后的白酒成分

一、前言从辐照食品问世以来,很多国家都广泛深入地开展了辐照食品的研究工作。研究辐射对有机化合物和无机气体产生的效应,气相色谱是一种优越的技术。据报导酒经~(60)Coγ辐照后,可以促使酒的陈化,并对酒的风味方面有一定的影响。我国四川和山东等地在酒的辐照方面也开展了不少工作,并取得较好的经济效益。本工作是配合北京大兴酒厂生     

酒的辐射化学Ⅳ.辐照的薯干白酒浓缩物对梨形四膜虫细胞繁殖的毒性作用

研究了酒的浓缩物对梨形四膜虫繁殖的影响。结果发现,d-2,3-丁二醇和乙醇的浓度分别高达250和1000ppm时,未见对四膜虫繁殖有任何影响。不同批次生产的酒的浓缩物(未辐照)有不同程度的抑制作用。辐照酒的浓缩物的影响更为明显,且随吸收剂量增加而加强,这表明辐照酒的浓缩物对四膜虫细胞的毒性作用可能来自所使用的薯干原料,也可能归因于辐照形成的高沸点产物。     

酒的辐射化学 Ⅰ.辐照酒中过氧化物生成的研究

本工作研究了酒及其模式体系乙醇水溶液辐照时过氧化物的生成。从过氧化物浓度对剂量曲线的起始线性部份求得了酒和乙醇体系中过氧化物的G值。从辐照酒求得过氧化物G值在1.0～3.6之间,60%(V/V)乙醇水溶液,G(过氧化物)=3.6。溶解氧参与辐射引发的化学作用过程,并对过氧化物形成起主要作用。在一些酒中,过氧化物呈现较大的稳定性,辐照酒在存放20天后,过氧化物含量仍高达6～7ppm,因此,确定辐照酒中H_2O_2的允许限量是极待解决的问题。     

灌注辐照的酒对大鼠生物效应的研究

用经~(60)Coγ射线照射10~6R的酒给大白鼠连续灌胃一年,给酒量分小剂量组(0.5 ml/只/次)和大剂量组(2ml/只/次),进行了体重、外周血象、肝功能、内分泌、免疫、骨髓嗜多染红细胞微核率、脏器系数等多项指标观察,结果表明,给大剂量的辐照酒组GPT阳性率明显低于非照酒组,其他各项指标,辐照酒组与非照酒组间无明显差异,证明辐照酒饮用是安全的。     

~(60)Coγ射线辐照黄酒陈化与杀菌效果研究

以黄酒感官品评和化学成分为指标,研究了~(60)Coγ射线辐照剂量、辐照温度、包装容器、容器的空隙度、酿造工艺、贮藏时间对黄酒加速陈化效果的影响。试验结果表明:用适宜剂量辐照黄酒具有加速陈化的效果,黄酒的色、香、味、格保持黄酒独有的风味;辐照酒对人体无害,是卫生安全的。辐照黄酒温度为30～40℃。包装容器陶罐优于玻璃瓶,容器(500ml玻璃瓶)的孔隙度以留有100ml为宜。新工艺酿造的酒贮藏时间为5～6个月。辐照生清黄酒结合60℃加热复合处理具有好的杀菌效果,且酒质稳定、卫生。生清黄酒具有传统风味,酒中化学成分无变化,符合出口酒的标准。     

~(60)Co γ射线辐照黄酒陈化与杀菌效果研究

以黄酒感官品评和化学成分为指标,研究~(60)Co γ射线辐照剂量、辐照温度、包装容器、容器的空隙度、酿造工艺、贮藏时间对黄酒加速陈化效果的影响。试验结果表明:用适宜剂量辐照黄酒有加速陈化的效果,黄酒的色、香、味、格保持黄酒独有的风味;辐照酒对人体无害,是卫生安全的。辐照黄酒温度为30～40℃。包装容器陶罐优于玻璃瓶、容器的孔隙度,(500ml玻璃瓶)以留有100ml为宜。新工艺酿造的酒优于传统工艺的贮藏时间为5～6个月。辐照生清黄酒结合60℃加热复合处理具有好的杀菌效果,且酒质稳定、卫生。生清黄酒具有传统风味,酒中化学成分无变化,符合出口酒的标准。     

酒的辐射化学IV.辐照的薯干白酒浓缩物对梨形四膜虫细…

研究了酒的浓缩对梨形四膜虫繁殖的影响。结果发现，ｄ－２，３－丁二醇和乙醇的浓度分别高达２５０和１０００ｐｐｍ时，未见对四膜虫繁殖有任何影响。不同批次生产的酒的浓缩物对四膜虫细胞的毒性作用可能来自所使用的著干原料，也可能归因于辐照形成的高沸点产物。     

隐藏爆炸物检测装置快中子辐照安全分析

为推广隐藏爆炸物检测装置在反恐领域的应用,对快中子辐照炸药、食品及药品的安全性进行了分析。通过蒙特卡罗方法建立了装置的快中子辐照炸药安全性评估模型。通过能量沉积计算及炸药起爆机理分析可知,快中子辐照炸药不会产生爆炸的危险。采用剂量分析法对快中子辐照食品及药品的安全性进行了分析,结果表明,在隐藏爆炸物检测装置的快中子辐照条件下,食品及药品的辐照剂量在国家和国际限定的标准内,快中子辐照食品及药品的安全性是可接受的。     

Methods for leak detection for KWU pressurized and boiling water reactors

Leakage monitoring is an essential criterion to rule out the possibility of double ended pipe rupture in the primary coolant system. Subcritical cracks can be detecred with a considerable margin before they extend to critical crack lengths resulting in spontaneous failure. In those KWU PWRs which went into operation recently, a Leakage Monitoring System was installed that is based on thermodynamic analysis. It utilizes the following measured parameters: dew point temperature, accumulated condensate inside aircoolers, air temperature, sump water level, gully monitoring. In KWU's BWRs, although the measurement concept has to be slightly changed because of a different design of buildings and components, the same instrumentation will be used. Besides this installed monitoring system, different approaches like acoustic leak detection systems or the application of moisture sensitive instrumentation have been considered. Both systems have been successfully tested.     

中国古代铜镜的穆斯堡尔谱学研究

本文用~(119)Sn穆斯堡尔谱学对中国古代青铜镜进行了研究。发现在铜镜表面锡以Sn~(4+)氧化物状态存在,而在铜镜内部则以Cu-Sn-Pb合金状态存在。铜镜表面是否具有“黑漆古”似与表面层中锡的存在状态无必然联系。由铜镜表面区分层的~(119)Sn内转换电子穆斯堡尔谱的分析可知,锡的存在状态由表面的Sn~(4+)氧化物逐渐过渡到内部的Cu-Sn-Pb合金,但在距离表面的不同深度区域,这两种物相相对含量比的变化速度并不完全相同。     

Determination of the residual stress tensor in textured zirconium alloy by neutron diffraction

Results of neutron diffraction studies of crystallographic texture and residual stress tensor components in cold-worked and annealed cylindrical components made from E-110 zirconium alloy are presented. Those components are used as plugs in the fuel elements of the VVER-type reactors; the resident residual stresses influence the durability and safety of the fuel elements. The experiments were carried out on the neutron diffractometers at Dubna (the IBR-2 pulsed reactor) and Berlin Helmholtz–Zentrum (the BER II research reactor). It is shown that the samples have fiber texture that is changed considerably with annealing. The type I residual stress tensors for both samples were calculated by the BulkPathGEO model. The cold worked component has 136–166 MPa tensile residual stress in the radial direction and zero stress along the axial direction. Residual stress values in the annealed component are close to zero.     

HELIAS 5-B magnet system structure and maintenance concept

Work has been continued on the design study of a 5-fold symmetric HELIAS reactor with increased field. The coil shapes were slightly changed from the straightforwardly upscaled W7-X coils to a better suited reactor configuration providing improved plasma confinement and more space for the blanket. This reactor version is now called “HELIAS 5-B”. The previously presented building block structure was adapted to the new shapes and forces, and was further optimized for better load distribution and reduced number of joints. Simplified panels with only one or two plates each are now used.In addition to the previously presented option to separate the whole torus for good access to the in-vessel components, a blanket maintenance concept based on exchange of 400 large blanket segments simultaneously through five vertical ports was devised. Even though this concept is still at an initial state it can be shown that also in a complex stellarator geometry it is possible to have robots running on rails inside the plasma vessel to transport heavy loads.     

Toward high accuracy in channeling Rutherford backscattering spectrometry analysis

Channeling Rutherford backscattering spectrometry (RBS) has been widely used to quantitatively analyze displacements in monocrystalline solid state thin films. Its accuracy, however, relies on the approach of separating yields contributed by channeled components and by dechanneled components. In this study, efforts have been made to increase accuracy through three major approaches: first, we have considered the stopping power difference between channeled and non-channeled components; second, we have proposed a mathematical formula to describe a smooth transition from single scattering to multiple scattering in describing dechanneling of analyzing beams as a function of displacements; third, we have used an iterative approach to extract yields from dechanneling components without using any predetermined dechanneling cross sections. These novel approaches are expected to increase accuracy in channeling RBS analysis.     

Theoretical Study of High Radon Emanation

Radon emanation coefficients larger than 0.6 have been reported; such large values were unexpected. This led the authors to study how the maximum possible radon emanation coefficient (hereafter referred to as ‘maximum radon emanation probability’) could be determined. Theoretical calculations were repeated in which the grain configuration was changed in order to get the maximum radon emanation probability. Two types of grains were targeted. The first type consisted of two components mixed together; one component was a large amount of mother grains including no radium and the other component was a small amount of very fine grains including radium. For this type, the maximum radon emanation probability was obtained as 0.75. The second type consisted of only one grain component including radium. For this type, the maximum radon emanation probability was 0.625. In both types, the high coefficients were attributed to the extremely small size of the radium-bearing grains. This finding hinted at a possible countermeasure to suppress radon emanation, i.e., sintering at a rather low temperature, which may best be fitted to industries which process naturally occurring radioactive materials (NORM).     

核电站辐照样品抓具抓头部件承载力研究

受辐照监督管在下部堆内构件上固定方式的影响,辐照监督管在取出时,其抽取力数值变化较大。抓具关键承载路径末端上的抓头部件因辐照监督管顶塞尺寸限制,而成为抓具上承载能力最薄弱的部件。为保证安全操作,本文结合设备结构特征,对抓头部件进行了承载分析,获得了抓头部件的极限承载力。根据计算结果和实验验证结果,提出了提高抓爪承载力的优化措施,为同类设备的设计和改进提供经验参考。      

Surface XPS-investigations of tobacco leaves treated with low-temperature plasma

The tobacco leaves were treated with low-temperature plasma in Ar, N2, O2. and air atmospheres at different powers （60-130 W）. The surface-elemental components, their relative contents, and the functional groups of the surface components of the tobacco leaves were determined using XPS （X-ray photoelectron spectroscopy）. The experimental results showed that the percentage of the elements C, N, and O had changed considerably and a large number of polar functional groups containing oxygen atoms were incorporated into the components on the tobacco surfaces. The measurements of the surface contact angle showed that the surface contact angle of the modified tobacco leaves was 0 degree, whereas it was 110 degrees before the plasma treatment. These results indicate that the wettability of the modified tobacco leaves improved dramatically. This work may be significant for future researches on the surface modification of the tobacco leaves.     

Unavailability of components with inspection and repair

A general set of integral equations and solutions have been obtained for the unavailability of standby components. The model uses general failure time, test duration and repair time distributions. Random failures as well as contributions from human testing errors and true demands have been taken into account. Optimal testing/inspection intervals have been obtained for practical inspection policies.     

Fuel for pebble-bed HTRs

More than half a million spherical fuel elements with high-enriched uranium have been manufactured in Germany. Containing high-enriched uranium and thorium oxide fuels, many elements have been successfully tested in MTRs and in AVR under high temperatures.In 1979 the reference fuel cycle was changed to low-enriched uranium fuel. Design specifications both for coated particles and the fuel element were reviewed in the light of previous experience with high-enriched fuel. The LEU qualification programme is well under progress to be completed by 1985/86.