被动积分测220Rn技术中222Rn的甄别方法

提出了在ＣＲ－３９ＳＳＮＴＤ受照面加一定厚度的吸收体甄别掉氡，从而实现直接被动积分测量钍射气水平的方法，这种甄别掉氡的方法会降低测钍射气灵敏度，但通过采样小室加静电场的方法可以将测钍射气灵敏度大大提高。     

国产与美国CR－39固体径迹探测器探测中子性能的比较研究

用Ａｍ—Ｂｅ中子源照射国产ＳＹ－２型ＣＲ－３９与美国ＣＲ—３９固体径过探测器，在蚀刻时间较短时，测量它们表面径迹密度与蚀刻时间的变化，求得单位质量ＣＲ－３９中可蚀刻径迹数目，并在蚀刻时间较长时，测量两种ＣＲ－３９表面径迹密度的饱和值，对两种ＣＲ—３９探测器进行对比。测量表明，国产ＳＹ—２型ＣＲ—３９与美国ＣＲ－３９探测快中子的灵敏度在误差范围内符合，它们具有相同的快中子灵敏度。     

NASOPHARYNGEAL CARCINOMA RADIOSENSITIVITY PREDICTION BY CYTOKINESIS－BLOCK MICRONUCLEUS ASSAY

ＮＡＳＯＰＨＡＲＹＮＧＥＡＬ　ＣＡＲＣＩＮＯＭＡ　ＲＡＤＩＯＳＥＮＳＩＴＩＶＩＴＹ　ＰＲＥＤＩＣＴＩＯＮ　ＢＹ　ＣＹＴＯＫＩＮＥＳＩＳ－ＢＬＯＣＫ　ＭＩＣＲＯＮＵＣＬＥＵＳ　ＡＳＳＡＹＹａｎｇＸｉｎｇ（杨星）；ＳｈｉＪｉａｎｈｕｉ（史剑慧）ａｎｄＣｈ...     

MONTE CARLO CALCULATION FOR CALIBRATION FUNCTIONS IN TOTAL REFLECTION X－RAY FLUORESCENCE SPECTROMETR

ＭＯＮＴＥ　ＣＡＲＬＯ　ＣＡＬＣＵＬＡＴＩＯＮ　ＦＯＲ　ＣＡＬＩＢＲＡＴＩＯＮ　ＦＵＮＣＴＩＯＮＳ　ＩＮ　ＴＯＴＡＬ　ＲＥＦＬＥＣＴＩＯＮ　Ｘ－ＲＡＹ　ＦＬＵＯＲＥＳＣＥＮＣＥ　ＳＰＥＣＴＲＯＭＥＴＲＹＦａｎＱｉｎｍｉｎ（范钦敏）；ＬｉｕＹａｗｅｎ（...     

A PHOTOEMISSIVE MONOENERGETIC ELECTRON SOURCE FOR CALIBRATING THE BETA－MAGNETIC SPECTROMETER

ＡＰＨＯＴＯＥＭＩＳＳＩＶＥＭＯＮＯＥＮＥＲＧＥＴＩＣＥＬＥＣＴＲＯＮＳＯＵＲＣＥＦＯＲＣＡＬＩＢＲＡＴＩＮＧＴＨＥＢＥＴＡ－ＭＡＧＮＥＴＩＣＳＰＥＣＴＲＯＭＥＴＥＲ￥ＣｈｅｎＺｈｉｃａｉ（陈志才）；ＳｕｎＨａｎｃｈｅｎｇ（孙汉城）ａｎｄＭａｏＹａｊ...     

STUDIES ON RADIATION INDUCED CROSSLINKING OF CIS 1，4－POLYBUTADIENE BY ~（13）C NMR

ＳＴＵＤＩＥＳ　ＯＮ　ＲＡＤＩＡＴＩＯＮ　ＩＮＤＵＣＥＤ　ＣＲＯＳＳＬＩＮＫＩＮＧ　ＯＦ　ＣＩＳ　１，４－ＰＯＬＹＢＵＴＡＤＩＥＮＥ　ＢＹ　~（１３）Ｃ　ＮＭＲＺｈａｏＸｉｎ；ＤｕＹｏｕｒｕａｎｄＹｅＣｈａｎｈｕｉ（ＬａｂｏｒａｔｏｒｙｏｆＭａｇｎｅ?..     

EFFECTS OF e－e INTERACTION ON LATTICE DISTORTIONS AND ELECTRONIC STRUCTURES OF ELECTRON OR HOLE DOPEDC_(60)

ＥＦＦＥＣＴＳＯＦｅ－ｅＩＮＴＥＲＡＣＴＩＯＮＯＮＬＡＴＴＩＣＥＤＩＳＴＯＲＴＩＯＮＳＡＮＤＥＬＥＣＴＲＯＮＩＣＳＴＲＵＣＴＵＲＥＳＯＦＥＬＥＣＴＲＯＮＯＲＨＯＬＥ　ＤＯＰＥＤＣ_(６０)ＣｕｉＹｕｎｌｏｎｇ（崔云龙）ａｎｄＬｉｎＳｅｎｈａｏ（林森浩）?..     

加速器电磁元件设计微机软件库的初步研制

描述了加速器电磁元件设计的微机软件库初步研制工作,包括ＰＯＩＳＳＯＮ／ＳＵＰＥＲＦＩＳＨ、ＲＥ－ＬＡＸ３Ｄ、ＴＲＡＮＳＰＯＲＴ、ＲＡＹＴＲＡＣＥ、ＭＡＤ、ＰＡＲＭＥＬＡ系统软件和软件包括移植、开发、以及自行开发的软件ＤＥ２Ｄ、ＤＥ３Ｄ、ＣＹＣＣＡＥ、ＣＹＣＣＥＮ的整理工作。介绍了这些软件在一定实际工程中的应用情况。     

地那米加速器自动控制系统

介绍了地那米加速器的一种自动控制系统，可编程序控制采用ＯＭＲＯＮ－Ｃ２００Ｈ，其软件用ＯＭＲＯＮ－ＬＳＳ２０００。微机采用ＰＡＲＡＧＯＮ５００软件，该系统简单可靠，特别适用于工厂环境运行。     

STUDY ON OCCURENCE FORM OF PLATINUM IN XINJIE Cu－Pt DEPOSIT BY NAA AND SCANNING PROTON MICROPROBE

ＳＴＵＤＹＯＮＯＣＣＵＲＥＮＣＥＦＯＲＭＯＦＰＬＡＴＩＮＵＭＩＮＸＩＮＪＩＥＣｕ－ＰｔＤＥＰＯＳＩＴＢＹＮＡＡＡＮＤＳＣＡＮＮＩＮＧＰＲＯＴＯＮＭＩＣＲＯＰＲＯＢＥＬｉＸｉａｏｌｉｎ，ＺｈｕＪｉｅｑｉｎｇ，ＧｕＹｉｎｇｍｅｉ，ｗｕＸｉａｎＫａｎｇ（Ｓ...     

固体核径迹探测器在中子辐射监测中的应用

介绍固体核径迹探测器近年来在中子辐射监测中的主要进展,其中包括发现CR-39径迹探测器及其主要性能,以及监测中子剂量的方法与应用。     

空间重离子的鉴别

采用地面加速的重离子模拟空间重离子标定了CR－39固体核径迹探测器，通过物理分析和计算方法获得了一个数学表达式，这样就可以通过CR－39固体核径迹探测器上径迹的测量进行离子鉴别和能量估计。     

Application of CR-39 Track Detector to Neutron Spectrum Measurement

A new technique for estimating the neutron energy spectrum with CR-39 track detectors has been proposed for application to a singly pulsed neutron field where prevailing counters cannot operate properly. The CR-39 sample exposed to neutrons was intermittently etched, then the major and minor radii of respective etch pits were measured for each etching stage and the growth curve was obtained. The analysis method of growth curves was also designed, with which both the energy and the angle of recoil protons could be evaluated and converted into the energy of neutrons incident normally.

The neutron irradiation experiments were carried out with the 46 MeV electron linear accelerator at the Research Reactor Institute, Kyoto University. It was confirmed from comparing with the reference spectrum measured by the neutron time-of-flight method that the present growth-curve method is useful for the estimation of the neutron energy distribution between about 0.3 and 2 MeV. Moreover, we have experimentally examined the unfolding method suggested by Matiullah and Durrani in order to extend the application of CR-39 detector to higher energies.     

测量CR39径迹参数求解中子源能谱

通过测量中子在ＣＲ３９固体核径迹探测器中形成的垂直迹参数来测量中子源快中子能谱，提出了蚀刻厚度修正系统的新概念，解决了特征参数和的求解问题，使ＣＲ３９探测器用来探测快子中能谱由设想变为现实。     

Comparison of photoneutron yield from beryllium irradiated with bremsstrahlung radiation of different peak energy

In an effort to set up microtron based photoneutron source and in order to optimize the neutron yield, photoneutron production from beryllium has been studied for different volumes of beryllium irradiated by different peak energy bremsstrahlung radiation. The theoretical estimation of neutron yield has been carried out using the MCNP simulation for 8.75, 8.15 and 7.58 MeV peak energy of bremsstrahlung radiation. The experimental measurements were carried out using two types of detectors: SSNTD CR-39 and custom designed Silver wrapped GM detector. The neutron yield corresponding to beryllium of volume 381.70 cm³ are found to be 2.13E+09, 2.00E+09 and 1.74E09 n/s (MCNP calculation values) for electrons of energy 8.75, 8.17 and 7.48 MeV, respectively. The experimental results are compared with the MCNP simulated results and are good agreement.     

微型反应堆裂变率分布实验研究

利用固体径迹探测器测量处于微型反应堆不同益的燃料元件内单位体积的裂变率，得到了堆的裂变经分布和总裂变率，并与其它参数相结合求得了反应堆功率。同时，测量了对应功率下反应堆内辐照座的热中子通量密度得到单位功率的热中子能量密度，即额定中子能量密度下的运行功率。文章给出的测量方法，避免了金箔法测量反应堆功率所引入的近似假设。     

CR-39对各向同性中子的能量响应研究

建立了由聚乙烯、铅和CR-39组成的叠层探测器探测各向同性中子能谱模型,计算了叠层探测器对各向同性中子的能量响应以及叠层探测器的能量分辨率。计算结果表明,叠层探测器的响应和能量分辨率与中子能量、聚乙烯以及铅衰减层厚度有关。聚乙烯厚度不变,响应峰值和能量分辨率随铅的厚度增加而变小：铅的厚度不变,响应峰值和能量分辨率随聚乙烯厚度增加而变大,且响应函数形状改变。     

用CR－39探测器测量有氡泉洗浴间房屋内氡浓度

用ＣＲ－３９固体核径迹探测器测量带有氡泉洗浴间房屋内氧浓度，同时测量了疗养院医护人员办公室和住宅内氡浓度，估算了氡暴露所致患者和医护人员的辐射剂量，探讨了有关防护问题。     

Neutron Dosimetry with Boron-Doped CR-39 Plastic

As a highly sensitive, simple and non-radioactive neutron dosimeter, CR-39 plastic plates doped with a boron compound: ortho-carborane were prepared. After thermal neutron irradiation, the plates were etched in an aqueous solution of 30%KOH, at 60°C for 2 to 16 h. The etch-pits generated by ¹⁰B(n, α)⁷Li reactions were then counted using an optical microscope or an automatic track counting system. The density of the etch-pits on an irradiated plate increases with the etching time. When the etching time is kept constant, the etch-pit density is proportional to the irradiated thermal neutron fluence. The proportional constant is termed “sensitivity”, which is 4.2 x 10^?4 for a plate containing ortho-carborane at a concentration of 0.5% by weight and for etching time of 16 h. By considering background counts, a thermal neutron dose of 0.025 mSv can be measured with this plate. The plates are insensitive to visible-, UV-, X-, β- and γ-rays and are easy to handle because the detector and converter are incorporated. There is no possibility of underestimating the dose equivalent due to fading. Furthermore, the isotopes of boron are not radioactive and thus are radio- logically safe.