元件破损实时监测与分析中裂变产物光子能量的选择

计算了不同裂变产物的主要γ光子对φ７６．２ｍｍ×７６．２ｍｍ ＮａＩ探测器光电峰的相对探测效率。结果表明，在燃料元件破损监测中，光电效应计数率最高的几种光子能量与核素是８１ｋｅＶ（＾１３３Ｘｅ）、１９６．３ｋｅＶ（＾８８Ｋｒ）、２２０．９ｋｅＶ（＾８９Ｋｒ）、２４９．８ｋｅＶ（＾１３５Ｘｅ）、４０２．６ｋｅＶ（＾８７Ｋｒ）和５２９．８ｋｅＶ（＾１３３Ｉ）。由于活化产物γ辐射的干扰，监测用γ光子的能     

用γ能谱分析法作元件破损实时监测中的影响因素

本文对用γ能谱分析法反应堆燃料元件破损实时监测中的影响因素进行了分析，干扰监测的主要因素为由＾１９Ｏ和＾１６Ｎ产生的γ光子，活化腐蚀产物的γ辐射，湮灭辐射以及ＮａＩ探测器周围铅屏蔽上由高能γ产生的ＰｂＸ射线，在一座压水反应堆的两次故障排除工作中，作者利用上述分析结果，对实时监测中产生的异常情况作了正确分析，并正确报判断了反应堆内元件的安全性。     

14MeV中子在φ600mm贫化铀球中造钚率测量

使用中子活化技术对２３８Ｕ（ｎ，γ）２３９Ｕ反应产物２３９Ｕ衰变后的２３９Ｎｐ子体的２７８ｋｅＶγ射线的绝对测量，获得了１４ＭｅＶ中子在６００ｍｍ贫化铀球中的造钚率。其实验测量值为２．４６±０．０９。２７８ｋｅＶγ射线用高纯锗探测器测量，探测器的有效计数效率用２４３Ａｍ源刻度。６００ｍｍ贫化铀球由７层贫化铀球壳组成，球心有一８０ｍｍ源腔，总重约２．１ｔ。     

碘化汞探测器的研制进展

使用片状法生长ＨｇＩ２单晶片制砀２０ｍｍ２×０．４ｍｍ探测器在常温下对５９．５ｋｅＶγ射线和５．９ｋｅＶＸ射线的能量分辨率分别为１．９ｋｅＶ和９００ｅＶ。已用于Ｃｕ、Ｐｂ、Ｚｎ等矿样分析，取得了新结果。     

乏燃料后处理溶液中U,Pu的^57Co原激发K—XRF分析

自制一套＾３７Ｃｏ源激发与Ｋ系Ｘ射线荧光（Ｋ－ＸＲＦ）分析系统，用＾３７Ｃｏ的ｋｅＶγ射线激发工艺溶液中Ｕ，Ｐｕ的Ｋ系Ｘ射线荧光，用ＨＰＧｅ探测器－多道微机分析系统进行测量，并以１２２ｋｅＶγ射线康昔顿散射线为内标，建立强度比－浓度校正曲线，快速同地测定了ＰＷＲ乏燃料后处理工艺溶液中Ｕ，Ｐｕ浓度，测定范围为０．５－２００ｇ／Ｌ，精密度为５．０％－１．５％。方法适于ＰＷＲ乏燃料后处理工艺中，Ｕ，Ｐｕ     

碘化汞半导体探测器的能量分辨率

介绍了ＨｇＩ２晶体的生长方法及探测器制备技术，讨论了ＨｇＩ２半导体探测器的能量分辨率，测得ＨｇＩ２探测器在室温玻地＾５５Ｆｅ５．９ｋｅＶ和＾２４１Ａｍ５９．５ｋｅＶＡ射线的能量分辨率分别为１．３ｋｅＶ和３．４ｋｅＶ。     

^75Se和^113Sn的KX射线发射几率测量

用＾５４Ｍｎ、＾５７Ｃｏ、＾６５Ｚｎ、＾８５Ｓｒ、＾１０９Ｃｄ、＾１３７Ｃｓ等核素发射的ＫＸ射线和Ｉ（ＫＸ）／Ｉ（γ）比值法在５￣４０ｋｅＶ范围内对Ｓｉ（Ｌｉ）探测器的效率进行了刻度（不确定度小于２％）。在此基础上,用Ｓｉ（Ｌｉ）Ｘ射线谱仪系统和ＨＰＧｅγ射线谱仪系统对核素＾７５Ｓｅ和＾１１３Ｓｎ的主γ射线和ＫＸ射线进行了测量,获得了＾７５Ｓｅ和＾１１３Ｓｎ的ＫＸ射线发射几率,并与文献报道值进行了     

乏燃料后处理溶液中U、Pu的~(57)Co源激发K-XRF分析

自制一套５７Ｃｏ源激发Ｋ系Ｘ射线荧光（Ｋ－ＸＲＦ）分析系统。用５７Ｃｏ的１２２ｋｅＶγ射线激发工艺溶液中Ｕ、Ｐｕ的Ｋ系Ｘ射线荧光，用ＨＰＧｅ探测器－多道微机分析系统进行测量，并以１２２ｋｅＶγ射线康普顿散射线为内标，建立强度比－浓度校正曲线，快速无损地测定ＰＷＲ乏燃料后处理工艺溶液中Ｕ、Ｐｕ浓度。测定范围为０．５—２００ｇ／Ｌ，精密度为５．０％—１．５％。方法适于ＰＷＲ乏燃料后处理工艺中Ｕ、Ｐｕ浓度的快速控制分析或在线分析。在同时应用５７Ｃｏ透射源的情况下，精密度达０．５％，方法适于核燃料衡算分析。     

HPGe低本底反康普顿γ谱仪

本文报道了以ＨＰＧｅ为主探测器的低本底反康普顿γ谱仪，该谱仪以环形和圆柱形ＮａＩ（ＴＩ）组成阱型反符合屏蔽探测器，以钢，铅及不锈钢等材料组成复合结构屏蔽室。对＾４０Ｃｏ１３３２．５ｋｅＶγ射线，ＨＰＧｅ主探测器能量分辨率为１．８６ｋｅＶ，相对效率为３８％，在阱型反符合屏蔽条件下，谱仪对＾１３７Ｃｓ点状薄膜源测得康普顿抑制系数为４．４；峰康比为８７０：１；５０￣２０００ｋｅＶ能区内每ｍｉｎ积分本底为     

186W(d,2n)186Re反应制备无载体186Re

１８６Ｒｅ的半衰期为９０．６ｈ,β~－粒子能量中等（最大能量为１．０７ＭｅＶ）,伴随发射可用于显像的１３７ｋｅＶ（９．２％）的γ射线。就核性质而言,１８６Ｒｅ最适宜标记单抗［１］,但遗憾的是,目前市场上可以获得的均为由反应堆生产的有载体中等比活度的１?..     

A Well-Type Ge(Li) Detector

The feasibility and usefulness of a coaxial Ge(Li) spectrometer as a well-type detector for sum spectra of coincident gamma rays is demonstrated. The value of the welltype geometry has previously been established in nuclear gamma spectroscopy with the use of (NaI(Tl) detectors. In this work a 16 cm3 hollow cylindrical germaniun detector has been made and mounted in such a way that access to the center of the detector is achieved from outside the cryostat. The detector is a fully depleted structure in which a hole of 1 cm diameter was ultrasonically cut, and a non-injecting contact applied to the inside surface. The measured resolution of the detector for a 1173 keV gamma ray sum peak from 144Pm was 2.6 keV f.w.h.m, which was mainly limited by statistics and preamplifier noise. The detection of sum lines arising from 2 or more coincident gamma rays is demonstrated by using the radioactive source of 144pm. With the source inside the well, for which the counting solid angle is nearly 4?, the sum peak of three lines at 1791 keV (696 + 618 + 477) was observed with an energy resolution of 3.5 keV f.w.h.m, and a peak to background ratio greater than 15:1. For the source outside the detector at a distance of 10 cm, this sum line was not observed above background for comparable counting statistics. Comparison is also made to results obtained from a 3" well-type NaI(Tl) crystal.     

核电厂运行现场高能γ射线的剂量调查

在核电厂正常运行期间,反应堆冷却剂系统内存在能够发射高能γ射线的¹⁶N等放射性核素。为了初步掌握核电厂运行期间不同区域内高能γ射线的辐射水平,利用NaI(Tl)谱仪在国内某核电站测量了反应堆厂房内的γ能谱,并根据γ测量谱和测量系统的响应函数计算了能量大于3 MeV的γ射线的场所剂量率。结果显示:在15个测量位置中,6个位置的γ测量谱中存在明显的高能成分,其对应的剂量率在1.02～30.14 μSv/h范围内。     

~(238)Pu低能光子源衰变γ能谱识别

利用同轴P型高纯锗探测器,对X荧光分析的~(238)Pu低能光子源进行γ能谱分析,并对~(233)Pa、~(224)Ra、~(212)Pb、~(212)Bi及~(208)Tl的特征γ射线进行分析,确定上述核素的来源。其中,~(233)Pa是生产~(238)Pu的原料237 Np的衰变产物,~(224)Ra、~(212)Pb、~(212)Bi及~(208)Tl均为生产~(238)Pu的副产物~(236)Pu的衰变子核。能量为350、440、844、1 014、1 130、1 266、1 368、1 454keV的γ射线是α粒子轰击源封装材料引起原子核库伦激发或γ射线照射周边环境引起核激发产生。进行效率刻度后,使用γ能谱法计算各放射性核素的活度,并根据放射性平衡计算各放射性核素的质量。通过对~(238)Pu源γ能谱的分析,建立计算放射性同位素活度与质量的方法。     

Development of a miniature gamma-ray endoscopic probe for tumorlocalization in nuclear medicine

Two types of miniature gamma-ray endoscopic probes developed for insertion into a body cavity to detect invisibly small or deeply located tumors are described. One is a single detector system using a small BGO (Bi₄Ge₃O₁₂) crystal connected with a fiber optic light guide, and the other is a dual detector system using a pair of single detector probes of the same size combined with a random coincidence technique. The performance of these detectors was tested by using a point source and a hollow cylindrical water phantom that simulated a body cavity. Measured and calculated results indicated that a dual detector system can be used for realistic tumor localization in a body cavity, and a single detector system may be applied only for the detection of tumors in which radiopharmaceuticals that emit gamma rays of energy below about 200 keV are accumulated     

Basic consideration of a nuclear power monitoring system using neutron-induced prompt gamma rays

ABSTRACT

Monitoring only neutron flux in a nuclear reactor core has an advantage of offering reactor power monitoring accuracy. We started the development of a new nuclear instrumentation based on the measurement of prompt gamma rays emitted from metals placed at the neutron flux monitoring positions. The thermal neutron flux at the position of each placed metal piece can be monitored by measuring the prompt gamma rays as the count rate of each energy. The gamma-ray energy range was limited from 6 to 10 MeV to mitigate the interference of environmental gamma rays. Four metals, Ti, V, Ni, and Cu, were chosen as candidates in consideration of their neutron emission rates and self-absorption. In an experiment with a high-purity germanium semiconductor detector, we considered the identification of individual peak energies in an assumed situation where prompt gamma rays were emitted from the four different metals at the same time. Energy resolutions of the peak with the largest energy gap from the nearest energy peak of the other candidate metals were smaller than the gap. Thus, we confirmed that at least one peak for each candidate metal was able to be separated from the peaks derived from other candidate metals.     

Resolution and sensitivity as a function of energy and incident geometry for germanium detectors

The use of modeling programs such as MCNP to predict the response of HPGe detectors is increasing in importance. Accurate simulation of germanium detectors to incident gamma rays relies on knowledge of the performance of the detector in different detector–source geometries. Two important performance parameters are the resolution and sensitivity. The resolution is the FWHM and FW.1M/FWHM ratio. The IEEE 325-1996 standard only specifies the FWHM measurement at one geometry and two energies. Nearly all measurements are made in a different geometry and at other energies. Other investigators [Specifications for Today’s Coaxial HPGe Detectors, 2001 ANS Annual Meeting, Milwaukee, WI; Metzger, private communication, see also: Radionuclide Depth Distribution by Collimated Spectroscopy, 2002 ANS Topical Meeting, Santa Fe, NM], have shown that the sensitivity and resolution change with position of the incident gamma ray on the front of the detector. Such variability has possible implications for the accuracy of peak shape and area determination, since the calibration is potentially a function of angle of incidence. To quantify the sensitivity and resolution variation as a function of energy and point of incidence, measurements have been made on several coaxial detectors of various crystal types and sizes in different source–detector geometries. The full-energy peaks from 59 keV to 2.6 MeV were used. The detectors were placed in a low-background shield to reduce any contribution from external sources. None of the detectors tested was a low-background type. The sources used were an ²⁴¹Am source, ⁶⁰Co source and a natural thorium oxide sample. The ²⁴¹Am 59 keV gamma rays were collimated by a 2 cm thick, 1 mm diameter lead collimator. Several gamma rays from the thorium source were used and collimated by a 10 cm thick and 2 mm diameter tungsten collimator. These collimated sources were used to collect spectra for the incident beam on the front and sides of the detectors. The peak widths were calculated using the methods outlined in IEEE 325-1996. Data are presented to show that the peak shape and sensitivity change with incident beam position and full peak energy.     

Validation of a NaI(Tl) detector's model developed with MCNP-X code

The Monte Carlo method was used to calculate the photon detection efficiency and energy resolution curves for a 1.5″ × 1″ NaI(Tl) scintillator detector (crystal + housing + photomultiplier tube material equivalent) exposed to gamma rays in the energy range from 20 keV to 662 keV. This work aims to design a precise computational model, based in Monte Carlo simulation, which can be used in practical application. The energy resolution curve was used to improve the response of the mathematical simulation of the detector. The detector was modeled with the MCNP-X code and the results were compared to experimental photopeak efficiency measurements of radiation sources. The results showed good agreement with the experimental data.     

闪烁薄膜探测器X/γ射线能量响应研究

为准确评估闪烁薄膜探测器(OSFD)在脉冲裂变中子参数测量中γ射线对测量结果的影响,利用Geant4程序对闪烁薄膜探测器的X（或γ）射线响应进行模拟,结合半经验电子发光效率曲线,获得探测器能量响应理论曲线,利用662 keV和1.25 MeV的单能γ射线源,以及窄谱剂量标准的48~208 keV准单能X射线能点对探测器响应进行刻度。本研究结果为闪烁薄膜探测器结构的改进,以及探测器在宽能谱脉冲X射线场测量中的应用提供了重要依据。     

Detection System for the Fuel Assembly Nondestructive Testing

Fuel assemblies are the central components of a reactor. The core fuel pellets in the fuel pins will swell and deform and the fuel cladding may even break under the complex environment of high temperature, high pressure and intense neutron radiation field, which threats the safety of the reactor. To better understand the changes in the behavior of the fuel assembly in the reactor and study the central void formations and deformations of fuel pins in fuel assemblies to high burn-up, high-energy X-ray non-destructive testing is an effective technical means. Irradiated nuclear fuel assembly has a strong radioactivity, it is necessary to optimize the design of the detector system and the collimator to reduce the effect from gamma rays emitted from the irradiated fuel assembly during detection system designing phase. Through modeling, estimating and optimization, the optimal size of the detector unit is obtained and the collimator design is optimized which can lay the foundation to improve the quality of the reconstructed images of the fuel assembly nondestructive system.     

核燃料组件无损检测探测系统设计

燃料组件是反应堆的核心部分,在高温、高压及强中子辐射场等复杂环境条件下,燃料棒中芯块会出现肿胀、变形甚至包壳破裂,严重威胁反应堆的安全运行。为了更好地了解燃料组件在反应堆内的变化,研究高燃耗的燃料组件中燃料棒的中心空洞形成和燃料棒的变形情况,高能X射线无损检测是一种有效的技术手段。由于辐照后核燃料组件自身具有强放射性,探测系统设计中必须考虑减弱燃料组件自身辐射对探测采集的影响,因此组件探测系统中探测器阵列及准直器的优化设计十分必要。经过建模及相关模拟计算,得到了探测器单元最佳尺寸,优化了后准直器的结构设计,为提高燃料组件无损检测系统重建图像的质量提供帮助。