Reactor dosimetry for VVERs RPV lifetime assessment

A state of the art review of Reactor Dosimetry used for reactor pressure vessel irradiation damage assessment and lifetime evaluation of the Russian type VVER reactors is presented. The necessity of prospective studies in Reactor Dosimetry for improvements that will reduce the neutron fluence uncertainty and in this way to substantiate the extension of NPP lifetime is summarized by specialists in Reactor Dosimetry from countries operating VVER reactors such as Russia, Ukraine, Czech Republic, Finland, Hungary, and Bulgaria, together with specialists from Western European countries such as France, Spain, Germany, Belgium, The Netherlands, and UK, operating PWR and BWR type reactors.     

60Coγ辐射剂量场分布理论计算的计算机程序开发

钴源辐照装置的剂量场分布对提高射线利用率和产品辐照质量至关重要，利用Visual Basic编制了辐射剂量场分布计算程序。程序将计算、排源及参数调整独立分开，操作简便，主要适用于3层排列板源结构。程序经过用于本中心板源，辐射剂量场分布的计算结果基本反映了辐射剂量场的实际分布。     

Ratio tests of dosimetry cross-sections for Nb(n,2n)Nb and Au(n,2n)Au to Al(n,α)Na reactions

Cross-section ratios of reaction ⁹³Nb(n,2n)^92mNb and ¹⁹⁷Au(n,2n)¹⁹⁶Au to the standard reaction ²⁷Al(n,α)²⁴Na have been measured in order to test the recently compiled dosimetry files: JENDL Dosimetry File and International Reactor Dosimetry File 1990 (IRDF-90). The experimental results for both reactions were consistent with the calculated ones based on IRDF-90 except for the ⁹³Nb(n,2n)^92mNb above 19 MeV.Both reactions, especially ⁹³Nb(n,2n)^92mNb, were recommended as new neutron monitors above 12 MeV because of their favorable characteristics from the decay-property and cross-section viewpoints.     

Comparison of different LMFBR primary containment codes applied to a benchmark problem

The CONT benchmark calculation exercise is a project sponsored by the Containment Loading and Response Group, a subgroup of the Safety Working Group of the Fast Reactor Coordinating Committee — CEC. A full-size typical pool-type LMFBR undergoing a postulated Core Disruptive Accident (CDA) has been defined by Belgonucleaire-Brussels under a study contract financed by the CEC and has been submitted to seven containment code calculations. The results of these calculations are presented and discussed in this paper.     

热释光测量法在空间辐射剂量学中的应用

空间电离辐射是带电粒子辐射,为了保障人类航天活动的辐射安全,空间辐射剂量学得到了很大的发展。热释光测量法已被证明是空间辐射剂量不研究的优选方法之一,它广泛应用于国内外航天器舱内累积剂量的测量。其中,氟化锂已成为必用的热释光探测器。研究其质子响应特性的发光量与空间剂量的关系是将氟化锂应用于空间要作的重要工作。本文介绍了国外应用情况和自己的工作。     

Variation in patient dose due to differences in calibration and dosimetry protocols

For precise and accurate patient dose delivery,the dosimetry system must be calibrated properly according to the recommendations of standard dosimetry protocols such as TG-51 and TRS-398. However, the dosimetry protocol followed by a calibration laboratory is usually different from the protocols that are followed by different clinics, which may result in variations in the patient dose.Our prime objective in this study was to investigate the effect of the two protocols on dosimetry measurements.Dose measurements were performed for a Co-60 teletherapy unit and a high-energy Varian linear accelerator with 6 and 15 MV photon and 6, 9, 12, and 15 MeV electron beams, following the recommendations and procedures of the AAPM TG-51 and IAEA TRS-398 dosimetry protocols. The dosimetry systems used for this study were calibrated in a Co-60 radiation beam at the Secondary Standard Dosimetry Laboratory(SSDL) PINSTECH,Pakistan, following the IAEA TRS-398 protocol. The ratio of the measured absorbed doses to water in clinical setting,D_w(TG-51/TRS-398), was 0.999 and 0.997 for 6 and15 MV photon beams,whereas these ratios were 1.013,1.009, 1.003, and 1.000 for 6, 9, 12, and 15 MeV electron beams, respectively. This difference in the absorbed dosesto-water D_w ratio may be attributed mainly due to beam quality(K_Q) and ion recombination correction factor.     

CFETR第一壁及赤道面外包层中子辐照损伤初步分析

中国聚变工程实验堆(Chinese Fusion Engineering Testing Reactor,CFETR)的包层和偏滤器第一壁面向堆芯等离子体,第一壁辐照损伤分析对于托克马克安全运行至关重要。赤道面外包层较其它包层距离堆芯等离子体中心更近,其结构材料承受中子辐照大。因此,进行中子辐照损伤评估十分必要。基于此目的,采用计算机辅助设计(Computer Aided Design,CAD)模型和蒙特卡罗中子学建模转换接口Mc CAD完成中子学建模,并用蒙特卡罗方法的粒子输运程序计算第一壁和氦冷固态外包层结构材料辐照损伤。此外,对比了铍和钨作为面向等离子体材料两种情况下第一壁的受损情况。计算结果表明,氦冷固态包层模型下结构材料可以满足CFETR一期的运行要求。     

反应堆堆外中子剂量测量技术试验验证

堆外中子剂量测量技术在反应堆压力容器辐照监督中有广泛的应用。本文介绍了在国内某试验堆上进行的堆外中子剂量测量技术验证试验及其结果。比较了堆外中子剂量测量所用探测片活度的理论计算值、实测值及解谱计算结果,同时分析对比了试验中各辐照位置处中子能谱的理论计算值及解谱结果。结果表明,基于测量值的解谱结果与理论计算结果符合良好。堆外中子剂量测量技术可以有效完成中子能谱测量。     

辐射测量仪器的进展

本文对在 IRPA-1 0上发表的近千篇论文中专门论述辐射测量仪器方面的文章做了简要介绍。主要包括以下几个方面 :电子个人剂量仪 ,中子剂量仪 ,塑料闪烁纤维辐射探测器 ,氡子体监测仪 ,环境监测仪器及热释光剂量计等。     

聚变实验堆ITER实验包层瞬态热工安全分析

在中国向ITER(International Thermonuclear Experiment Reactor)实验包层工作组提交的双功能锂铅实验包层模块(DFLL-TBM)设计分析的基础上,通过对DFLL-TBM系统相关的瞬态事故如真空室内部冷却剂泄漏、TBM(实验包层模块)内部冷却剂泄漏以及真空室外部冷却剂泄漏事故进行计算分析,评价DFLL-TBM对ITER在热工方面对安全的影响.结果表明:当发生瞬态事故时,DFLL-TBM有能力通过热辐射将余热排出,且包层结构不会熔化.DFLL-TBM可满足ITER在热工方面对安全的要求.     

细胞遗传学技术在辐射生物剂量估算中的应用

细胞遗传学技术作为生物剂量测定方法,已在生物剂量估算特别是急性照射剂量估算方面得到广泛应用和验证。本文重点综述染色体畸变、微核、早熟染色体凝集作为生物剂量测定方法在剂量估算应用中的优缺点,扼要介绍近年来发展起来的一些分子生物学指标用作生物计量估算的进展。     

压水堆核电厂反应堆压力容器辐照脆化评价与监督

反应堆压力容器是压水堆核电厂的核心关键设备,受快中子(E1MeV)辐照造成的辐照脆化是其运行失效的重要因素,因此需要对压力容器进行辐照评价与监督,以保证其寿期内的安全运行。     

Production of a "Standard" Radiation Environment to Minimize Dosimetry Errors in Flash X-Ray Parts Testing

Calculations have been performed to indicate the effects of differing device caps and of spectrum filtration on dosimetry errors in flash x-ray parts testing. Dosimetry typically used for upset or latch-up testing of microelectronic devices with flash x-ray sources can be in error by 300% or more due to interface dose enhancement effects. When the use of spectrum hardening is permissible, placing the device to be irradiated within a Pb/Ta box can reduce the dosimetry errors to less than 20% in most cases. Obtaining the interface dose enhancement factor by using the experimentally obtained ratio of effects on devices behind Kovar/Au caps to effects measured using alumina caps is shown to give erroneous results.     

西安脉冲堆大空间中子辐照实验平台辐射场参数测量

西安脉冲堆于2010年建成了大空间中子辐照实验平台。本文介绍了该实验平台辐射场设计参数、辐射场测量方法和实测结果。采用蒙特卡罗方法计算了实验平台内中子初始谱。利用多箔活化法测量了中子能谱,解谱方法采用遗传算法,并与SAND-Ⅱ解谱方法进行了对比,对比结果较为一致,证明了遗传算法解谱的有效性。应用热释光剂量计测量了γ射线吸收剂量率。测量结果表明,该实验平台辐射场参数符合设计要求。     

Neutron interactions and atomic recoil spectra

This paper presents a discussion of neutron interactions with materials that lead to activation, transmutation, and atomic displacements. The emphasis will be on current applications including neutron irradiation facilities, neutron dosimetry techniques, and computer codes for spectral adjustment and radiation damage calculations.     

测量反应堆快中子注量率的电流型宽禁带半导体探测器设计

为解决强流混合场快中子注量率实时测量的难题,本文基于反冲质子法,以耐辐照性能强、噪声低的半绝缘型（SI）GaN半导体材料为基础,采用带石墨平衡体及聚乙烯转换靶的并联结构,设计补偿式电流型探测器的方案,有效地降低了γ射线灵敏度。利用该探测器测量了西安脉冲堆1#径向孔道内混合场的快中子注量率,其结果与已有测量结果符合较好,验证了该方案的可行性。     

10-50kV X射线水吸收剂量的测量与研究

X射线水吸收剂量是辐射剂量学的重要物理量,它的精确测量在放射治疗中至关重要。开展低能X射线水吸收剂量的研究与测量,可为完善水吸收剂量溯源体系及扩宽计量部门校准范围提供重要技术支持。确定低能X射线水吸收剂量的测量方法,在辐射场中使用PTW23344电离室对10-50 k V的治疗水平辐射质下的X射线水吸收剂量进行了测量。最终得到了电离室的水吸收剂量刻度因子N_D以及厚度为6 cm有机玻璃前表面的水吸收剂量D_W。本项工作为建立国内X射线水吸收剂量标准及进行国际比对提供了条件和基础。     

200 MeV以下光子诱发50,51V核反应数据理论计算

光核反应数据在辐射损伤、反应堆剂量、加速器屏蔽等方面有重要应用。本工作基于MEND-G程序,对200 MeV能量范围内光子诱发^50,51V核反应数据进行理论计算,给出包含中子、质子、⁴He等主要出射粒子的核反应的数据;对光子诱发V同位素核反应的实验测量进行自洽性分析,结合光子强度函数和准氘模型,将光核反应吸收截面计算能力提升到200 MeV,为光核反应理论计算提供数据基础。经系统比对,理论计算值与实验测量值一致性很好,数据收录在即将发布的CENDL-3.2光核子数据库中。     

主动式电离辐射剂量仪的脉冲X射线响应特性研究

国际上对于辐射防护剂量学的研究主要针对连续辐射,然而脉冲式电离辐射在工业探伤、X射线诊断、闪光X射线照相技术、安检和科研等领域中得到了广泛应用。主动式电离辐射剂量仪采用稳态辐射场进行刻度,难以准确测量短脉冲、高剂量率的脉冲式电离辐射。为了解主动式电离辐射剂量仪的脉冲响应特性,基于毫秒级脉冲X射线机搭建脉冲X射线参考辐射场,针对常用4款主动式剂量仪开展脉冲X射线响应特性测试。测试结果表明,目前常用4款主动式剂量仪均不适用于短脉冲、高剂量率辐射场的剂量测量和预警。