10 MW高温气冷堆燃料元件的辐照考验

10 MW高温气冷堆燃料元件的辐照考验在俄罗斯IVV-2M堆内进行,辐照考验于2000年7月13日开始,现仍在进行中.至2002年6月14日,燃料元件最高燃耗(以金属铀计,全文同)已达77 000 MW*d/t,累积快中子注量达8.59×1020 cm-2.本文描述辐照样品的冷态性能、辐照装置、辐照条件和已获得的辐照考验结果.     

5MW低功率堆本体结构设计

本文介绍了5MW 低功率反应堆(5MW LPR)本体结构设计的指导思想、材料选择、工艺参数、堆芯布置及结构特点。堆本体是反应堆的核心部分,设计的内容包括燃料元件、控制棒、反射层、辐照管、屏蔽、核测量装置的结构和布置,堆芯支承形式和堆内构件的装配等。     

中国先进研究堆2019年度运行年报

<正>1反应堆运行情况中国先进研究堆(CARR)2019年超额完成年度运行计划,年度累计功率运行58天,最大稳定运行功率约为40MW,总释放能量约为1 233.75MW·d。本年度顺利完成了ITER靶件堆内辐照考核、8#-02靶件辐照任务。反应堆运行过程中还进行8#-01靶件辐照、3#靶件辐照、ALN靶件、中子散射实验装置调试等实验。2异常、故障和事故情况本年度开堆期间发生一次非计划停堆事件。     

世界实验堆现状

【法国《核综论》2000年第6期报道】 1.世界实验堆概况 从1950年初开始,全世界共建造了600多座实验堆,现按它们的用途进行分类: —临界模型(0～150 kW) 用于核反应堆物理教学和动力堆中子计算图的说明。 —初始(启蒙)反应堆(1～5 MW) 用于反应堆物理测量技术、活化分析、某些放射性元素生产、计量测定等。 —多用途反应堆(5～20 MW) 生产核医学用钼-99、半导体用硅嬗变掺杂材料和核发电用材料的辐照。 —辐照反应堆(>20 MW) 核反应堆系列研究(燃料实验)以及强中子流下材料性能。 —中子源(>10 MW) 利用中子束轰击进行基础研究。 —原型…     

10 MW高温气冷堆燃料元件辐照后检验

为了评价10 MW高温气冷堆(HTR-10)用燃料元件的性能,从第1和第2生产批次中分别随机抽取两个球形燃料元件进行辐照考验.辐照考验在俄罗斯的IVV-2M堆内进行,采用动态辐照试验的方法,可分别控制每个辐照盒中燃料元件的温度和测量气态裂变产物的释放.辐照后检验包括外观检查、尺寸测量、固体裂变产物在基体石墨内的分布测量、包覆燃料颗粒破损率测量和金相观察.辐照后检验结果表明辐照没有引起燃料元件中包覆燃料颗粒的破损, 生产的燃料元件满足10 MW高温气冷堆的设计要求.     

印度推进核电厂的建设

【澳大利亚铀信息中心《每周新闻简报》2002年4月5日报道】 印度核动力公司和国家监管机构已批准开始建造库坦库拉姆核电厂,这个核电厂有两个俄罗斯提供的VVER-1000反应堆。 与此同时,政府批准为拉贾斯坦-5号和6号机组投资6.4亿美元,这两个机组是本国的加压重水堆(PHWR),每个堆202 MW而且是标准设计。但是监管机构在今年初决定1972年达临界的拉贾斯坦1号机组应该在4月底关闭。1号机组是加拿大先期投资建造的一个200 MW机组,是在没有援助下 建成的,后来由于技术问题功率下降到90 MW。 盖加核电厂3号和4号机组的202 MW的双堆的建造提…     

重水研究堆(HWRR)2005年度报告

1反应堆运行时间和释放能量反应堆运行功率为6500～7300kW,安全运行4126h,总释放能量为1212.8MW·d。每月运行情况列于表1。2科研生产及检修情况1)辐照同位素388罐;辐照单晶硅4000kg;2)开展中子衍射等物理实验工作;3)第1批(2根)特种靶件达到考验要求并出堆,完成靶件切割,运至25室热室。第2批2根特种靶件入堆辐照考验;4)按计划完成二次循环水系统技改工程土建、设备安装、调试工作,并于12月通过初步验收;5)完成《重水研究堆安全分析报告》(B版)的修订和审查;6)配合国家核安全局对重水研究堆进行的安全再审查工作;7)完成《101堆最终安全停闭…     

5MW低温核供热试验堆三个冬季供热运行总结

5MW低温核供热试验堆(5MW THR)是我们自行研究发展的一种具有固有安全性的先进堆型。它也是世界上第一座投入运行的壳式供热堆。5MW THR于1989年11月建成并投入运行,到目前已完成三个冬季的供暖,总运行时数已达8174小时,供热可利用率达到99％。通过各种实验研究了5MW THR的功率调节特性,负荷跟随特性,反应性扰动特性,以及在ATWS事故时反应堆各种参数的变化规律。三年来的运行实践充分验证了5MW THR的一系列先进技术特点。5MW THR是性能优异的理想供热堆型。     

5MW低功率反应堆（5MW LPR）

本文概括地介绍了5MW LPR 的主要设计参数、设施及特点。本堆主要特点是使用 HFETR的卸料燃料元件,并设置了可对堆内每根元件进行监测的破损监测系统。本堆可进行单晶硅中子辐照掺杂、钼-锝同位素生产及宝石辐照着色等。     

5MW低温核供热试验堆三个冬季供热运行总结

5MW低温核供热试验堆(5MW THR)是我们自行研究发展的一种具有固有安全性的先进堆型。它也是世界上第一座投入运行的壳式供热堆。5MW THR于1989年11月建成并投入运行,到目前已完成三个冬季的供暖,总运行时数已达8174小时,供热可利用率达到99％。通过各种实验研究了5MW THR的功率调节特性,负荷跟随特性,反应性扰动特性,以及在ATWS事故时反应堆各种参数的变化规律。三年来的运行实践充分验证了5MWTHR的一系列先进技术特点。5MW THR是性能优异的理想供热堆型。     

Preparation of Zn/TiO2 powder and its photocatalytic performance for oxidation of P-nitrophenol

Zn-doped TiO2 catalysts were prepared using a sol-gel method and characterized by XPS,UV-Vis, BET, XRD in this study. Under the irradiation of simulant sunlight, the photocatalytic activity for the degradation of p-nitrophenol was studied too. After irradiation for 2.5 h, the degradation percentage of p-nitrophenol could rise to more than 80 %. The results showed that the spectrum absorption band edge of Zn/TiO2 powder does not broaden obviously comparing with pure TiO2 powder. Zinc exists as Zn （11）. When calcined at 973 K, there is a new phase as ZnTiO3 in Zn/TiO2 catalyst. The order of photocatalytic activity of Zn/TiO2 catalysts calcined at different temperatures for p-nitrophenol is 773 K 〉 673 K 〉 873 K 〉 573 K 〉 973 K and the photocatalytic activity of Zn/TiO2 catalyst calcined at 773 K is better than TiO2 catalysts heated at the same temperature, and outclasses that of commercial TiO2 catalyst. It also showed that the photocatalytic degradation of p-nitrophenol follows first-order kinetics under the irradiation of simulant sunlight.     

Current status of radiation therapy for prostate cancer

Radiotherapy for the treatment of prostate cancer has been extensively explored in the past. Along with the comprehensive understanding of the biology of prostate cancer and rapid advances in terms of technology, the out- come of treatment for the patients with prostate cancer has improved. The authors review radiotherapy as the primary treatment for the disease, with particular emphasis on the technological advances from both the radiobiological and radiophysics aspects. Nonconventional fractionated irradiation like hyper- or hypo-fractionation has been imple- mented in the clinic, the final results still need to be confirmed in the future. Technological advances like IMRT, IGRT, in the last two decades have significantly improved the delivery of external radiotherapy to the prostate. This has re- sulted in an overall increase in the total dose that can be safely delivered to the prostate, which has led to modest im- provements in the biochemical outcome. However, establishing the standard therapy for prostate cancer remains con- troversial. It is hoped that the next decades will bring continued advances in the development of biologicals that will further improve current clinical outcomes.     

The control system for SSRF injection and extraction

This paper introduces the injection and extraction control system design for SSRF,which is a distributed control system aimed at stability and reliability of the pulse power supplies,PPS(Personnel Protection System)and MPS(Machine Protection System).The hardware environment is mainly based on PLC(Programmable Logic Con- troller),and ARM(Advanced RISC Machine)is also applied for studying stability of the power supplies.WinCC and EPICS(Experimental Physics and Industrial Control System)have been selected as the platforms of SCADA(Super- visory Control and Data Acquisition).For unifying the interfacing to the control computer,all front-end equipments are connected via Industrial Ethemet.     

水平管内含空气蒸汽强制对流冷凝换热模型研究

为研究含空气蒸汽在水平管内强制对流冷凝换热特性,基于对传热传质过程的分析,建立了管内为环状流与波状流条件下的流动冷凝换热模型。从潜热、显热和液膜3个环节对整个换热过程进行建模,最终得到计算局部冷凝换热系数的理论关系式。模型预测结果与实验数据的对比表明,二者相对偏差在±20%以内,验证了该换热模型的准确性与适用性。通过进一步的研究发现：从换热管入口至出口,随着冷凝的进行,管内换热主要热阻由液膜热阻向气液界面的凝结热阻转变;主流气体对流换热过程基本可忽略。     

Investigations on landmine detection by BF3 detector

Experiments were carried out to investigate the possible use of neutron backscattering for the detection of polyethylene (PE) sample buried in the soil. In detection of landmine by neutrons, the neutron detector and its shield play an important role. In this paper, the effects of graphite, heavy water, polyethylene and boric acid moderators on the flux of back scattered neutrons were investigated. We have also experimentally verified the effect of BF3 detector shield and obtained good agreement with theory.     

Web Services interface of SSRF archive data analysis system

Accelerator database stores various static parameters and real-time data of accelerator. SSRF (Shanghai Synchrotron Radiation Facility) adopts relational database to save the data. We developed a data retrieval system based on XML Web Services for accessing the archive data. It includes a bottom layer interface and an interface applicable for accelerator physics. Client samples exemplifying how to consume the interface are given. The users can browse, retrieve and plot data by the client samples. Also, we give a method to test its stability. The test result and performance are described.     

Assessment of radioactivity levels in some oil samples from the western desert, Egypt

Distributions of natural gamma-emitting radionuclides were determined in 93 oil samples collected from some petroleum fields in the western desert of Egypt. The radioisotope activities in the area under investigation lay in the range of (21 ± 4) to (38 ± 13) Bq?L-1 for 226Ra, (9 ± 2) to (15 ± 5) Bq?L-1 for 232Th, and (154 ± 28) to (303 ± 54) Bq?L-1 for 40K. The mean values were 27, 12, and 201 Bq?L-1, respectively. Among oils, variations in radionuclide ac- tivities could be on account of differences in TDS, HCO3, and Ba, with high or low pH. In this environment, oil prop- erties differently affected the mobilization of natural radionuclides. The range of 226Ra variation had been compared with available data from other countries. The calculated absorbed dose rate ranged from 22.33 to 32.66 nGy?h-1 in lo- cation (B) and (E) respectively, which was less than the accepted value.     

Preparation and properties of 117m Sn(IV)-TTHMP in in-vitro and in small animals

In this work,TTHMP was synthesized and labelled with 117m Sn.The preparation conditions,stability and lipophilicity of 117m Sn(IV)-TTHMP were investigated.Biodistribution of the complex in rabbits and mice was studied.It was found that the quantity of TTHMP and pH value of the prepararion solution had vital effects on the labeling yield of 117m Sn(IV)-TTHMP.It was also found that 117m Sn(IV)-TTHMP was hydrophilic and stable at room temperature and 37℃ in open air 117m Sn(IV)-TTHMP showed unexpectedly high bone uptake and bone-to-blood ratio in the animals.This made it potentially useful as an reagent for skeletal scintigraphy and radiotherapy of bone tumors.     

The role of AGFA high-energy CR in the calibration and quality control of multileaf collimators （MLC）

Linear accelerators equipped with multileaf collimators （MLC） are becoming more common and are widely used in the intensity-modulated radiotherapy （IMRT）. There is an imperative need to ensure the commissioning specification of the linear accelerators for the sake of quality assurance （QA） and quality control （QC）. This paper is aimed to investigate the role of AGFA high-energy CR （Computed Radiography） in calibrating dynamic multileaf collimators and evaluating the accuracy of the leaf position. The result shows that AGFA high-energy CR can easily and conveniently be used to calibrate MLC and verify its position. Hence, the application of AGFA high-energy CR is proved to be an accurate and time-saving method for routine MLC QC, especially when MLC calibration adjustments are required.     

Gamma radiation levels in the ambient environment of the QNPP Base

Monitoring results of gamma dose rate level in 1992～2004 in the ambient environment of the Qinshan Nuclear Power Plants(QNPP)Base,the northeast of Zhejiang Province,are reported in this paper.It is shown that the gamma dose rate of five monitoring sites of 2.5 km to QNPP Base is 84～113 nGy/h,with an average of 96 nGy/h in the 13 years.The average value is close to the background level of 93 nGy/h prior to operation of the QNPP Base,and is lower than the monitoring result of 101 nGy/h at the reference site in Hangzhou City.Within 50 km from the QNPP Base,the cumulative dose rate of the thermoluminescent dosimeter(TLD)is 90 nGy/h,which is lower than the back- ground level of 111 nGy/h.