2 快堆混合氧化铀钚燃料研制课题验收总结

“863”计划能源技术领域国际科技合作重点项目——快堆混合氧化铀钚燃料研制课题已按规定要求于2004年年底进行了验收并通过。本课题分成2001年和2002年两期合同执行。本课题的依托课题为国防科工委“十五”核能开发科研课题“MOX燃料元件技术研究”（MixedOXide fuel，简称MOX）。依托课题的最终目标是掌握轻水堆MOX燃料组件生产制造技术。但目前对MOX燃料有迫切需求的是CEFR。CEFR使用的MOX燃料与压水堆MOX燃料在制造技术和工艺方面有许多共同点，但也有较大差别。因此需要充分利用国防科工委核能开发研究项目所开发的技术，加快快堆MOX燃料技术的研究。     

MOX燃料用于压水堆的经济性分析及回收钚的价值测算

我国采取闭式核燃料循环政策,对压水堆乏燃料进行后处理,提取其中的铀钚等可裂变材料制成混合氧化物燃料(MOX)循环再利用。本文基于法国压水堆使用MOX燃料的经验和相关数据,重点从燃料成本本身,对比分析MOX燃料用于压水堆的经济性。在此基础上,按照与替代燃料等价计算的原则,分别对回收钚用于压水堆和快堆的价值进行测算。结果显示,压水堆使用MOX燃料的成本远高于普通UO2燃料,回收钚用于压水堆中的价值为负,在快堆中利用具有较高价值。     

俄罗斯确定MOX燃料的质量标准

俄罗斯的监管机构Rostechnadzor已经确定了混合氧化物（MOX）燃料的质量标准。俄罗斯的目标是在快堆中使用MOX燃料。     

MOX燃料在轻水堆核电站中的应用

目前MOX燃料已成为一种可用于轻水堆核电站成熟的核燃料。简要介绍了国外该领域的发展状况以及MOX燃料对反应堆性能的主要影响和应对措施。探讨了MOX燃料在国内压水堆核电站中的应用问题。     

“文殊”快堆初次装料已到位

2008年12月16日,快增殖原型堆“文殊”的首批燃料由东海研究开发中心核燃料循环工程研究所运往日本原子能研究开发机构（JAEA）快堆研究开发中心。此次运输的燃料为混合氧化物（MOX）燃料,共6件,分别装在3个容器中。     

俄罗斯和日本加强快堆的研发合作

俄罗斯和日本在以下几个方面扩大在快堆研发方面的合作。 —促进在燃料辐照试验中积累数据方面的研发; —关于金属燃料辐照的联合研究; —关于氧化物燃料干法后处理的研究,以及振动填料工艺的研究; —“振动密实”MOX燃料辐照性能的调查; —交流有关氮化物燃料的信息; —举办关于快堆系统的研讨会。俄罗斯和日本加强快堆的研发合作     

混合氧化物燃料是一种有价值的能源

[英国《核能》1996年8月号第253页报道] 自1963年首次利用铀-钚混合氧化物(MOX)燃料以来,法国、德国、瑞士和比利时的电力公司在其轻水堆(LWR)内再循环环已取得成功。此外,日本已确定了钚利用的战略,并正计划本世纪以前在其压水堆(PWR)和沸水堆(BWR)系统中利用MOX燃料。英国、法国、德国和日本的快中于增殖堆(FBR)也一直在使用MOX燃料。尽管     

燃料元件性能分析程序中的燃料热导率模型分析

热导率是燃料元件性能分析程序最重要的参数之一,本文介绍了各国部分性能分析程序的燃料热导率模型,按照MOX和UO2燃料分类,给出了这些性能分析程序热导率模型的计算结果,并进行分析对比,给出了国产快堆性能分析程序的热导率推荐模型。     

混合氧化物燃料应用前景及核燃料循环战略

本文叙述了不同国家在不同核电发展条件下的核燃料循环战略初步考虑,并着重叙述了在快堆商业化进程推迟后所发展的混合氧化物(MOX)燃料的设计、制造技术及定量经济分析的基本情况,并建议我国近期应主要采用中间贮存并配以建造后处理中间试验工厂,为今后的商业后处理厂做好技术准备,同时还要跟踪 MOX 燃料技术。     

日本核循环开发研究帮助俄销毁其核武器拆解的钚

【《日本原子》 1999年 4月号第 10页报道】　日本核循环开发研究所 (JNC)决定 ,就销毁从核武器拆除中得到的钚同俄罗斯进行合作。不久将签订一项协议 ,根据该协议 ,JNC将帮助俄罗斯把功率为 6 0 0 MW的BN- 6 0 0快堆 (FBR)改造成能够装铀、钚混合氧化物 (MOX)燃料的反应堆。届时该快堆将装载由 2 0公斤从核武器拆除中得到的钚制成的 3个 MOX燃料组件。其目的是验证到 2 0 0 3年时在快堆中使用 MOX燃料的可行性。JNC董事会成员 Yamato先生和科技厅(STA)副厅长在 2月 2 3日 JNC主办的国际论坛上解释了该项计划。如果该项目能够…     

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.