核科技图书馆元旦快乐 - 反应堆和核电厂.doc

22一、 反应堆和核电厂H-081-001无现场换料的小型堆设计情况Status of small reactor designs without on-site refuelling.R,e/IAEA-TECDOC -1536, 2007, 870p.001H-081-002国际原子能机构成员国脱盐情况Status of nuclear desalination in IAEA member states.R,e/ IAEA- TECDOC-1524, 2007, 80p. 001H-081-003核脱盐的经济学：新发展和特定场址研究（2002-2006年合作研究计划最终结果）Economics of nuclear desalination: new developments and site specific studies. Final results of a coordinated research project 2002-2006.R,e/ IAEA- TECDOC- 1561, 2007, 226p. 001H-081-004模拟轻水堆燃料包壳在失水事故条件下的行为的实验数据评论Review of experimental data for modeling LWR fuel cladding behaviour under loss of coolant accident conditions.R,e/ SKI-R-07-14, 2007, 100p.001H-081-005用中子断层X线照相法研究沸水堆燃料棒水膜Investigation of films on fuel rods in boiling water reactor using neutron tomography.R,e/UU-NF-06-05, 2006, 40p.001H-081-006用SRAC编码系统分析MEX-15多用反应堆Analysis of the MEX-15 multipurpose reactor using SRAC code system.R,e/ INIS-MX-RI-1818, 1992, 69p.001H-081-007商用核电厂灵活计算机管理基础发展Development of a flexible computerized management infrastructure for a commercial nuclear power plant.R,e/ DOE/ID-14554, 2006, 33p.001H-081-008固态氢化物燃料在改进长寿命轻水堆堆芯设计中的应用（最终摘要报告）Use of solid hydride fuel for improved long-life LWR core designs. Final summary report.R,e/DOE/SF-22615-1, 2006, 117p.001H-081-009核电站设计特征：国际原子能机构动力堆信息系统中核电站设计特征的结构Nuclear power plant design character istics. Structure of nuclear power plant design characteristics in the IAEA power reactor infor- mation system.R,e/ IAEA-ECDOC- 1544, 2007, 40p. 001H-081-010对安全重要的主要核电厂部件老化的评估及管理：压水堆容器内部部件（2007年更新）Assessment and management of ageing of major nuclear power plant components important to safety: PWR vessel internals: 2007 update.R,e/ IAEA- TECDOC-1557, 2007, 76p. 001H洲核合作论坛研究堆利用专题讨论会会议录Proceeding of the FNCA 2005 workshop on the utilization of research reactors. R,e/JAEA-Conf-2006-010, 2007, 83p. 001H-081-012高温工程试验堆堆芯支持石墨结构监督试验的基本数据Basic data for surveillance test on core support graphite structures for the high temperature engineering test reactor (HTTR).R,j/ JAEA-DATA/ code-2007- 001, 2007, 64p. 001H-081-013COREBN：全面中子学计算编码系统的堆芯燃耗计算模块COREBN: A core burn-up calculation module for SRAC 2006.R,e/JAEA-DATA/ code-2007-003, 2007, 128p.001H-081-014SRAC 2006：全面中子学计算编码系统SRAC 2006: A comprehensive neutronics calculation code system.R,e/ JAEA- DATA/code-2007-004, 2007, 327p. 001H-081-015印度Kakrapar核电站1号机组高燃耗和加压重水堆燃料棒束56504辐照后检查Post-irradiation examination of high burn-up PHWR fuel bundle 56504 from KAPS-1.R,e/BARC-2007/E/002, 2007, 36p.001H-081-016先进重水堆整体试验回路28棒热关闭被动阀的功能及性能评价Functional and performance evaluation of 28 bar hot shutdown passive valve (HSPV) at integral test loop(ITL) for advanced heavy water reactor (AHWR). R,e/BARC-2007/E/003, 2007, 42p. 001H-081-017运行反应堆物理学分析编码Operational reactor physics analysis codes (ORPAC).R,e/BARC-2007/E/008, 2007, 34p.001H-081-018先进轻水堆被动安全系统设计的新改进基础：教育研发项目Providing the basis for innovative improvements in advanced LWR reactor passive safety systems design: an educational R and D project.R,e/ DOE/ID-14500, 2007, 27p.001H-081-019NSRR实验中燃料包壳表面瞬态温度测量研究Study on transient temperature measurement at fuel clad surface in NSRR experiments.R,e/JAEA-Research-2006-083, 47p.001H-081-020采用振动填充燃料及球pac燃料堆芯与燃料设计的影响研究Study on influence to core and fuel design by adopting vibro-packed fuel and sphere-pac fuel.R,j/JAEA- Research-2006-087, 2007, 80p.001H-081-021用外部凝胶化工艺制造燃料微球的发展Development of fuel microspheres fabrication by the external gelation process.R,j/JAEA-Research-2006-088, 2007, 105p.001H-081-022含镅混合氧化物燃料氧/金属比的特性Behavior on O/M ratio for am containing MOX fuel.R,j/ JAEA-Research-2007- 013, 2007, 74p.001H-081-023高温工程试验堆（HTTR）核特性评价方法的改进研究Research on improvement of nuclear characteristic evaluation method for high temperature engineering test reactor (HTTR) (Thesis).R,j/JAEA - Review-2006-038, 2007, 171p.001H-081-024核电厂概率安全评估：内部事件的1级概率安全评估。东京大学工程研究院讲座教科书Probabilistic safety assessment for nuclear power plants: level 1 PSA for internal events. Textbook for lecture in graduate school of engineering in the university of Tokyo.R,j/JAEA- Review -2006-041, 2007, 52p.001H-081-025热实验室的运行及利用年度报告（2005年4月1日至2006年3月31日）Annual report on operation and utilization of hot laboratories. From April 1, 2005 to March 31, 2006.R,j/ JAEA-Review-2007-006, 2007, 97p. 001H-081-026高温工程试验堆无人看管乏燃料流监测核保障系统的研发Development of the unattended speat fuel flow monitoring safeguards system (UFFM) for the high temperature engineering test reactor (HTTR).R,e/JAEA- Technology-2007-003, 2007, 31p.001H-081-027混合氧化物燃料数据库的研发Development of MOX fuel database. R,e /JAEA-Technology-2007-010, 2007, 55p. 001H-081-028环形燃料设计编码CEPTAR的验证：常阳II型驱动燃料辐照数据的验证Verification of annual fuel design code CEPTAR verification with the irradiation data of JOYO MK-II driver fuel.R,j/ JAEA-Technology-2007-013, 2007, 47p.001H-081-029核安全研究堆中反应性引发事故模拟实验的B-I型高压水辐照样品盒的操作手册Handling-manual of B-I type high pressure water capsule for reactivity enitiated accident simulation exper- iment in.R,j/JAEA-Testing- 2007-001, 2007, 70p.001H-081-030未来第4代核系统：未来核系统策略方向建议Nuclear systems of the future- generation 4. proposals of strategic orientations for the nuclear systems of the future.R,f/INIS-FR-6640, 2007, 15p.001H-081-031欧洲核学会信息资料交换2004：第16届国际核通信会议：核明天观点的定义（会刊）ENS PIME 2004: 16th international meeting of nuclear communicators: defining tomorrows vision of nuclear transactions.R,e/INIS-BE-V-002, 2004, 178p.001H-081-032在RB反应堆大中央空气孔道中测定中子通量分布Determination of neutron flux distribution across the RB reactor with large central air hole.R,e/INIS-RS- 1109, 1998, 6p.001H-081-033核电厂安全重要主要部件老化评估及管理：压水堆压力容器（2007年更新）Assessment and management of ageing of major nuclear power plant components important to safety: PWR pressure vessels 2007 update.R,e/IAEA-TECDOC -1556, 2007, 215p.001H-081-034核电及全球能源安全挑战：世界核协会年度座谈会（2007年9月6日，伦敦）Nuclear power and the global challenges of energy security, 6 September 2007 London, England, world nuclear association annual symposium.R,e/ INIS-XA-1014, 2007, 4p.001H-081-035世界应急援助要求的回答：事件及应急中心Answering the request for emergency assistance worldwire. The incident and emergency centre.R,e/INIS-XA-999, 2007, 4p.001H-081-036第1届日本原子能机构/韩国原子能研究所关于高温气冷堆及核氢技术信息交换会议会议录Proceedings of the 1st JAEA/KAERI infor- mation exchange meeting on HTGR and nuclear hydrogen technology.R,e/ JAEA-Conf-2007-005, 2007, 203p.001H-081-037紧密栅格棒束热工-水力学试验数据报告（3）：用37-棒束模拟水冷增殖堆进行棒挠曲效应试验Data report of tight-lattice rod bundle thermal-hydraulic tests (3). Rod-bowing effect test using 37-rod bundle simulated water cooled breeder reactor (Contract research).R,j/JAEA-Data/ Code-2007-011, 2007, 135p.001H-081-038加速器驱动系统功率展平的中子学设计Neutronics design for power flattening of accelerator-driven system.R,j/ JAEA-Research-2007-025, 2007, 50p. 001H-081-039在日本材料试验堆中辐照的惰性基体氮化物燃料（01F-51A辐照盒）的辐照后检验Post-irradiation examinations of inert matrix nitride fuel irradiated in JMTR (01F-51A capsule)R,j/JAEA-Research -2007-026, 2007, 82p.001H-081-040低能水平破裂堆芯池中流动特性的基本研究Fundamental study on flow characteris- tics of disrupted core pool at a low energy level (Joint research).R,e/ JAEA-Research-2007-032, 2007, 56p. 001H-081-041在压水堆具有高压注入故障及聚积注入系统气体进入时容器底部的破裂失水事故时快速减压动作定时研究A study on timing of rapid depressurize- tion action during PWR vessel bottom break-LOCA with HPI failure and AIS-gas inflow (ROSA-V/LSTF test SB-PV-06). R,e/ JAEA-Research-2007-037, 2007, 163p.001H-081-042高温工程试验堆的运行、试验、研究与发展Operation, test, research and develop- ment of the high temperature engineer- ing test reactor (HTTR).R,j/JAEA- Review-2007-017, 2007, 88p.001H-081-043环形燃料概率设计方法的发展：BORNFREE- CEPTAR编码的发展Development of probabilistic design method for annular fuel. Development of BORNFREE-CEPTAR code.R,j/JAEA- Technology-2007-009, 2007, 27p.001H-081-044高温工程试验堆自提升功率试验以来的运行经验Operating experience since rise-to- power test in high temperature engineer- ing test reactor (HTTR).R,e/ JAEA- Technology-2007-014, 2007, 69p.001H-081-045JRR-4堆采用低缩铀硅化物燃料的堆芯特点。初始堆芯及烧过的堆芯Core characteristics of JRR-4 using low- enriched-uranium-silicide-fuel. Initial core and burn-up core.R,j/ JAEA-Technology-2007-017, 2007, 101p. 001H-081-046JRR-4运行实践及反应堆物理实验指南Guidance of operation practice and reactor physics experiments using JRR-4. R,j/JAEA-Technology-2007- 018, 2007, 114p.001H-081-047钚、镅再分布堆芯的发展Development of plutonium and americium redistribution code.R,j/JAEA- Technology-2007-020, 2007, 27p. 001H-081-048用燃气轮机的高温堆300磁轴承支撑涡轮机的振动分析，第1部分Vibrational analysis of magnetic bearing support turbo machine for GTHTR 300, Part 1R,j/JAEA-Technology-2007 -021, 2007, 27p. 001H-081-049高温工程试验堆产氢系统：模型试验设施的结构及主要规格HTTR hydrogen production system. Structure and main specifications of mockup test facility.R,j/JAEA- Technology-2007-022, 2007, 219p. 001H-081-050核安全研究堆中B型辐照盒的发展Development of type-B capsule loader in the NSRR.R,j/JAEA- Technology-2007- 028, 2007, 59p.001H-081-051（文殊快堆）燃料组件发热评价检验Heat evaluation examination of fuel assembly.R,j/ JAEA- Technology-2007 -029, 2007, 85p.001H-081-052IBR-2脉冲堆在不同平均功率水平的稳定性及功率反馈参数的估计Estimation of the parameters of power feedback and stability of the IBR-2 pulsed reactor at different levels of the mean power.R,ru/JINR-R-13- 2006- 101, 2006, 12p.001H-081-053核反应堆安全关键软件审批：欧洲7个核法规团体及授权技术支持组织共同决定Licensing of safety critical software for nuclear reactors. Common position of seven European nuclear regulators and authorized technical support organiza- tions.R,e/NEI-SE-659, 2007, 147p. 001H-081-054IBR-2反应堆产生中子平均寿命测量Measurement of the average lifetime of generation of neutrons at the IBR-2 reactor.R,ru/JINR-R-13-2006-115, 2006, 12p.001H-081-055先进重水堆临界设备通量测绘系统Flux mapping system for AHWR critical facility.R,e/BARC-2007/E/015, 2007, 32p.001H-081-056用WIMS编码对MARIA堆进行中子物理分析的计算不确定性Computational uncertainties in neutron-physics analysis of MARIA reactor using WIMS codes.R,e/IAE- 125/A, 2006, 26p.001H-081-057全球核电现状及展望：国际原子能机构报告Nuclear power worldwide: status and outlook. A report from the IAEA.R,e/ IAEA-PR-2007/19E, 2007, 3p.001H-081-058核动力：不影响气候变化Nuclear power: no solution to climate change.R,e/INIS-AU-0060, 2005, 132p. 001H-081-059京都大学核研究堆设施运行及管理教育资料：运行及管理40年经验The educational document of operation and management for Kyoto-university nuclear research reactor facility. Experience of operation and management for 40years (No.1).R,j/KURRI-TR-436, 2006, 278p.001H-081-060液态钠湍流导致磁场输运Transport of magnetic field by a turbulent flow of liquid sodium.R,e/ CEA-DRECAM-SPEC-S-06-023, 2006, 5p. 001H-081-061欧洲国际核能会议会议录（2006年）Proceedings of the international conference nuclear energy for new Europe 2006.R,e/INIS-SI-07-002, 2006, 13p. 001H-081-062研究堆（JRR-3及JRR-4）利用活动报告Activity report on the utilization of research reactors (JRR-3 and JRR-4) Japanese fiscal year, 2005.R,j/JAEA- Review-2007-018, 2007, 182p.001H-081-063“核知识管理现状及前景”专题讨论会摘要Workshop summary of nuclear knowledge management: present status and perspec- tive.R,j/JAEA-Review-2007-020, 2007, 274p. 001H-081-064医用及工业用极小加速器驱动次临界Highly compact accelerator-driven subcritical assembly for medical and industrial applications.R,e/DOE/ID- 14502, 2006, 89p.001H-081-065用以LIGA为基础的微加工技术改进压水堆整体传热效率：1.不同微图对整体传热的影响Using LIGA based microfabrication to improve overall heat transfer effici- ency of pressurized water reactor: I. effects of different micro pattern on overall heat transfer.R,e/DOE/NA- 27041-1, 2006, 2p.001H-081-066压水堆核电厂一回路冷却剂的化学及放射化学净化的最佳化Contribution to the optimization of the chemical and radiochemical purification of pressuried water nuclear power plants primary coolant.R,f/FRNC-TH-6941, 2004, 305p.001H-081-067轻水堆催化氦复合器实验研究Experimental studies on catalytic hydrogen recombiners for light water reactors.R,de/INIS-DE-0347, 2006, 113p.001H-081-068氢复合器工艺流程模拟Modeling of processes in catalytic recombiners.R,de/INIS-DE-0349, 2007, 136p.001H-081-069核聚变及X射线激光器中激光产生等离子体的X射线光诊断X-ray optical diagnostic of laser produced plasmas for nuclear fusion and X-ray lasers.R,e/INIS-DE-0319, 2001, 124p.001H-081-070DIII-D边缘等离子体、破裂及辐射过程（最终报告）DIII-D edge plasma, disruptions and radiative processes. Final report.R,e /DOE/ER-54294-1, 2001, 92p.001H-081-071从源到靶高强度重离子束的产生、加速、输运及最终聚焦研究Investigation of generation, accelera- tion, transport and final focusing of high-intensity heavy ion beams from sources to targets.R,e/DOE/ER- 54662 -1, 2006, 271p.001H-081-072计算中心对微湍的研究Computational center for studies of microturbulence.R,e/DOE/ER-54675-1, 2006, 3p.001H-081-073磁伯努利实验最终报告Final report of MBX experiment.R,e/ DOE/ER-54697-1, 2007, 3p.001H-081-074输运特别工作组活动最终技术报告Final technical report transport task force activities.R,e/DOE/ER-54707-1, 2006, 19p.001H-081-075通过高功率低成本开关功率放大器先进反馈控制器改进创新约束概念实验性能ICC experiment performance improvement through advanced feedback controllers for high-power low-cost switching power amplifiers.R,e/DOE/ER-84190-1, 2006, 22p.001二、核燃料和核材料H-081-076用离子交换及煅烧法进行铀再循环燃料生产现场铀回收。工艺流程及设备设计摘要Uranium recycle by ion exchange and calcination-summary of process develop- ment and equipment design.R,e /WSRC- TR-2005-00432, 2005, 22p.001H-081-077钚：核装置气溶胶的再悬浮（书目调查）Plutonium: resuspension of aerosols in nuclear installations: bibliographic survey.R,f/CEA-R-6126, 2006, 182p. 001H-081-078偏离理想浓缩锕系元素及镧系元素盐溶液的表征：Bimsa理论的贡献Characterization of the deviation to the ideality of concentrated actinide and lanthanide salt solutions: contribution of the Bimsa theory.R,f/CEA-R-6127, 2006, 130p.001H-081-079用蒙特卡罗法模拟碳化铌在铁素体中的非均匀沉淀Heterogeneous precipitation of niobiun carbide in the ferrite by Monte Carlo simulations.R,f/CEA-R-6129, 2005, 191p.001H-081-080室温离子性液体在乏核燃料后处理中的应用：三价铕的形成和溶剂化效应Application of a room temperature ionic liquid for nuclear spent fuel reprocessing: speciation of trivalent europium and solvatation effects.R,f /CEA-R-6134, 2007, 227p.001H-081-081适用于含锕系元素反应的多金属氧化物合成以及固态溶解结构的溶胶-凝胶化学Sol-gel chemistry applied to the synthesis of polymetallic oxides including actinides reactivity and structure from solution to solid state. R,f/CEA-R-6142, 2006, 189p.001H-081-082聚（氯乙烯）辐解研究：在辐照退化及工业聚氯乙烯浸出研究中的应用Study on the gamma radiolysis of poly (vinyl chloride) application to the study on degradation by irradiation and leaching of industrial PVC.R,f/CEA- R-6145, 2006, 288p.001H-081-083铀浓缩物料处理系统的建设、示范及执行的建议Proposal for construction/ demonstra- tion/ implementation of a material handling system.R,e /DOE/MC-29120/ Rev.A, 2001, 30p.001H-081-084燃耗信用在增强乏燃料运输、贮存、后处理及处置方面的应用进展（技术会议会议录）Advances in applications of burnup credit to enhance spent fuel transporta- tion, storage, reprocessing and disposition. Proceedings of a technical meeting.R,e/IAEA-TECDOC-1547, 2007, 462p.001H-081-085测定铀及钚的国产可控电势库仑计的性能评价Performance evaluation of indigenous controlled potential coulometer for the determination of uranium and plutonium. R,e/BARC-2007/E/012, 2007, 16p. 001H-081-086熔盐混合物中金属离子行为的分子动力学模拟研究Molecular dynamics simulation study on behavior of metallic ion in molten salt mixture bath.R,j/JAEA-Research- 2007-005, 2007, 33p.001H-081-087Vinca核科学研究所乏核反应堆燃料的后处理Reprocessing of spent nuclear reactor fuel in the Vinca institute of nuclear sciences.R,e/INIS-RS-1107, 1998, 8p. 001H-081-088第18届国际铂金属化学、分析学及工艺大会，第1部分（报告摘要）XVIII international cherngaev conference on chemistry, analytics and technology of platinum metals. Summaries of report. Part I.R,ru/ INIS-RU-500, 2006, 252p.001H-081-089第18届国际铂金属化学、分析学及工艺大会，第2部分（报告摘要）XVIII international cherngaev conference on chemistry, analytics and technology of platinum metals. Summaries of report. Part II.R,ru/ INIS-RU-501, 2006, 278p.001H-081-090IAEA/NEA燃料事件通知及分析系统指南IAEA/NEA fuel incident notification and analysis system (FINAS) guidelines.R,e /IAEA-SVS-14, 2006, 57p.001H-081-091镎离子对不锈钢在硝酸溶液中腐蚀的影响Effect of neptunium ions on corrosion of stainless steel in nitric acid solution.R,j/JAEA-Research-2007- 031, 29p.001H-081-092巴巴原子能研究中心分子激光同位素分离计划Molecular laser isotope separation programme at BARC.R,e/BARC-2007/E/ 014, 2007, 31p.H-081-093采矿水处理技术：地球科学应用及发展（会议录）Technologies for treatment of mining water/GIS-geoscientific applications and developments. Proceedings.R,de/ INIS-DE-0342, 2006, 352p.001H-081-094辐射损伤模拟的积极而关键的方法Constructive and critical approach of the radiation damage simulation.R,f /FRNC-TH-6942, 2002, 294p.001H-081-095铀在黄铁矿表面的滞留及还原Retention and reduction of uranium on pyrite surface.R,f/FRNC-TH-6975, 2006, 290p.001H-081-096经典破裂力学方法Classical fracture mechanics methods. R,e/GKSS-2007-14, 2007, 42p.001H-081-097应力腐蚀破裂Stress corrosion cracking.R,e/GKSS- 2007-15, 2007, 32p.001H-081-098澳大利亚的铀（能源短缺世界的无温室效应的燃料）为调查发展澳大利亚非化石燃料能源工业对澳大利亚的铀资源策略重要性的情况研究Australias uranium-greenhouse friendly fuel for an energy hungry world: a case study into the strategic importance of Australias uranium resources for the inquiry into developing Australias non-fossil fuel energy industry.R,e/INIS-AU-0061, 2006, 802p.001H-081-099半导体中由高能离子辐照引起的辐射效应及损伤形成Radiation effects and damage formation in semiconductors due to high-energy ion irradiation.R,e/INIS-DE-0344, 2006, 92p.001H-081-