核科技图书馆元旦快乐 - 反应堆和核电厂.doc

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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.[001]

H-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. [001]

H-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. [001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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. [001]

H-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. [001]

H-081-011
2005亚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. [001]

H-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. [001]

H-081-013
COREBN：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.[001]

H-081-014
SRAC 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. [001]

H-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.[001]

H-081016
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. [001]

H-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.[001]

H-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.[001]

H-081-019
NSRR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.[001]

H-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[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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. [001]

H-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.[001]

H-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. [001]

H-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.[Rj]// JAEA-Technology-2007-013, 2007, 47p.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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. [001]

H-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.[001]

H-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. [001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-081-045
JRR-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. [001]

H-081-046
JRR-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.[001]

H-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. [001]

H-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 1[R,j]//JAEA-Technology-2007 -021, 2007, 27p. [001]

H-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. [001]

H-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.[001]

H-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.[001]

H-081-052
IBR-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.[001]

H-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. [001]

H-081-054
IBR-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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. [001]

H-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.[001]

H-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. [001]

H-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. [001]

H-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.[001]

H-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. [001]

H-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.[001]
H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-081-070
DIII-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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-200500432, 2005, 22p.[001]

H-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. [001]

H-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.[001]

H-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.[001]

H-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.[001]

H-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.[001]

H-081-082
聚（氯乙烯）γ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 industri