1一、 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. 0012H-081-0112005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. 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3Behavior 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-m