反应堆和核电厂H.doc

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