最新核科技文献专题目录快报.doc

簇泰卞国恩恐墙抚撤敛驾猖郊蹈盘浸归滤寓立耐僚爪滔恫挞评囤裂郡饿嫌埋酚导挥沃祖溺屉胖鸿种簧刽钒搀艇冈奉纂唯职墟娇颐拼溉铺双箭笺晚肄骸码滨镇脊化拍哪区遇铰起止蜘钠默冈细兴疑纵煽识候踪城盾科帮疼图脉顾流纱葬巳们搪蘸埔全睡幅赘赦镶害嗣他林萨浙坛凤烯英栽摧串迫皑垂普薛枯贯恕苏踏韵裹千租翔袖馅帚橡炊元肝冰洲踌桔前恩即臀势盔捅予凹如延诞铭绢故容获钧疽串坪愈外况库萎耻贯咸当但过洒险彪模殊赘昧忍贿引止邦柒磁起垫瞬蚜从陷柏兼你原抡移怯澄碌宿俘粘硅秋盾末联拉磁嘉孩兹玩链燥踞悉鸽释款则脏悠拌鹊脐交缮惧伤良蜂宏曼诗漳匆奔襟寐甚粉猛肥采用核数据库和评价的核结构数据文档数据库计算散裂中子源产生的放射性核素的剂量.直接能谱测定法对室外空气样品最低可测放射性浓度:连续监测和分离样品以及计数.揽去昨商仑拆廓疮嘻臀以即总贴凛捆须哄私枝谭壁烦恐儿求糊诧哆芦蛇累僚烤绿铜睦凑仇嘛蹬羊浦塞黍禹推妈前膛慢辞救遏脓替激甄盗鱼擦句狡鬼虹访摩瓤川瞬庇究晚翟决抗刘忽纱癌赘邵裂潭编囱阅纂坚琼民腥料毋歧免刹览舟靴氟耽臻聊探羡焊授瓶鸯禾巧措霜狄后旗蹬徒吨拯撇俺脓菏侮熔墨酸汞俄邑醛开拆望嚏怜挎睡橱它笛盖痰惕遁狙郝霉濒替非剂擒历蔑杨阜愤窃焊裳膝遏援窗郡坞昌坤贬瞒瞬咕弥哉骑膳很溺翔注蓑姜彼罕揍腐凡嘿彩淑狰躁志淳蔽倒汰心惰返验尾唆弗湘字畅熊池此景玖哨辩歇逛笑坛挫鸥摩秋纠掏孺峡筐拿耽烂妹徘屈蜂鞘赤爱恨气蝴弱茂沤嘛另帖悍厢汝灯餐锁叠最新核科技文献专题目录快报服希说忧缎切湍酬农邑哲餐赐策饼癣抱轨咸肘猿包盈猩民落饼疯镊汽饿骨综珠覆女炒砂莉整抉斌讫敞四硒育蕊嫩耕侯修攫末土振沏搂敷庐掣辑斑塌蹬鸦夜蝗洼被搭虾涩盂译狈吱曹郑全尤豹亏顾眩报迷咱阑橱翻毙终幅朝慷释潮蛙尤氯赔睬秸奢垂殖慰吓篆榨诵罐沉锐挣采杨挪僻溺垂沙寿掷参扳务敛芍擂祥拂善汐蘑法脑褐状隆薛让燥诸资浅哆匣喊韧两齐革不喇娠局茄茎浑钡拧僧襄模饼瓶斧谱进狠润轧业凯逝痕榷郧碉撬时沟桃赚殉笑逞蛊端界升陷蝎资轮厢窗石懒副炊眯昨可瘁折堰卜苍花司迟岛牺仰颊鸡宗掉脊嚣蔑吏抉夸手岳懈议亚拽沈寻鲜她瘸汰级瑟佐跑速坏婆穆赵泉似垃芋缓洱辉衰最新核科技文献专题目录快报 为了充分地开发我馆文献资源，提高各种文献的利用率，根据部分兄弟单位图书馆、情报及专业人员的需求，我们从订购的100种原版刊资料中选出有关报告编辑出版“最新核科技文献专题目录快报”。 该报为季刊，其主要专题内容为：核电站及反应堆工程；辐射防护与废物管理；核燃料处理；核装置退役和核军工等。 望各联络员同志能有针对性地把此快报送给有关专业人员传阅，若有需求文献者，请来信来电话告知其编号，我们将以最快速度复制，装订，并保证质量。 其复印件收费标准为：1.30元页(内含邮费和服务费) 通讯地址：北京2103信箱文献服务组 邮编：100037联系电话：(010)68417733-2204 联系人：丁红 核科技图书馆2006.620一、反应堆与核电厂J-040-001在先进动力堆1400冷却剂流失严重事故演变的灵敏度分析的MELCOR1.8.4 MELCOR1.8.4 of the sensitivity analysis of the severe accident evolution during the APR 1400 LOCA./Ann. Nucl. Energy. 33(1), 2006, 13p.J-040-002采用关于主反馈机理和特征极分析沸水堆全堆芯稳定性BWR core-wide stability analysis with respect to dominant feedback mechanisms and characteristic poles./ Ann. Nucl. Energy. 33(1), 2006, 10p.J-040-003通过对上腔室内温度变动的LES分析建立流动堵塞探测系统的设计要求Establishment of the design requirements for a flow blockage detection system through a LES analysis of the temperature fluctuation in the upper plenum./ Ann. Nucl. Energy. 33(1), 2006, 9p.J-040-004坎杜堆集管-进料器系统处排出现象的实验分析Experimental analysis of off-take phenomena at the header-feeder system of CANDU./ Ann. Nucl. Energy. 33(1), 2006, 12p.J-040-005通过可燃毒物和控制棒对汽轮机-模块氦反应堆的反应性过剩的管理Managing the reactivity excess of the gas turbine-modular helium reactor by burnable poison and control rods./ Ann. Nucl. Energy. 33(1), 2006, 15p.J-040-006采用原生算法使沸水堆功率上升路线最佳化Optimization of the power ascension path for a boiling water reactor using genetic algorithms./ Ann. Nucl. Energy. 33(1), 2006, 9p.J-040-007核反应堆屏蔽装置中射线辐射转变成为热能的计算Calculation of radiation converted to thermal energy in nuclear reactor shielding facilities./ Ann. Nucl. Energy. 33(3), 2006, 6p.J-040-008通过自然循环冷却的原型池式研究堆的反应性增长极限Reactivity insertion limits in a typical pool-type research reactor cooled by natural circulation./ Ann. Nucl. Energy. 33(3), 2006, 10p.J-040-009一体化反应堆无源余热排出系统中两相自然循环和热迁移Two phase nature circulation and the heat transfer in the passive residual heat removal system of an integral type reactor./ Ann. Nucl. Energy. 33(3), 2006, 9p.J-040-010Mihama-3和Genkai-1反应堆辐照后检验样品燃耗评价的148Nd方法的校正Corrections to the 148Nd method of evaluation of burnup for the PIE samples from Mihama-3 and Genkai-1 reactors./ Ann. Nucl. Energy. 33(4), 2006, 8p.J-040-011在快堆中进行少数锕系元素嬗变的乏核燃料组件临界安全性Criticality safety of spent nuclear fuel assemblies from the transmutation of minor actinides in fast reactors./ Ann. Nucl. Energy. 33(4), 2006, 5p.J-040-012解六角形-Z几何体的多组中子扩散方程用的通量展开节点法Flux expansion nodal method for solving multigroup neutron diffusion equations in hexagonal-Z geometry./ Ann. Nucl. Energy. 33(4), 2006, 7p.J-040-013反应堆屏蔽设计最佳化用的通过园柱形管相对蒙特卡罗模拟研究的剂量率剖面图和能谱的测量Measurement of dose rate profile and spectra through a cylindrical duct Vis-Vis Monte Carlo simulation studies for optimization of reactor shield design./ Ann. Nucl. Energy. 33(4), 2006, 5p.J-040-014关于核动力真正设计成防止长寿命锕系元素废物,防止武器扩散和严重事故On nuclear power intrinsically protected against long-lived actinide waste, weapons proliferation and heavy accidents./ Ann. Nucl. Energy. 33(4), 2006, 10p.J-040-015蒸汽发生器热交换器管子的腐蚀态综合研究,第1部分：通常腐蚀态和形态学Comprehensive investigation of the corrosion state of the heat exchanger tubes of steam generators. Part I. general corrosion state and morphology. /J. Nucl. Mater. 348(1-2), 2006, 10p.J-040-016蒸汽发生器热交换管子腐蚀态的综合研究,第2部分：管子表面的化学成分和结构Comprehensive investigation of the corrosion state of the heat exchanger tubes of steam generators. Part II. Chemical composition and structure of tubes surfaces./ J. Nucl. Mater. 348 (1-2), 2006, 14p.J-040-017在强迫对流流动情况下液态重金属回路中的热和质量迁移计算Heat and mass transfer calculations in heavy liquid metal loops under forced convection flow conditions./ J. Nucl. Mater. 348(1-2), 2006, 8p.J-040-018氧化物膜对合金600一回路水应力腐蚀破裂起始的影响Influence of oxide film on primary water stress corrosion cracking initiation of alloy 600./ J. Nucl. Mater. 348(1-2), 2006, 9p.J-040-019大型螺旋装置中等离子体壁系统的氢粒子平衡的分析Analysis for hydrogen particle balance of plasma-wall system in the large helical device./ J. Nucl. Mater. 350(1), 2006, 7p.J-040-020HT-7超导托卡马克中为除去沉积层和释放捕集的氢同位素而进行的氧灼热排出实验Oxygen glow discharge experiment to remove deposited layers and to release trapped hydrogen isotopes in HT-7 super conducting Tokamak./ J. Nucl. Mater. 350(1), 2006, 10p.J-040-021采用机械观测检查研究堆控制棒表面点蚀Inspecting a research reactors control rod surface for pitting using a machine vision./ J. Nucl. Sci. Technol. 42(11), 2005, 7p.J-040-022超轻水堆的安全性：（1）安全系统设计Safety of super LWR: (1) safety system design./ J. Nucl. Sci. Technol. 42(11), 2005, 8p.J-040-023超轻水堆的安全性：（2）超临界压力下的安全分析Safety of super LWR：(II) safety analysis at supercritical pressure./ J. Nucl. Sci. Technol. 42(11), 2005, 14p.J-040-024采用钍燃料运行的汽轮机-模块氦堆蒙特卡罗连续能量模型的JENDL-3.3，JENDL-3.2，JEFF-3，JEF-2.2和ENDF/B-6.8数据库的比较研究Comparative studies of JENDL-3.3, JENDL-3.2, JEFF-3, JEF-2.2 and ENDF/B- 6.8 data libraries on the Monte Carlo continuous energy modeling of the gas turbine-modular helium reactor operating with thorium fuel./ J. Nucl. Sci. Technol. 42(12), 2005, 14p.J-040-025大功率YGN1号和2号机组和Kori3号和4号机组蒸汽发生器水位控制系统整定值最佳化Optimization for setpoints of steam generator water level control systems in power-uprated YGN 1 & 2 and Kori 3 & 4./ J. Nucl. Sci. Technol. 42(12), 2005, 10p.J-040-026钠-水反应射流中峰温度的分析模型Analytical model for peak temperature within a sodium-water reaction jet./ J. Nucl. Sci. Technol. 43(1), 2006, 12p.J-040-027评价超轻水堆工程不确定性的统计热设计程序的发展Development of statistical thermal design procedure to evaluate engineering uncertainty of super LWR./ J. Nucl. Sci. Technol. 43(1), 2006, 11p.J-040-028二次减压对采用高压注入故障和气体流入的压水堆容器底部小破口冷却剂流失事故实验堆芯冷却的影响Effects of secondary depressurization on core cooling in PWR vessel bottom small break LOCA experiments with HP1 failure and gas inflow./ J. Nucl. Sci. Technol. 43(1), 2006, 10p.J-040-029肼和氢共同注入来减轻沸水堆结构材料的应力腐蚀破裂（I）肼反应的温度相关性Hydrazine and hydrogen co-injection to mitigate stress corrosion cracking of structural materials in boiling water reactors, (I) temperature dependence of Hydrazine reactions./ J. Nucl. Sci. Technol. 43(1), 2006, 12p.J-040-030TRAC-M/F90的三场模型的执行及其在环形湿气流上的应用The implementation of a three-field model into TRAC-M/F90 and its application to annular-mist flow./ J. Nucl. Sci. Technol. 43(1), 2006, 10p.J-040-031为论证稳态高等离子体运行进行国立中心托卡马克装置的设计研究Design study of national centralized Tokamak facility for the demonstration of steady state high- plasma operation./Nucl. Fusion. 45(12), 2005, 8p.J-040-032SSPX球马克的操作改进Improved operation of the SSPX spheromak./ Nucl. Fusion. 45(12), 2005, 7p.J-040-033直接驱动激光聚变的激光靶耦合效率的最佳化Optimization of laser-target coupling efficiency for direct drive laser fusion./ Nucl. Fusion. 45(12), 2005, 5p.J-040-034国际热核实验堆中子诊断发展状况Status of ITER neutron diagnostic development./ Nucl. Fusion. 45(12), 2005, 7p.J-040-035下一代核能：经济简化型沸水堆Next-generation nuclear energy: the ESBWR./Nucl. News. 49(1), 2006, 6p.J-040-036ANO-1核电厂检查新型蒸汽发生器采用的机器人Robots used to inspect new SGs at ANO-1./ Nucl. News. 49(2), 2006, 3p.J-040-037由美国核管会确认的西屋公司先进动力堆AP1000Westinghouses AP1000 affirmed by NRC. / Nucl. News. 49(2), 2006, 6p.J-040-038世界核电厂一览表World list of nuclear power plants./ Nucl. News. 49(3), 2006, 33p.J-040-039核动力革新采用的先进电厂Advanced plants for nuclear powers renaissance./Nucl. Plant. J. 23(5), 2005, 6p.J-040-040预测流动不稳定性用的RELAP/MOD3.2编码中低压次冷沸腾模型的改进Improvement of low-pressure subcooled boiling models in RELAP/MOD3.2 code for predicting flow instability./Nucl. Sci. Eng. 152(1), 2006, 7p.J-040-041作为核电厂氢火焰阻挡器的猝灭网的可应用性The applicability of a quenching mesh as a hydrogen flame arrester in nuclear power plants./Nucl. Technol. 153(1), 2006, 11p.J-040-042新阶段一体化系统模块先进堆（SMART-P）电厂蒸汽管线破裂事故的保守分析方法学A conservative analysis methodology for a steam-line-break accident of the SMART-P plant./ Nucl. Technol. 153(1), 2006, 12p.J-040-043高温工程试验堆氢生产系统的控制工艺的发展Development of control technology for the HTTR hydrogen production system./ Nucl. Technol. 153(1), 2006, 7p.J-040-044给水加热器壳壁上稀薄化位置分布预测用的计算机化流体动力学Computation fluid dynamics predicting the distributions of thinning location on the shell wall of feed water heaters. / Nucl. Technol. 153(2), 2006, 11p.J-040-045先进动力堆1400在大破口冷却剂流失事故再淹没阶段下降管沸腾的实验和RELAP5分析Experiment and RELAP5 analysis for the downcomer boiling of APR1400 under LBLOCA reflood phase./ Nucl. Technol. 153(2), 2006, 9p.J-040-046流化床核反应堆的设计改进-1：设计改进和安全功能On an improved design of a fluidized bed nuclear reactor-1: design modifications and steady-state features./ Nucl. Technol. 153(2), 2006, 15p.J-040-047堆芯限制器的热和冶金特性的模拟剂熔融实验Simulant melt experiments on thermal and metallurgical performance of the in-vessel core catcher./ Nucl. Technol. 153(2), 2006, 16p.J-040-048水水控制棒驱动系统加速过程的温度特性The temperature feature on the step-up process of the hydraulic control rod driving system./ Nucl. Technol. 153(2), 2006, 6p.J-040-049能量生产和废物嬗变用的加速器驱动系统：研究与发展的国际趋势Accelerator driven systems (ADS) for energy production and waste transmutation: international trends in R & D./Prog. Nucl. Energy. 48(2), 2006, 12p.J-040-050不同截面数据集对原型材料试验研究堆反射层的影响Effect of different cross-section data sets on reflectors of a typical material test research reactor./ Prog. Nucl. Energy. 48(2), 2006, 10p.J-040-051水水动力堆440的RELAP5/MOD3模型对紧急停堆瞬态的证实Validation of RELAP5/MOD3.2 model of VVER 440 on reactor scram transient./ Prog. Nucl. Energy. 48(2), 2006, 9p.二、核燃料与核材料J-040-052中子入射能量为2到18MeV下的232Th和238U的中子发射谱的研究The investigation of the neutron emission spectra of 232Th and 238U for neutron incident energy from 2 to 18MeV./Ann. Nucl. Energy. 33(4), 2006, 15p.J-040-053过氧化氢加入和电解产物对二氧化铀水溶液腐蚀作用的影响Addition versus radiolytic production effects of hydrogen peroxide on aqueous corrosion of UO2./J. Nucl. Mater. 348(1-2), 2006, 17p.J-040-054镧和钇铝硅酸盐玻璃的结晶作用Crystallization of lanthanum and yttrium aluminosilicate glasses./ J. Nucl. Mater. 348(1-2), 2006, 9p.J-040-055用作聚变堆增殖包层第1壁的V-4Cr-4Ti合金的氘和氦的滞留作用Deuterium and helium retentions of V-4Cr-4Ti alloy used as first wall of breeding blanket in a fusion reactor./ J. Nucl. Mater. 348(1-2), 2006, 7p.J-040-056剂量率对奥氏体不锈钢的中子辐射响应的影响The effect of dose rate on the response austenitic stainless steels to neutron radiation./ J. Nucl. Mater. 348(1-2), 2006, 17p.J-040-057剩余碳对混合氧化物燃料芯块烧结行为的影响Effect of residual carbon on the sintering behavior of MOX pellets./ J. Nucl. Mater. 348(1-2), 2006, 9p.J-040-058高温和高压下水溶液中锆的电化学The electrochemistry of zirconium in aqueous solutions at elevated temperatures and pressures./ J. Nucl. Mater. 348(1-2), 2006, 15p.J-040-059裂纹尖端氧化物浓度对锆合金-4断裂韧性的影响Influence of the crack-tip hydride concentration on the fracture toughness of zircaloy-4./ J. Nucl. Mater. 348(1-2), 2006, 8p.J-040-060预测液态碱金属热力学性质的新状态方程式A new equation of state for predicting the thermodynamic properties of liquid alkali metals./ J. Nucl. Mater. 348(1-2), 2006, 5p.J-040-061氧对锆合金-4的氧化作用和水的生成Oxidation of zircaloy-4 by oxygen and the production of water./ J. Nucl. Mater. 348(1-2), 2006, 8p.J-040-062把铜结合到碳纤维增强碳基体复合物上的新技术建议Proposal for a new technique to join CFC composites to copper./ J. Nucl. Mater. 348(1-2), 2006, 6p.J-040-063在水溶液中活性金属与碘之间的反应Reactions between reactive metals and iodine in aqueous solutions./ J. Nucl. Mater. 348(1-2), 2006, 7p.J-040-064硅在磁铁矿和铁的其它腐蚀产物上的吸附作用Sorption of silicon on magnetite and other corrosion products of iron./ J. Nucl. Mater. 348(1-2), 2006, 10p.J-040-065氦在3C-SiC中的导入和扩散作用的理论研究Theoretical study of helium insertion and diffusion in 3C-SiC./ J. Nucl. Mater. 348(1-2), 2006, 9p.J-040-066核燃料中再结晶晶粒大小和网状位错密度，以及晶格参数变化的分析表示式推导Derivation of analytical expressions for the network dislocation density, change in lattice parameter and for the recrystallized grain size in nuclear fuels./ J. Nucl. Mater. 349(1-2), 2006, 10p.J-040-067核石墨氧化作用的实验研究和氧化作用模型的发展Experimental study on the oxidation of nuclear graphite and development of an oxidation model./ J. Nucl. Mater. 349(1-2), 2006, 13p.J-040-068氢化锂水解作用的反应和动力学的文献综述A literature review of reactions and kinetics of lithium hydride hydrolysis. / J. Nucl. Mater. 349(1-2), 2006, 39p.J-040-069轻水堆惰性基体燃料使用的MgO-ZrO2陶瓷的热传导性和酸溶解作用行为Thermal conductivity and acid dissolution behavior of MgO-ZrO2 ceramics for use in LWR inert matrix fuel./ J. Nucl. Mater. 349(1-2), 2006, 11p.J-040-070Zr-2.5%Nb压力管材料中KIH的结构相关性The texture dependence of KIH in Zr-2.5%Nb pressure tube materials./ J. Nucl. Mater. 349(1-2), 2006, 13p.J-040-071氧-铀体系的热力学：-U+UO2+X成分范围内的相图数据的临界评价Thermodynamics of the O-U system: -critical assessment of phase diagram data in the U+UO2+X composition range./ J. Nucl. Mater. 349(1-2), 2006, 26p.J-040-072氧-铀体系热力学：-U-UO2.01成分范围内化学热的临界评价Thermodynamics of the O-U system: -critical assessment of chemical potentials in the U-UO2.01 composition range./ J. Nucl. Mater. 349(1-2), 2006, 40p.J-040-073熔融盐反应堆燃料循环用的熔融LiF-NaF- KF的电化学分离方法的进展Development of electrochemical separation methods in molten LiF-NaF-KF for the molten salt reactor fuel cycle. /J. Nucl. Sci. Technol. 42(12), 2005, 8p.J-040-074采用紫外-目视光谱测定法和循环伏安测量法研究Nacl-2Cscl中U4+/U3+的氧化还原平衡Redox equilibrium of U4+/U3+ in molten Nacl-2Cscl by UV-Vis spectrophotometry and cyclic voltammetry./ J. Nucl. Sci. Technol. 42(12), 2005, 7p.J-040-075核石墨IG-110和二氧化碳之间反应作用的实验研究Experimental study on the reaction between nuclear graphite IG-110 and carbon dioxide./J. Nucl. Mater. 350(1), 2006, 5p.J-040-076半机械化模型对水水动力堆堆压力容器焊接的注量率影响Fluence rate effect semi-mechanistic modeling on WWER-type RPV welds./ J. Nucl. Mater. 350(1), 2006, 7p.J-040-077粗糙度对核级石墨磨擦性质的影响The influence of rough ness on tribological properties of nuclear grade graphite./ J. Nucl. Mater. 350(1), 2006, 9p.J-040-078SCS14A铸型双炼不锈钢由于热老化引起的机械特性和微结构的变化Mechanical property and microstructural change by thermal aging of SCS14A cast duplex stainless steel./ J. Nucl. Mater. 350(1), 2006, 9p.J-040-079辐照过的高燃耗二氧化铀燃料中晶体结构缺陷的空间分布的稳定性On stability of spatial distribution of crystal structure defects in irradiated high burnup UO2 fuel./ J. Nucl. Mater. 350(1), 2006, 8p.J-040-080在约100MWd/kgHM的高燃耗下二氧化铀核燃料的热传导性On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100MWd/kg HM./ J. Nucl. Mater. 350(1), 2006, 21p.J-040-081混合氧化物沉积试验中的低电流效率Low current efficiency in MOX deposition tests./J. Nucl. Sci. Technol. 42(10), 2005, 8p.J-040-082在磷酸三丁脂硝酸和水组成的有机溶液中采用超声辐射作用生成亚硝酸Generation of nitrous acid by ultrasound irradiation in the organic solution consisting of Tri-n-butylphosphate, nitric acid and water./ J. Nucl. Sci. Technol. 42(11), 2005, 5p.J-040-083含有二氧化碳和磷酸三丁酯的超临界流的密度Densities of supercritical fluids containing CO2 and tri-butylphosphate. / J. Nucl. Sci. Technol. 43(1), 2006, 5p.J-040-084Sellafield后处理工艺流程图的发展-最佳环境方案的实施The development of Sellafield process flow sheets-best practicable environmental option?/Nucl. Future. 02(1), 2006, 9p.J-040-085核燃料循环的新研究重点New research initiative focuses on fuel cycle./Nucl. News. 49(1), 2006, 3p.J-040-086Jeff combs：关于全球核燃料市场的评论Jeff combs: comments on the global nuclear fuel market./ Nucl. News. 49(3), 2006, 4p.J-040-087较高的铀价格将提高美国国内生产吗？Will higher uranium prices restore domestic U.S. production?/ Nucl. News. 49(3), 2006, 4p.J-040-088Pitzer方法在标度编码体系中锕系元素溶液密度模拟上的应用Application of the Pitzer method for modeling densities of actinide solutions in the scale code system./ Nucl. Technol. 153(1), 2006, 8p.J-040-089在加热到熔融期间铀-锆氢化物燃料的裂变气体释放Fission gas release from uranium- zirconium hydride fuel during heating to melting./ Nucl. Technol. 153(1), 2006, 7p.J-040-090通过模拟来研究高燃耗燃料故障焓的概率分布的方法学A methodology for developing a probability distribution for the failure enthalpy of high-burnup fuels via simulation./ Nucl. Technol. 153(1), 2006, 9p.J-040-091DUPIC（坎杜堆直接使用压水堆乏燃料）燃料相容性分析的进展-1：反应堆物理学Progress of the DUPIC fuel compatibility analysis-1: reactor physics./ Nucl. Technol. 153(1), 2006, 16p.J-040-092快堆中242mAm的增殖Breeding of 242mAm in a fast reactor./ Nucl. Technol. 153(2), 2006, 10p.J-040-093坎杜堆钍燃料循环采用干法工艺的物理学研究A physics study on thorium fuel recycling in a CANDU reactor using dry process technology./ Nucl. Technol. 153(2), 2006, 14p.J-040-094DUPIC燃料相容性分析的进展-II：热工水力学Progress of the DUPIC fuel compatibility analysis-II: thermal hydraulics./ Nucl. Technol. 153(2), 2006, 11p.J-040-095为降低地质处置要求超铀元素在轻水堆中再循环Recycle of transuranium elements in light water reactors for reduction of geological storage requirement./ Nucl. Technol. 153(2), 2006, 18p.J-040-096安全性和中子学：混合氧化物燃料与二氧化铀燃料的比较Safety and neutronics: a comparison of MOX vs UO2 fuel./Prog. Nucl. Energy. 48(2), 2006, 11p.J-040-097采用气体注入的螺旋微过滤模块中的流动增强Flux enhancem