首页> 外文OA文献 >The Establishment of the Interactive Program on the Analysis of the Equivalent Thermal Properties of the Nuclear Fuel Bundle and Nuclear Fuel Casing Materials

【2h】

The Establishment of the Interactive Program on the Analysis of the Equivalent Thermal Properties of the Nuclear Fuel Bundle and Nuclear Fuel Casing Materials

机译：关于核燃料束和核燃料套管等同热特性分析的互动计划的建立

代理获取

本网站仅为用户提供外文OA文献查询和代理获取服务，本网站没有原文。下单后我们将采用程序或人工为您竭诚获取高质量的原文，但由于OA文献来源多样且变更频繁，仍可能出现获取不到、文献不完整或与标题不符等情况，如果获取不到我们将提供退款服务。请知悉。

页面导航

著录项
引文网络
相似文献
相关主题

著录项

作者
唯耕林;
展开▼
作者单位

展开▼
年度 2013
总页数
原文格式 PDF
正文语种
中图分类

相似文献

外文文献
中文文献
专利

1. Erratum: Analytical determination of thermal conductivity of W-UO _2 and W-UN CERMET nuclear fuels (Journal of Nuclear Materials (2012) 427 (87-94)) [J] . Webb J.A., Charit I. Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2013,第1a3期

机译：勘误：W-UO _2和W-UN CERMET核燃料导热系数的分析测定（核材料学报（2012）427（87-94））
2. Development of interactive software for evaluations of effective thermal properties in fuel bundles and fuel tubes in Spent Fuel Dry Storage Systems [J] . Wei-Keng Lin, Jong-Rong Wang, Yung-Shin Tseng, Journal of the Chinese Institute of Engineers . 2013,第2期

机译：开发用于评估乏燃料干式存储系统中燃料束和燃料管中有效热特性的交互式软件
3. Study on the mechanical properties and thermal conductivity of silicon carbide-, zirconia- and magnesia aluminate-based simulated inert matrix nuclear fuel materials after cyclic thermal shock [J] . Lee YW., Lee SC., Kim HS., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2003,第0期

机译：循环热冲击后碳化硅，氧化锆和铝酸铝基惰性基质核燃料材料的力学性能和导热系数的研究
4. CHANGE IN MECHANICAL PROPERTIES AND THERMAL CONDUCTIVITY OF INERT MATRIX NUCLEAR FUEL MATERIALS AFTER THERMAL SHOCK [C] . YOUNG-WOO LEE, SANG CHUL LEE, CHANG YOUNG JOUNG, Ninth Annual International Conference on Composites Engineering ICCE/9 Jul 1-6, 2002 San Diego, California . 2002

机译：热冲击后惰性矩阵核燃料材料的力学性能和导热系数的变化
5. Enabling CTF for Thermal Expansion Analysis of Metallic Fuels in Advanced Nuclear Reactors [D] . Godbole, Chaitee Milind. 2019

机译：在先进的核反应堆中启用CTF用于金属燃料的热膨胀分析
6. Thermally-Conductive and Mechanically-Robust Graphene Nanoplatelet Reinforced UO2 Composite Nuclear Fuels [O] . Tiankai Yao, Guoqing Xin, Spencer Michael Scott, -1

机译：导热和机械稳健的石墨烯纳米片增强UO2复合核燃料
7. COBRA IIIcMIT-2 : a digital computer program for steady state and transient thermal-hydraulic analysis of rod bundle nuclear fuel elements [O] . Jackson J. W., Todreas Neil E. 1981

机译：COBRa IIIcmIT-2：用于杆束核燃料元件的稳态和瞬态热工水力分析的数字计算机程序

The Establishment of the Interactive Program on the Analysis of the Equivalent Thermal Properties of the Nuclear Fuel Bundle and Nuclear Fuel Casing Materials

著录项

引文网络

相似文献

相关主题

期刊订阅