1.
Study on Core Fuel Management of Slightly Enriched Uranium Fuel for CANDU6 Reactor;
CANDU6反应堆提高燃料富集度的堆芯燃料管理研究
2.
Application Research for VVER Fuel Management Code System;
六角形组件堆芯燃料管理程序包的应用开发
3.
In this paper, the genetic algorithm( GA) has been used in reactor fuel management of core arrangement optimal calculation.
应用遗传算法编制了核反应堆堆芯燃料管理优化计算程序。
4.
Preliminary Study on Improving In?CoreFuel Management Strategy ofGNPS and QNP
秦山和大亚湾核电厂堆芯燃料管理策略改进的初步探讨
5.
Genetic algorithm for the optimization of the loading pattern for reactor core fuel management
遗传算法在堆芯燃料管理装载模式优化中的应用
6.
Radiant Deformation of PWR AFA17×17 Fuel Assembly and Core Loading of Deformed Fuel Assembly;
压水堆AFA17×17燃料组件辐照变形及其堆芯装料
7.
Manufacturing of Nuclear Fuel Assembly for PWR and Study for the Fuel Pellets with Central Hole;
压水堆核燃料制造及中孔环形燃料芯块的研制
8.
Design and Application of Reactor Core with Tight-Lattice Rod Type Fuel Element
稠密栅棒型燃料元件堆芯设计及应用
9.
Analysis of MOX core thermal characteristics and design criteria
MOX燃料堆芯热工特性及设计限值研究
10.
Preliminary study on thorium-uranium fuel cycle in the equilibrium core of PWR
压水堆平衡堆芯钍铀燃料循环初步研究
11.
Optimization of BurnablePoison Assignment for PWRLow Leakage Reload Core
压水堆低泄漏换料堆芯可燃毒物的优化配置
12.
Development of an In-Core Fuel Management Program for Solution Reactors
溶液堆燃料管理计算方法初步研究与程序研制
13.
loading grid for fuel elements (cartridges) for nuclear reactors
承载格栅,核反应堆烯料元件（燃料管）用
14.
non-irradiated fuel cartridge for nuclear reactors
未辐照过的核反应堆燃料管
15.
Low-Temperature Release Mechanism of Kr and Xe in Fuel Pellet
燃料棒芯块中Kr、Xe的低温释放机理
16.
Development and Validation of Thermal-Hydraulic Analysis Code for Plate Type Fuel Research Reactors
板状燃料元件堆芯热工水力特性分析程序开发及验证
17.
The Principle and methodology of pressurized water reactor nuclear power plant core power capability verification for reload are introduced.
介绍了压水堆核电厂换料堆芯功率能力验证分析的原理和方法。
18.
RESEARCH ON SOLVENT EXTRACTION PROCESS FOR REPROCESSING OF Th-U FUEL FROM HTGR
高温气冷堆钍铀燃料后处理溶剂萃取工艺研究