1.
GNPS 18-Months Fuel Cycles Core Thermal Hydraulic Design
大亚湾核电站18个月换料堆芯热工水力设计
2.
The Nuclear Core Design of 450MWt Pressurized Water Reactor
45万千瓦(热)压水堆堆芯核设计
3.
A THERMAL-HYDRAULIC MODEL FOR BWR SIMULATORS
沸水堆堆芯模拟程序中的热工-水力模型
4.
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
5.
Development of Steady-State Thermal Hydraulic Analysis Code for Rectangle Channel Core
矩形通道堆芯稳态热工水力分析程序的开发
6.
Three-dimension thermal hydraulic studies for the pool-type fast reactor of CEFR
池式快堆三维热工流体力学设计研究
7.
Coupled Thermal-Hydraulics and Neutron-Physics Analysis of Supercritical Water Cooled Reactor With Mixed Spectrum Core
混合能谱超临界水堆堆芯热工-物理性能分析
8.
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
9.
Neutronics/thermal-hydraulics coupled axial 1D model for SCWR core static analysis
超临界水堆堆芯轴向一维物理热工耦合稳态分析
10.
Heat Balance Test for Determined Reactor Core Power
计算核反应堆堆芯功率的热平衡试验
11.
Core Stable Flowrate Distribution of High Flux Engineering Test Reactor(HFETR)
高通量工程试验堆堆芯流量分配计算
12.
Thermal Design of Integrated Power Electronics Module Using Flip-Chip Technology
倒装芯片集成电力电子模块的热设计
13.
Design of Core Vessel and Core Structure in China Advanced Research Reactor
中国先进研究堆堆芯容器及堆内构件设计研究
14.
Safety Analysis for Xi’an Pulsed Reactor in Pulse Operation Mode with the Core in Steady Arrangement and Design Project for the New Core Arrangement
西安脉冲堆稳态堆芯脉冲运行安全性分析及新堆芯布置方案设计
15.
A practical BWR thermal-hydraulic model has been introduced.
本文介绍了一个实用的沸水堆热工一水力模型。
16.
Core Physics Design Calculation of Minitype Fast Reactor by MCNP Code;
基于MCNP的微型钠冷快堆堆芯物理设计计算
17.
Core Neutron Space-time Kinetics of High Temperature Gas Cooled Reactor
高温气冷堆堆芯中子时空动力学模拟计算
18.
The comparison of the computational results for reactor core of PWR and BWR are also presented.
文中还给出了压水堆和沸水堆堆芯计算实例的比较。