反应堆堆芯

M5锆合金主要应用于核反应堆堆芯的燃料包壳和结构件。

M5 zirconium alloy is mainly applied in the nuclear reactor core as the fuel cladding tubes and structure materials .

要设计成能传输出从反应堆堆芯产生的热量。

The system is designed for transferring heat from the reactor core .

用涡格子CFD方法研究反应堆堆芯元件流致振动的流体力学机理

Investigation of Flow Induced Vibration of Core Rods in Nuclear Reactor Using Vortex Lattice CFD Method

加速器驱动次临界系统（ADS）与核能可持续发展三束流驱动ADS次临界反应堆堆芯初步设计

Study on ADS and the sustainable development of nuclear energy Preliminary Design of Sub-critical Reactor Core for Accelerator Driven System with Three Proton Beams

MCNP程序在反应堆堆芯建模中的应用

Application of MCNP in the modeling for reactor core

三束流驱动ADS次临界反应堆堆芯初步设计加速器驱动的次临界系统快堆次锕系核素非均匀布置堆芯的中子学研究

Preliminary Design of Sub-critical Reactor Core for Accelerator Driven System with Three Proton Beams Neutronics Study on Minor Actinide Heterogeneous Core of ADS Fast Reactor

600MW反应堆堆芯入口流量分配实验研究

Test of flow distribution at the core inlet of 600 MW reactor

对反应堆堆芯中子通量的计算首先介绍了传统的方法，包含Hermite插值、Gear方法、常源瞬跳等。

For the calculation of the reactor core neutron flux , the traditional methods is introduced first , including Hermite interpolation , Gear , Prompt jump approximate and so on .

将反应堆堆芯元件简化为圆柱排列，用涡格子CFD（计算流体力学）方法对其中基本并列双圆柱元素进行数值研究。

In this paper , the vortex lattice CFD ( Computational Fluid Dynamics ) method is employed to investigate the dynamic response of core fuel and control rods on the fluid flow in nuclear reactors .

反应堆堆芯几何结构比较复杂，本文利用MCNP程序的重复结构功能构建了SPRR&300反应堆堆芯的计算模型。

This thesis sets up the calculational model of SPRR-300 reactor core with the repeated-structures capability of MCNP to dealing with the complex geometric structure .

用HAMMER-JUR和EXT-2程序校核了几种反应堆堆芯的临界实验。

In this paper , HAMMER-JUR and EXT-2 code matching check of Critical condition for some reactor cores is introduced .

反应堆堆芯热功率测量方法及其误差分析

A Measurement Method Regarding Reactor Core Thermal Power and Error Analysis

船用反应堆堆芯物理计算软件包的研制

Development of core physics analysis code packages for marine nuclear reactor

反应堆堆芯核测量数据在线处理方法研究

Research on Online Data Processing Method for Nuclear Monitoring of Reactor Core

测量了反应堆堆芯里的中子通量分布。

Neutron flux distributions in the reactor core are measured .

船用反应堆堆芯时空中子动力学仿真软件的研制

Development of spatio-temporal neutron kinetics simulation software for marine nuclear reactor core

板型燃料组件池式反应堆堆芯流量分配

Flow distribution in a pool type nuclear reactor core with planar fuel assemblies

三个反应堆堆芯熔化了装它们的容器。

Three reactor cores melted though their containment vessels .

用分子动力学方法研究反应堆堆芯熔化机理

A Mechanism Investigation of Core Melting in Nuclear Reactor Using Molecular Dynamics Method

反应堆堆芯由205个afa-3gxl燃料组件组成；

The reactor core is composed of205afa-3gxl fuel assemblies .

计算核反应堆堆芯功率的热平衡试验

Heat Balance Test for Determined Reactor Core Power

反应堆堆芯容器在泄压冲击波作用下的应力分析

Analysis of Stress in Reactor Core Vessel under Effect of Pressure Lose Shock Wave

舰艇核反应堆堆芯寿期的论证研究

Verification of the Ship Reactor Core Life

虽然故障频频，但工作人员必须不断向反应堆堆芯泵水。

Breakdowns arefrequent , but workers must keep the water pumping over the nuclear cores .

核反应堆堆芯中子通量三维阶梯状立体图的计算机实现

Computer Implementation of 3-Dimensional Stairs-appearance Graph Display of the Neutron Flux Distribution in the Reactor Core

反应堆堆芯的换料管理对核反应堆持续、安全的运行非常重要。

The fuel management is very important for the stable and safe operation of the reactor .

反应堆堆芯隔离冷却系统

Reactor core isolation cooling system

本文给出了用于核反应堆堆芯热工水力瞬态分析的两流体模型。

This paper presents a two-fluid model applied in thermal hydraulic transient analysis of nuclear reactor cores .

金山核热电厂反应堆堆芯热工-水力设计

The Thermal and Hydraulic Design of the Reactor Core for Jinshan Nuclear Combined Heat and Power Plant

在对核反应堆堆芯冷却剂系统分析的基础上，建立了海洋条件下冷却剂系统自然循环运行状态仿真模拟的数学模型。

Mathematical simulation model of nuclear reactor coolant system under ocean conditios is constructed in system analysis .