基本释义:

压水型堆

网络释义

1)pwr,压水型堆

2)LPWR (large pressurized water reactor),大型压水堆

3)PWR(pressurized water reactor),压水型轻水堆

4)pressurized water reactor core, PWR core,压水堆堆芯

5)FDR (Fortschrittlicher Druckwasser Reaktor),改进型压水堆(德国)

6)PWR,压水堆

用法和例句

PWR LOCA Analysis with Condensation Reflux Model;

采用冷凝回流模型的压水堆失水事故分析

Fuzzy Control of Boron Concentration for Load Following on PWR;

用于压水堆负荷跟踪运行的硼浓度模糊控制系统

The development trend of PWR technology;

压水堆技术发展趋势概述

Analysis of the PWR Primary Shield with 3-D S_N Method

大型压水堆核电站堆本体主屏蔽三维离散纵标计算分析

Canadian Deuterium-Uranium Reactor

加拿大重水铀反应堆(坎杜型反应堆)

The main factor of localization of nuclear island major equipment of PWR nuclear power plant--Large forgings

压水堆核电厂核岛主设备国产化关注点——大型锻件

candu pressurized heavy water cooled

加拿大重水慢化加压重水冷却反应堆

Quality Control of Hot-working Process for Large-sized Forging Reactor Pressure Vessel

反应堆压力容器大型锻件热加工质量控制研究

burnable poison pressurized water reactor

可燃毒物压水反应堆

natural circulation pressurized water reactor

自然循环压水反应堆

The Nuclear Core Design of 450MWt Pressurized Water Reactor

45万千瓦(热)压水堆堆芯核设计

Study on Assessment of Severe Accident Models for PWR Based on Comparison and Parameters Sensitivity Analysis;

基于比较和参数敏感性分析的压水堆严重事故模型评价研究

Studay on Performance of Cement-based Composite Materials Based on Compressible Packing Model;

基于可压缩堆积模型的水泥基复合材料性能研究

Research on unified models of heat-economic analysis for PWR nuclear power plants

压水堆核电机组二回路热力系统热经济性分析统一模型的研究

External Reactor Vessel Cooling Measure in Severe Accident for Pressurized Water Reactor Nuclear Power Plant

压水堆核电厂严重事故下堆腔注水措施研究

This comprises two 985MW pressurised water reactors which went into commercial operation in February and May 1994, respectively.

大亚湾核电站设有两座985兆瓦压水式反应堆，这两座反应堆分别于一九九四年二月及五月投产。

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。

CANDU (Canadian deuterium uranium)

加拿大重水铀反应堆

Measurements for monitoring adequate cooling within the core of pressurized light water reactors

GB/T13632-1992监督压水堆堆芯充分冷却的测量要求

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

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