nuclear excursion是什么意思

网络释义

用法例句

They were a series of new kinds of method to discriminate the aberrant responses behaviors in psychological tests which based on Guttman model and Item response theory.

人格测验中的偏差反应与能力测验存在很大差别。

nuclear excursion

反应堆工作状况偏差

(4) poor status of prop working and low security in working face.

(4) 支柱工作状况差，工作面安全性低。

FISHWAFT (Fission -product Super-Heating Wasteelement Fuelled Reactor)

利用已用过的释热件工作的反应堆

granular graphite cooled reactor

颗粒状石墨冷却反应堆

NETR (Nuclear Engineering Test Reactor)

核子工程试验反应堆

A Measurement Method Regarding Reactor Core Thermal Power and Error Analysis

反应堆堆芯热功率测量方法及其误差分析

The Analysis of Soil-Structure Interaction and Floor Response Spectrum for Nuclear Reactor Engineering;

核反应堆工程地基—结构相互作用与楼层反应谱分析

“The average is thus a poor representation of the large variability of the stress amplitudes in the crust.

“平均的情况则只能较差的反映地壳中应力振幅非常大不同的状况。

Areas covered by this audit process included Element19 implementation, Avian Flu epidemic plan and Medical Emergency Response protocols.

检查工作主要项目包括元素19工作的执行状况，禽流感预防准备和医疗紧急反应预案。

The Behavior Finance Explanation of Overreaction and Underreaction in Chinese Stock Market;

中国股市反应偏差的行为金融学解释

An Investor s Sentiment Model of Over-reaction and Under-reaction to China s Stock Markets;

中国股市反应偏差的投资者心态模型

divergent reactor

功率增长状态下的反应堆

the branch of engineering concerned with the design and construction and operation of nuclear reactors.

工程学中有关核子部反应堆的设计,建造与操作的分支。

Source Terms Calculation Analysis for the Reactor and Primary Coolant System of Qinshan Phase II NPP Project

秦山核电二期工程反应堆及反应堆冷却剂系统源项计算分析

Design of the Reactor and Reactor Coolant System for Qingshan Phase II NPP Project

秦山核电二期工程反应堆及反应堆冷却剂系统设计

Situation and Analysis on Grass-roots ADR Monitoring

基层药品不良反应监测工作现状分析

reactor core radiation detector

反应堆堆芯辐射检测仪

The reactor afterheat under conditions of depressuriza-tion and loss of main heat sink would be removed away through mechanism ofpassive heat transfer by conduction, radiation and natural convection.

失冷和失压工况下,由导热、辐射和自然对流等被动传热机制能将剩余发热安全地传出反应堆。