reactor coolant leakage calculatio

反應(yīng)堆冷卻劑泄漏計(jì)算

Optimization of Leakage Calculation in RCP System of PWR

壓水堆核電廠一回路冷卻劑泄漏率計(jì)算的優(yōu)化

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

秦山核電二期工程反應(yīng)堆及反應(yīng)堆冷卻劑系統(tǒng)源項(xiàng)計(jì)算分析

coolant leakage indicator

冷卻劑回路泄漏指示器

coolant leakage measuring assembly

冷卻劑泄漏測(cè)量裝置

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

秦山核電二期工程反應(yīng)堆及反應(yīng)堆冷卻劑系統(tǒng)設(shè)計(jì)

Improvement and practice of speed measurement system for reactor coolant pump

反應(yīng)堆冷卻劑泵轉(zhuǎn)速測(cè)量系統(tǒng)改進(jìn)設(shè)計(jì)及實(shí)踐

reactor coolant system dose equivalent

反應(yīng)堆冷卻劑系統(tǒng)劑量當(dāng)量

charging/make-up flow [reactor coolant system]

上充／補(bǔ)給水流量〔反應(yīng)堆冷卻劑系統(tǒng)〕

a nuclear reactor using gas as a coolant.

用氣體做冷卻劑的核子反應(yīng)堆。

reactor coolant circuit integrity

反應(yīng)堆冷卻劑回路完整性

reactor building cooling unit

反應(yīng)堆建筑物冷卻裝置

granular graphite cooled reactor

顆粒狀石墨冷卻反應(yīng)堆

liquid metal cooled reactor

液態(tài)金屬冷卻反應(yīng)堆

light water cooled heavy water reactor

輕水冷卻重水反應(yīng)堆

primary reactor coolant system

反應(yīng)堆一次冷卻系統(tǒng)

graphite moderated sodium cooled reactor

石墨慢化鈉冷卻反應(yīng)堆

BGR (Bismuth-Graphite Reactor)

石墨慢化鉍冷卻反應(yīng)堆