1、Analysis of Small Break LOCA for ACR-700 NPP
ACR-700核電廠(chǎng)小破口失水事故分析

2、Introduction of DRM for Large Break LOCA Analysis
大破口失水事故的DRM分析方法介紹

3、Licensing LOCA analysis is an important issue of Nuclear Power Plant design and safety analysis.
認(rèn)證級(jí)LOCA分析是核電廠(chǎng)設(shè)計(jì)和安全分析的重要內(nèi)容之一。

4、The effect of condensation reflux model in PWR LOCA analyses was investigated.
研究了冷凝回流在壓水堆中破口失水事故中的作用。

5、Simulation Experiment of Small Break LOCA in Upper Plenum
上空腔小破口失水事故模擬實(shí)驗(yàn)

loca翻譯