钠冷快堆的安全性

 钠冷快堆具有许多固有安全特征: 高的热导率，低压的钠系统，钠对快堆材料腐蚀甚微，熔融燃料与钠无剧烈相互作用，钠辐照后不产生长寿命放射性核素，有足够的运动粘度和热膨胀系数，易于设计非能动事故余热排出系统等。中国实验快堆是一座热功率65 MW、电功率20 MW的钠冷池式快堆，除具有上述固有安全特征外，它还设计有负的温度效应、功率效应和堆芯钠空泡效应，设有独立的非能动事故余热排出系统、非能动接钠盘、堆容器非能动超压保护系统、非能动冷却的堆芯熔化收集器等，以及具有完备可靠的主动安全系统。中国实验快堆达到了第四代核电系统的安全目标。

Safety on sodium cooled fast reactor

The sodium cooled fast reactor possesses a number of inherently safe properties: high thermo-conductivity, low pressurized sodium system, tiny corrosion on materials used in SFR by sodium, no any acute molten fuel-sodium interaction, no long-lived nuclides produced after irradiation, enough dynamic viscosity and heat volume expansion to design possibly an passive accident decay heat removal system, etc. The CEFR is a sodium cooled pool type fast reactor with thermal power 65 MW and electric power 20 MW. Besides above-mentioned properties, the CEFR is designed with negative reactivity effect of temperature, power and sodium void, independent passive accident decay heat removal systems, passive leaked sodium receivers, passive over-pressure protection system and passive cooled reactor core molten receiver, etc. And the CEFR is also equipped by reliable active maturity safety systems. The safety of CEFR is reached to the safety aims of Generation Ⅳof nuclear systems.