The loss of coolant accident (LOCA), as one of the design basis accidents (DBAs), is a hypothetical accident that is usually considered in the design of nuclear power plant. LOCA is caused by small/large breaks in the reactor primary coolant and pressure boundary and may result in a loss of reactor coolant at a rate in excess of the reactor makeup system capability. Currently, the typical mitigation measures for LOCA are through the vessel high/low pressure coolant injection (HPCI/LPCI), core spray system, or reactor core isolation cooling (RCIC) system, to protect reactor from fuel melting and core degradation. However, is it possible to directly repair the small breaks passively? Inspired by the hemostasis and coagulation mechanism of human blood vessels, the authors are considering to develop a technology which would allow the reactor self-coagulation during the small break loss of coolant accident (SBLOCA). With the assistance of this innovative technology, the speed of losing coolant through reactor primary loop breaks could be significantly reduced or even the loss is stopped. With more and longer existing coolant in the core, the possibility of core degradation will also be significantly reduced. This innovative technology needs to be designed feasible and simple, which can be directly used into the existing nuclear power plants to improve the inherent safety of the cooling system, benefit the economy and safety of the nuclear power plant. In this paper, the authors compare the reactor primary loop of nuclear power plant with the blood circulation system of human beings from comprehensive and multi-angle perspectives, discuss the similarity, feasibility, and economy of nuclear power plant self-coagulation system based on the existing hemostasis and coagulation mechanism of human blood vessels. If possible, this technology will play a revolutionary positive role in alleviating DBAs related to SBLOCA.

冷却剂损失事故（LOCA）作为设计基准事故（DBA）之一，是核电厂设计中通常考虑的假设性事故。LOCA 是由反应堆主冷却剂和压力边界的小/大断裂引起的，并且可能导致反应堆冷却剂以超过反应堆补充系统能力的速度损失。目前，典型的 LOCA 缓解措施是通过容器高/低压冷却剂喷射（HPCI/LPCI）、堆芯喷射系统或反应堆堆芯隔离冷却（RCIC）系统来保护反应堆免受燃料熔化和堆芯降解。但是，有没有可能直接被动修复小断点？受人体血管的止血和凝血机制启发，作者正在考虑开发一种技术，允许反应堆在冷却剂小破损事故 (SBLOCA) 期间自凝。在这项创新技术的帮助下，冷却剂通过反应堆主回路中断损失的速度可以显着降低，甚至可以停止损失。随着堆芯中存在更多和更长的冷却剂，堆芯退化的可能性也将显着降低。这种创新技术需要设计得可行和简单，可以直接应用于现有核电站，提高冷却系统的固有安全性，有利于核电站的经济性和安全性。在本文中，作者从综合、多角度比较核电站反应堆一回路与人体血液循环系统，在现有止血和凝血系统的基础上，探讨核电站自凝系统的相似性、可行性和经济性。人体血管的机制。如果可能的话，这项技术将对减轻与SBLOCA相关的DBA起到革命性的积极作用。