基本信息:
- 专利标题: 원자력 발전소의 피동 붕괴열 제거계통
- 专利标题(英):Passive decay heat removal system for nuclear power plant
- 专利标题(中):用于核电厂的被动衰减除热系统
- 申请号:KR1020140022700 申请日:2014-02-26
- 公开(公告)号:KR1020150101240A 公开(公告)日:2015-09-03
- 发明人: 이정익 , 이제경 , 정화영
- 申请人: 한국과학기술원
- 申请人地址: 대전광역시 유성구 대학로 ***(구성동)
- 专利权人: 한국과학기술원
- 当前专利权人: 한국과학기술원
- 当前专利权人地址: 대전광역시 유성구 대학로 ***(구성동)
- 代理人: 특허법인충정
- 主分类号: G21C15/18
- IPC分类号: G21C15/18
The present invention discloses a passive decay heat removal system of a nuclear power station to supply electricity required for cooling the pump of still operate reliably. The invention consists of cooling the pump group suspended, stopped the cooling heat exchanger, turbine generators and the external heat exchanger group. Stop cooling the pump is mounted on a reactor coolant pipe to circulate the reactor coolant for cooling the reactor. Groups are still cooling heat exchanger is disposed between the reactor and stopping the cooling pump for the heat exchange between the supercritical fluid which is circulated through the reactor coolant and the supercritical fluid pipe. Turbine generator is connected groups still cooling heat exchanger, an cooling heat to stop the electric power generation by the supercritical fluid state in the last high-temperature gas is supplied to stop the cooling pump. External heat exchanger is mounted in the supercritical fluid pipe to the second to the last turbine generator cooling the supercritical fluid may send group still cooling heat. According to the present invention, the abnormal condition, for example, continue to advance and supplied stably by the electricity required for the still cooling pump even when all of the power loss of the supercritical fluid cycle to cool the reactor coolant of a nuclear reactor, the reactor It can significantly improve health. In addition, because the second critical pressure still cooling heat exchanger and the turbine generator, by fluid cycle it can be easily miniaturized and new nuclear power plants as well, the conventional effect of economically installed in a nuclear power plant.
公开/授权文献:
- KR102238185B1 원자력 발전소의 피동 붕괴열 제거계통 公开/授权日:2021-04-09
信息查询:
EspacenetIPC结构图谱:
G | 物理 |
--G21 | 核物理;核工程 |
----G21C | 核反应堆 |
------G21C15/00 | 装有堆芯的压力容器中的冷却装置;特殊冷却剂的选择 |
--------G21C15/18 | .紧急冷却装置;排除停堆余热 |