Study on the behavior of reactor core isolation cooling system (RCIC) under severe accident condition
Creators
- 1. Institute of Applied Energy, Nuclear Power Engineering Center, Tokyo (Japan)
Description
The Fukushima Daiichi Nuclear Station accident (hereinafter Fukushima Daiichi accident) revealed the risks that had not been envisaged in the past, but on the other hand, there were the devices that were unexpectedly effective for safety, one of which was a reactor core isolation cooling system (RCIC). RCIC is a system that when the BWR core is isolated from the main turbine, the RCIC's turbine is started instead of the main turbine, and cooling water is injected into the core with the power obtained from it. Although the design operation time is about 8 hours, in the Fukushima Daiichi accident, core cooling was performed for about 20 hours for Unit 3, and for about 66 hours for Unit 2. From the experience of the Fukushima Daiichi accident, the safety re-evaluation of RCIC has a possibility to increase the safety of reactors without requiring additional costs. So, a joint project "Study on the behavior of reactor core isolation cooling system (RCIC) under severe accident condition" is under promotion in cooperation with the U.S. Sandy National Laboratory. Experiments will be conducted mainly for the purpose of driving a full-scale turbine with steam, and important data for understanding the characteristics of the turbine will be obtained. (A.O.)
Additional details
Additional titles
- Original title (Japanese)
- 過酷事故条件下における原子炉隔離時冷却系(RCIC)の挙動に関する研究
Publishing Information
- Journal Title
- Kiho Enerugi Sogo Kogaku
- Journal Volume
- 42
- Journal Issue
- 2
- Series
- 雑誌名:季報エネルギー総合工学
- Journal Page Range
- p. 52-63
- ISSN
- 0286-3162
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 50070889
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; FLUID MECHANICS; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; INTERNATIONAL COOPERATION; MELTDOWN; NUCLEAR POWER PLANTS; RCIC SYSTEMS; REACTOR SAFETY; REACTOR VESSELS; S CODES; TURBINES; WATER
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; COMPUTER CODES; CONTAINERS; COOLING SYSTEMS; COOPERATION; ENERGY SYSTEMS; EQUIPMENT; HYDROGEN COMPOUNDS; MACHINERY; MECHANICS; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; POWER PLANTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SITES; SAFETY; SEVERE ACCIDENTS; SIMULATION; THERMAL POWER PLANTS; TURBOMACHINERY
Optional Information
- Notes
- 3 refs., 19 figs.