Research on passive cooling system with isolation condenser. (1) Evaluation of the operating condition in Fukushima Daiichi unit 1
- 1. Hokkaido Univ., Sapporo, Hokkaido (Japan)
Description
In the Fukushima Daiichi Nuclear Power Plant unit 1, isolation condenser (IC) should play an important role in core cooling during station blackout. To evaluate cooling capability of the IC, two phase flow analyses with the TRAC code and experiments for high pressure conditions were conducted. The analyses for the actual BWR indicated that decay heat could be removed if the IC worked properly at 18:18. However, our results showed that core uncovery occurred at 17:30, which will lead to hydrogen production from the heated core. Further efforts should be made to properly consider the effect of hydrogen accumulation for degradation of core cooling. The experiments simulating IC operation indicated that the natural convection occurred and decay heat could be removed by the IC at high pressure conditions. (author)
Additional details
Additional titles
- Original title (Japanese)
- 非常用復水器を用いた静的冷却系に関する研究. (1) 福島第一発電所1号機の作動状況評価
Publishing Information
- Imprint Title
- Proceedings of the 22nd national symposium on power and energy systems (SPES 2017)
- Imprint Pagination
- 4 p.
Conference
- Title
- 22. national symposium on power and energy systems
- Acronym
- SPES 2017
- Dates
- 14-15 Jun 2017
- Place
- Toyohashi, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49074690
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; COMPUTER CODES; FLOW VISUALIZATION; FUKUSHIMA-1 REACTOR; HYDROGEN; ISOLATION CONDENSERS; NATURAL CONVECTION; PRESSURE VESSELS; REACTOR ACCIDENT SIMULATION; REACTOR CORES; REACTOR VESSELS; RHR SYSTEMS; STATION BLACKOUT
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; CONTAINERS; CONVECTION; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; MASS TRANSFER; NONMETALS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; SIMULATION; STEAM CONDENSERS; THERMAL REACTORS; VAPOR CONDENSERS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as USB Flash Memory Card in PDF format, Folder Name: pdf; Paper ID: A223.pdf; 6 refs., 8 figs. Imprint:#7B2C#22#56DE##52D5##529B##30FB##30A8##30CD##30EB##30AE##30FC##6280##8853##30B7##30F3##30DD##30B8##30A6##30E0##8B1B##6F14##8AD6##6587##96C6#