Basic study on PWR plant behavior under the condition of severe accident (1)
- 1. Fukui University of Technology, Department of Applied Nuclear Technology, Fukui (Japan)
Description
In this paper, we report on the results using the PWR plant simulator about the plant behavior under the condition of the severe accident that LOCA occurs but ECCS fails the water irrigation into the reactor core. As for the results about the relationship between the LOCA area and the time from LOCA occurs until fuel temperature rise start, the time became shorter as the area was the larger. But, in LOCA area of 1000 cm2 or more large, the time was almost constant regardless of the area. For small LOCA of 25 cm2 area, from the results of the comparative experiments for RCS natural circulation cooling effect in the case of SG open or not, in SG open condition compared with SG not open, the effect was observed more, but the reactor water level was greatly reduced and the time until the fuel temperature rise start was shortened, so the fuel temperature at the time of water irrigation into the reactor core has become higher. On the other hand, for the large LOCA of 1000 cm2, the effect was not observed regardless of SG open or not. In addition, the reactor core damage was not spared in the irrigation into the reactor core after 30 minutes from LOCA, however, the hydrogen concentration in the containment building is less than the lower limit of hydrogen detonation, and also the pressure in the containment building is less than the designed value. That is, although suffered the core damage, the integrity of the containment building has been shown to be secured. (author)
Availability note (English)
Available from DOI: http://doi.org/10.57375/00001552Additional details
Additional titles
- Original title (Japanese)
- シビアアクシデント発生時におけるPWRプラント挙動の基礎的研究 (1).(1次系LOCA+ECCS 失敗)事故
Identifiers
- DOI
- 10.57375/00001552;
Publishing Information
- Journal Title
- Fukui Kogyo Daigaku Kenkyu Kiyo (Online)
- Journal Volume
- 45
- Journal Page Range
- p. 293-303
- ISSN
- 1884-4456
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54073349
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTAINMENT BUILDINGS; ECCS; LOSS OF COOLANT; NATURAL CONVECTION; PWR TYPE REACTORS; RCIC SYSTEMS; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR KINETICS; REACTOR SAFETY EXPERIMENTS; REACTOR SIMULATORS; STEAM GENERATORS
- Descriptors DEC
- ACCIDENTS; ANALOG SYSTEMS; BEYOND-DESIGN-BASIS ACCIDENTS; BOILERS; BUILDINGS; CONTAINMENT; CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FUNCTIONAL MODELS; HEAT TRANSFER; KINETICS; MASS TRANSFER; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SEVERE ACCIDENTS; SIMULATORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 refs., 20 figs., 1 tab.; This record replaces 49020517