Small-break LOCAs. Analysis, control and experimental results
Description
With respect to small breaks, attention has been focused on two items: sufficient injection rates to assure adequate water inventory for decay heat removal; guaranteeing decay heat energy release through the availability of an additional heat sink. In KWU PWRs control of small breaks is guaranteed by automatic measures in the short term and by manual measures in the longer term. Besides the design of the safety injection pumps a main feature is the immediate shutdown of the secondary side to obtain an additional heat sink. The different energy transport modes from the core to the steam generators have been verified by tests in the PKL test facility. The PKL test facility represents a typical KWU 1300-MW(e) 4-loop PWR at a model scale of 1:134. In view of the importance of the driving gravity forces for natural circulation all heights and elevations correspond to actual reactor dimensions. The simulated loops have active steam generators whose secondary sides can be depressurized. In steady-state tests the behaviour of the system with subcooled and two-phase flow natural circulation as well as the energy transport from the core to the steam generators in the reflux condenser mode was investigated. The results proved that the decay heat could be removed from the primary system via the steam generator secondary side by natural circulation and with even better heat transfer in the reflux condenser mode. The analytical and experimental investigations have shown that in KWU PWRs the measures taken provide assured control of all conceivable break sizes. (author)
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna
- ISBN
- 92-0-020281-0
- Imprint Title
- Current nuclear power plant safety issues
- Imprint Pagination
- 682 p.
- Series
- Proceedings series.
- Journal Page Range
- v. 2 p. 663-674.
Conference
- Title
- International conference on current nuclear power plant safety issues.
- Dates
- 20 - 24 Oct 1980.
- Place
- Stockholm, Sweden.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 12638369
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DIAGRAMS; ENGINEERING; HEAT TRANSFER; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REACTOR SIMULATORS; SECONDARY COOLANT CIRCUITS; STEAM GENERATORS; TESTING
- Descriptors DEC
- ACCIDENTS; ANALOG SYSTEMS; BOILERS; COOLING SYSTEMS; ENERGY TRANSFER; FUNCTIONAL MODELS; INFORMATION; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SIMULATORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- IAEA-CN--39/30.