After-heat removing device from PWR type reactor core
Description
A gas stagnation prevention means is disposed between a reactor container and a steam generator so that incondensible gases generated in a reactor do not disturb the natural convection of coolants upon loss of coolant accident As a result, since the coolants can be naturally circulated in a primary coolant loop by utilizing a steam generator without relying on an active safety system which requires an external driving source such as an AC power source, the operation procedure is simple and the reliability of the safety system is high. In particular, if a customary steam generator is used, no additional facility is necessary, thereby enabling to simplify the facility and improve the economical property. In addition, since it is designed intending for heat removal from the reactor core during normal operation, it has an excellent cooling performance. (N.H.)
Availability note (English)
Available from JAPIO. Also available from INPADOC.Additional details
Publishing Information
- Imprint Pagination
- 19 p.
- IPC:
- Int. Cl. G21C15/18.
- IPC
- Int. Cl. G21C15/18.
- Patent number
- JP patent document 4-109197/A/
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 24007298
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; COOLANTS; LOSS OF COOLANT; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR CORES; REACTOR VESSELS; STEAM GENERATORS
- Descriptors DEC
- ACCIDENTS; BOILERS; CONTAINERS; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- JP patent application 2-401077.