Effect of flow blockage on reflooding behaviour in pressure - tube type reactor
Creators
- 1. Power Reactor and Nuclear Fuel, Development Corporation (Japan)
Description
The purpose of the full-scale reflooding tests were to study the effects of flow blockage, reflooding rate and initial cladding temperature on reflooding behaviour and the effectiveness of heat removal. Reflooding tests were conducted with a 370 cm-long electrically heated 28-rod bundle. A flow blockage, with an axial length of 3 inches, of approximately 60 % of the flow area in a pressure tube was mounted at the middle elevation of the rods to simulate the uniform expansion of each of the outer 16 rods. The experimental results are as follows: 1. Heat transfer coefficients at the just downstream positions of the flow blockage are lower than those for other positions, but they are higher than 25 BTU/ft2.hr.F. Delay of the turn-around time at the zone is negligible. 2. Quench time and turn-around time increased with decreasing reflooding rate. 3. Heat transfer coefficient increased with increasing initial temperature
Additional details
Publishing Information
- Imprint Title
- Proceedings of a specialist meeting on the behaviour of water reactor fuel elements under accident conditions
- Imprint Pagination
- 774 p.
- Journal Page Range
- p. 2-23
- Report number
- NEA-CSNI-R--1977-13
Conference
- Title
- Specialist meeting on the behaviour of water reactor fuel elements under accident conditions
- Dates
- 13-16 Sep 1976
- Place
- Spaatind (Norway)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 42006192
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ECCS; FLOW BLOCKAGE; HEAT TRANSFER; JATR REACTOR; LOSS OF FLOW; NEA; PRESSURE TUBE REACTORS; PRESSURE TUBES; QUENCHING; REACTOR ACCIDENT SIMULATION; REACTOR COOLING SYSTEMS; REACTOR EXPERIMENTAL FACILITIES; REACTOR SAFETY; TEMPERATURE DEPENDENCE
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; HEAVY WATER MODERATED REACTORS; HWLWR TYPE REACTORS; INTERNATIONAL ORGANIZATIONS; NATURAL URANIUM REACTORS; OECD; PLUTONIUM REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; TUBES; WATER COOLED REACTORS
Optional Information
- Notes
- 11 refs.