Fundamental study on thermo-hydraulic behaviors of a fuel channel during a severe power transient
- 1. Tokyo Inst. of Tech. (Japan). Research Lab. of Nuclear Reactor
Description
Thermo-hydraulic behavior during a severe power transient is studied experimentally. A stainless rod of 4mm in diameter and 120mm in length, simulating a fuel rod is transiently heated by Joule heating using discharge of a power condenser charged up to 50KJ. Expansion of transiently developed thermal boundary layer, transient nucleate and film boiling around the heater rod generate a high pressure pulse which is converted to mechanical energy of the fluid. When the power input becomes large enough, the heated rod is melted and dispersed into the liquid. The peak pressure and the mechanical energy due to the transient power input are investigated for various power input and coolant conditions. The main results are; 1. When the heated rod do not melted, there is a combination of power input and subcooling that generates peak pressure and maximum mechanical energy where nucleate boiling is the dominant mechanism through the transient. However, they are suppressed in the high power input region. 2. When the rod melts, the peak pressure and the mechanical energy increase to about 10 times larger than those of the non-melting case. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- The 1st JSME/ASME joint international conference on nuclear engineering
- Imprint Pagination
- 1273 p.
- Journal Page Range
- v. 2 p. 227-233.
Conference
- Title
- 1. JSME/ASME joint international conference on nuclear engineering.
- Dates
- 4-7 Nov 1991.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 23075989
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EXCURSIONS; FILM BOILING; FUEL CHANNELS; HYDRAULICS; LWGR TYPE REACTORS; MOCKUP; NUCLEATE BOILING; SIMULATION; THERMODYNAMIC PROPERTIES; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BOILING; GRAPHITE MODERATED REACTORS; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; STRUCTURAL MODELS; WATER COOLED REACTORS
Optional Information
- Notes
- Imprint:Composed of two volumes.