Quenching of metal surfaces in a narrow annular gap
Creators
- 1. Fauske and Associates, Inc., Burr Ridge, IL (United States)
Description
The quenching of overheated core debris and reactor components is the fundamental objective of emergency procedures and accident management guidelines. Knowing the reasons that (a) quenching can occur and (b) the approximate net steam generation are important elements for developing such guidelines. For example, the TMI-2 accident resulted in high temperature core debris draining into the RPV lower head (approximately 20 tons) with the resulting consequence that a significant part of the vessel lower head was heated to temperatures of approximately 1100 deg C. At this time, the lower plenum wall apparently cooled rapidly (10 to 100 deg C/min) and the vessel integrity was preserved. What was the reason that such cooling occurred? Is this specific to the TMI-2 design and accident sequence or is it more generic? There is experimental evidence that a contact resistance, specifically a narrow gap, is formed when molten material contacts a metal surface which is submerged in water. If a narrow gap exists, what would be the cooling behavior in this gap? Is such cooling important to preservation of the vessel integrity? To address these questions, fundamental experiments have been performed to assess the counter-current two-phase cooling rate in narrow annular gaps (1 to 3 mm) with an overlying water pool. These experiments were performed on concentric carbon steel pipes with initial temperatures of approximately 800 deg C; the cooling transient being monitored by thermocouples in the steel walls. The measured cooling transients show that significant cooling can occur in narrow gaps. Through such fundamental investigations, the importance of cooling in such narrow regions for reactor accident conditions can be assessed for different reactor designs and for various possible debris locations in these designs. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-47-X
- Imprint Title
- Simulation methods in nuclear engineering
- Imprint Pagination
- 2 v.
- Journal Page Range
- (v.2) [14 p.]
Conference
- Title
- 5. International conference on simulation methods in nuclear engineering
- Dates
- 8-11 Sep 1996
- Place
- Montreal, PQ (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 33018547
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNULAR SPACE; COUNTERFLOW SYSTEMS; FILM BOILING; HEAT FLUX; HEAT TRANSFER; QUENCHING; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR CORE DISRUPTION
- Descriptors DEC
- ACCIDENTS; BOILING; CONFIGURATION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; SPACE
Optional Information
- Notes
- 5 refs., 1 tab., 8 figs.