Cooling of safety rods in the Savannah River K reactor during the gamma heating phase of a postulated loss-of-coolant accident
- 1. Los Alamos National Lab., NM (United States). Nuclear Technology and Engineering Div.
Description
This paper documents the heat-transfer analysis for the safety rod placed in a perforated guide tube during the gamma heating phase of a large-break loss of coolant accident in Savannah River K-reactor. The cooling mechanisms are natural convection to air and radiation to the surrounding structures. The limiting component is the guide tube. The guide tube is shown to remain coolable below its thermal limit for the anticipated reactor powers unless it is contacted by the hotter safety rod. Sample calculations are performed for various contact scenarios, and the results are reported within the paper. The results indicate that the most limiting contact scenario results when the safety rod heats up to its maximum temperature while remaining concentric in the guide tube and then contacts the guide tube. The worse contact location appears to be in line with the slugs-cladding contact and in between the rows of holes in the guide tube
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0636-7
- Imprint Title
- 2nd ASME-JSME international conference on nuclear engineering -- 1993
- Imprint Pagination
- 770 p.
- Journal Page Range
- p. 105-116.
Conference
- Title
- 2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering.
- Dates
- 21-24 Mar 1993.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25058964
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COOLING; GUIDE TUBES; K REACTOR; LIMITING VALUES; LOSS OF COOLANT; MATHEMATICAL MODELS; RADIATION HEATING; SCRAM RODS; THEORETICAL DATA
- Descriptors DEC
- ACCIDENTS; CONTROL ELEMENTS; DATA; HEATING; HEAVY WATER MODERATED REACTORS; INFORMATION; NUMERICAL DATA; PRODUCTION REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SPECIAL PRODUCTION REACTORS; TUBES
Optional Information
- Secondary number(s)
- CONF-930352--.