Published 1900
| Version v1
Report
Evaluation of conservatism in analysis of fuel-coolant interaction
- 1. Virginia Univ., Charlottesville (USA)
- 2. USAEC Directorate of Licensing, Washington, D.C.
Description
Using the ANL parametric model developed by Cho e.a. the following mechanisms and parameters involved in fuel-coolant interaction were examined: coherence of fuel-sodium mixing; two-phase heat transfer; sodium-to-fuel mass ratio; fuel particle size; heat transfer to plenum and core cladding; constraint geometry. Both overpower and loss-of-flow transients were studied. Main attention is given to the maximum mechanical work to be expected. As a general conclusion, it can be stated that more realistic models will result in a reduction of the estimated mechanical work
Additional details
Publishing Information
- Imprint Title
- Second specialist meeting on sodium/fuel interaction in fast reactors, Ispra, 21-23 November 1973
- Imprint Pagination
- p. 571-601 (paper SNI 2-6).
- Report number
- EUR--5309
Conference
- Title
- 2. Specialist meeting on sodium/fuel interaction in fast reactors.
- Dates
- 21 Nov 1973.
- Place
- Ispra, Italy.
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- European Commission (EC), Brussels (Belgium)
- INIS RN
- 7229216
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONFIGURATION; COOLANTS; HEAT TRANSFER; LIQUID METALS; LOSS OF COOLANT; MASS; MELTING; MIXING; NUCLEAR FUELS; PARTICLE SIZE; SODIUM; TRANSIENTS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; FLUID FLOW; FLUIDS; FUELS; LIQUIDS; METALS; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTOR MATERIALS; SIZE