Containment related tests at HDR - energy transfer to structures
Creators
Description
The containment experiments conducted at the HDR facility represent an important contribution to a better understanding of the physical processes taking place within the containment after a LOCA. The experiments have greatly expanded the limited data base of measured energy and mass transfer rates within and between large, complex geometry volumes. The new data has: (A) In several domains bracketed the parameter range to be found in actual reactor containments. As a consequence, interpolation rather than extrapolation of experimental data can now be used in containment analysis. (B) Provided severe tests of some modeling aspects. The tests have shown that in the best estimate sense shortcomings exist in the modeling of: (1) energy transfer into structures; and (2) short term pressure gradients between containment zones. This presentation analyses the experiment to calculation agreement of energy transfer into structures
Additional details
Publishing Information
- Imprint Title
- Eleventh water reactor safety research information meeting. Volume 3. Containment systems research; status of source term reassessment; fuel systems research program; risk analysis
- Journal Page Range
- p. 325-360.
- Report number
- NUREG/CP--0048-Vol.3
Conference
- Title
- 11. NRC water reactor safety research information meeting.
- Dates
- 14-24 Oct 1983.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16010906
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BLOWDOWN; CONTAINMENT SYSTEMS; ENERGY TRANSFER; EXPERIMENTAL DATA; HDR REACTOR; LOSS OF COOLANT; MECHANICAL STRUCTURES; PRESSURE GRADIENTS; REACTOR SAFETY; RESEARCH PROGRAMS; STEAM; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; CONTAINMENT; DATA; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS