Flow reduction transient burnout in an annular test section
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
In order to understand the transient boiling phenomena during PCM (power-cooling-mismatch) in light water reactors, transient burnout experiments were performed using a vertical annular test section under atmospheric pressure. The gap between the electrically heated stainless steel tube and the outer glass shroud was 2.0 mm and 1.4 mm, and the heated tube outer diameter and length were 10 mm and 800 mm respectively. Experiment ranges were as follows. Heat flux: 0.65 -- 1.36 x 106 kcal/hm2, inlet water temperature: 30 -- 760C, initial mass velocity: 2.4 -- 6.0 x 106 kg/hm2, flow reduction time: 0.1 -- 68 sec, and flow reduction rate: 0.29 -- 752 cm/sec/sec. The experimental results showed that beyond a flow reduction rate of about 5 cm/sec/sec (1.4 mm gap) and about 1 cm/sec/sec (2.0 mm gap), burnout mass velocity became lower than the steady state one. When the flow reduction rates were further increased to 20 -- 40 cm/sec/sec or beyond, the burnout delay time became constant at about 0.4 sec. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
11502933.pdf
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Additional details
Additional titles
- Subtitle (English)
- Transient flow boiling under atmospheric pressure, (6)
Publishing Information
- Imprint Pagination
- 106 p.
- Report number
- JAERI-M--8047
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 11502933
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ANNULAR SPACE; BURNOUT; CRITICAL HEAT FLUX; EXPERIMENTAL DATA; FLOW RATE; GRAPHS; POWER-COOLING-MISMATCH ACCIDEN; REACTOR SAFETY; TRANSIENTS; TRANSITION BOILING; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; BOILING; CONFIGURATION; DATA; DATA FORMS; FLUID FLOW; HEAT FLUX; INFORMATION; NUMERICAL DATA; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; SAFETY