Analysis of three ex-vessel loss-of-coolant accidents in the first wall cooling system of NET/ITER
Description
An ex-vessel LOCA may be caused by a rupture of a cooling pipe located outside the vacuum vessel. No plasma shutdown and no other counteractions have been assumed in order to study the worst case conditions of the accidents. The next three ex-vessel LOCAs in the primary cooling system of the first wall have been analysed: 1. a large break ex-vessel LOCA caused by a rupture of the cold leg (inner diameter 0.314 m) of the main circuit; 2. an intermediate break ex-vessel LOCA caused by a rupture of a sector inlet feeder (inner diameter 0.158 m); 3. an intermediate break ex-vessel LOCA caused by a rupture of the surge line (inner diameter 0.180 m) of the pressurizer. The analyses have been performed using the thermal-hydraulic system analysis code RELAP5/MOD3. In the first two scenarios, melting in the first wall starts about 90 s after break initiation. In the third scenario, melting in the first wall start about 323 s after break initiation. Special emphasis has been paid to the characteristics of the break flows, the transient thermal-hydraulic behaviour of the cooling system, and the temperature development in the first wall. (orig.)
Availability note (English)
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25035526.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 117 p.
- Report number
- ECN-R--93-001
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 25035526
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- COMPUTERIZED SIMULATION; COOLING SYSTEMS; FIRST WALL; HYDRAULICS; ITER TOKAMAK; LOSS OF COOLANT; MELTING; NET TOKAMAK; RUPTURES; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; CLOSED PLASMA DEVICES; FAILURES; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS