Transient analysis of the water-cooled eutectic LiPb blanket of NET
Description
For the liquid LiPb blanket concept of NET the response of the first wall and the water cooled blanket to coolant tube blockage, loss of pumping power and coolant tube break events has been evaluated. Thermal-hydraulic calculations were carried out with the code RELAP followed by 2- and 3-dimensional transient non-linear heat transfer calculations with the code MARC. The main conclusion is that the concept of two parallel coolant loops provides a good safety measure since a flow coastdown in one coolant loop while the plasma is still burning does not lead to any significant temperature increase of the structures. Also passive shutdown cooling by natural convection flow or thermal radiation is sufficiently adequate to remove the decay heat in first wall and blanket. (author). 7 refs, 11 figs, 3 tabs
Additional details
Publishing Information
- Imprint Title
- Fusion reactor safety
- Imprint Pagination
- 367 p.
- Journal Page Range
- p. 113-121.
- Report number
- IAEA-TECDOC--440
Conference
- Title
- Technical committee meeting on fusion reactor safety.
- Dates
- 3-7 Nov 1986.
- Place
- Culham (UK).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 19056813
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; BREEDING BLANKETS; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; NET TOKAMAK; THERMONUCLEAR REACTOR COOLING; TRANSIENTS
- Descriptors DEC
- CLOSED PLASMA DEVICES; COOLING SYSTEMS; ENERGY TRANSFER; SIMULATION; THERMONUCLEAR DEVICES; TOKAMAK DEVICES