Conceptual design of helium experimental loop
Description
In a future demonstration fusion power station (DEMO), helium is envisaged as coolant for plasma facing components, such as blanket and dive,or. All these components have a very complex geometry, with many parallel cooling channels, involving a complex helium flow distribution. Test blanket modules (TBM) of this concept will under go various tests in the experimental reactor ITER. For the qualification of TBM, it is indispensable to test mock-ups in a helium loop under realistic pressure and temperature profiles, in order to validate design codes, especially regarding mass flow and heat transition processes in narrow cooling channels. Similar testing must be performed for DEMO blanket, currently under development. A Helium Experimental Loop (HELOOP) is planed to be built for TBM tests. The design parameter of temperature, pressure, flow rate is 550 degree C, 10 MPa, l kg/s respectively. In particular, HELOOP is able to: perform full-scale tests of TBM under realistic conditions; test other components of the He-cooling system in ITER; qualify the purification circuit; obtain information for the design of the ITER cooling system. The main requirements and characteristics of the HELOOP facility and a preliminary conceptual design are described in the paper. (authors)
Additional details
Publishing Information
- Imprint Title
- Ninth China-Japan symposium on materials for advanced energy systems and fission and fusion engineering jointed with CAS-JSPS core-university program seminar on fusion materials, system and design integration book of abstracts
- Imprint Pagination
- 117 p.
- Journal Page Range
- p. 107
Conference
- Title
- 9. China-Japan symposium on materials for advanced energy systems and fission and fusion engineering jointed with CAS-JSPS core-university program seminar on fusion materials, system and design integration
- Dates
- 23-26 Oct 2007
- Place
- Guilin (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 44042209
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COOLANTS; COOLING; COOLING SYSTEMS; DESIGN; DISTRIBUTION; EXPERIMENTAL REACTORS; FIRST WALL; FLOW RATE; HEAT; HELIUM; ITER TOKAMAK; TESTING; THERMONUCLEAR POWER PLANTS
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELEMENTS; ENERGY; ENERGY SYSTEMS; FLUIDS; GASES; NONMETALS; POWER PLANTS; RARE GASES; REACTORS; RESEARCH AND TEST REACTORS; THERMAL POWER PLANTS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS