1-pin blanket mockup: Results of the extended test campaign
- 1. EURATOM-ENEA, Frascati (Italy)
- 2. ENEA, S. Maria in Galeria (Italy)
Description
Following a preliminary test campaign (200 thermal cycles) on a solid breeder blanket mockup, an extended test campaign (about 1000 thermal cycles) has been carried out by ENEA. The duration of the test campaign represents a significant fraction of the blanket module lifetime in the ITER device. In particular, these out-of-pile experiments have been performed in order to test (both functional and endurance testing) the thermal-hydraulic and thermo-mechanical performance of a water cooled breeder-in-tube blanket mockup (1-PIN) using Li2ZrO3 pebbles as a breeder material. The test campaign has been completed and the resulting data concerning thermal and thermal-hydraulic parameters have been elaborated and analyzed by means of a comparison with theoretical predictions based on a proper thermal-hydraulic model. The post test examination of the pebbles is in progress in order to investigate the thermo-mechanical behavior of the breeder material under cycling. The paper deals with the first part of the results. 6 refs., 11 figs., 1 tab
Additional details
Publishing Information
- Journal Title
- Fusion Technology
- Journal Volume
- 30
- Journal Issue
- 3
- Journal Page Range
- p. 1011-1015.
- ISSN
- 0748-1896
- CODEN
- FUSTE8
Conference
- Title
- Annual meeting of the American Nuclear Society (ANS).
- Dates
- 16-20 Jun 1996.
- Place
- Reno, NV (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28039907
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BREEDING BLANKETS; COOLING SYSTEMS; HEAT TRANSFER; HYDRAULICS; ITER TOKAMAK; LITHIUM COMPOUNDS; MOCKUP; NUMERICAL DATA; TESTING; THERMAL CYCLING; THERMOMECHANICAL TREATMENTS; THERMONUCLEAR REACTOR MATERIALS; WATER
- Descriptors DEC
- ALKALI METAL COMPOUNDS; CLOSED PLASMA DEVICES; DATA; ENERGY TRANSFER; FABRICATION; HEAT TREATMENTS; HYDROGEN COMPOUNDS; INFORMATION; MATERIALS; MATERIALS WORKING; OXYGEN COMPOUNDS; STRUCTURAL MODELS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Secondary number(s)
- CONF-9606116--.