First results of the post-irradiation examination of the Ceramic Breeder materials from the Pebble Bed Assemblies Irradiation for the HCPB Blanket concept
Creators
- 1. NRG P.O. Box 25 1755 ZG Petten (Netherlands)
Description
In the framework of developing the European Helium Cooled Pebble-Bed (HCPB) blanket an irradiation test of pebble-bed assemblies is performed in the HFR Petten. The experiment is focused on the thermo-mechanical behavior of the HCPB type breeder pebble-bed at DEMO representative levels of temperature and defined thermal-mechanical loads. To achieve representative conditions a section of the HCPB is simulated by EUROFER-97 cylinders with a horizontal bed of ceramic breeder pebbles sandwiched between two beryllium beds. Floating Eurofer-97 steel plates separate the pebble-beds. The structural integrity of the ceramic breeder materials is an issue for the design of the Helium Cooled Pebble Bed concept. Therefore the objective of the post irradiation examination is to study deformation of pebbles and the pebble beds and to investigate the microstructure of the ceramic pebbles from the Pebble Bed Assemblies. This paper concentrates on the Post Irradiation Examination (PIE) of the four ceramic pebble beds that have been irradiated in the Pebble Bed Assembly experiment for the HCPB blanket concept. Two assemblies with Li4SiO4 pebble-beds are operated at different maximum temperatures of approximately 600 oC and 800 oC. Post irradiation computational analysis has shown that both have different creep deformation. Two other assemblies have been loaded with a ceramic breeder bed of two types of Li2TiO3 beds having different sintering temperatures and consequently different creep behavior. The irradiation maximum temperature of the Li2TiO3 was 800oC. To support the first PIE result, the post irradiation thermal analysis will be discussed because thermal gradients have influence on the pebble-bed thermo-mechanical behavior and as a result it may have impact on the structural integrity of the ceramic breeder materials. (author)
Files
38005569.pdf
Files
(10.4 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:7296813d3a3dfdb2da5a62c659dcfed4
|
10.4 kB | Preview Download |
Additional details
Identifiers
Publishing Information
- Imprint Title
- Books of invited abstracts
- Imprint Pagination
- 515 p.
- Journal Page Range
- p. 332
- Report number
- INIS-PL--2006-0010
Conference
- Title
- 24. Symposium on Fusion Technology - SOFT 2006
- Dates
- 11-15 Sep 2006
- Place
- Warsaw (Poland)
INIS
- Country of Publication
- Poland
- Country of Input or Organization
- Poland
- INIS RN
- 38005569
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BERYLLIUM; BREEDING BLANKETS; CERAMICS; COOLING; DEFORMATION; EXTERNAL IRRADIATION; HELIUM; HFR REACTOR; LITHIUM SULFATES; MICROSTRUCTURE; NEUTRON FLUX; OXIDES; SINTERING; STEELS; TEMPERATURE RANGE 0400-1000 K; THERMAL ANALYSIS; TITANIUM COMPOUNDS
- Descriptors DEC
- ALKALI METAL COMPOUNDS; ALKALINE EARTH METALS; ALLOYS; CARBON ADDITIONS; CHALCOGENIDES; ELEMENTS; ENRICHED URANIUM REACTORS; FABRICATION; FLUIDS; GASES; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION; IRRADIATION REACTORS; LITHIUM COMPOUNDS; MATERIALS TESTING REACTORS; METALS; NONMETALS; OXYGEN COMPOUNDS; RADIATION FLUX; RARE GASES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SULFATES; SULFUR COMPOUNDS; TANK TYPE REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS