| Autor: |
L. Baraer, E. Proust, J. Quintric-Bossy, X. Raepsaet, L. Giancarli, L.A. Sedano, J. Szczepanski, Y. Severi, J.-F. Salavy, B. Bielak |
| Rok vydání: |
2002 |
| Předmět: |
|
| Zdroj: |
15th IEEE/NPSS Symposium. Fusion Engineering. |
| DOI: |
10.1109/fusion.1993.518272 |
| Popis: |
For several years the EC laboratories have developed breeding blankets for DEMO. From this experience, it has been derived a proposal of tritium breeding blanket for the Extended Performance Phase (EPP) of ITER. The general basic ideas are the following: i) the switch from the shielding blanket used during the BPP to the breeding blanket for the EPP should not require segments replacement ("convertible" blanket); ii) its use should not have significant impact on the Basic Performance Phase (BPP); iii) design and used materials should assure good safety standards and acceptable public perception; iv) the blanket coolant should be compatible with the coolant required in the high heat-flux components (e.g. Divertor, etc.); v) the required RD vi) the blanket should be able to withstand large power excursions and to accept long downtimes. The proposed design consists of a water-cooled liquid metal blanket, using the eutectic Pb-17Li during the EPP and a non-breeding Pb-alloy (Pb-18Mg or Pb-50Bi) during the BPP. Each segment is basically formed by a box containing the alloy, cooled by an array of poloidal hairpintype cooling tubes and reinforced by toroidal and radial stiffeners. The coolant tubes are double-walled tubes allowing leak detections. The selected First Wall (FW) is a toroidally-drilled steel plate with brazed water-cooling U-tube. The structural material is austenitic stainless steel (316L(N)) which limits the maximum acceptable neutron fluence to about 1 MWa/m/sup 2/. The advantages of using other structural materials requiring longer leadtimes, such as ferritic/martensitic steels, are also briefly discussed. |
| Databáze: |
OpenAIRE |
| Externí odkaz: |
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