Pre-irradiation testing of actively cooled Be-Cu divertor modules
- Forschungszentrum Juelich GmbH (Germany); and others
A set of neutron irradiation tests is prepared on different plasma facing materials (PFM) candidates and miniaturized components for ITER. Beside beryllium the irradiation program which will be performed in the High Flux Reactor (HFR) in Petten, includes different carbon fiber composites (CFQ) and tungsten alloys. The target values for the neutron irradiation will be 0.5 dpa at temperatures of 350{degrees}C and 700{degrees}C, resp.. The post irradiation examination (PIE) will cover a wide range of mechanical tests; in addition the degradation of thermal conductivity will be investigated. To determine the high heat flux (HHF) performance of actively cooled divertor modules, electron beam tests which simulate the expected heat loads during the operation of ITER, are scheduled in the hot cell electron beam facility JUDITH. These tests on a selection of different actively cooled beryllium-copper and CFC-copper divertor modules are performed before and after neutron irradiation; the pre-irradiation testing is an essential part of the program to quantify the zero-fluence high heat flux performance and to detect defects in the modules, in particular in the brazed joints.
- Research Organization:
- Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
- OSTI ID:
- 212912
- Report Number(s):
- CONF-9509218-; ON: DE96002404; TRN: 96:010061
- Resource Relation:
- Conference: 2. International Energy Agency (IEA) workshop on beryllium technology for fusion, Jackson, WY (United States), 6-8 Sep 1995; Other Information: PBD: Sep 1995; Related Information: Is Part Of Proceedings: 2nd IEA international workshop on beryllium technology for fusion; Longhurst, G.R.; PB: 399 p.
- Country of Publication:
- United States
- Language:
- English
Similar Records
Numerical Analysis of Fatigue Behavior of ITER-Like Monoblock Divertor Interlayer Under Coupled Heat Loads
Development of ITER Divertor Vertical Target with Annular Flow Concept - II: Development of Brazing Technique for CFC/CuCrZr Joint and Heating Test of Large-Scale Mock-Up