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1
PHENIX PFC evaluation by tritium Plasma, HEat and Neutron Irradiation eXperiments
2013~2018Japan USA
Representative Yoshio Ueda (Osaka U.) Peter Pappano (DOE)Coordinator Yuji Hatano (U. Toyama) Peter Pappano (DOE)
Japan-US Joint Project Technological Assessment of Plasma
Facing Components for DEMO Reactors
2Summary of the project
The goal of this project is to evaluate the feasibility of He gas-cooleddivertor with neutron irradiated tungsten armor materials for DEMOreactors. Main research subjects are listed below;
1. Heat transfer mechanism and modeling in He-cooled systems,improvement of cooling efficiency and system design.
2. Response of tungsten layered materials and advanced tungstenmaterials to steady state and pulsed heat loads.
3. Thermo-mechanical properties measurement of tungsten basedmaterials after neutron irradiation at elevated temperatures relevantto divertor conditions (500-1200 oC).
4. Effects of high flux plasma exposure on tritium behavior in neutron-irradiated tungsten materials.
5. Evaluation of feasibility (under ~10 MW/m2 heat load with irradiationof plasma and neutrons) and safety (tritium retention andpermeation) of He-cooled PFCs and clarification of critical issues forDEMO divertor design.
3Structure of this Project
Task 3(TPE, Idaho NL)
Permeation devices (INL, SNL)
Tritium Behaviorin n damaged W
Task 2(HFIR, Oak Ridge NL)Neutron-irrad. Effects Physical PropertiesThermo mechanical