Design standard issues for ITER in-vessel components

Design standard issues for ITER in-vessel components

Design loadings and potential mechanical damage in ITER in-vessel components are enumerated. Design by analysis requirements for ITER blanket and divertor are discussed in the light of the decreasing ductility of the structural material as a function of the neutron fluence. The applicability and lim...

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Veröffentlicht in:Fusion engineering and design 1995-03, Vol.29, p.158-163
1. Verfasser: Majumdar, Saurin
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Sprache:eng
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Applied sciences
Controled nuclear fusion plants
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Installations for energy generation and conversion: thermal and electrical energy
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description Design loadings and potential mechanical damage in ITER in-vessel components are enumerated. Design by analysis requirements for ITER blanket and divertor are discussed in the light of the decreasing ductility of the structural material as a function of the neutron fluence. The applicability and limitations of the ASME Boilers and Pressure Vessels Code, Section III to ITER components are discussed. The design rules from fission reactor core components are reviewed for potential application to ITER.
doi_str_mv 10.1016/0920-3796(95)80017-R
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subjects Applied sciences
Controled nuclear fusion plants
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Installations for energy generation and conversion: thermal and electrical energy
title Design standard issues for ITER in-vessel components
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