Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 10 / Number 2 / Pages 243-252
Glen R. Edwards, Kent A. Jones, Steven F. Halvorson
Fusion Science and Technology / Volume 10 / Number 2 / Pages 243-252
Format:electronic copy (download)
Recent inertial confinement fusion reactor designs utilize liquid 17Li-83Pb blankets to absorb the neutron and thermal fluxes. One of the crucial concerns of these designs is the compatibility of structural alloys with this lithium-lead alloy, especially because of this liquid's possible propensity for embrittling materials. Current candidate pressure vessel steels for liquid lithium or lithium-lead containment are the Cr-Mo steels such as HT-9 (12 Cr-1 Mo), 2.25 Cr-1 Mo, and niobium-stabilized 2.25 Cr-1 Mo. This investigation was therefore aimed at characterizing the lithium-lead embrittlement susceptibility of the weldments of these steels subjected to a 17Li-83Pb liquid. Results of these embrittlement studies have shown that as-welded heat-affected zones of low phosphorus and sulfur 2.25 Cr-1 Mo, niobium-stabilized 2.25 Cr-1 Mo, and HT-9 steels all exhibit liquid-metal-induced embrittlement susceptibility when subjected to a 17Li-83Pb liquid. The embrittlement, however, was found to be very dependent on post-weld heat treatment. Normally extensive post-weld heat treatments greatly ameliorate the 17Li-83Pb embrittlement, rendering these steels acceptable for 17Li-83Pb containment.
Your cart is empty.
Home|Invoice Payment|Nuclear Links