The performance of ferritic alloys in advanced-fueled inertial confinement fusion systems is studied. Advanced-fuel pellets, which are tritium self-sufficient, allow a unique approach to reactor chamber design. The need for a large lithium-containing blanket to breed tritium is eliminated and, therefore, flexibility in liquid metal chamber coolant choice is possible. Neutronics calculations to determine radiation damage and gas production rates in several commonly proposed reactor structural materials were performed. Relations are presented which correlate damage rates to expected wall life and results of expected wall life for the proposed chamber structural materials are given. The advantages gained in terms of wall life with advanced-fuel pellets over standard DT pellets are shown.
|Original language||English (US)|
|Title of host publication||Unknown Host Publication Title|
|Editors||J.W. Davis, D.J. Michel|
|Publisher||Metallurgical Soc of AIME|
|Number of pages||10|
|State||Published - Dec 1 1984|
ASJC Scopus subject areas