PERFORMANCE OF FERRITIC ALLOYS IN ADVANCED (DD AND D**3He) FUELED INERTIAL CONFINEMENT FUSION REACTORS.

James F. Stubbins, Bradley J. Adams

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

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 languageEnglish (US)
Title of host publicationUnknown Host Publication Title
EditorsJ.W. Davis, D.J. Michel
PublisherMetallurgical Soc of AIME
Pages223-232
Number of pages10
ISBN (Print)0895204584
StatePublished - Dec 1 1984

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ASJC Scopus subject areas

  • Engineering(all)

Cite this

Stubbins, J. F., & Adams, B. J. (1984). PERFORMANCE OF FERRITIC ALLOYS IN ADVANCED (DD AND D**3He) FUELED INERTIAL CONFINEMENT FUSION REACTORS. In J. W. Davis, & D. J. Michel (Eds.), Unknown Host Publication Title (pp. 223-232). Metallurgical Soc of AIME.