A Technical Note on D-T Fusion Reactor Afterheat
- 1 March 1971
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 10 (3), 391-392
- https://doi.org/10.13182/nt71-a30972
Abstract
The afterheat in a D-T fusion reactor of conventional design is shown to be a serious consideration for loss-of-flow or loss-of-coolant accidents. Some previous estimates of the radioactivation of a niobium vacuum wall and structure are shown to be grossly low. The major additional contributions to the afterheat are from 94mNb, 92mNb, 95Nb, 95mNb, and a long-lived metastable state of93Nb. By considering some of these additional decay sources, the afterheat from a 5-GW(th) D-T reactor of typical design is computed to be at least 30 MW. Early in the reactor lifetime, the decay of the after-heat power should be characterized by the 10.1-day half-life of 92mNb. A qualitative review of the activation cross sections of molybdenum, an alternate possibility as a structural material, does not give expectation of decay powers significantly lower than niobium.Keywords
This publication has 5 references indexed in Scilit:
- The Nuclear Performance of Fusion Reactor BlanketsNuclear Applications and Technology, 1970
- NEUTRON BLANKET CALCULATIONS FOR THERMONUCLEAR REACTORS. [PART] II.Published by Office of Scientific and Technical Information (OSTI) ,1969
- COMPILATION OF ENDF/B DATA FOR MAGNESIUM, TITANIUM, VANADIUM, MOLYBDENUM, AND GADOLINIUM.Published by Office of Scientific and Technical Information (OSTI) ,1968
- FEASIBILITY OF POWER BY NUCLEAR FUSION.Published by Office of Scientific and Technical Information (OSTI) ,1968
- Analysis of (n, 2n) Cross Sections for Medium and Heavy Mass NucleiNuclear Science and Engineering, 1965