Abstract
The design and performance of a relatively low-cost, plasma-based, 14-MeV D-T neutron source for accelerated end-of-life testing of fusion reactor materials are described in this article. An intense flux (up to 5×1018 n/m2·s) of 14-MeV neutrons is produced in a fully-ionized high-density tritium target (n e ≈ 3×1021 m−3) by injecting a current of 150-keV deuterium atoms. The tritium plasma target and the energetic D+ density produced by D0 injection are confined in a column of diameter ⩽ 0.16 m by a linear magnet set, which provides magnetic fields up to 12 T. Energy deposited by transverse injection of neutral beams at the midpoint of the column is conducted along the plasma column to the end regions. Longitudinal plasma pressure in the column is balanced by neutral gas pressure in the end tanks. The target plasma temperature is about 200 eV at the beam-injection position and falls to 5 eV or less in the end region. Ions reach the walls with energies below the sputtering threshold, and the wall temperature is maintained below 740 K by conventional cooling technology.
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Technical Planning Activity, Final Report (Chap. 5) (1987). (Argonne National Laboratory, Argonne, IL, ANL/FPP-87-1).
R. F. Post, T. K. Fowler, J. Killeen, and A. A. Mirin (1973).Phys. Rev. Lett.,31, 280.
W. Heckrotte, J. R. Hiskes, and R. P. Freis (1975).Proc. of 5th IAEA Conf. Plasma Phys. Cont. Fusion Research (Vol. 3) (Tokyo, Japan, 1974), p. 557; (1974).Parametric Survey for the Linear Two-Component System (Lawrence Livermore National Laboratory, Livermore, California, UCRL-75953, Rev. 1).
F. H. Coensgen et al., Proc. Int. Symp. Fusion Nucl. Technol., Tokyo, April 10–15, 1988,Fusion Eng. Design, May–June 1989.
C. D. Boley, R. K. Janev, and D. E. Post (1984).Phys. Rev. Lett.,52, 534.
L. Spitzer, Jr. (1956).Physics of Fully Ionized Gases (Interscience Publishers, New York) p. 86.
W. C. Turner et al. (1979).Nucl. Fusion,19, 1001.
D. L. Correll et al. (1980).Nucl. Fusion,20, 655.
W. L. Hsu, M. Yamada, and P. J. Barrett (1982).Phys. Rev. Lett.,49, 1001.
M. Fumelli, F. Jequier, and J. Pamela, Experimental Results of Energy Recovery on a Neutral Beam Injector, to be published inPlasma Phys. Cont. Fusion; M. Fumelli, F. Jequier, and J. Pamela (1988). Operation of the Tore Supra NBI with Energy Recovery of the Unneutralized Beam, Proc. 15th SOFT Conf., Utrecht, the Netherlands, September 19–23, 1988;Fusion Technology (1988). (Pergamon Press, Oxford).
F. H. Coensgen et al., MFTF-B Acceptance Tests and Operation, Proc. 11th Int. Conf. Plasma Phys. Cont. Nucl. Fusion Research, Kyoto, Japan, November 13–20, 1986.
J. R. Ferron, S. N. Golovato, N. Hershkowitz, and R. Goulding (1987).Phys. Fluids,30, 1869.
P. A. Bagryanskii et al. (1987).Proc. 11th Int. Conf. Plasma Phys. Cont. Fusion Research, Kyoto, 1986 (International Atomic Energy Agency, Vienna).
M. Z. Caponi, B. I. Cohen, and R. P. Freis (1987).Phys. Fluids,30, 1410.
P. D. Weber et al. (1986). 120-kV testing of a 10×40-cm prototype of the U.S. common long pulse neutral beam source,Rev. Sci. Instr.,57, 2714.
R. J. Burke et al. (1985). Super-FMIT, an accelerator-based neutron source for fusion components irradiation testing.Nucl. Instr. Meth.,B10/11, 483.
S. A. Khan and T. D. Rognlien (1981).Phys. Fluids.,24, 1442.
C. E. Walter and F. H. Coensgen, Design for a Fusion Material Irradiation Facility, Proc. 15th Symp. Fusion Technol., Utrecht, The Netherlands, September 19–23, 1988; (1988).Fusion Technology (Pergamon Press, Oxford).
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Coensgen, F.H., Casper, T.A., Correll, D.L. et al. Beam plasma neutron sources based on beam-driven mirror. J Fusion Energ 8, 237–247 (1989). https://doi.org/10.1007/BF01051652
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DOI: https://doi.org/10.1007/BF01051652