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Example text
_" A similar slope analysis of the data used to obtain Fig. I yields a comparable value of _ -_ 0,25, although this value cannot be considered as reliable due to the use of different copper specimens for the tensile and number density measurements, The polycrystal values for" _ obtained from the slope of the radiation hardening data are an upper limit for the matrix radiation hardening since the grain size-dependent hardening rate in polycrystals is higher than that for single crystals due to the Hall-Petch effect [Eq.
ENDF-210), 3rd ed. (ENDF/B-V)_ BNL-NCS-17451, 11. G. R. Odette and D. R. Dorian, Nucl. Tech. 29 (1976) 346. 12. T. W. Armstrong and K. C. Chandler, Nucl. Sci. Fng. 49 (1972) 110. 34 NEUTRON DOSIMETRY AND DAMAGE CALCULATIONS FORTHE ORR-MFE6JEXPERIMENT - L. R. Greenwood and D. V. Steldl (Argonne National Laboratory) OBJECTIVE To provlde dosimetry and damageanalysis for fusion reactor materia]s irradiation experiments. -Japanese MFE 6J experiment in the Oak Ridge Research Reactor. Specimens were irradiated from June 28, 1983 to March 26, 1987 (475 full_powerdays) in positionC7 at temperaturesof 60 and 200°C .
L, Heinisch, S. D. Atkin and C. Martinez, J. Nucl. Mater. 141-143 _(1986) 807. 13. H. L. Heinisch and C. Martinez, J. Nucl. Mater. 141-143 (1986) 883. 14. Y. Satoh, I. Ishida, T. Yoshiie and M. Kiritani, J. Nucl. Mater. 155-157 (1988) 443. 15. T. L. Johnston and C. E. Feltner, Met. Trans. I (1970) 1161. 16. M. A. Adams and P. R. B. Higgins, Phil. Mag. 4 (1959) 777. 17, M. J. Makin, in: Radiation Effects, Ed. W. F. Sheely (Gordon and Breach, New York, 1967) p. 627. 18. A. Rukwied, Z. Metallk. 55 (1964) 146.