ORNL-1771 - Oak Ridge National Laboratory

UNCLASSIFIED
ORNL-LR-DWG 1552A
..............., ---
PERlOD ENDING SEPTEMBER IO, 1954
MTR NEUTRON-FLUX SPECTRA - RADIATION
DAMAGE STUDY
T. L. Trent J. 5. Trice
64 P. M. Uthe
Sol id State Division
-
32 J, Moteff
.- c
.- E
w 8
z +-
General Electric Company
16 Fission probes with different fissionable rna-
4
terials were used to make neutron flux traverses
in H5-3 of the MTR. The fissionable materials
used included U238, Y2361 Np237, and Th232,
whose fission threshold energies span the energy
region between '/2 and 2 MeV. The data from these
2
traverses will be used with the results from activations
in H5-3 of other, nonfi ssionable, threshold
detectors that are in the process of being irradi-
.I ated.
After measurements have been completed in HB-3
0.5
1800 1900 2000 ~100 2200 2300 2400
with the hole empty, several inches of beryllium
will be introduced into the hole in such a way as
TEMPERATURE (OF)
Fig. 9.9, Grain Growth Characteristics of In.
conel.
to change the energy distribution of the transmitted
neutrons. The new energy distribution will
then be measured, and materials will be irradiated
in both moderated and unrnoderated neutron spectra.
An attempt will then be made to correlate spectra
12
and radiation damoge.
"J. B. Trice and P. M. Uthe, Solid Stute Semiunn.
Prog. Rep. Fe6. 28, 1954, ORNL-1677, p. 14.
147