ORNL-4191 - the Molten Salt Energy Technologies Web Site

4
V
S; 0.06
v
F
2.25
2.24
2.23
2.22
ORNL-DWG 67-14808
I I I I I
0' I I I I I
I I I
NEUTRON LOSSES TO MODERATOR r-
1 1 I
O 20 40 60 80
POWER DFNSITY (w/crnJ)
Fig. 4.3. Variation of MSBR Parumeters with Average
Core Power Density.
values of the adiustoble constant X.
Numbers attached to curves are
84
' :: 10
Useful Life 04 Moderator Graphite
A. M. Perry
Information currently used in the MSR project re-
garding the dependence of graphite dimensional
changes on fast neutron dose is derived primarily
from experiments carried out in the llounreay Fast
Reactor (DFR).
A curve of voliirne change vs fast neutron dose
for a nearly isotropic graphite at temperatures in
the range 550 to 6OOOC is shown in Fig. 6.4, which
is taken from the paper of Henson, Perks, and Sim-
mons.' (The neutron dose in Fig. 6.4 is expressed
....................
'R. '3'. Henson, A. J. Perks, and J. H. W. Simmons,
Lattice Parameter and Dimensional Changes in Graphite
Irradiated Between 300 and 1350°C, AEKE-XS489, to be
published in the proceedings of the Eighth Carbon Con-
ference.
-2 t
OR NL- DWG 67- 1 48 09
I
* 400-440"c
0 550-600°C I
0 1 2 3
EQUIVALENT PLUTO DOSE (40'~neutrons/cm')
Fig, 4.4. Yolrsme Changes of Near-Isotropic Graphite
Resulting from Neutron Irradiation.
terms of MSBR flux.
See text for dose in