ORNL-4191 - the Molten Salt Energy Technologies Web Site

io9
5
2
408
DlST4NCE FROM SURF4CE (mils)
ORNL-DIG 67-4 2237
Fig, 9.7. Distribution Profile of 89Sr in Graphite
from MSRE Core.
Graphite
Location
125
specimen but about the same deposited activity
in the two series of tests.
The uranium values correspond in every case to
negligible quantities. It appears that, if these
analyses are typical of all metal suriaces in the
system, about 1 g of 235U may be deposited on or
in the Nastelloy of the MSRE,
Fission Product Distribution in MSRE
The computer code for calculation of total inventory
of many fission product nuclides in the
operating MSRE has not yet been completed. Accordingly,
no detailed information as to expected
quantities of several isotopes is available. IIowever,
from the data given in previous sections of
this chapter approximate values can be given for
the distribution of several important fission products
among the salt, graphite, and metal phases
of the reactor system. These are presented in
Table 9.7. Such approximate values must, of
course, assume that the fission products found
on the relatively small samples from the surveillance
specimens in midcore are those to be found
on all graphite and metal in MSRE.
Since there is, as yet, no test of this assumption
we regard the values in Table 9.7 as tentativc.
Table 9.3. Fission Product Deposition on MSRE Graphite Faces After 24,000 Mwhr
____
Fission Product (dis rnin-' rrn--')
Face 66-hr 78-hr 37.6-day 1.02-year 35-day 65-day
~- .... . . . . .. ____
"Mo 132Te Io3Ru Io6Ru "Nb 95zr
x 1010 x 1010 io9 x 108 x 10'O x 108
TOP 1 2.10 1.45 4.54 2.26 5.00 2.26
2 3.59 1.75 8.86 3.58 6.15 3.58
3 2.76 1.74 6.97 2.77 4.77 2.77
4 6.30 3.52 15.9 3.08 9.16 3.08
Middle 1 2.28 2.51 6.92 3.51 2.00 3.51
2 5.32 3.47 12.9 6.33 17.8 6.33
3 6.16 3.31 7.91 7.91
4 5.41 4.68 15.9 6.98 15.4 6.98
Bottom 1 3.24 1.79 6.95 3.11 11.6 3.11
2 8.05 4.50 18.6 8.01 30.6 8.04
3 2.85 2.22 9.72 3.64 14.2 3.64
4 3.43 2.14 8.65 3.74 13.3 3.74
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