ORNL-4191 - the Molten Salt Energy Technologies Web Site

m
40 00
5 50
CRNL DWC 67 11818
109
IS 18 ,‘rl 22 74 .n 71 30 ‘7 34 3- 58 40
MIG~~LVOI
r IIOJRS (~10~1
Fig. 8.2. Uranium Concentration in MSRE Fuel Salt.
I? 00
,-
the present uranium concentration While this
6:
; ! I 50
method has been used with moderate success with
the MSRE fuel salt, the low total concentration of
2
o
0
10 00
4 700
4 500
40
20
200
0
uranium which is anticipated in future fuel salts
makes it improbable that this method can have
continued application. It will be of considerable
importance in the near future to employ dlrect
spectrophotometnc methods for the determination
of u3+ concentration in the fuel salt. Results of
recent laboratory experiments indicate that this
approach is feasible. ’
In the future, the MSKE fuel sa!t as well as the
fuel salts in the large reactor plants will be subjected
to fluorination and to HF-W, purge streams
during chemical reprocessing. Salt streams in
those teactors may be expected to contain even
lower concentrations of contaminant oxides than
currently exist in the MSRE and should therefore
not require oxide analysis
Results of the chemical analysis for chromium
have shown sufficient precision (110%) that the
method has come to serve as an excellent and
reliable measure of generalized corrosion within
the MSRE The utility of this analysls as an
indicator results from the tsct that at present
the total concentration of chroniium in the fuel
salt is low (9‘0 ppm). Relatively minor changes
are, therefore, reflected in significant
n
I ri concentratlon. In future
J
LIJ Y
100
I o 4 5 6 7 8 9 1 0 1 1 12
RiJN NUMBER
Flg. 8.1. Summary of MSRE Fuel Solt Analyses.
operation it is possible that the total concentra-
tion of chromium in the fuel circuit will increase
~
-
A S. Meyer, Jr., to R. E. Thoma, prlvate communlration,
May 12, 1967.
’J. P. Young, MSR Program Sen7rann Progr Rept
Fer). 28, 1967, ORNL-4119, p. 153.