Review of Molten Salt Reactor Physics Calculations [Disc 2]

Table 3.1 (cont 'a)
mUclide ua(2200), b. Data Sources
Nickel 4.6
Molybdenum
Lead
sodium
Fluorine
~ithi~m-6
Lithim-7
Carbon
Beryllium
*91
l35xe
-325 (Ref. 9)
[uS(2200) = 17.5 bo]
2.70 BIG-325 (Ref. 1)
fus(2200) = 7.061
0.170 BIBEX5 (Ref. '9)
[~,(2200) = 11.0 b.1
0,534 BNL-325 (Ref. 1)
[~,(2200) = 40.0 b.1
0.0098 -325 (Ref. 1)
[uS(2200) = 3.9 b.1
945 -0 BIoE325 (Ref.
[us(2200) = 1.
0 037
tj
-
-325 (Ref. 1
[us(2200) 1.4
0.004 Average of measurements
of delivered
-
graphite to
WCR.
[us(Z!200) 4.8J
0 0095
=325 (Ref. 1)
[us(2200) = 7.0J
13.9 ' BIG0325 (Ref.. 9)
31.0 mock et
2.65 x lo6 AEEW-RllG (Ref. 14)
I
Basis for the Energy Dependence
of the Cross Section
Assumed' l/v in thermal range.
Assumed l/v
Assumed l/v
Assumed l/v
Assumed l/v
Assumed l/v
Assumed l/v
Assumed l/v
Assumed l/v
Assumed l/v
Assumed l/v
Computed by
in thermal range.
in thermal range.
in them1 range.
in thermal range.
in therm3 range
in thermal range
in thermal range.
in thermal range.
method outlined in m-rn16.
P
o\
t
a