Small Liquid Metal Cooled Reactor Safety Study Page: 54 of 63
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Comparison of Neutron Balance and Core Spectra
1E19.
1E18.
1E17.
S1E16.
e 1E15
1E14.Pb ENHS
Na ENHS (P/D=1 36,12 20% Pu)
Na ENHS (P/D=1 16,11 87% pu)
Na ENHS (P/D=1 36,13 89% pu)
10 100 1000 10000 100000 1000000 1E7
Neutron Energy (eV)Q The lead cooled core has hardest neutron spectrum, smallest leakage probability, largest
absorption by coolant (its value is small), and largest absorption by HM.
Q The sodium cooled core (Sodium-1) having the same P/D ratio and Pu wt% as the lead cooled core
has much smaller keff because of its larger leakage probability.
Q Sodium-Il having the same P/D ratio (1.36) but Pu wt% needed for criticality at BOL has smallest
initial conversion ratio (ICR) because of its larger Pu-239/U-238 ratio.
4
Sensitivity of Control Elements Reactivity WorthCentral absorber; r=10.5-15.5 cm
Pb cooled core Na cooled core
Parameters
40%B4C+40%W+20%HT-9
5cm thick 4.143%dk 4.174%dk
7cm thick 4.310%dk 4.354%dk
10cm thick 4.385%dk 4.448%dk
15cm thick 4.408%dk 4.460%dk
5cm thick
40%B4C+40%W+20%HT-9 4.143%dk 4.174%dk
50%B4C+30%W+20%HT-9 4.299%dk 4.378%dk
60%B4C+20%W+20%HT-9 4.418%dk 4.535%dk
70%B4C+10%W+20%HT-9 4.511%dk 4.664%dk
10cm thick
40%B4C+40%W+20%HT-9 4.385%dk 4.448%dk
50%B4C+30%W+20%HT-9 4.430%dk 4.615%dk
60%B4C+20%W+20%HT-9 4.511%dk 4.742%dk
70%B4C+10%W+20%HT-9 4.573%dk 4.841%dkPeripheral absorber
Pb cooled core Na cooled core
Parameters
Cavity (20%HT-9)
5cm thick 0.371%dk 0.115%dk
7cm thick 0.413%dk 0.120%dk
10cm thick 0.469%dk 0.126%dk
15cm thick 0.547%dk 0.132%dk
40%B4C+40%W+20%HT-9
5cm thick 1.998%dk 1.099%dk
7cm thick 2.071%dk 1.154%dk
10cm thick 2.100%dk 1.173%dk
15cm thick 2.110%dk 1.187%dk
5cm thick
40%B4C+40%W+20%HT-9 1.998%dk 1.099%dk
50%B4C+30%W+20%HT-9 2.082%dk 1.197%dk
60%B4C+20%W+20%HT-9 2.146%dk 1.273%dk
70%B4C+10%W+20%HT-9 2.196%dk 1.333%dk52
Characteristic Lead-R Sodium-I Sodium-II Sodium-R
P/D ratio 1.36 1.36 1.36 1.16
Pu wt% 12.20 12.20 13.854 11.87
keff 1.00475 0.934583 1.00571 1.00562
Leakage 0.178 0.239 0.233 0.210
Absorption
In HM 0.778/0.434 0.729/0.409 0.736/0.392 0.758/0.414
In coolant 0.010 0.002 0.002 0.001
In Zr 0.013 0.009 0.009 0.010
In HT-9 0.021 0.021 0.020 0.021
Total 0.822 0.761 0.767 0.790
Fission 0.344 0.320 0.344 0.344
v 2.921 2.915 2.921 2.916
.q 1.292 1.270 1.365 1.323
ICR 1.0445 1.0449 0.8939 1.0382
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Minato, A.; Ueda, N.; Wade, D.; Greenspan, E. & Brown, N. Small Liquid Metal Cooled Reactor Safety Study, report, November 2, 2005; Livermore, California. (https://digital.library.unt.edu/ark:/67531/metadc874500/m1/54/: accessed April 25, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.