Appendix A2: 235 U-Fueled and Pb–Bi–Zoned ADS Core
263
Fig. A2.6 Comparison
between neutron spectra with
the use of W and W–Be
targets (Refs. [1–2])
0
20
40
60
80
100
10
-10
10
-9
10
-8
10
-7
10
-6
Neutron energy [MeV]
Neutron flux per lethargy bin [1/cm
2
/source]
W (9 mm)
W (9 mm) - Be (6 mm)
W (9 mm)
W (9 mm) - Be (6 mm)
Fig. A2.7 Proportionality of
cross sections of 115 In
capture and 235 U fission
reactions (Refs. [1–2])
10
-11 10
-10 10
-9 10
-8 10
-7 10
-6 10
-5 10
-4 10
-3 10
-2 10
-1 10
0 10
1
10
-3
10
-2
10
-1
10
0
10
1
10
2
10
3
10
4
10
5
Energy [MeV]
Cross sections [Barn]
115 In (n, γ)
116m In
235 U (n, f)
Fig. A2.8 Comparison
between normalized reaction
rates obtained in ADS
experiments (Refs. [1–2])
0
10
20
30
40
50
60
70
0
10.0
20.0
30.0
40.0
Distance from location of original target [cm]
Normalized reaction rates [Arbitrary units]
W target
W-Be target
Pb-Bi target
Air region
Polyethylene
region
Core region