Calculate the moderator average log-decrement (()) and thermal utilization factor (f) for a reactor fueled with natural uranium and moderated with beryllium oxide (BeO), having NM/NF = 500 ratio of moderator to fuel. Use data in Table 10.3 of the textbook, plus element Be 160 0₂ 6.50 b 3.92 b da 10.1 mb 0.2 mb

Chemistry for Engineering Students
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Chapter11: Chemical Kinetics
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Calculate the moderator average log-decrement (()) and thermal utilization factor
(f) for a reactor fueled with natural uranium and moderated with beryllium oxide
(BeO), having NM/NF = 500 ratio of moderator to fuel. Use data in Table 10.3 of the
textbook, plus
element
0₂
0
"Be 6.50 b 10.1 mb
3.92 b 0.2 mb
160
Show Transcribed Text
answers are 0.18 and 0.60. Please
write neatly
THE QUESTION IS COMPLETE
Material
H₂O
D₂0
Graphite
G
Table 10.3 Properties of materials used as moderators.
M.Wt
18.01
20.02
12.01
density
(g cm ³)
1.0
1.1
1.6
Os
(b)
49.2
10.6
4.7
0₂
(b)
0.66
0.001
0.0045
Š
0.920
0.509
0.158
SDP
.(m-¹)
151
18
6.0
Transcribed Image Text:Calculate the moderator average log-decrement (()) and thermal utilization factor (f) for a reactor fueled with natural uranium and moderated with beryllium oxide (BeO), having NM/NF = 500 ratio of moderator to fuel. Use data in Table 10.3 of the textbook, plus element 0₂ 0 "Be 6.50 b 10.1 mb 3.92 b 0.2 mb 160 Show Transcribed Text answers are 0.18 and 0.60. Please write neatly THE QUESTION IS COMPLETE Material H₂O D₂0 Graphite G Table 10.3 Properties of materials used as moderators. M.Wt 18.01 20.02 12.01 density (g cm ³) 1.0 1.1 1.6 Os (b) 49.2 10.6 4.7 0₂ (b) 0.66 0.001 0.0045 Š 0.920 0.509 0.158 SDP .(m-¹) 151 18 6.0
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