624
Appendix: Problem Index
Q-value in
30 Si (d, p)
31 Si
8.53
Q-value for inelastic scattering
8.54
E γ for producing 5 MeV protons in Compton like scattering
8.55
Elastic and inelastic scattering of protons from
10 B
8 . 5 6
E p at 90
0 from
27 Al (d, p)
28 Al
8.57
Fusion reaction
8.58
Which is unstable
17 O or
17 F?
8.59
Energy level diagram
8.60
Neutron and hydrogen atom mass difference
8.61
Range of neutron energy in
3 H (d, n)
4 He
8.62
Forward and backward reactions
8.63
E threshold for endoergic reaction
8.64
8.2.11 Cross-Sections
Neutron absorption in indium foil
8.65
60 Co production in reactor
8.66, 67
σ (θ ) parameters
8.68
σ t for
48 Ca (α, p)
8 . 6 9
8.2.12 Nuclear Reactions via Compound Nucleus
Contribution of scattering to resonance at 0.178 eV
8.70
σ (n, γ ) & σ (n, α) given Γ n , Γ γ , Γ α and E R
8.71
Γ el given E R , Γ and J N = 0
8 . 7 2
8.2.13 Direct Reactions
Spin value from detailed balance
8.73
, ΔE & θ in D-stripping
8.74
8.2.14 Fission and Nuclear Reactors
Production and activity of
24 Na
8.75
Production and activity of
198 Au
8.76
Energy released in fission of
238 U
8 . 7 7
Spatial distribution of neutrons
8.78, 87,
88, 91
Thermal utilization factor
8.79
Critical size of bare reactor
8.80
235 U consumption
8.81
Fission processes/second
8.82
Annual electricity consumption in Britian
8.83
Neutron flux near reactor centre
8.83
To show= 1 for neutron scattering
8.84
Neutron moderation
8.85
Criticality of homogeneous reactor
8.86
Thermal diffusion time
8.89
Generation time
8.90
Number of collisions required for thermalization of fission
neutrons
8.92
Appendix: Problem Index
Q-value in
30 Si (d, p)
31 Si
8.53
Q-value for inelastic scattering
8.54
E γ for producing 5 MeV protons in Compton like scattering
8.55
Elastic and inelastic scattering of protons from
10 B
8 . 5 6
E p at 90
0 from
27 Al (d, p)
28 Al
8.57
Fusion reaction
8.58
Which is unstable
17 O or
17 F?
8.59
Energy level diagram
8.60
Neutron and hydrogen atom mass difference
8.61
Range of neutron energy in
3 H (d, n)
4 He
8.62
Forward and backward reactions
8.63
E threshold for endoergic reaction
8.64
8.2.11 Cross-Sections
Neutron absorption in indium foil
8.65
60 Co production in reactor
8.66, 67
σ (θ ) parameters
8.68
σ t for
48 Ca (α, p)
8 . 6 9
8.2.12 Nuclear Reactions via Compound Nucleus
Contribution of scattering to resonance at 0.178 eV
8.70
σ (n, γ ) & σ (n, α) given Γ n , Γ γ , Γ α and E R
8.71
Γ el given E R , Γ and J N = 0
8 . 7 2
8.2.13 Direct Reactions
Spin value from detailed balance
8.73
8.74
8.2.14 Fission and Nuclear Reactors
Production and activity of
24 Na
8.75
Production and activity of
198 Au
8.76
Energy released in fission of
238 U
8 . 7 7
Spatial distribution of neutrons
8.78, 87,
88, 91
Thermal utilization factor
8.79
Critical size of bare reactor
8.80
235 U consumption
8.81
Fission processes/second
8.82
Annual electricity consumption in Britian
8.83
Neutron flux near reactor centre
8.83
To show
8.84
Neutron moderation
8.85
Criticality of homogeneous reactor
8.86
Thermal diffusion time
8.89
Generation time
8.90
Number of collisions required for thermalization of fission
neutrons
8.92
