Neutron Generation Using Ultra-Intense Laser Plasma Interactions
Neutron Interactions (revisited)
description
Transcript of Neutron Interactions (revisited)
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
1
Neutron Interactions (revisited)
• Chadwick’s discovery.• Neutrons interact with nuclei, not with atoms. (Exceptions).
• Recall from basic Nuclear Physics:o Inelastic scattering (n,n\). Q = -E* Inelastic gammas.
Threshold?o Elastic scattering (n,n). Q = ?? (Potential and CN).
Neutron moderation?o Radiative capture (n,). Q = ?? Capture gammas.o (n,), (n,p). Q = ?? Absorption Reactions.o (n,2n), (n,3n) Q = ?? Energetic neutrons on heavy water can easily eject the loosely bound neutron.o Fission. (n,f).
HW 2HW 2 Examples of such exo- and endo-thermic reactions with Q calculations.
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
2
• Elastic or inelastic.• Analogous to diffraction.• Alternating maxima and minima.• First maximum at
• Minimum not at zero (sharp edge of the nucleus??)• Clear for neutrons.• Protons? High energy, large angles. Why?
• Inelastic Excited states, energy, X-section and spin-parity.
31
ARR
p
h
o
R
Neutron Scattering (revisited)
24
222
sin
1
4
1
4
)(
ao T
zZe
d
d
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
3
• Probability.• Projectile a will more probably hit target X if area is larger.• Classically: = (Ra + RX)2. Classical = ??? (in b) n + 1H, n + 238U, 238U + 238U • Quantum mechanically: = 2.
• Coulomb and centrifugal barriers energy dependence of . What about neutrons?What about neutrons?• Nature of force: Strong: 15N(p,)12C ~ 0.5 b at Ep = 2 MeV. Electromagnetic: 3He(,)7Be ~ 10-6 b at E = 2 MeV. Weak: p(p,e+)D ~ 10-20 b at Ep = 2 MeV.• Experimental challenges to measure low X-sections..
CMaXaXaaX
Xa
EEmm
mm
22
Reaction Cross Section (revisited)
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
4
Reaction Cross Section (Simple terms)
XA (Area of what??!!)
Monoenergetic (and unidirectional) neutrons of speed v (cm.s-1) and
density n (cm-3)
Target with N atoms.cm-3 or NAX atoms.
Position of a neutron 1 s
before arriving at target
|v|
Volume = vAcontaining nvA neutrons that hit the
“whole!!” target in 1 s.Beam Intensity I nvA/A = nv (cm-2s-1)
Number of neutrons interacting with target per second I, A, X and N= t I N A X
NX??
Total microscopic cross section
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
5
Reaction Cross Section (Simple terms)
Number of neutrons interacting with target per second= t I N A X
Number of interactions with a single nucleus per second = t I Interpretation and units of .
nvA = IA neutrons strike the target per second, of these
tI neutrons interact with any single nucleus. Thus,
measures the probability for a neutron to hit a nucleus (per unit area of target).
Total microscopic cross section
Total number of nuclei in the
target
AAI
I tt
Effective cross-sectional area of the nucleus.
Study
examples in
Lamarsh
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
6
Reaction Cross Section (Simple terms)
AAI
I tt
The probability for a neutron to hit a nucleus (per unit area of target):
Function of
what?
Typical nucleus (R=6 fm): geometrical R2 1 b.Typical : <b to >106 b.
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
7
Reaction Cross Section (Simple terms)
Number of neutrons interacting with target per second= t I N A X
Number of interactions per cm3 per second (Collision Density) Ft = t I N = I t
t = N t
Volume of the target
Macroscopic total cross
section.Probability per
unit path length.
tt
XteIXI
1
)( 0
Mean free path
Study
examples in
LamarshTotal
microscopic cross section
Nuclear Reactor Theory, JU, First Semester,2010-2011 (Saed Dababneh).
8
Neutron Attenuation
X
X
t
t
eXP
eXP
1)(
)(
ninteractio
ninteractiono
Recall t = N t
Probability per unit path length.
X
I0 I
Probability
mfp for scattering s = 1/s
mfp for absorption a = 1/a
…………. total mfp t = 1/t
XteIXI 0)(
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
9
Reaction Cross Section (Simple terms)
Homogeneous Mixture
Molecule xmyn Nx=mN, Ny=nN
given that events at x and y are independent.
yyxxyx NN
yx nm
Study
examples in
Lamarsh
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
10
Reaction Cross Section
d,Ia
\
Detector for particle “b”
\\NI
dRd
a
b
“X“ t
arge
t Nuc
lei /
cm2
“a” particles / s
“b” particles / scm2
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
11
Reaction Cross Section
Many different quantities are called “cross section”.Krane Table 11.1
\\4
),(4),(
NI
r
d
d
drdR
a
b
Angular distribution
“Differential” cross section(,) or ( )or “cross section” …!!
Units … !
d
dddd
d
d
ddd
0
2
0
sin
sin
dEd
d 2Doubly differential
dE
d
t for all “b” particles.
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
12
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
13
n-TOFn-TOFCERNCERN
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
14
Nuclear Reactor Theory, JU, First Semester, 2010-2011 (Saed Dababneh).
15
1/v
235U thermal cross sectionsfission 584 b.scattering 9 b.radiative capture 97 b.
Fast neutrons should be moderated.
Fission Barriers
Neutron Cross Section (Different Features)