Chapter 1
Learning Objectives
• Historical R e c a p
• U nderstand the different length scales of nu c l e a r p h y s i c s
• K now the nomenclature for isotopes and nuclear reactions
• K now the different types of neutron nuclear c o l l i s i o n s a n d t h e i r relationship t o each other
• B a s i c p r i n c i p l e s o f n u c l e a r r e a c t o r
Learning Objectives
• N eutron Sources
• B asic Principles of Nuclear Reactor
• B indin g ener g y curve
• Liquid drop model
• F ission Reaction
• ODE Review
• R adioactive Decay
• D ecay Chains
• C hart of Nuclides
Historical Recap
• D r i s c o l l h a n d o u t
• N ew programs
GNEP/AFCI
– GNEP/AFCI
– G en-IV
– Nuclear Power 2010
W h y nuclear?
• P o w e r d e n s i t y
– 1000 MW electric
• 1 0 0 0 0 t ons o f coa l per D A Y ! !
• 20 tons of uranium per YEAR (of which only 1 ton is U - 235)
A typical pellet of uranium weighs about 7 grams (0.24ounces). It can generate as much energy as……
3.5 barrel s of oi l or…… 17,000 cubic feet of natural gas, or… .. 1,780 pounds of coal.
Why nuclear?
• Why still use coal
– C a p i t a l c o s t
– P olitics
What do you think is the biggest barrier to constructing the next U.S. nuclear power plant?
50%
40%
30%
20%
10%
0% Political Nuclear W aste Resistance to Disposal
Nuclear Ener gy Issues
Cost of Nuclear Power Plant Construction
Fear of Nuclear Accident
Other
– P u b l i c p e r c e p t i o n of n u c l e a r , n u c l e a r w a s t e r issue
44%
16%
15%
10%
14%
- 2008 surve y of energy professionals
Image by MIT OpenCourseWare.
“ Eighty - t w o p e r c e n t o f A m e r i c a n s living i n close proximity to nuclear power plants f a v o r nuclear e n e r g y , a n d 7 1 percent a r e willing to see a new reactor built near them , a c c o r d i n g t o a new p u b l i c o p i n i o n survey of more than 1,100 adults
nationwide . ” – N E I , S eptember 2 0 0 7
B a s i c P r i n c i p l e s of N u c l e a r R e a c t o r
• S i m p l e d e v i c e
– F issioning fuel releases energy in the “core”
– H e a t is t r a n s p o r t e d a w a y by a c o o l a n t w h i c h couples the heat source to a Rankine steam cycle
– V ery similar to a coal plant, with the exception of the combustion p rocess
– M ain complication arises from the spent fuel, a mix of over 300 fission p roducts
Public domain image from wikipedia.
Main T urbine
Electric Generator
Dischar ge
Lar ge Body of W ater (Ocean, Lake, etc.)
Intake
Main Condenser
• P o w e r p l a n t s w i l l
o f t e n
Circulating W ater Pump
discharge their circ ulating water directly back to the ocean
– Strict environmental pro t ec t i on regu l a t i ons
– Temperature increases by 5 - 1 0 F a r e n h e i t s
Image by MIT OpenCourseWare.
Electric
Main Generator T urbine
Main Condenser
Cooling T ower
Circulating W ater Pump
Image by MIT OpenCourseWare.
• If far from a water source, coo li ng towers are use d to transfer the heat to air.
– W a t e r v a p o r i s v i s i b l e a t t h e contact of the warm wet air inside the tower with the cool dry air outside
R e a c t o r s C o n cepts
• Fuel
– U ranium
– Plutonium
– Thorium
• M oderator (optional)
– L ight water
– H eavy water
– Graphite
– Be
• Coolant
– L ight water
– Heav y wate r
– S odium
– Molten salt
– H elium
– C O 2
– L ea d - B i smu t h
– …
M acroscop i c t o m i croscop i c wor l d
C utaway of PWR pressure vessel and I nternals.
Fission chain reaction
Public domain image from wikipedia. Public domain image from wikipedia.
M o d e r a t o r ( W a t e r )
R e a c t o r V e s s e l W a l l
S h i e l d W a l l
C o n t r o l R o d
Neutrons in a reactor
F u e l R o d s
Image by MIT OpenCourseWare.
Nomenclature -- Isotopes
A X s u ch as 12 C or
23 5 U
Z 6 9 2
Z is the atomic number
A is the atomic mass
U
N = A-Z is the number of neutrons N uclei with the same Z and dif f erent A are called isotopes.
92
E.g. 23 5 U
a nd
23 8
1
92
1 2 3
1 1
1 H a n d 2 H
a nd 3 H
Nuclear Stability
Image removed due to copyright restrictions.
• A s Z i n c r e a se s , the long range Coulomb repulsion between protons is balanced by the presence of a dditi ona l neu t rons t o provide additional short - range a t t r a c t i v e nuclear forces.
Even Even Even 159
D i s t r i b u t i o n of Stable N u c l i d e s
A |
Z |
N |
# nuclides |
Even |
Even |
Even |
159 |
O d d |
E v e n |
O d d |
5 3 |
Odd |
O dd |
Even |
50 |
Even |
Odd |
O dd |
4 |
266 |
Nuclear Collision Reactions
a + b c + d a(b, c)d
1 n
23 5 U
23 6 U
U
0 92 92
23 5
92
( n , )
23 6
U
92
F u n d a m e n t a l L a w s
• C o n s e r v a t i o n o f n u c l e o n s
– T otal “A” remains the same
Conservation of charge
• Conservation of charge
– T otal “Z” remains the same
• C onservation of momentum
• C onservation of Ener gy
– E nergy, including rest mass, is conserved
Rest Mass
E 2 _
(pc) 2 = (mc 2 ) 2
Mass is a characteristic of the total ener gy and momentum of an object or a system of objects that is the same in all frames of reference.
m 0 = E/c 2
The invariant mass of the system is equal to the total system ener gy divided by c 2 .
This total ener gy in the center of momentum frame, is the minimum ener gy which the system may be observed to have.
Special Relativity Mass
1 _ 2 /
c 2
m = m 0
A body ’ s mass increases when it is in motion with speed v relative to an observer at rest.
Q - value
Exothermic reaction produces ener gy Endothermic reaction requires ener gy
An exothermic reaction is defined with Q < 0 therefore it is important to understand the concept:
E = mc 2
Q = [( M a + M b ) _ ( M c + M d )] c 2
Q > 0 exothermic
Q < 0 endothermic
E a + E b
+ M a c 2
+ M b c 2 = E c + E d
+ M c c 2 + M d c 2
Examples of Q-value
Exothermic
Q = [ M
( 9 Be) + M ( 4 He ) _ M ( 12 C)
_ m n ]c 2
4 2 6
Q = [9.012182u + 4.002603u _
12.000000u
_ 1.008664u]931.5MeV/u
Q = 5.702MeV
9 Be + 4 He 12 C + 1 n
4 2 6 0
Examples of Q-value
Endothermic
8
Q = [ M ( 1 6 O) + m n
_ M ( 1 3 C)
2
_ M ( 4 He) ]c 2
6
Q = [15.994915u + 1.008664u _
_ 4.002603u]931.5MeV/u
13.003354u
Q = _ 2.215MeV
1 6 O + 1 n 13 C + 4 He
8 0 6 2
Examples of Q-value
1 6 O( n,p ) 16 N
8 7
Assumption
Q m n M 16 O M 16 N m p c 2
8 7
Why is this incorrect?
0 8 7
1 n 1 6 O 1 6 N
0 e 1 p
1 1
This is approximately equivalent to
1 n 16 O 16 N 1 H
0 8 7 1
8
7 1
Q m n M 16 O M 16 N M 1 H c 2
Most important Reactions
An Example
235 U + 1 n 129 I + 10 4 Y + 3 1 n
92 0 53 39 0
Nuclear fission (n, fission)
1 n A X A 1 X A 2 X
neutrons 200 Me V
0 Z Z 1 Z 2
Radiative Capture
An Example
238 U + 1 n ( 239 U) * 239 U + 0
92 0 92 92 0
X
Z
Radiative capture (n, )
n
X
X
1 A A 1
0 Z Z
*
A 1
Scattering
Examples
elastic 12 C + 1 n 12 C + 1 n
6 0 6 0
94 0 94 0 94 0 0
inelastic
( Pu + n Pu)* + n Pu + + n
Scattering ( n, n ) or ( n, n' )
0
Z
1 n
A X
1 n
A X elastic scattering (n,n)
0
Z
1 n
A X
1 n
A X *
1 n
A X
0 Z 0 Z
0
Z
inelastic scattering (n,n')
Beta decay
When the weak interaction converts a neutron into a proton and emits an electron and an anti-neutrino, Beta (minus) decay occurs. This happens when an atom has an excess of neutrons.
A X 0 e A Y _
E nerg y
Z 1 Z 1
-1
_
Cs
56
13 7
55
13 7 Ba +
0 e +
Positron Emission
Positron emission cannot occur in isolation unlike Beta deca y .
This happens because it requires ener gy (the mass of the neutron is greater than the mass of the proton).
Positron emission happens inside the nuclei when the absolute value of the binding ener gy of the mother nucleus is lower than that of the daughter nucleus.
A X + Ene r gy A Y + 0 e +
Z Z-1 1
22 Na 22 Ne + 0 e +
1 1 10 1
Capture of Electron
A X + 0 e + Ene r gy A Y +
Z -1 Z-1
In cases where ß+ decay is allowed ener geticall y , it is accompanied by the electron capture process.
22 Na + 0 e 22 Ne +
1 1 -1 10
If the ener gy dif ference between initial and final states is low (less than 2 m e c 2 ), then decay is not ener getically possible and electron capture is the sole mode deca y .
Alpha Decay
Coulomb repulsion increases ~ Z 2
Alpha decay occures only in heavy atoms (A > 100 amu )
Alpha particle has small mass relative to parent nucleus and has very high binding ener gy
Nuclear binding force increases ~ A
A X + A- 4 Y + Ene r gy
Z
U
238
92
Z-2
90
234 Th + a
0.31 MeV
Gamma decay
27
Co 60
5.26 a
60
28
Ni
1.17 MeV
1.33 MeV
Image by MIT OpenCourseWare.
• G amma decay is the emission of a gamma ray (photon) from a nucleus
• O c c u r s w h e n nucleus transitions f r o m a h i g h e r t o l o w e r e n e r g y s t a t e
• E nergy of photon(s) equal to the change in energy of nuclear states
• Nuclear structure does not change so parent and daughter are the same
or Electron Capture
Predicting type of decay
90
80
70
60
Line of Stability
50
40
30
20
10
0
0
10 20 30 40 50 60 70 80 90 100 1 10 120 130 140
Neutron (N)
Proton Number (Z)
Image by MIT OpenCourseWare.
Binding Ener gy
ZM p + NM n - M X
The weights of these constituent masses exceeds the weight of the nucleus if we add the masses of Z protons and N neutrons that make up a nucleus.
The dif ference is the mass defect which is positive for all nuclides. Multiplying by c 2 yields the binding ener gy of the nucleus.
When the nucleus is formed, the loss in mass is due to the conversion of mass to binding energy . It is defined as the ener gy that is supplied to a nucleus to completely separate its nucleons.
A measure of nuclear stability is obtained when the binding ener gy is normalized to the number of nucleons.
f i 23
Calculate mass defect and binding energy f or uran i um- 23 5
M a s s o f n e u t r o n 1 . 0 0 8 6 6 5 amu Mass of proton 1.007826 amu
M f t f U 235 235 043924
M ass o f one a t om o f U- 235 235 . 043924 Binding energy = mass defect x c 2
• M a s s defect = 1 . 9 1 5 1 7 amu
BE 1 91517 931 5 M V / 1
• BE = 1 . 91517 amu x 931 .5 Me V / 1 amu
• BE = 1784 MeV
1 a m u =
1 . 66054 x 10 -27 kg =
931 . 5 M e V / c 2
B i n d i n g Energy C u r v e
• E xothermic reactions result in reaction products with higher binding energy
T t i
• T wo op ti ons
– Fission of heavy nuclides
– Fusion of light nuclides
First - O r d e r O D E - Review
• A p p e n d i x A of L e w i s + H andout
Radioactive D e c a y
• Le w i s , S e c t i o n 1 . 7
Decay c h a i n
(a) B = 5 x A ; t 1 = 5 x t 1
1 2 A 2 B
Normalized activity
0.75
0.5
0.25
0
0 1
(b) B = A / 5; t 1 A = t 1 B / 5
2 3 4
t
(c) B = A ; t 1 A = t 1 B
2 2
Normalized activity
1
0.75
0.5
0.25
0 0 1 2 3 4
t
1 2 2
Normalized activity
0.75
0.5
0.25
0
0 1 2 3 4
t
A A (t)/ A A (0)
A B (t)/ A A (0)
Image by MIT OpenCourseWare.
Decay Chains
Definition of Decay Chain: The radioactive decay of dif ferent discrete radioactive decay products as a chained series of transformations.
Decay Chains
_ Thorium series or 4n
_ Neptunium series or 4n + 1
_ Uranium or Radium series 4n + 2
_ Actinium series or 4n + 3
C h a r t o f N uclides
3
He in
in
3n
3
out
p in
d in
t in
p, n
3
2n He, n p,
d, n
n
3
n out
Original Nucleus
n in
n
n, 2n
He, np
T ar get
Nucleus
a, np t, n He, p d, p
n,
t, np
t out d out
p out out
np
p
n, p
3
out
He
out
n,
n, 3
He
t, p
Image by MIT OpenCourseWare.
Chart of Nuclides
• G r a y shaded square (stable n u c l i d e )
Symbol, mass number
Percent abundance Activation cross-section in
"bars" to two isomers Mass (C-12 scale)
Fission product, slow neutron fission of U-235
Pd 108
26.71
(0.2 + 12)
107.9030
Image by MIT OpenCourseWare.
Fe 52
8 h
B 0.80, (263),
0.17, 380, (1.43)
E 2.38
• White or "color" square: ( Artificially Produced Radioactive Nuclide )
Symbol, mass number
Fe 52
Half life
Modes of decay , radiation, and ener gy in Me V . ( ) means radiation from short-lived daughter .
Disintegration ener gy in Me V .
Image by MIT OpenCourseWare.
C h a r t o f N uclides
• B lack rectangles across the top of square
– On gray-shaded square: R adioactive nuclide with long half life (Considered Stable)
Symbol
Ce 142
1 1.07
Percent abundance
Half life
5 x 10 15 yrs
, 1.5
1
141.9090
Modes of decay
Thermal neutron absorption cross-section
in barns
Mass
Image by MIT OpenCourseWare.
– On white square: Radioactive nuclide found in n a t u r e with r e l a t i v e l y s hort h a l f life
C h a r t o f N uclides
• S maller black rectan g le near to p
of s q uare
( Nuclide is a
member of a natural radioactive decay chain)
Po 218
Ra A
6.00
3.05 m
218.0089
Symbol, mass number
Symbol Half life
Modes of decay and ener gies
Mass
Image by MIT OpenCourseWare.
• B lack triangle at bottom corner of square ( nuclide is
formed b y
fission of U-235 or Pu-239 )
Pd 108
26.71
(0.2 + 12)
107.9030
Symbol, mass number
Percent abundance
Mass (C-12 scale)
Activation cross-section in "bars" to two isomers
Fission product, slow neutron fission of U-235
Image by MIT OpenCourseWare.
C h a r t o f N uclides
• V e r t i c a l l y divided s q uare
– T wo isomeric states, one stable
Symbol
Half life
Modes of decay radiation, and ener gies in Mev
14 d
IT 0.159
0.161
e -
Sn 1 17
7.61
1 16.9031
Percent abundance
Mass
Radioactive upper isomer
Stable lower isomer
Image by MIT OpenCourseWare.
– T wo isomeric states, both radioactive
Symbol
Radioactive upper isomer
? 16d
0.45
Pm 145
18y
,e -
0.068, 0.073
E 0.14
Half life, ?
means uncertainty
Modes of decay radiation, and ener gies in Mev
Disintegration ener gy in Mev
Stable lower isomer
Image by MIT OpenCourseWare.
Neutron Sources
Definition of Spontaneous Fission
Spontaneous fission (SF) is a form of radioactive decay characteristic for very heavy isotopes. In practice, only ener getically feasible for atomic masses above 230 amu. It is theoretically possible for any atomic nucleus with mass >= 100 amu.
Radioisotopes for which spontaneous fission is a nonnegligible decay mode may be used as neutron sources notably Cf-252 (half-life 2.645 years, SF branch ratio 3.09%)
Intensity (ARB. UNITS)
10 2
10 1
10 0
1
2
3
4
5
Neutron ener gy (MeV)
Measured neutron ener gy spectrum from the spontaneous fission of 252 Cf.
Image by MIT OpenCourseWare.
• A lpha Neutron Source
Neutrons are produced when alpha particles impinge upon any
– Neutrons are produced when alpha particles impinge upon any of several low atomic weight isotopes
• beryllium, carbon and oxygen
• M ust have loosel y bound neutron
– Alpha emitters must be long-lived
• R adium, polonium, plutonium, americium
– T he low A material and alpha emitter are usually mixed in powdered form
– T ypical emission rates for alpha reaction neutron sources range from 1×10 6 to 1×10 8 neutrons per second.
Th i d t f th t l bl
– Th e s i ze an d cos t o f th ese neu t ron sources are a l so compara bl e to spontaneous fission sources.
– U sual combinations of materials are plutonium-beryllium (PuBe), americium - b e r y l l i u m ( A mB e ) , o r a m e r i c i u m - l i t h i u m (A m L i )
– R adium is not used as much now because of its high gamma emission rate
Relative neutron intensity (MeV -1 )
8
6
Stilbene
4
Emulsions
2
0
2
4
6
8
10
Neutron ener gy (MeV)
Measured ener gy spectra for neutrons from a 239 Pu/Be source containing 80g of the isotope.
Image by MIT OpenCourseWare.
• P hotoneutrons
– A photon that is absorbed by t he nucleus creates an excited state from which a neutron is emitted. There are two such sources:
– 9 Be + >1.7 Mev photon → 1 neutron + 2 4 He
– 2 H ( d e u t e r i u m ) + > 2 . 26 M e V p h o t o n → 1 neutron + 1 H
ti R h l i 106 i t t S
– T he resulting neutron energies ar e discrete if the photons are monoenerge ti c. R oughl y, one gamma ray i n 106 int erac t s. S o, the gamma ray source needs to be very large (as in a fission reactor) for these sources to be appreciable. The most common u s e is t h e d e u t e r i u m r e a c t i o n a s a s o u r c e o f n e u t r o n s f o r t h e startup of light-water reactors. The source of the photons would be fission products. (Note: Sufficient D 2 O exists in light water for t h i s s o u r c e t o b e e f f e c t i v e i n L W R s . )
• A c c e l e r a t e d c h a r g e d p a r t i c l e s
• F ission
F i
• F us i on
• …
Fission
• C onsider the followin g exam p le of U-235 fission
• From binding energy curve, energy released is about
~200 MeV (235*(8.9 – 8 ))
– Most of the energy leaves in the form of kinetic energy of the fission products
– R e s t go e s to p a r t ic l e s emitted d u r i n g f i s s i o n
• A distinction must be made betw een energy produced and energy recuperated – Fission products are large ionized particles that travel a short distance, thus
e e n n e e r r g g y y is deposited l l o o c c a a l l l l y y
– The electrons released by beta decay of the fission products are also absorbed locally.
– T he gamma rays (photons) travel much greater distances and are sometimes a b sor b e d b y t h e reac t or s h i e l d .
– The neutrinos escape entirely
Fission Products |
168 |
168 |
Beta (FP) |
8 |
8 |
Gamma (FP) |
7 |
7 |
Neutrinos |
~12 |
- |
Prompt Gammas |
7.5 |
7 |
Prompt Neutrons |
5 |
5 |
(n, gamma) |
- |
3-12 |
~207 |
198-207 |
Ener gy Recuperated
Ener gy Released
Image by MIT OpenCourseWare.
• For fission to occur, we must provide some energy to the
nucleus. A
p otential barrier exists that
p revents
spontaneous fission from happening very frequently.
• L iquid drop model: A water drop doesn’t separate in two s p o n t a n e o u s l y e ve n i f i t s e n e r g e t i c a l l y f a v o r a b l e . T h e superficial tension of the drop acts as a barrier that tries to keep the fragments from splitting.
Liquid Drop Model of Fission
A
+
+ B
B
+
+
C
Image by MIT OpenCourseWare.
nucleus together Initially the potential energy of the nucleus is
potential energy of the nucleus However t he strong nuclear forces
• I n nuclear fission, the short nucl ear bonds of the nucleons keeps the nucleus together . Initially , the potential energy of the nucleus is equal to the binding energy of the nuc leons (no kinetic energy). To deform the nucleus, energy must be pr ovided in an effort to increase the average distance between the nucleons, thus increasing the potential energy of the nucleus . However , the strong nuclear forces are very short. Thus when the separation starts, the repulsive forces diminish and the potential ener gy diminishes as well. There is thus a threshold energy required (about 6 MeV) for fission
Q t h i l l i h t f i i
• Q uan t um mec h an i cs a l so exp lai ns h ow spon t aneous fi ss i on can happen, but with very-low probability, thru a tunnelling effect without any energy input.
d l E i i t t h l b
• W hen a neutron interacts with a nuclide, it forms a compoun d nuc l eus. E nergy i s g i ven t o th e nuc l eus b y the binding energy of the incident neutron and its kinetic energy
If the b inding energy is sufficient to get above t he fission
– If the binding energy is sufficient to get above the fission threshold of the nuclide, than t he nuclide is fissile to thermal neutrons
f f
– If it requires additional kinetic energy, than it is said to be fissile to f ast neutrons or f issionable
• F issile nuclides
– U -235: only naturally occurring fissile isotope
P 239 di i f U 238
– P u- 239 : ra di at i ve capture o f U - 238
– U -233: radiative capture of Th-232
– Pu-241: radiative capture of Pu-240
Critical Energy
232 Th 90 |
7.5 MeV |
5.4 MeV |
-2.1 MeV |
238 U 92 |
7.0 MeV |
5.5 MeV |
-1.5 MeV |
235 U 92 |
6.5 MeV |
6.8 MeV |
+0.3 MeV |
233 U 92 |
6.0 MeV |
7.0 MeV |
+1.0 MeV |
239 Pu 94 |
5.0 MeV |
6.6 MeV |
+1.6 MeV |
Critical Ener gies Compared to Binding Ener gy of Last Neutron
BE n _ E crit
Binding Ener gy of Last Neutron BE n
Critical Ener gy E crit
T ar get Nucleus
Image by MIT OpenCourseWare.
f , barn
Fission cross sections for fi ss i ona b l e nuc l e i
3
2
242 Pu
240 Pu
234 U
236 U
238 U
232 Th
1
0
0
2
4
6
8
10
Neutr on energy , Mev
Image by MIT OpenCourseWare.
Fertile Materials
• M a t e r i a l s t h a t c a n u n d e r g o t r a n s m u t a t i o n to become fissile materials.
233
U
92
-
233
Pa
N
91
-
232
90
Th
n,
233
90
Th
N
239
94
Pu
-
239
Np
N
93
-
238
n,
92
U
239
U
92
N
Image by MIT OpenCourseWare.
Fission Y ield, %
Fission Products
• G e n e r a l l y o b s e r v e o n l y t w o f i s s i o n fragments
– N o t e the logarithmic s c a l e
10
1
0.1
0.01
0.001
14 MeV
Thermal
0.0001
70
90
1 10
130
150
170
Mass Number
Image by MIT OpenCourseWare.
S t a b i l i t y of f i s s i o n p r o d u c t s
Image removed due to copyright restrictions.
• N e u t r o n r i c h fission products beta decay towards stability
Criticality – N e u t r o n M ultiplication
k m u l t i p l i cat i o n fact or
num ber of neut r ons in one ge ne r a tion
n u m b e r o f n e u t r o n s i n p r e c e d i n g g e n e r a t i on
• C ritical, k=1
• S ub-critical k<1
• S upe r -critical k>1
1
235 U
2
238 U
X
235 U
X
235 U
3
235 U
N(t)
Supercritical
k > 1
N(0)
k = 0 Critical
k < 1
Subcritical
t
Image by MIT OpenCourseWare.
N e u t r o n generation
• Lewis , p . 1 2
N e u t r o n s released from f i s s i o n
• Prompt
– S pectra
Average energy
– Average energy
• D elayed
– Delay discussion to kinetics
N e u t r o n s released from f i s s i o n
5
4
233 U
239 Pu
v
3
235 U
v 49 = 2.874 + 0.138 E
v 25 = 2.432 + 0.066 E (0 < E < 1)
= 2.349 + 0.15E (E > 1)
v 23 = 2.482 + 0.075 E (0 < E < 1)
= 2.412 + 0.136 E (E > 1)
2
0
5
10
15
E (MeV)
v
Pu -239 pr oduces mor e neutr ons
per fission than U -235 .
v (E)=average number of neutr ons pr oduced per fission
Image by MIT OpenCourseWare.
(E)
Fission prompt neutron energy spectrum
2.29 E
( E ) 0.45 3 e 1.036 E sinh
( E ) d E
A v e r a g e num be r of f i s s i o n n e u t r o n s e m i t t e d wi t h en erg y i n E t o
E d E p e r f i s s i o n
ne utron.
0.5
0.4
0.3
0.2
0.1
0
1
2
3
E (MeV)
4
5
Image by MIT OpenCourseWare.
D e l a y e d f i s s i o n neutrons
87 Br 55s
( 87 Kr)*
87 Kr
Neutron emission
86 Kr + Neutron
Less than 1% of neutrons from fissi on
are considered delayed. Delayed n eutrons appear long after the fission event t hrough the
87 Rb
decay of certain fission products, al so called neutron
87 Sr
precursors. These delayed neutron s are essential to Image by MIT OpenCourseWare.
the control of nuclear reactors since they appear many
orders of magnitude later than the p rompt neutrons.
MIT OpenCourseWare http://ocw.mit.edu
22.05 Neutron Science and Reactor Physics
Fall 20 09
For information about citing these materials or our Terms of Use, visit: http://ocw.mit.edu/terms .