Chapter 5 Kinetics
Fission chain r eaction
Public domain image from wikipedia.
Delayed neutrons
Delayed neutrons emitted from the decay of fission pro d uc t s l ong a ft er th e fi ss i on even t . D e l ay i s cause d b y half-life of beta decay of delayed neutron pre-cursor nucleus .
Delayed neutrons
Delayed neutrons are grouped into 6 groups of delayed neutron precursors with an average decay constant i d e f i n e d for each .
i T he dec a y co nsta nt fo r the i th g r o u p o f de lay ed ne utro ns
i T h e f r a c tio n o f f i ssio n ne utr o ns e m itte d by de la y e d ne utro n pre c u r s o r g r o u p i.
T h e f r a c tio n o f f i ssio n ne utr o ns tha t a r e de lay e d.
6
= i i=1
~ 0 . 0 0 7 5
Point Kinetic Equations
For an initially critical system
dp ( t )
( t )
p ( t ) K
c ( t )
d t
k k
k 1
dc k
( t ) k
p ( t ) c
( t )
d t k k
Most important assumption: Assumes that the perturbation introduced in the reactor af fects only the amp litude of the flux and not its shape.
Dynamic Reactivity ρ (t)
• Most important kinetics parameter
– Its variations are usually the source of changes in neutronic power
– O nly term that contains the neutron loss operator (M operator)
• A ssociated to control mechanisms
• A lso sensitive to temperature
– N o units
• E xpressed in terms of mk (milli-k) or pcm
Delayed - Neutron Fraction β (t)
• E ffective dela y ed neutron fraction is linked to the constants of each fissionable isotope which measure the fraction of fission product precursors
– C alled “effective” because it is weighted by the flux in the reactor
• C an vary with burnup
– Different values exist at BOL and EOL
– Variations in burnup are on a much larger time scale than usual range of application of point kinetics equations
Prompt - Neutron Lifetime
• Measure of the average time a neutron survives after it appears as either a prompt neutron or a delayed - neutron
Solution with one ef fective delayed neutron precursor group
dP ( t )
0
P ( t ) C ( t )
dt
d C ( t ) dt
Step reactivity change
t 0 ( t ) 0 , P ( t ) P 0
t 0 ( t ) 0
P ( t ) C ( t ) , t 0
Solution
0
P ( 0 )
P , C ( 0 )
P
0
Initial conditions
P ( t ) Pe st , C ( t ) Ce st
Solutions
sP 0
P C
Substitute
s C P
C
s 0
Solution
P 0 Linear
C 0 Homogeneous
s
System
s 0
s
0
Non-trivial solution if and only if
s 2 ( 0 ) s 0 0
det A=0
Solution
2
4
0
s 1
1 , 2
2
0
P ( t )
Pe s 1 t
P e s 2 t
and
C ( t )
C e s 1 t
C e s 2 t
1 2 1 2
Approximate solution
Assume
/
1
s 0
, s
0
0
1
2
0
P ( t ) P
exp
0
t 0
exp
0 t
0
0 0 0
Solution
This solution is not valid for large changes in reactivity!
P ( t ) P
0 t
0
0
0
ex p
ex p
t
0
0
0
0 0.002 5 , 0.007 5 , 0.0 8 s -1 , 10 3 s
1
s 1 ~ 25 s
1
s 1 ~ 0 . 2 s
2
Prom p t neutrons
Delayed neutrons
Reactor Period
• D efined as the p ower level divided b y the rate change of power
( t )
p ( t )
dp ( t )
d t
– Period of infinity implies steady-state
– S mall positive period means a rapid increase in p owe r
– S mall negative period means rapid decrease in power
– If period is constant, power varies according to
p ( t ) p 0 e t /
Reactor Period
• For the case with one delayed group , the
reactor period can be separated in two parts
– P rompt period
– Stable period
• T he solution has two exponential and they usua ll y h ave very diff eren t coe ffi c i en t s.
• ρ 0 < 0
Scenario 1
– C orresponds to a quick reactor shutdown
– Both roots are negative
– s 2 <<< s1 thus the power drops almost instantly to a fraction of its initial power (prompt drop)
– However , it is impossible to stop a reactor
instantaneously
Example
• T h e s e c o n d r o o t is s o
• T h u s
the s t a b l e
small that in the matter of a fraction of second becomes inconsequential
• P ower drops almost instantly to the coefficient of the f i r s t exponential term
period is equal to 1/s 1
• A nd the p rom p t period is equal to 1/s 2
1
0. 9
0. 8
0. 7
0. 6
0. 5
0. 4
0. 3
0. 2
0. 1
0
0 0. 1 0. 2 0. 3 0. 4 0. 5 0. 6 0. 7 0. 8 0. 9 1
P ( t ) P
e x p 0
t 0
e x p 0 t
0
0
0
0
Courtesy of canteach@candu.org. Used with permission.
Demo
• N e g a t i v e S t e p i n s e r t i o n o f - 12mk
• P arameters
– B e t a = 0 . 006
– L AMBDA = 0.001
– Lambda = 0.1 s - 1
• P ower d rops b y 3 3 % a l mos t i ns t an t l y, an d then decays slowly
• 0 < ρ 0 < β
Scenario 2
• O ne root is positive and the other is negative
• P ower increases rapidly and the grows exponen ti a ll y
• Power increases rapidly by beta/(beta - rho)
– P ositive prompt jump
• Stable period is equal to 1/s 1
• P rompt period is equal to 1/s 2
1. 4
1. 2
1
0. 8
0. 6
0. 4
0. 2
0
0 0. 1 0. 2 0. 3 0. 4 0. 5 0. 6 0. 7 0. 8 0. 9 1
Demo
• Positive Step insertion of 1mk
• P arameters
– B e t a = 0 . 006
– L AMBDA = 0.001
– Lambda = 0.1 s - 1
• If rho approaches beta, the stable period becomes very short
• ρ 0
Scenario 3
> β (prompt s uper - critical)
• R eactor is critical without the need of the delayed neutrons
• O ne root is positive and one is negative
• R eactor period becomes less than 1s
• Power increases at a very rapid rate
• D isastrous consequences
– U nless a feedback mechanism can cancel out the reactivity
8
7
6
5
4
3
2
1
0 0 0. 01 0. 02 0. 0 3 0. 04 0. 05 0. 0 6 0. 07 0. 08 0. 09 0. 1
Demo
• Positive Step insertion of 7mk
• P arameters
– B e t a = 0 . 006
– L AMBDA = 0.001
– Lambda = 0.1 s - 1
• R eactor is critical (or supercritical) without the presence of delayed neutrons
– P rompt jump dominates
Limiting cases - Small reactivity insertions
0 1 1 2
, thus s ...
l 1
T 1 1 l
6 i
s
i 1
k 1
l
l
1 0 i 0
, thus s
0 1 i
Limiting cases- Lar ge reactivity insertions
0
s 1
l 1
s 1 l 1
s 1 l 1
s 1 l 1
i
i 1
6
s 1 l 1
T 1 l l s 1 k ( 0 ) k 1
Positive Reactivity
Negative Reactivity
Typical parameters
L W R |
CANDU |
Fast Reactor |
|
Λ |
5 x 10 - 5 |
1 x 10 - 3 |
1 x 10 - 6 |
β |
0.0075 |
0.006 |
0.0035 |
λ |
0.1 |
0.1 |
0.1 |
MIT OpenCourseWare http://ocw.mit.edu
22.05 Neutron Science and Reactor Physics
Fall 20 09
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