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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