nuclear reactors, bau, 1st semester, 2008-2009 (saed dababneh). 1 one-speed neutron diffusion in a...

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Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 ne-speed neutron diffusion in a finite mediu ne-speed neutron diffusion in a finite mediu Steady State Diffusion Equation A B A • At the interface • What if A or B is a vacuum? • Linear extrapolation distance. dx d D dx d D J J B B A A B A x

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Page 1: Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

1

One-speed neutron diffusion in a finite mediumOne-speed neutron diffusion in a finite medium

Steady State Diffusion Equation

A B

BA • At the interface

• What if A or B is a vacuum?• Linear extrapolation distance.

dx

dD

dx

dDJJ B

BA

ABA

x

Page 2: Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

2

One-speed neutron diffusion in a multiplying mediumOne-speed neutron diffusion in a multiplying medium

More realistic multiplying medium

The reactor core is a finite multiplying medium.• Neutron flux?• Reaction rates?• Power distribution in the reactor core?Recall:• Critical (or steady-state):Number of neutrons produced by fission = number of neutrons lost by:absorptionandleakage

)( rate absorptionneutron

rate productionneutron

A

(S)k

)( rate leakageneutron )( rate absorptionneutron

)( rate productionneutron

LEA

Skeff

Page 3: Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

3

More realistic multiplying medium

yprobabilit leakage-nonleaknoneff P

LEA

A

k

k

aa

a

V

SA

S

LE

VolumeVS

SALE

1

area surface

3

2

)()()(0 2 rDrrk aa

Steady state homogeneous reactorSteady state homogeneous reactor

2222 1

0)()(L

kBrBr

Material buckling

For a critical reactor:Keff = 1K > 1

Recall:

multiplying m

edium

multiplying m

edium

Things to be used later…!

Page 4: Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

4

More on One-Speed DiffusionHW 20HW 20

Show that for a critical homogeneous reactorcritical homogeneous reactor

DBDLBP

a

a

a

aleaknon 2222 1

1

Infinite Bare Slab Reactor Infinite Bare Slab Reactor (one-speed diffusion)(one-speed diffusion)

x

aa/2

d da0/2

• Vacuum beyond.• Return current = 0.d = linear extrapolation distance = 0.71 tr (for plane surfaces) = 2.13 D.

z

Reactor

Page 5: Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

5

HW 21HW 21

022

2

B

dx

dFor the infinite slab . Show that the general solution

with BC’sBxCBxAx sincos)(

0)(

0)2

(

0

0

xdx

xd

a

Flux is symmetric about

the origin.

0cos)( ABxAx

,...2

5,

2

3,

2)

2(0)

2(cos)

2( 000

aB

aBA

a

More on One-Speed Diffusion

Page 6: Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

6

,...2

5,

2

3,

2)

2( 0

a

BHW 21 HW 21 (continued)(continued)

,...5

,3

,0 BBBa

Fundamental mode, the only mode significant in critical reactors.

Buckling lGeometricacos)(00

0 a

Bxa

x

For a critical reactor, the geometrical buckling is equal to the material buckling.To achieve criticality

2

2

0

1

L

k

a

More on One-Speed Diffusion

Page 7: Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

7

More on One-Speed Diffusion

???0

• To achieve criticality

• But criticality at what power level??• 0 can not be determined by the geometry alone.

2

2

0

1

L

k

a

xa

Px0

0 cos,..,..)()(

Do it.

Do it.

Page 8: Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

8

More realistic multiplying medium0)()( 22 rBr

)(

)(22

r

rB

• The buckling is a measure of extent to which the flux curves or “buckles.”• For a slab reactor, the buckling goes to zero as “a” goes to infinity. There would be no buckling or curvature in a reactor of infinite width. • Buckling can be used to infer leakage. The greater the curvature, the more leakage would be expected.

Page 9: Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

9

Spherical Bare Reactor (one-speed diffusion)Spherical Bare Reactor (one-speed diffusion)

334

2

3

2 46

a

a

a

a

Minimum leakage minimum fuel to achieve criticality.

r0

0

2 22

2

B

dr

d

rdr

dHW 22HW 22

Brr

CBr

r

Asincos

Br

r

r

r

C 00

,sin

Continue!Reactor

More on One-Speed Diffusion

CubeCube SphereSphere

r

Page 10: Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

10

HW 23HW 23Infinite planer source in an infinite Infinite planer source in an infinite medium.medium.

LxeD

SLx /

2)(

D

xS

Ldx

xd )(1)(22

2

x

aa/2

a0/2

Source

)2/cosh(

2/2sinh

2 0

0

La

Lxa

D

SL

HW 24HW 24

More on One-Speed Diffusion

Infinite planer source in a finite Infinite planer source in a finite medium.medium.

Page 11: Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

11

More on One-Speed Diffusion

Infinite planer source in a multi-region medium.Infinite planer source in a multi-region medium.

FiniteInfinite Infinite

BCmore

dx

dD

dx

dD

aa

axax

2/

22

2/

11

21 )2/()2/(

Project 2Project 2

Page 12: Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

12

Back to Multiplication Factor

k = fp, leaknoneff P

k

k

leaknoneff Pfk

• Fast from thermal,• Fast from fast, .• Thermal from fast, p.• Thermal available for fission

Thinking QUIZThinking QUIZ• For each thermal neutron absorbed, how many fast neutrons are produced?

i

fa

ii )()(1

poisona

eratora

clada

fuela

fuelaf

mod

Recall:

Things to be used later…!