Lecture 6 Flashcards

1
Q

Under steady state conditions, neutron conservation requires that

A

(neutrons leaking) + (neutrons absorbed) = (source neutrons emitted) + (fission neutrons produced)

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2
Q

The neutron diffusion equation is

A
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3
Q

Fick’s approximation is

A

relating the current to the flux so that

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4
Q

D =

A
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5
Q

Diffusion equation for uniform, non-multiplying system

A
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6
Q

diffusion area =

A

L2=D/Σa

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7
Q

Differential equation for source-free, plane geometry

A
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8
Q

general solution of

A
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9
Q

Boundary conditions for a source-free example in semi-infinite plane geometry

A
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10
Q

For a uniform source in plane geometry, φh =

A
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11
Q

For a uniform source in plane geometry, φp =

A
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12
Q

boundary conditions for uniform source in plane geometry

A
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13
Q

cosh(x)=

A
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14
Q

sinh(x) =

A
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15
Q
A
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16
Q

The vacuum boundary condition

A
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17
Q

The vacuum boundary condition 2/3λ is the ______, at which point the flux is _____.

A

extrapolation distance, zero

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18
Q

If the solution is symmetric about x=0 such that the _________ is zero, then we may solve the problem only for _____, and bc becomes

A

net number of neutrons crossing the plane, x>0, dφ(0)/dx=0

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19
Q

For a surface source

A

s’’

20
Q

albedo eqn

A

α = (1-2D/L)/(1+2DL) or

21
Q

Flux for surface source

A
22
Q

Diffusion theory requires continuity of ______, ______, and _____ at interface conditions.

A

flux, normal component of current,

23
Q

If there is a localized source along the interface, the diffusion equation becomes

A
24
Q

For a point source, sp =

A
25
Q

Neutron diffusion eqn in sperical geometry

A
26
Q

Find current equation for point source

Jr =

A
27
Q

For a point source, φ(r) =

A
28
Q

Find φh for spherical geometry with uniform source

A
29
Q

Find φp for spherical geometry with uniform source

A
30
Q

Boundary and interface conditions for a uniform sphere in non-multiplying medium

A
31
Q

Diffusion theory is valid for situations where neutrons ______ with a _____ distribution. And if the neutron distibution is changing _____ in space.

A

travel in all directions, uniform, gradually

32
Q

Diffusion theory leads to significant errors for saptial distributions of neutrons near _____ and at ______.

A

boundaries, materials with sharply different properties

33
Q

In reactor lattices consisting of fuel, coolant, moderators, and other materials, we use diffusion theory to examine the _____ distribution of neutrons only after taking appropriate _____ over the lattice cells.

A

global, averages

34
Q

Diffusion length, L, in terms of r

A
35
Q

Diffusion length in terms of λ and c

A
36
Q

The uncollided flux drops off as _____ while total flux drops of as ____

A

1/r2, 1/r

37
Q

root mean square idstance between birth and first collision

A
38
Q

For the diffusion equation to give reasonable accuracy, ____ of the neutron populatin at a point can remain uncollided

A

only a small fraction

39
Q

material buckling (B2) equation

A
40
Q

Geometric buckling equation

B2=

A
41
Q

In a reactor, the flux level becomes _____ when it is critical

A

infinite

42
Q

For a fixed source, the flux level __________ with increasing k

A

increases

43
Q

laplacian in cartesian coordinates

A
44
Q

Laplacian in cylindrical coordinates

A
45
Q

Laplacian in spherical coordinates

A