Lecture 2 Flashcards

1
Q

Intensity change eqn

A

∆I=στNI

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2
Q

Macroscopic cross sectition eqn and definition

A

Σ=σN

Interaction probablity per unit thickness

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3
Q

Reaction rate per unit volume eqn

A
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4
Q

Intensity at x eqn

A
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5
Q

Probablity to reach x without collision

A
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6
Q

Probablity to make first collision in dx, around x

A

probablity to collide at x * probablity to collide within dx

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7
Q

Mean free path def and eqn

A

average distance neutron travels w/o collision, 1/Σ

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8
Q

Neutron flux for mono speed and direction

A

φ = I = nv

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9
Q

Flux from point source (geometric only)

A
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10
Q

Attenuation of flux from point source (geometrically and collissions)

A

Geometric flux * I(x)

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11
Q

Number density equation

A
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12
Q

Absorption at a specific E eqn

A
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13
Q

The energy dependency of the cross sections in the vicinity of each resonance take the form of

A

the Briet-Wigner formula

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14
Q

Resonances correspond to what?

A

Excitetation of nuclear levels from the incient neutron.

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15
Q

Define Doppler Broadening

A

The broadening of resonance peaks due to the change in relative velocity between the neutron and the incident nucleus.

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16
Q

P(V)dV is…?

A

the probablity that a nuclus has velocity V within dV

17
Q

Reaction rate

A
18
Q

Why threshold cross sections?

A

The incident neutron needs to have enough kinetic energy to raise the nucleus to an excited state

19
Q

What is the equation for E’ min

A
20
Q

Nameless alpha = ?

A
21
Q

What is the equation for the energy distribution of a scattered neutron?

A
22
Q

What is the slowing down decrement? (definition)

A

lograrithmic energy loss per colission

23
Q

What is the equation for the slowing down decrement?

A

Aproximately 1/(A+2/3)

or

24
Q

What is the equation for the number of elastic collisions required to slow a neutron from fission (E_0) to thermal energy(E_n)?

A
25
Q

What is the equation for the AVERAGE slowing down decrement?

A
26
Q

Slowing-down power is given by…?

A
27
Q

The slowing-down ratio is given by…?

A