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Neutronics > Lecture 3 > Flashcards

Lecture 3 Flashcards

1
Q

Given the non-leakage probablity, what is the equation for k?

A
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2
Q

Equation for caputre-to-fission ratio?

A
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3
Q

The capture-to-fission ratio ratio decreases sharply above ____ keV

A

100

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4
Q

The number of neutrons produced per fission ______ above 1 MeV

A

increases rapidly

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5
Q

What is the equation for the ratio of fission neutrons produced to neutrons absorbed)?

A
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6
Q

What is the equation for isotopic eta?

A
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7
Q
A
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8
Q

Equation for fuel eta (using fissile enrichment ratio)

A
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9
Q

Fast reactors must have a U-235 enrichment percent of at least

A

10%

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10
Q

The average fractional energy loss from isotropic elastic scattering is given by

A
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11
Q

Average slowing down decrement

A
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12
Q

Average slowing down power

A
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13
Q

Average slowing down ratio

A
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14
Q

define

A

number of neutrons/cm^3 with energies between E and E+dE

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15
Q

define

A

total number of neutrons / cm^3

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16
Q

define φ(E)dE

A

total distance traveled during one second by all neutrons with energies E and E+dE in 1 cm^3

17
Q

What is the equation for φ(E)?

A
18
Q

Define

A

probablity/cm of flight of a neutron with energy E undergoing a reaction of type x

19
Q

Define

A

probable number of colllisions of type x /s-cm^3 for neutrons with energies between E and E+dE

20
Q

Define

A

probable number of collisions of type x /s-cm^3 of all neutrons

21
Q

Fill in the blanks

A
22
Q

define q(E)

A

numer of neutrons slowing down past energy E /s/cm^3

23
Q

Primary form of absorption comes from

A

the resonance cross sections

24
Q

Between resonances, the absorption cross sections are

A

small enough to be ignored

25
Q

In the intermediate range below the fission spectrum

A
26
Q

In the intermediate range below the ifssion spectrum ϕ(E) =

A
27
Q

The flux is no longer proportional to 1/E when what kind of material is present?

A

resonance absorber

28
Q

What is the equation for ϕ(E) using the the narrow resonance approximation?

A
29
Q

Since self-shielding ____ the flux where the absorption cross section is large, it _____ overall neutron losses to absorption and thus ____ the propogation of the chain reaction.

A

reduces

reduces

aids

30
Q

Absorption cross sections in the _____ range are approximately 1/v

A

thermal

31
Q

Equation for thermal cross section averages

A
32
Q

In many cases, thermal scattering cross sections are _____ of energy

A

independent

33
Q

At thermal energies, the binding of atoms to molecules or within crystal lattices can significantly affect

A

thermal scattering cross sections

34
Q

Equation for number of fission neutrons produced

A
35
Q

Equation for number of neutrons absorbed

A
36
Q

Infinite multiplicaton factor (given cross sections)

A

Neutronics (7 decks)

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