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Introduction to Nuclear Energy > 2014 MCQ > Flashcards

2014 MCQ Flashcards

1
Q

Name three two-phase regimes that occur in vertical two-phase flow?

A

Bubble flow
Slug flow
Annular flow

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2
Q

What is the typical enrichment for a PWR fuel?

A

5%

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3
Q

What would happen to a sub-critical satellite nuclear reactor after it plunges into seawater?

A

Neutron reflection by the seawater would make the reactor more reactive

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4
Q

What would be the effect on the thermal efficiency of a plant if the fuel enrichment of AGR were increased?

A

Little changed

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5
Q

A new rib design for an AGR increases its heat transfer coefficient. If nothing else is changed, as a result:

A

Cladding temperature will be reduced.

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6
Q

Order the following in decreasing energy release of U235:

Neutron kinetic energy
Fission fragment kinetic energy
Prompt gamma rays
Fission product radiation

A

Fission fragment kinetic energy
Fission product radiation
Prompt gamma rays
Neutron kinetic energy

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7
Q

Wigner energy is

A

Neutron induced strain energy in the hexagonal lattice of graphite

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8
Q

What is the fuel for Magnox?

A

U-metal

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9
Q

What is the moderator and coolant for AGR?

A

Graphite
CO2

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10
Q

What is the moderator and coolant for Magnox?

A

Graphite
Coolant

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11
Q

List the following in ascending order of CO2 release per unit of electricity:

Coal
Nuclear
Oil
Gas

A

Nuclear
Gas
Oil
Coal

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12
Q

Why are delayed neutrons so important in reactor control?

A

They increase the average neutron lifetime

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13
Q

What does the microscopic cross section provide?

A

The properties of an individual nucleus

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14
Q

A sub-critical multiplying assembly can ________ the number of neutrons beyond the number introduced

A

increase

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15
Q

Do fission neutrons have a higher or lower KE than fission fragments?

A

Lower

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16
Q

What charge are fission neutrons?

A

Uncharged

17
Q

The ‘activation energy’ to permit fission comes largely from

A

the binding energy of the neutron that causes the fission

18
Q

What does the absorption cross section comprise of?

A

absorption cross section = capture cross section + fission cross section

19
Q

What is the reactivity of a sub-prompt-critical nuclear reactor?

A

N/A

20
Q

Following a period of normal full power operation, a reactor suddenly loses coolant to the extent that the fuel rod may be considered to be adiabatic, and the fission reaction ceases. As a result the fuel pellet edge temperature will

A

Rise.

21
Q

Fuel burnup in a PWR is typically first limited because:

A

Fission product production and release to the plenum threatens pin integrity

22
Q

What does the second and fourth term in the differential equation give?

A

(ii) local fission neutron production rate
(iv) local divergence of neutron current

23
Q

Name four material effects as a consequence of radiation damage?

A

embrittlement
Phase changes
creep
hardening

24
Q

Unit for neutron current?

A

neutrons per square metre per second

25
Q

What moderator is used in a gas cooled fast breeder reactor?

A

No moderator

26
Q

What coolant is used in CANDU?

A

Heavy water

27
Q

List the following in increasing order of operating pressure:

CANDU
AGR
PWR
RBMK

A

AGR
RBMK
CANDU
PWR

28
Q

A fast reactor typically requires a fissile concentration of plutonium around ___

A

20%

29
Q

List the following in increasing coolant heat transfer coeffieicnt:

Water
Liquid sodium
High pressure CO2
Boiling water

A

High pressure CO2
water
liquid sodium
boiling water

30
Q

True or false:
There is a decrease in the number of Frenkel defects as a result of radiation damage.

A

False

31
Q

Which gas is used to pressurize reactor fuel pins?

A

Helium

32
Q

Why is this statement inaccurate:
In a fast breeder reactor fuel is converted into energy rapidly, resulting in a shortened fuel cycle.

A

While fast breeder reactors are designed to produce energy more efficiently by using fast neutrons to convert fertile material (like uranium-238) into fissile material (like plutonium-239), they don’t necessarily convert fuel into energy more rapidly.

33
Q

During a small break loss of coolant accident (LOCA) in a PWR, the core can remain uncovered for a significant time because ____

A

the reactor vessel remains pressurised and inhibits ingress of ECCS water

34
Q

As the size of nuclei increases, the neutron to proton ratio

A

increases (gets larger)

Introduction to Nuclear Energy (16 decks)

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