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E.4 Fission Topic Practice

E.4 Fission Topic Practice
IB Physics syllabusPhysics SL/HLFirst assessment 2025

Practise the main fission ideas students meet in exams: balancing reactions, energy release, sustaining chain reactions and reactor component roles.

Exam points

  • balance fission equations by conserving nucleon and proton number, including the number of neutrons released
  • explain how moderator, control rods and enriched fuel work together to keep the chain reaction controlled
  • calculate fission energy or fuel use from binding energy per nucleon, power output and efficiency data

Question 23

[Maximum number: 1]

Which two components of a nuclear power station are primarily responsible for ensuring that a controlled chain reaction is maintained?

A

Control rods and heat exchangers

B

Moderators and shielding

C

Shielding and heat exchangers

D

Moderators and control rods

Question 23

[Maximum number: 1]

A suitable material for use as a moderator in a nuclear reactor is...

A

cadmium.

B

concrete.

C

uranium-238.

D

water.

Question 24

[Maximum number: 1]

A nucleus of uranium- 235(92235U)235\left({ }_{92}^{235} \mathrm{U}\right) absorbs a neutron and decays into two nuclides, xenon-140 ( 54140Xe{ }_{54}^{140} \mathrm{Xe} ) and strontium-94 ( 3894Sr{ }_{38}^{94} \mathrm{Sr} ).

How many neutrons are released in this reaction?

A

1

B

2

C

3

D

4

Question 24

[Maximum number: 1]

The moderator in a nuclear power station...

A

increases the proportion of U-235 in the fuel source.

B

transfers internal energy from the reactor to the turbines.

C

allows operators to regulate the rate of power production.

D

decreases the kinetic energy of neutrons in the reactor.

Question 24

[Maximum number: 1]

Which component is responsible for slowing down neutrons in a nuclear reactor to increase the likelihood of nuclear fission?

A

Moderator

B

Control rods

C

Fuel rods

D

Heat exchanger

Question 24

[Maximum number: 1]

In a simple model of a nuclear reactor, four neutrons are emitted per fission on average.

The average number of neutrons absorbed by the control rods is NcN_{\mathrm{c}} per fission.
The average number of neutrons that are lost through the walls of the reactor is N1N_{1} per fission.
Any remaining neutrons induce further fissions.
What are possible values for NcN_{\mathrm{c}} and N1N_{1} for the reactor to maintain a steady reaction?

Nc\boldsymbol{N}_{\mathbf{c}}

N1\boldsymbol{N}_{\mathbf{1}}

1

1

1

3

2

1

2

2

Question 38

[Maximum number: 1]

A nucleus of uranium-235 (92235U)\left({ }_{92}^{235} \mathrm{U}\right) absorbs a neutron and decays into two nuclides, xenon-140 ( 54140Xe{ }_{54}^{140} \mathrm{Xe} ) and strontium-94 ( 3894Sr{ }_{38}^{94} \mathrm{Sr} ).

How many neutrons are released in this reaction?

A

1

B

2

C

3

D

4

0 selected