14.9 Nuclear Reactions and Nuclear Fission 447
The activation energy for the
238
92
U fission is 6.6 MeV; hence, to enable the
fission of this isotope, neutrons with kinetic energy T
n
>1:8MeV are required.
In the case of uranium, the term a
4
in (14.15) plays a decisive role. In the neutron
capture reaction, the even-even nuclei, for example,
236
92
U and
238
92
U , become even-
odd nuclei. An additional energy equal to a
4
=A
1=2
D 12:6 MeV=
p
236 ' 0:8 MeV
should be provided. Instead, the nucleus
235
92
U becomes an even-even nucleus
after neutron capture, but the same amount of energy ('0.8 MeV) now becomes
available. Note that the difference between the binding energies in the two cases
reflects the difference between M
235
M
238
.
14.9.2 Fission Nuclear Reactors
A fission reaction typically produces an average number of neutrons >1; these neu-
trons may subsequently induce new fission reactions. Conditions for self-powered
chain reactions can be created to produce energy by fission. The first nuclear pile
was built by Fermi and collaborators in 1942. A nuclear reactor based on controlled
fission reactions are used to produce: (1) energy; (2) neutron sources for research
and medical purposes; (3) radio-isotopes or other fissile substances, for example,
239
94
Pu or
233
92
U . Uncontrolled chain reactions are the basis for nuclear bombs.
A typical nuclear reactor for energy production is based on chain reactions
in uranium. By
235
92
U fission reaction, each produces an average of ' 200 MeV
and 2.5 neutrons. The cross-section of neutron capture is small and only thermal
neutrons are efficiently captured by
235
92
U to produce successive fission reactions.
For this reason, it is necessary to moderate neutrons, forcing them to lose energy
in successive collisions with light nuclei. From the construction point of view, the
core of a uranium nuclear reactor consists of a moderator material and of enriched
uranium, i.e., a kind of uranium in which the percent composition of
235
92
U is
increased typically at 3% level (in nature, this isotope has an abundance of 0.7%).
To moderate neutrons, materials containing low Z nuclei are used, e.g., H
2
O,
D
2
O (the so-called heavy water)orC . Carbon is not very efficient, but can be
distributed effectively in the fuel. The Chernobyl energy power plant in the former
USSR used carbon as a moderator. The water (normal or heavy) is also an efficient
heat exchanger to cool the reactor. The hydrogen nuclei in the molecule of water
are also very efficient to moderate neutrons; there is a disadvantage due to the high
cross-section of the competitive reaction n Cp !
2
1
H C, that reduces the neutron
budget. The deuterium nucleus present in heavy water (instead of hydrogen) has a
much smaller cross-section for the process n C
2
1
H !
3
1
H C , but it produces
radioactive tritium that must be filtered out from the cooling system.
With a proper combination of fuel and moderator, the situation in which there
is on average one thermal neutron per fission is reached. This is the so-called
critical reactor situation. Preventing that this factor exceeds unity and that the
reactor reaches the super-critical situation with the risk of failures, materials with