In general, the nuclear fission
results in the release of enormous quantities of energy
. The amount of energy depends strongly on
the nucleus to be fissioned and also depends strongly on the kinetic energy of an incident neutron
. In order to calculate the power of a reactor, it is necessary to be able precisely identify the individual components of this energy
. At first, it is important to distinguish between the total energy released
and the energy that can be recovered in a reactor
The total energy released in fission can be calculated from binding energies of initial target nucleus to be fissioned and binding energies of fission products. But not all the total energy can be recovered in a reactor. For example, about 10 MeV is released in the form of neutrinos (in fact antineutrinos). Since the neutrinos are weakly interacting (with extremely low cross-section of any interaction), they do not contribute to the energy that can be recovered in a reactor.
In order to understand this issue, we have to first investigate a typical fission reaction such as the one listed below.
Using this picture, we can identify and also describe almost all the individual components of the total energy energy released during the fission reaction.
The total energy released
As can be seen when the compound nucleus
splits, it breaks into two fission fragments
. In most cases, the resultant fission fragments have masses that vary widely, but the most probable pair of fission fragments for the thermal neutron
-induced fission of the 235U
have masses of about 94 and 139.
The largest part of the energy produced during fission (about 80 % or about 170 MeV or about 27 picojoules) appears as kinetic energy of the fission fragments. The fission fragments interact strongly (intensely) with the surrounding atoms or molecules traveling at high speed, causing them to ionize. Creation of ion pairs requires energy, which is lost from the kinetic energy of the charged fission fragment causing it to decelerate. The positive ions and free electrons created by the passage of the charged fission fragment will then reunite, releasing energy in the form of heat (e.g. vibrational energy or rotational energy of atoms).
The range of these massive, highly charged particles in the fuel is of the order of micrometers, so that the recoil energy is effectively deposited as heat at the point of fission. This is the principle how fission fragments heat up fuel in the reactor core.
See also: Interaction of Heavy Charged Particles with Matter
are emitted directly from fission and they are emitted within very short time of about 10-14 second
. Usually more than 99 percent
of the fission neutrons are the prompt neutrons
, but the exact fraction is dependent on the nuclide to be fissioned and is also dependent on an incident neutron energy (usually increases with energy).
For example a fission of 235U by thermal neutron yields 2.43 neutrons, of which 2.42 neutrons are the prompt neutrons and 0.01585 neutrons (0.01585/2.43=0.0065=ß) are the delayed neutrons. Almost all prompt fission neutrons have energies between 0.1 MeV and 10 MeV. The mean neutron energy is about 2 MeV. The most probable neutron energy is about 0.7 MeV.
Most of this energy is deposited in the coolant (moderator), because the water have the highest macroscopic slowing down power (MSDP) of the materials that are in a reactor core (PWR). The range of neutrons in a reactor depends strongly on certain reactor type, in the case of PWRs it is usually of the order of centimeters.
With the prompt neutrons prompt gamma rays
are associated. Most of prompt gamma rays are emitted after prompt neutrons.
The fission reaction releases approximately ~7 MeV
in prompt gamma rays.
The gamma rays are well attenuated by high-density and high Z materials. In a reactor core the largest share of the energy will be deposited in the fuel containing uranium dioxide, but a significant share of the energy will be deposited also in the fuel cladding and in the coolant (moderator).
The range of gamma rays in a reactor vary according to the initial energy of the gamma ray. It can be stated the most of gammas in a reactor have range from 10cm-1m.
About 6 MeV
of fission energy is in the form of kinetic energy of electrons
). The fission fragments are neutron-rich nuclei
and therefore they usually undergo beta decay
in order to stabilize itself. Beta particles deposit their energy essentially in the fuel element
, within about 1 mm of the fission fragment.
are produced in a negative beta decay
. In a nuclear reactor
occurs especially the β− decay, because the common feature of the fission fragments
is an excess of neutrons
. The existence of emission of antineutrinos and their extremely low cross-section
for any interaction leads to very interesting phenomenon. Roughly about 5% of released energy
per one fission is radiated away
from reactor in the form of antineutrinos.
For a typical nuclear reactor with a thermal power of 3000 MWth (~1000MWe of electrical power), the total power produced is in fact higher, approximately 3150 MW, of which 150 MW is radiated away into space as antineutrino radiation. This amount of energy is forever lost, because antineutrinos are able to penetrate all reactor materials without any interaction.
In fact, a common statement in physics texts is that the mean free path of a neutrino is approximately a light-year of lead. Moreover, a neutrino of moderate energy can easily penetrate a thousand light-years of lead (according to the J. B. Griffiths).
The fission fragments are neutron-rich
and very unstable nuclei.
These nuclei undergo many beta decays
in order to stabilize itself. Gamma rays
the beta decay. Their energy is transferred as heat to the surrounding material similarly as the energy carried by prompt γ-rays
A fraction of the neutron absorption reactions
result in radiative capture
followed by gamma ray emission
, producing on average about 7 MeV per fission
in the form of energetic gamma rays
. Their energy is transferred as heat to the surrounding material similarly as the energy carried by prompt γ-rays.
in a reactor is about 210 MeV
per 235U fission
, distributed as shown in the table. In a reactor, the average recoverable energy
per fission is about 200 MeV
, being the total energy minus the energy of the energy of antineutrinos
that are radiated away. This means that about 3.1⋅1010 fissions per second
are required to produce a power of 1 W
. Since 1 gram
of any fissile material
contains about 2.5 x 1021 nuclei
, the fissioning of 1 gram of fissile material yields about 1 megawatt-day (MWd)
of heat energy.
As can be seen from the description of the individual components of the total energy energy released during the fission reaction, there is significant amount of energy generated outside the nuclear fuel (outside fuel rods). Especially the kinetic energy of prompt neutrons is largely generated in the coolant (moderator). This phenomena needs to be included in the nuclear calculations.
For LWR, it is generally accepted that about 2.5% of total energy is recovered in the moderator. This fraction of energy depends on the materials, their arrangement within the reactor, and thus on the reactor type.