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## Interactions of Neutrons with Matter

**Neutrons** are neutral particles, therefore they travel in **straight lines**, deviating from their path only when they actually collide with a nucleus to be scattered into a new direction or absorbed. Neither the electrons surrounding (atomic electron cloud) a nucleus nor the electric field caused by a positively charged nucleus affect a neutron’s flight. In short, **neutrons collide with nuclei**, not with atoms. A very descriptive feature of the transmission of neutrons through bulk matter is the mean free path length (** λ – lambda**), which is the mean distance a neutron travels between interactions. It can be calculated from following equation:

**λ=1/Σ**

**Neutrons may interact with nuclei in one of following ways:**

## Types of neutron-nuclear reactions

## Neutron cross-section

The extent to which neutrons interact with nuclei is described in terms of quantities known as **cross-sections**. **Cross-sections** are used to express the **likelihood** of particular interaction between an** incident neutron** and a **target nucleus**. It must be noted this likelihood do not depend on real target dimensions. In conjunction with the neutron flux, it enables the calculation of the reaction rate, for example to derive the thermal power of a nuclear power plant. The standard unit for measuring the microscopic cross-section (**σ-sigma**) is the **barn**, which is equal to **10 ^{-28} m^{2}**. This unit is very small, therefore barns (abbreviated as “b”) are commonly used. The microscopic cross-section can be interpreted as the

**effective**‘target area’ that a nucleus

**interacts**with an incident neutron.

A **macroscopic cross-section** is derived from microscopic and the material density:

** ****Σ=σ.N**

** **Here σ, which has units of m^{2}, is referred to as the microscopic cross-section. Since the units of N (nuclei density) are nuclei/m^{3}, the **macroscopic cross-section** **Σ** have units of **m ^{-1}**, thus in fact is an incorrect name, because it is not a correct unit of cross-sections.

**Neutron cross-sections** constitute a key parameters of nuclear fuel. Neutron cross-sections must be calculated for fresh fuel assemblies usually in two-Dimensional models of the fuel lattice.

** **The neutron cross-section is variable and depends on:

**Target nucleus**(hydrogen, boron, uranium, etc.) Each isotop has its own set of cross-sections.**Type of the reaction**(capture, fission, etc.). Cross-sections are different for each nuclear reaction.**Neutron energy**(thermal neutron, resonance neutron, fast neutron). For a given target and reaction type, the cross-section is strongly dependent on the neutron energy. In the common case, the cross section is usually much larger at low energies than at high energies. This is why most nuclear reactors use a neutron moderator to reduce the energy of the neutron and thus increase the probability of fission, essential to produce energy and sustain the chain reaction.**Target energy**(temperature of target material – Doppler broadening) This dependency is not so significant, but the target energy strongly influences inherent safety of nuclear reactors due to a Doppler broadening of resonances.

See also: JANIS (Java-based nuclear information software)

See also: Neutron cross-section

## Law 1/v

For thermal neutrons (**in 1/v region**), absorption cross-sections increases as the velocity (kinetic energy) of the neutron decreases. Therefore the **1/v Law** can be used to determine shift in absorbtion cross-section, if the neutron is in equilibrium with a surrounding medium. This phenomenon is due to the fact the nuclear force between the target nucleus and the neutron has a longer time to interact.

This law is aplicable only for absorbtion cross-section and only in the 1/v region.

**Example of cross- sections in 1/v region:**

The absorbtion cross-section for 238U at 20°C = 293K (~0.0253 eV) is:

.

The absorbtion cross-section for 238U at 1000°C = 1273K is equal to:

This cross-section reduction is caused only due to the shift of temperature of surrounding medium.

## Resonance neutron capture

Absorption cross section is often highly dependent on neutron energy. Note that the nuclear fission produces neutrons with a mean energy of 2 MeV (200 TJ/kg, i.e. 20,000 km/s). The neutron can be roughly divided into three energy ranges:

- Fast neutron. (10MeV – 1keV)
- Resonance neutron (1keV – 1eV)
- Thermal neutron. (1eV – 0.025eV)

The resonance neutrons are called resonance for their special bahavior. At resonance energies the cross-section can reach peaks more than 100x higher as the base value of cross-section. At this energies the neutron capture significantly exceeds a probability of fission. Therefore it is very important (for thermal reactors) to **quickly** **overcome** this range of energy and operate the reactor with thermal neutrons resulting in increase of probability of fission.

## Doppler broadening

** **

A **Doppler broadening** of resonances is very important phanomenon, which **improves reactor stability**. The prompt temperature coefficient of most thermal reactors is **negative**, owing to an nuclear Doppler effect. Although the absorbtion cross-section depends significantly on incident neutron energy, the shape of the cross-section curve depends also on target temperature.

Nuclei are located in atoms which are themselves in continual **motion** owing to their thermal energy. As a result of these **thermal motions** neutrons impinging on a target appears to the nuclei in the target to have a continuous spread in energy. This, in turn, has an effect on the observed shape of resonance. The resonance becomes **shorter and wider** than when the nuclei are at rest.

Although the shape of a resonance changes with temperature, the **total area** under the resonance remains essentially constant. But this **does not imply** **constant neutron absorbtion**. Despite the constant area under resonance, **a resonance integral**, which determines the absorbtion, increases with increasing target temperature. This, of course, decreases coefficient k (negative reactivity is inserted).

**Typical cross-sections of materials in the reactor**

Following table shows **neutron cross-sections** of the most common isotopes of reactor core.

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