**Shielding of ionizing radiation**simply means having

**some material between the source of radiation and you**(or some device) that will

**absorb the radiation**. Lead blocks or sheets are widely used as a

**gamma rays**shield. The major advantage of the lead shield is its compactness due to its higher density.

In short, effective shielding of gamma radiation is in most cases based on the use of materials with two following material properties:

**high-density of material****the high atomic number of material (high Z materials)**

**However, low-density materials and low Z materials can be compensated with increased thickness, which is as significant as density and atomic number in shielding applications. **

**A lead is widely used as a gamma shield. The major advantage of the lead shield is its compactness due to its higher density. On the other hand, depleted uranium is much more effective due to its higher Z. Depleted uranium shields in portable gamma-ray sources. **

In nuclear power plants, shielding of a reactor core can be provided by materials of reactor pressure vessel, reactor internals (neutron reflector). Also, heavy concrete is usually used to shield both neutrons and gamma radiation.

Although water is neither high density nor high Z material, it is commonly used as gamma shields. Water provides a radiation shielding of fuel assemblies in a spent fuel pool during storage or transports from and into the reactor core.

In general, gamma radiation shielding is more complex and difficult than alpha or beta radiation shielding. To comprehensively understand how a gamma-ray loses its initial energy, how it can be attenuated, and how it can be shielded, we must have detailed knowledge of its interaction mechanisms.

See also more theory: Interaction of Gamma Radiation with Matter

See also calculator: Gamma activity to dose rate (with/without shield)

See also XCOM – photon cross-section DB: XCOM: Photon Cross Sections Database

## Characteristics of Gamma Rays / Radiation

**Key features of gamma rays** are summarized in the following few points:

Gamma rays are

**high-energy photons**(about 10 000 times as much energy as the visible photons), the same photons as the photons forming the visible range of the electromagnetic spectrum – light.- Photons (gamma rays and X-rays) can ionize atoms directly (despite they are electrically neutral) through the Photoelectric effect and the Compton effect, but secondary (indirect) ionization is much more significant.
- Gamma rays ionize matter primarily via
**indirect ionization**. - Although many possible interactions are known, there are three key interaction mechanisms with the matter.
- Gamma rays travel
**at the speed of light,**and they can travel thousands of meters in the air before spending their energy. - Since gamma radiation is very penetrating, it must be shielded by very dense materials, such as lead or uranium.
- The distinction between X-rays and gamma rays is not so simple and has changed in recent decades. According to the currently valid definition, X-rays are emitted by electrons outside the nucleus, while
**the nucleus emits gamma rays**. - Gamma rays frequently
**accompany the emission**of alpha and beta radiation.

## Gamma Rays Attenuetion

The total cross-section of the interaction of gamma rays with an atom is equal to the sum of all three mentioned partial cross-sections:**σ = σ _{f} + σ_{C} + σ_{p }**

**σ**_{f}– Photoelectric effect

**σ**_{C}– Compton scattering

**σ**_{p}– Pair production

One of the three partial cross-sections may become much larger than the other two depending on the gamma-ray energy and the absorber material. At small values of gamma-ray energy, the** photoelectric effect** dominates. **Compton scattering** dominates at intermediate energies. The Compton scattering also increases with decreasing atomic number of matter. Therefore the interval of domination is wider for light nuclei. Finally, **electron-positron pair production** dominates at high energies.

Based on the definition of interaction cross-section, the dependence of gamma rays intensity on the thickness of absorber material can be derived. If **monoenergetic gamma rays** are collimated into a **narrow beam** and if the detector behind the material only detects the gamma rays that passed through that material without any interaction, then the dependence should be simple **exponential attenuation gamma rays**. Each interaction removes the photon from the beam either by absorption or scattering away from the detector direction. Therefore the interactions can be characterized by a fixed probability of occurrence per unit path length in the absorber. The sum of these probabilities is called the **linear attenuation coefficient**:

**μ = τ _{(photoelectric)} + σ_{(Compton)} + κ_{(pair)}**

### Linear Attenuation Coefficient

The following equation can then describe the attenuation of gamma radiation.

**I=I _{0}.e^{-μx}**

where I is intensity after attenuation, I_{o} is incident intensity, μ is the linear attenuation coefficient (cm^{-1}), and the physical thickness of absorber (cm).

The materials listed in the table beside are air, water, and different elements from carbon (*Z*=6) to lead (*Z*=82). Their linear attenuation coefficients are given for three gamma-ray energies. There are two main features of the linear attenuation coefficient:

- The linear attenuation coefficient increases as the atomic number of the absorber increases.
- The linear attenuation coefficient for all materials decreases with the energy of the gamma rays.

## Half Value Layer

The half-value layer expresses the thickness of absorbing material needed to reduce the incident radiation intensity by a **factor of two**. There are two main features of the half-value layer:

- The
**half-value layer**decreases as the atomic number of the absorber increases. For example, 35 m of air is needed to reduce the intensity of a 100 keV gamma-ray beam by a factor of two, whereas just 0.12 mm of lead can do the same thing. - The
**half-value layer**for all materials increases with the energy of the gamma rays. For example, from 0.26 cm for iron at 100 keV to about 1.06 cm at 500 keV.

### Example

How much water shielding do you require if you want to reduce the intensity of a 500 keV **monoenergetic** gamma-ray beam (**narrow beam**) to **1%** of its incident intensity? The half-value layer for 500 keV gamma rays in water is 7.15 cm, and the linear attenuation coefficient for 500 keV gamma rays in water is 0.097 cm^{-1}. The question is quite simple and can be described by the following equation:If the half-value layer for water is 7.15 cm, the linear attenuation coefficient is:Now we can use the exponential attenuation equation:thereforeSo the required thickness of water is about **47.5 cm**. This is a relatively large thickness, and it is caused by small atomic numbers of hydrogen and oxygen. If we calculate the same problem for **lead (Pb)**, we obtain the thickness **x=2.8cm**.

Linear Attenuation Coefficients

**Table of Linear Attenuation Coefficients** (in cm-1) for different materials at gamma-ray energies of 100, 200, and 500 keV.

Absorber | 100 keV | 200 keV | 500 keV |

Air | 0.0195/m | 0.0159/m | 0.0112/m |

Water | 0.167/cm | 0.136/cm | 0.097/cm |

Carbon | 0.335/cm | 0.274/cm | 0.196/cm |

Aluminium | 0.435/cm | 0.324/cm | 0.227/cm |

Iron | 2.72/cm | 1.09/cm | 0.655/cm |

Copper | 3.8/cm | 1.309/cm | 0.73/cm |

Lead | 59.7/cm | 10.15/cm | 1.64/cm |

Half Value Layers

The half-value layer expresses the thickness of absorbing material needed to reduce the incident radiation intensity by a factor of two. With a half-value layer, it is easy to perform simple calculations.

Source: www.nde-ed.org

**Table of Half Value Layers** (in cm) for different materials at gamma-ray energies of 100, 200, and 500 keV.

Absorber | 100 keV | 200 keV | 500 keV |

Air | 3555 cm | 4359 cm | 6189 cm |

Water | 4.15 cm | 5.1 cm | 7.15 cm |

Carbon | 2.07 cm | 2.53 cm | 3.54 cm |

Aluminium | 1.59 cm | 2.14 cm | 3.05 cm |

Iron | 0.26 cm | 0.64 cm | 1.06 cm |

Copper | 0.18 cm | 0.53 cm | 0.95 cm |

Lead | 0.012 cm | 0.068 cm | 0.42 cm |

## Mass Attenuation Coefficient

When characterizing an absorbing material, we can sometimes use the mass attenuation coefficient. **The mass attenuation coefficient** is defined as the ratio of the linear attenuation coefficient and absorber density **(μ/ρ)**. The following equation can then describe the attenuation of gamma radiation:

**I=I _{0}.e^{-(μ/ρ).ρl}**

, where ρ is the material density, (μ/ρ) is the mass attenuation coefficient, and ρ.l is the mass thickness. The measurement unit was used for the mass attenuation coefficient cm^{2}g^{-1}.

For intermediate energies, the Compton scattering dominates, and different absorbers have approximately equal mass attenuation coefficients. This is because the cross-section of Compton scattering is proportional to the Z (atomic number), and therefore the coefficient is proportional to the material density ρ. At small gamma-ray energy values or high gamma-ray energy values, the coefficient is proportional to higher powers of the atomic number Z (for photoelectric effect σ_{f} ~ Z^{5}; for pair production σ_{p} ~ Z^{2}), the attenuation coefficient μ is not a constant.

## Validity of Exponential Law

The exponential law will always describe the attenuation of the primary radiation by matter. If secondary particles are produced, or the primary radiation changes its energy or direction, the effective attenuation will be much less. The radiation will penetrate more deeply into matter than is predicted by the exponential law alone. The process must be taken into account when evaluating the effect of radiation shielding.

## Buildup Factors for Gamma Rays Shielding

The **buildup factor** is a correction factor that considers the influence of the scattered radiation plus any **secondary particles** in the medium during shielding calculations. If we want to account for the buildup of secondary radiation, then we have to include the **buildup factor**. The buildup factor is then a multiplicative factor that accounts for the response to the un-collided photons to include the contribution of the scattered photons. Thus, the buildup factor can be obtained as a ratio of the total dose to the response for un-collided dose.

The **extended formula** for the dose rate calculation is:

The ANSI/ANS-6.4.3-1991 Gamma-Ray Attenuation Coefficients and Buildup Factors for Engineering Materials Standard, contains derived gamma-ray attenuation coefficients and buildup factors for selected engineering materials and elements for use in shielding calculations (ANSI/ANS-6.1.1, 1991).