Neutron Interactions – Part I · Neutron Interactions – Part I ... • Eric J. Hall. Radiobiology for the ... • Calculate the mean free path for the previous example. 6

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Neutron Interactions – Part INeutron Interactions – Part I

George Starkschall, Ph.D.George Starkschall, Ph.D.

Based on lectures by Rebecca Howell, PhD

References/AcknowledgmentsReferences/Acknowledgments

• Glenn Knoll. Radiation Detection and Measurement, 4th Ed. (2010)

• Herman Cember. Introduction to Health Physics 3rd Ed. (1996)

• Eric J. Hall. Radiobiology for the Radiologist 5th Ed. (2000)

• Frank H. Attix. Introduction to Radiological Physics and Radiation Dosimetry. (1986)

• Glenn Knoll. Radiation Detection and Measurement, 4th Ed. (2010)

• Herman Cember. Introduction to Health Physics 3rd Ed. (1996)

• Eric J. Hall. Radiobiology for the Radiologist 5th Ed. (2000)

• Frank H. Attix. Introduction to Radiological Physics and Radiation Dosimetry. (1986)

Why do we as Medical Physicists care about neutrons?

Why do we as Medical Physicists care about neutrons?

• Neutrons in Radiation Therapy– Neutron Therapy

– Contamination Neutrons on X-Ray Therapy

– Contamination Neutrons in Proton Therapy

• The above will be discussed in lecture #2.

• Today’s focus will be general neutron interactions

• Neutrons in Radiation Therapy– Neutron Therapy

– Contamination Neutrons on X-Ray Therapy

– Contamination Neutrons in Proton Therapy

• The above will be discussed in lecture #2.

• Today’s focus will be general neutron interactions

• Unwanted patient dose

• Shielding Considerations

• Neutron Dose

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Outline – Neutron Interactions

Outline – Neutron Interactions

• General properties

• Neutron Reaction Cross Sections

• Neutron Interactions

• General properties

• Neutron Reaction Cross Sections

• Neutron Interactions

General PropertiesGeneral Properties

• Neutrons are Neutral– Can Not interact by coulomb forces

– Can travel through several cm of material without interacting.

• Neutrons interact with nucleus of absorbing material (do not interact with orbital electrons).

• Neutrons are Neutral– Can Not interact by coulomb forces

– Can travel through several cm of material without interacting.

• Neutrons interact with nucleus of absorbing material (do not interact with orbital electrons).

Reaction Cross SectionsReaction Cross Sections

• A neutron reaction cross section quantitatively describes the probability of a particular interaction occurring between a neutron and matter.

• A neutron reaction cross section quantitatively describes the probability of a particular interaction occurring between a neutron and matter.

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• When the reaction cross section is defined microscopically on a nucleus, it is denoted by and has S.I. Units = cm2

– Common unit for reaction neutron cross sections is the barn (10-24cm2).

• Reaction cross sections are BOTH energyand interaction type dependent.

• When the reaction cross section is defined microscopically on a nucleus, it is denoted by and has S.I. Units = cm2

– Common unit for reaction neutron cross sections is the barn (10-24cm2).

• Reaction cross sections are BOTH energyand interaction type dependent.


• Energy and interaction type dependent -tabulated as a function of energy and interaction type.

• Energy and interaction type dependent -tabulated as a function of energy and interaction type.


• Macroscopic cross section, probability per unit path length that a particular type of interaction will occur.

– = microscopic cross section, cm2

– N = number of nuclei per unit volume, nuclei/cm3

• Macroscopic cross section, probability per unit path length that a particular type of interaction will occur.

– = microscopic cross section, cm2

– N = number of nuclei per unit volume, nuclei/cm3

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• All processes can be combined to calculate total, probability per unit path length that any type of interaction will occur.

• All processes can be combined to calculate total, probability per unit path length that any type of interaction will occur.

Exponential AttenuationExponential Attenuation• Neutrons are removed

exponentially from a collimated neutron beam by absorbing material.

• Neutrons are removed exponentially from a collimated neutron beam by absorbing material.

Io I

whereN = number of absorber atoms

per cm3 (atomic density) = the microscopic cross

section for the absorber, cm2

t = the absorber thickness, cm

whereN = number of absorber atoms

per cm3 (atomic density) = the microscopic cross

section for the absorber, cm2

t = the absorber thickness, cm

Exponential AttenuationExample


• In an experiment designed to measure the total cross section of lead for 10 MeV neutrons, it was found that a 1 cm thick lead absorber attenuated the neutron flux to 84.5% of its initial value. – The atomic weight of lead is 207.21, and

its density is 11.3 g cm-3.

• Calculate the total cross section from these data.

• In an experiment designed to measure the total cross section of lead for 10 MeV neutrons, it was found that a 1 cm thick lead absorber attenuated the neutron flux to 84.5% of its initial value. – The atomic weight of lead is 207.21, and

its density is 11.3 g cm-3.

• Calculate the total cross section from these data.

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• Rearrange/Solve the general attenuation equation for :

• Rearrange/Solve the general attenuation equation for :

Calculate N, the atomic density of lead:

Neutron Mean Free Path, Neutron Mean Free Path,

• Slow (low-energy) neutrons– is on the order of 1cm or less

• For fast (high-energy) neutrons– may be tens of centimeters

• Slow (low-energy) neutrons– is on the order of 1cm or less

• For fast (high-energy) neutrons– may be tens of centimetersUnits: cm

Neutron Mean Free Path, Example

Neutron Mean Free Path, Example

• Calculate the mean free path for the previous example.

• Calculate the mean free path for the previous example.

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Some preliminary background

Some preliminary background

compound nucleus model and resonance

compound nucleus model and resonance

Compound Nucleus ModelMulti-step Reaction


• Incident neutron and target nucleus fuse together, then by successive nucleon-nucleon collisions within the combined system, the reaction energy becomes shared among many nucleons. A + a C

• Incident neutron and target nucleus fuse together, then by successive nucleon-nucleon collisions within the combined system, the reaction energy becomes shared among many nucleons. A + a C



• Eventually an equilibrium occurs and the compound nucleus exists in an excited state (10-16-10-18 sec). A + a C*

• Excitation is followed by de-excitation when a single nucleon or group of nucleons acquires enough energy to escape. A + a C B + b

• Eventually an equilibrium occurs and the compound nucleus exists in an excited state (10-16-10-18 sec). A + a C*

• Excitation is followed by de-excitation when a single nucleon or group of nucleons acquires enough energy to escape. A + a C B + b

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The energy and nature of outgoing particles is determined by properties of the excited compound nucleus and NOT by the properties of the colliding particles from which it was formed.

The energy and nature of outgoing particles is determined by properties of the excited compound nucleus and NOT by the properties of the colliding particles from which it was formed.

Compound Nucleus ModelCompound Nucleus Model

• Note: if the excitation energy is close to the threshold energy, the compound nucleus will decay by emitting only -rays or the competing decay mode of internal conversion of electrons.

– Recall: electron capture is a process that competes with -ray emission in which the energy of an excited nuclear state is transferred to an atomic electron (typically K or L).

• Note: if the excitation energy is close to the threshold energy, the compound nucleus will decay by emitting only -rays or the competing decay mode of internal conversion of electrons.

– Recall: electron capture is a process that competes with -ray emission in which the energy of an excited nuclear state is transferred to an atomic electron (typically K or L).

ResonanceResonance• In this example, at ≈ 250 keV, the neutron energy is such

that the compound nucleus 7Li is formed at an excitation which corresponds exactly to one of its higher states or natural frequencies.

• In this example, at ≈ 250 keV, the neutron energy is such that the compound nucleus 7Li is formed at an excitation which corresponds exactly to one of its higher states or natural frequencies.

Peak is due to “resonance” in initial fusion process of the neutron with 6Li target.

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ResonanceResonance• At higher energies x-section may have large

peaks.– Peaks = resonances

– Occur at neutron energies where reactions with nuclei are enhanced

• At higher energies x-section may have large peaks.– Peaks = resonances

– Occur at neutron energies where reactions with nuclei are enhanced

Rinard, Fig. 12.3

• A resonance will occur if the energy of the incident neutron is close to the energy of an excited state of the compound nucleus

Neutron Classifications and

Interactionsby energy

Neutron Classifications and

Interactionsby energy

Classification of Neutrons by Energy (NCRP-38)


1. Thermal neutrons are in thermal equilibrium with the medium they are in. The average energy of thermal neutrons is typically below 1eV, depending on temperature. The most probable velocity for thermal neutrons is 2200 meters per second at 20.44oC. This velocity corresponds to an energy of 0.0253eV.

1. Thermal neutrons are in thermal equilibrium with the medium they are in. The average energy of thermal neutrons is typically below 1eV, depending on temperature. The most probable velocity for thermal neutrons is 2200 meters per second at 20.44oC. This velocity corresponds to an energy of 0.0253eV.

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2. Intermediate Energy Neutrons are classified as having intermediate energy range from above 1eV to tens of keV.

3. Fast Neutrons are classified as having energies above the intermediate neutrons.

2. Intermediate Energy Neutrons are classified as having intermediate energy range from above 1eV to tens of keV.

3. Fast Neutrons are classified as having energies above the intermediate neutrons.

Classification of Neutrons by EnergyClassification of Neutrons by Energy

The classification of neutrons by energy is somewhat dependent on the reference text. Some sources may include an epithermal category while others only include fast and slow (thermal).

The classification of neutrons by energy is somewhat dependent on the reference text. Some sources may include an epithermal category while others only include fast and slow (thermal).

Category Energy Range

Fast > 500 keV

Intermediate 10 keV – 500 keV

Epithermal 0.5 eV – 10 keV

Thermal < 0.5 eV

Cd-cutoff energy: sharp drop occurs in Cdabsorption cross section at 0.5 eV

0.5 eV

Neutron Interactions are Energy DependentNeutron Interactions

are Energy Dependent

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Overview of Neutron Interactions Scatter and Absorption

Overview of Neutron Interactions Scatter and Absorption

To

a

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as

c

Sca

er

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n

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as

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Processes

n

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(n

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(n

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(n

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F

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(n

f)

Sometimes called

“radiative” capture

Sometimes called “transmutation”

Sometimes shown as (n,n)

Also called “neutron capture”

Boxes shaded in light blue follow the compound nucleus model.

Neutron ScatterNeutron Scatter

• When a neutron is elastically or inelastically scattered by the nucleus, the speed and direction change, but nucleus is left with same number of protons and neutrons as before the interaction.

–Elastic Scatter (n,n)–Inelastic Scatter (n,n’)

• When a neutron is elastically or inelastically scattered by the nucleus, the speed and direction change, but nucleus is left with same number of protons and neutrons as before the interaction.

–Elastic Scatter (n,n)–Inelastic Scatter (n,n’)

Neutron AbsorptionNeutron Absorption

• When neutron is absorbed by nucleus, a wide range of radiations can be emitted or fission can be induced.

• Different number of protons and/or neutrons from before the interaction.

• When neutron is absorbed by nucleus, a wide range of radiations can be emitted or fission can be induced.

• Different number of protons and/or neutrons from before the interaction.

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Neutron Interactions are Energy-Dependent

Neutron Interactions are Energy-Dependent

• Fast neutrons are most likely to undergo scatter interactions with atoms in their environment.– Elastic Scatter – dominate for lower energy

fast neutrons– Inelastic Scatter - above 1-Mev

• Lower-energy neutrons (thermal or near thermal) are likely to undergo absorption reactions with atoms in their environment.

• Fast neutrons are most likely to undergo scatter interactions with atoms in their environment.– Elastic Scatter – dominate for lower energy

fast neutrons– Inelastic Scatter - above 1-Mev

• Lower-energy neutrons (thermal or near thermal) are likely to undergo absorption reactions with atoms in their environment.

Neutron Scatter Neutron Scatter

• Elastic Scatter – kinetic energy conserved– More likely in low-Z materials– More likely at lower energies, < 1MeV– Maximum amount of energy that can

be lost is function of target nuclei mass.

– Larger cross sections

• Elastic Scatter – kinetic energy conserved– More likely in low-Z materials– More likely at lower energies, < 1MeV– Maximum amount of energy that can

be lost is function of target nuclei mass.

– Larger cross sections

Neutron Scatter Neutron Scatter

• Inelastic Scatter – kinetic energy not conserved.– More likely in high-Z materials– More likely at higher energies (E >

1MeV)– Can lose large amounts of energy in

one collision– Smaller cross sections– Threshold energy

• Inelastic Scatter – kinetic energy not conserved.– More likely in high-Z materials– More likely at higher energies (E >

1MeV)– Can lose large amounts of energy in

one collision– Smaller cross sections– Threshold energy

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Neutron Elastic Scatter (n,n)Neutron Elastic Scatter (n,n)

• Elastic scattering is the most likely interaction between (lower energy) fast neutrons and low-Z absorbers.

– Billiard ball type collision• Direct (head-on) collision – More energy transferred

• Indirect (grazing) collision – Less energy transferred

– Kinetic energy and momentum are conserved

– Light recoiling nucleus can cause high LET tracks

• Elastic scattering is the most likely interaction between (lower energy) fast neutrons and low-Z absorbers.

– Billiard ball type collision• Direct (head-on) collision – More energy transferred

• Indirect (grazing) collision – Less energy transferred

– Kinetic energy and momentum are conserved

– Light recoiling nucleus can cause high LET tracks

Kinematics of Neutron Elastic Scattering


• For incoming neutrons, conservation of energy and momentum in the center-of-mass coordinate system gives the following relation for energy of the recoil nucleus:

• For incoming neutrons, conservation of energy and momentum in the center-of-mass coordinate system gives the following relation for energy of the recoil nucleus:



• Convert to laboratory system (general target nucleus is at rest):

–Recoil nucleus energy in terms of its own angle of recoil.

• Convert to laboratory system (general target nucleus is at rest):

–Recoil nucleus energy in terms of its own angle of recoil.

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Definition of SymbolsDefinition of Symbols

• A= mass of target nucleus (laboratory system)

• En = incoming neutron kinetic energy (laboratory system)

• ER = recoil nucleus kinetic energy (laboratory system)

• scattering angle of the recoiled neutron in the center-of-mass coordinate system

• scattering angle of the recoiled nucleus in the lab coordinate system

• A= mass of target nucleus (laboratory system)

• En = incoming neutron kinetic energy (laboratory system)

• ER = recoil nucleus kinetic energy (laboratory system)

• scattering angle of the recoiled neutron in the center-of-mass coordinate system

• scattering angle of the recoiled nucleus in the lab coordinate system



• Equation demonstrates that energy given to recoil nucleus is determined by scattering angle:

• Equation demonstrates that energy given to recoil nucleus is determined by scattering angle:

• For grazing angle encounter, the neutron is only slightly deflected and the recoil target nucleus is emitted almost perpendicular to the incident neutron, ≈90.

• Energy of recoil nucleus :

• For grazing angle encounter, the neutron is only slightly deflected and the recoil target nucleus is emitted almost perpendicular to the incident neutron, ≈90.


Elastic ScatterGrazing Angle Encounter

Elastic ScatterGrazing Angle Encounter

0

• For a grazing hit almost no energy goes to recoil nucleus, regardless of mass of the target nuclei.

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• For head-on direct collision between an incoming neutron and a target nucleus, the recoil is emitted in almost the same direction as the incident neutron, ≈0.


• For head-on direct collision between an incoming neutron and a target nucleus, the recoil is emitted in almost the same direction as the incident neutron, ≈0.


Elastic ScatterDirect Head-On Encounter

Elastic ScatterDirect Head-On Encounter

1

• For a direct hit, energy that goes to recoil nucleus, depends on mass of the target nuclei.

Maximum Fractional Energy Transfer in Neutron Elastic

Scattering

Maximum Fractional Energy Transfer in Neutron Elastic

Scattering

Target Nucleus

1H 1

2H 8/9=0.889

3He 3/4=0.750

4He 16/25=0.640

12C 48/169=0.284

16O 64/289=0.221

For direct head-on collisions:

• The maximum fractional energy transfer increases as the mass of target nuclei decreases:

• Nuclei with lower mass are more effective on a “per collision” basis for slowing down neutrons!

Energy Distribution of Recoil Nuclei (from Elastic Neutron

Scatter)

Energy Distribution of Recoil Nuclei (from Elastic Neutron

Scatter)• All scattering angles are allowed.

– However, for most target nuclei, forward and backward scattering are somewhat favored.

• Actual energy distribution for recoil nuclei is a continuum between the two extremes.

• All scattering angles are allowed. – However, for most target nuclei, forward

and backward scattering are somewhat favored.

• Actual energy distribution for recoil nuclei is a continuum between the two extremes.

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Neutron Inelastic Scatter (n,n’ or (n,n)


• Inelastic Scatter - neutron is captured by target nucleus and is reemitted (may not be same neutron) along with -ray.



Inelastic scatter follows the compound nucleus model:

1.Neutron collides with nucleus and fuse together to form a combined system.

2.By successive nucleon-nucleon collisions within the combined system, the reaction energy becomes shared among many nucleons.



Inelastic scatter follows the compound nucleus model:

3. Eventually an equilibrium occurs and the compound nucleus exists in an excited state.

4. Excitation energy is emitted as gamma photon, can have substantial energy.

5. Neutron (not necessarily the incoming neutron) is emitted.

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Neutron Inelastic ScatterNeutron Inelastic Scatter

• Inelastic Scatter - threshold phenomenon– Infinite threshold for H (inelastic

can not occur)

– 6 MeV threshold for O

– 1 MeV threshold for U

• Inelastic Scatter - threshold phenomenon– Infinite threshold for H (inelastic

can not occur)

– 6 MeV threshold for O

– 1 MeV threshold for U

Neutron Inelastic ScatterNeutron Inelastic Scatter

• Cross section increases with increasing energy.– ≤1 barn for low-energy neutrons.

– approaches physical cross-section of target nucleus at high energies

– inelastic scatter is dominant interaction mechanism at higher energies.

• Cross section increases with increasing energy.– ≤1 barn for low-energy neutrons.

– approaches physical cross-section of target nucleus at high energies

– inelastic scatter is dominant interaction mechanism at higher energies.

Non-elastic ProcessesNon-elastic Processes

• Similar to inelastic scatter in that the process follows a compound nucleus model and that there is a recoil neutron.

• Different from inelastic scatter because instead of emitting -rays, additional secondary particles can be emitted (in addition to scattered neutron).

• Similar to inelastic scatter in that the process follows a compound nucleus model and that there is a recoil neutron.

• Different from inelastic scatter because instead of emitting -rays, additional secondary particles can be emitted (in addition to scattered neutron).

(n,n’3α)

(n,n’4α)

(n,n’etc)

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Non-elastic ProcessesNon-elastic Processes

• Nucleus has different number of p+ and no after interaction.

• Different from absorption because neutron is not absorbed, a scattered neutron is emitted (may not be the same one that entered reaction).

• Sometimes called non-elastic scatter.

• Nucleus has different number of p+ and no after interaction.

• Different from absorption because neutron is not absorbed, a scattered neutron is emitted (may not be the same one that entered reaction).

• Sometimes called non-elastic scatter.

(n,n’3α)

(n,n’4α)

(n,n’etc)

Non-elastic vs InelasticNon-elastic vs Inelastic

• Both non-elastic and inelastic scatter follow a compound nucleus model.

• Whether the compound nucleus will de-excite via non-elastic or inelastic scatter is determined by the energy of the incident neutron

• Both non-elastic and inelastic scatter follow a compound nucleus model.

• Whether the compound nucleus will de-excite via non-elastic or inelastic scatter is determined by the energy of the incident neutron

Non-elastic vs InelasticNon-elastic vs Inelastic

• If the energy of the incident neutron is very close to the threshold energy, de-excitation occurs by emission of gamma rays rather than by additional particle emissions i.e. inelastic scatter is favored over non-elastic scatter.

• If the energy of the incident neutron is very close to the threshold energy, de-excitation occurs by emission of gamma rays rather than by additional particle emissions i.e. inelastic scatter is favored over non-elastic scatter.

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Absorption (Neutron Capture)Absorption (Neutron Capture)

• Low-energy neutrons (thermal or near thermal) are likely to undergo absorption reactions.

• In this energy range, the absorption cross-section of many nuclei, has been found to be inversely proportional to the square root of the energy of the neutron.

– one-over-v law for slow neutron absorption

• Low-energy neutrons (thermal or near thermal) are likely to undergo absorption reactions.

• In this energy range, the absorption cross-section of many nuclei, has been found to be inversely proportional to the square root of the energy of the neutron.

– one-over-v law for slow neutron absorption

Thermal Neutron AbsorptionThermal Neutron Absorption

Cember fig 5.23

Thermal Neutron Absorption Cross Sections


Isotope AbundanceIsotope

ProducedHalf-life

Cross section

[barn atom-1]23Na 100% 24Na 15 h 0.93

31P 100% 32P 14.3 d 0.18

41K 6.9% 42K 12.4 h 1.46

58Fe 0.33% 59Fe 45.1 d 1.15

59Co 100% 60Co 5.26 y 37

197Au 100% 198Au 2.69 d 99

10B 19.8% 7Li Stable 3837

B (all isotopes)

759

113Cd 12.3% 114Cd Stable 20000

Cd (all isotopes)

2450

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• Thermal neutron cross sections are given for neutrons whose energy is 0.025eV.

• If the cross section at E0 is 0, then the cross section for any other neutron (within the validity of the 1/v law is given by:

• Thermal neutron cross sections are given for neutrons whose energy is 0.025eV.

• If the cross section at E0 is 0, then the cross section for any other neutron (within the validity of the 1/v law is given by:

Neutron ActivationNeutron Activation

• Neutron activation is the production of a radioactive isotope by absorption of a neutron.

• Activation reactions follow absorption reactions.

Examples:

– 14N(n,p)14C

– 10B(n,)7Li

– 113Cd(n,)114C

• Neutron activation is the production of a radioactive isotope by absorption of a neutron.

• Activation reactions follow absorption reactions.

Examples:

– 14N(n,p)14C

– 10B(n,)7Li

– 113Cd(n,)114C

ActivationGood and Bad

ActivationGood and Bad

• Detection class: We will discuss neutron detection via activation foils.

• Byproducts of activation can have substantial energy:

– Good: These byproducts can be measured. This technique is one of the methods most frequently used for neutron detection.

– Bad: These byproducts can pose a radiation hazard.

• Byproducts of activation can have substantial energy:

– Good: These byproducts can be measured. This technique is one of the methods most frequently used for neutron detection.

– Bad: These byproducts can pose a radiation hazard.

• Must be considered in neutron shielding design.

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Neutron Interactions with Tissue


• The type of interaction and the amount of dose deposited in the body is strongly dependent on neutron energy and absorbing material. – The most common elements in the

human body are Hydrogen, Carbon, Nitrogen, and Oxygen.

• The type of interaction and the amount of dose deposited in the body is strongly dependent on neutron energy and absorbing material. – The most common elements in the

human body are Hydrogen, Carbon, Nitrogen, and Oxygen.



• Neutrons are indirectly ionizing and but give rise to densely ionizing (high-LET) particles: recoil protons, particles, and heavier nuclear fragments– These particles then deposit dose in

tissue.

• Neutrons are indirectly ionizing and but give rise to densely ionizing (high-LET) particles: recoil protons, particles, and heavier nuclear fragments– These particles then deposit dose in

tissue.

Fast Neutron Interactions in Tissue


• Higher energy neutrons interact with carbon and oxygen via non-elastic processes and result in the release of charged particles, (n,n’3α) and (n,n’4α).

• These particles then deliver dose to tissue

• Higher energy neutrons interact with carbon and oxygen via non-elastic processes and result in the release of charged particles, (n,n’3α) and (n,n’4α).

• These particles then deliver dose to tissue

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• Recoil -particles• Recoil -particles

A neutron interacts with a carbon nucleus (6 protons and 6 neutrons), resulting in three -particles. (Hall, Fig 1.10)

A neutron interacts with an oxygen nucleus (8 protons and 8 neutrons) , resulting in four -particles. (Hall, Fig 1.10)

Intermediate Neutron Interactions in Tissue

Intermediate Neutron Interactions in Tissue

• Intermediate energy neutrons primarily interact with hydrogen nuclei via elastic scatter.

• Dominant mechanism of energy transfer in soft tissues

• Intermediate energy neutrons primarily interact with hydrogen nuclei via elastic scatter.

• Dominant mechanism of energy transfer in soft tissues

Hydrogen is the most abundant atom in tissue.

A proton and a neutron have similar mass, 938 MeV/cm2

versus 940 MeV/cm2.

Hydrogen has a large elastic scatter cross-section for neutrons.

3 Reasons

Thermal Neutron Interactions in Tissue


• Absorption is the dominant interaction mechanism for thermal neutrons in tissue.

• Absorption is followed by activation.

• Activation decay products deliver dose to tissue.

• Absorption is the dominant interaction mechanism for thermal neutrons in tissue.

• Absorption is followed by activation.

• Activation decay products deliver dose to tissue.

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• The major component of dose from thermal neutrons is a consequence of the 14N(n,p)14C + 0.62 MeV– 0.04 MeV to recoil nucleus (local

absorption)– 0.58 MeV to proton (range of ~10-6 m

local absorption)– Dominant energy transfer mechanism in

thermal and epithermal region in body– Kerma = dose

• The major component of dose from thermal neutrons is a consequence of the 14N(n,p)14C + 0.62 MeV– 0.04 MeV to recoil nucleus (local

absorption)– 0.58 MeV to proton (range of ~10-6 m

local absorption)– Dominant energy transfer mechanism in

thermal and epithermal region in body– Kerma = dose



• Another thermal neutron interaction of some consequence is the 1H(n,)2H + 2.2 MeV– 2.2 MeV to gamma (nonlocal absorption)– Small amount of energy to deuterium

recoil (local absorption)– Kerma dose (non-local absorption)

• Another thermal neutron interaction of some consequence is the 1H(n,)2H + 2.2 MeV– 2.2 MeV to gamma (nonlocal absorption)– Small amount of energy to deuterium

recoil (local absorption)– Kerma dose (non-local absorption)

Summary: Neutron Interactions with Tissue

Summary: Neutron Interactions with Tissue

The amount of dose deposited in the body is strongly dependent on neutron energy.

– Fast neutrons: Interact with carbon and oxygen via non-elastic processes and result in the release of charged -particles, (n,n’3) and (n,n’4). These -particles then deposit dose to tissue.

– Intermediate energy neutrons: Interact with hydrogen nuclei via elastic scatter. The recoil proton then deposits dose in tissue.

– Thermal neutrons: Interact via absorption followed by activation. The major component of dose from thermal neutrons is a consequence of the 14N(n,p)14C which results in a 0.58 MeV proton.

The amount of dose deposited in the body is strongly dependent on neutron energy.

– Fast neutrons: Interact with carbon and oxygen via non-elastic processes and result in the release of charged -particles, (n,n’3) and (n,n’4). These -particles then deposit dose to tissue.

– Intermediate energy neutrons: Interact with hydrogen nuclei via elastic scatter. The recoil proton then deposits dose in tissue.

– Thermal neutrons: Interact via absorption followed by activation. The major component of dose from thermal neutrons is a consequence of the 14N(n,p)14C which results in a 0.58 MeV proton.

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Neutron Interactions – Part I · Neutron Interactions – Part I ... • Eric J. Hall. Radiobiology for the ... • Calculate the mean free path for the previous example. 6