1. Neutron Interactions Part I Rebecca M. Howell, Ph.D. Radiation Physics rhowell@mdanderson.org B1.4580 November 2010

2. 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 Unwanted patient dose Shielding Considerations Neutron Dose

3. Outline – Neutron Interactions General properties Neutron Reaction Cross Sections Neutron Interactions

4. General 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 (no not interact with orbital electrons).

5. Reaction Cross Sections Used to describe neutron interaction probabilities.

6. Reaction Cross Sections A neutron reaction cross section quantitatively describes the probability of a particular interaction occurring between a neutron and matter. When the reaction cross section is defined microscopicly on per nucleus, it is denoted by  and has S.I. Units = cm 2 Common unit for reaction neutron cross sections is the barn (10 -24 cm 2 ). Reaction cross sections are BOTH energy and interaction type dependent.

7. Reaction Cross Sections Energy and interaction type dependent - tabulated as a function of energy and interaction type.

8. Reaction Cross Sections Macroscopic cross section,   probability per unit path length that a particular type of interaction will occur.  = microscopic cross section, cm 2 N = number of nuclei per unit volume, nuclei/cm 3 All processes can be combined to calculate  total, probability per unit path length that any type of interaction will occur.

9. Exponential Attenuation Neutrons are removed exponentially from a collimated neutron beam by absorbing material. IoIo I where N = number of absorber atoms per cm 3 (atomic density)  = the microscopic cross section for the absorber, cm 2 t = the absorber thickness, cm

10. Exponential Attenuation Example 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.

11. Exponential Attenuation Example Rearrange/Solve the general attenuation equation for  : Calculate N, the atomic density of lead:

12. 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 Units: cm

13. Neutron Mean Free Path, Example Calculate the mean free path for the previous example.

14. Some preliminary background compound nucleus model and resonance

15. Compound Nucleus Model Multi-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 Eventually an equilibrium occurs and the compound nucleus exists in an excited state (10 -16 -10 -18 seconds ). A + a  C* Excitation is followed by deexcitation when a single nucleon or group of nucleons acquires enough energy to escape. A + a  C  B + b

16. Compound Nucleus Model Multi-step Reaction 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.

17. Compound 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).

18. Resonance In this example, at ≈ 250 keV, the neutron energy is such that the compound nucleus 7 Li 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 6 Li target.

19. Resonance 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

20. Neutron Classifications and Interactions by energy

21. Classification of Neutrons by Energy There are three energy categories of neutrons (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 20.44 o C. This velocity corresponds to an energy of 0.0253eV. 2.Intermediate Energy Neutrons are classified as having intermediate energy range from above 1eV to tens of keV. 1.Fast Neutrons are classified as having energies above the intermediate neutrons.

22. Classification 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). CategoryEnergy Range Fast> 500 keV Intermediate10 keV – 500 keV Epithermal0.5 eV – 10 keV Thermal< 0.5 eV Cd-cutoff energy: sharp drop occurs in Cd absorption cross section at 0.5 eV 0.5 eV

23. Neutron Interactions are Energy Dependent

24. Overview of Neutron Interactions Scatter and Absorption 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.

25. General Neutron Interactions Scattering and Absorption Scatter When neutron is elastically or inelastically scattered by nucleus 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’) Absorption When neutron is absorbed by nucleus, a wide range of radiations can be emitted or fission can be induced. Different the number of protons and/or neutrons than before the interaction. Neutral (n,2n) (n,3n) (n,4n) (n,etc) Fission (n,f) Electromagnetic (n,  ) Charged (n,p) (n,  ) (n,d) (n,etc)

26. 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.

27. 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 Inelastic Scatter – Kinetic Energy NOT Conserved. More likely in high Z materials More likely at higher energies E > 1MeV Can loose large amounts of energy in one collision Smaller cross sections Threshold Energy

28. 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

29. 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: Convert to laboratory system (general target nucleus is at rest): Recoil nucleus energy in terms of its own angle of recoil. Note: assume incoming neutrons have nonrelativistic kinetic energy (E n <939MeV), Knoll fig 15-12

30. Definition of Symbols A= mass of target nucleus (laboratory system) E n = incoming neutron kinetic energy (laboratory system) E R = recoil nucleus kinetic energy (laboratory system)  scattering angle of the recoiled neutron in the center-of- mass coordinate system  scattering angle of the recoiled neutron in the lab coordinate system

31. Kinematics of Neutron Elastic Scattering Equation demonstrates that energy given to recoil nucleus is determined by scattering angle:

32. 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 : Elastic Scatter Grazing Angle Encounter 0 For a grazing hit almost no energy goes to recoil nucleus, regardless of mass of the target nuclei.

33. 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. Energy of recoil nucleus : Elastic Scatter Direct Head-On Encounter 1 For a direct hit, energy that goes to recoil nucleus, depends on mass of the target nuclei.

34. Maximum Fractional Energy Transfer in Neutron Elastic Scattering Target Nucleus 1H1H1 2H2H8/9=0.889 3 He3/4=0.750 4 He16/25=0.640 12 C48/169=0.284 16 O64/289=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!

35. 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.

36. Neutron Inelastic Scatter (n,n’ or (n,n  ) 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 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. Inelastic Scatter - neutron is captured by target nucleus and is reemitted (may not be same neutron) along with  -ray.

37. Neutron Inelastic Scatter Inelastic Scatter = Threshold Phenomenon Infinite threshold for H (inelastic can not occur) 6 MeV Threshold for O 1 MeV Threshold for Ur Cross section increases with increasing energy.  ≤1 barn for low Energy neutrons.  approaches geometric cross-section of target nucleus at high energies i.e. inelastic scatter is dominate interaction mechanism at higher energies.

38. General Neutron Interactions Nonelastic Processes Nonelastic 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). Nucleus has different number of p+ and n o 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 nonelastic scatter. (n,n’3a) (n,n’4a) (n,n’etc)

39. Nonelastic verses 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….. 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.

40. 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

41. Thermal Neutron Absorption Cember fig 5.23

42. Thermal Neutron Absorption Cross Sections IsotopeAbundance Isotope Produced Half- life Cross section [barn atom -1 ] 23 Na100% 24 Na15 h0.93 31 P100% 32 P14.3 d0.18 41 K6.9% 42 K12.4 h1.46 58 Fe0.33% 59 Fe45.1 d1.15 59 Co100% 60 Co5.26 y37 197 Au100% 198 Au2.69 d99 10 B19.8% 7 LiStable3837 B (all isotopes) 759 113 Cd12.3% 114 CdStable20000 Cd (all isotopes) 2450 Thermal neutron cross sections are given for neutrons whose energy is 0.025eV. If the cross section at E 0 is  0, then the cross section for any other neutron (within the validity of the 1/v law is given by:

43. Neutron Activation Neutron activation is the production of a radioactive isotope by absorption of a neutron. Activation reactions follow absorption reactions. Examples: 14 N(n,p) 14 C 10 B(n,  ) 7 Li 113 Cd(n,  ) 114 C

44. Activation Good 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. Must be considered in neutron shielding design.

45. Neutron Interactions in Tissue “Most Common”

46. 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. 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.

47. Fast Neutron Interactions in Tissue Higher energy neutrons interact with carbon and oxygen via nonelastic processes and result in the release of charged  -particles, (n,n’3a) and (n,n’4a). These  -particles then deliver dose to tissue

48. Fast Neutron Interactions in Tissue 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)

49. Intermediate Neutron Interactions in Tissue Intermediate energy neutrons primarily interact with hydrogen nuclei via elastic scatter. Dominant mechanism of energy transfer in soft tissues 1.Hydrogen is the most abundant atom in tissue. 2.A proton and a neutron have similar mass, 938 MeV/cm 2 versus 940 MeV/cm 2. 3.Hydrogen has a large elastic scatter cross-section for neutrons. 3 Reasons

50. 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.

51. Thermal Neutron Interactions in Tissue The major component of dose from thermal neutrons is a consequence of the 14 N(n,p) 14 C + 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 1 H(n,  ) 2 H + 2.2 MeV 2.2 MeV to gamma (nonlocal absorption) Small amount of energy to deuterium recoil (local absorption) Kerma  dose (non-local absorption)

52. Summery 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 nonelastic processes and result in the release of charged  -particles, (n,n’3  ) and (n,n’4  ). These  -particles then deposits dose to tissue. Intermediate energy neutrons primarily interact with hydrogen nuclei via elastic scatter. The recoil proton then deposits dose in tissue. Absorption is the dominant interaction mechanism for thermal neutrons in tissue and is followed by activation. The major component of dose from thermal neutrons is a consequence of the 14 N(n,p) 14 C which results in a 0.58 MeV proton.

53. References/Acknowledgements Glenn Knoll. Radiation Detection and Measurement, 4th Ed. (2010) Herman Cember. Introduction to Health Physics 3 rd Ed. (1996) Eric J. Hall. Radiobiology for the Radiologist 5 th Ed. (2000) Frank H. Attix. Introduction to Radiological Physics and Radiation Dosimetry. (1986)