Neutron interactions and dosimetry. Eirik Malinen Einar Waldeland

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1 Neutron interactions and dosimetry Eirik Malinen Einar Waldeland

2 Topics 1. Neutron interactions 1. Scattering 2. Absorption 2. Neutron dosimetry 3. Applications

3 The neutron Uncharged particle, mass close to that of proton Unstable as free particle; disintegrates into a proton, an electron and an antineutrino (t 1/2 =12 min) Do not interact with electrons Only nuclear interactions; complex cross sections Neutron attenuation similar to that for photons

4 Neutron reactions (n,n) (n,n ) (n,p) (n,α) (n,f) X + n b + Y Elastic scattering Inelastic scattering Absorption Absorption Fission Thermalization of neutrons: Collisions with nuclear targets until equilibrium

5

6 Neutron interactions Principally two types of interaction with matter: 1. Scattering: Elastic Inelastic 2. Absorption: creation of compound nucleus, deexcitation yields p, α, fission products

7 Interactions

8 Interactions Cross section depends on: - Kinetic energy T n - Nuclear structure Names on neutrons Thermal Thermal neutrons Low Low energetic energy neutrons High High energetic energy neutrons Slow Intermediate Fast Low energy neutrons Very fast Ultra fast 0.01eV 0.1eV 1eV 10eV 100eV 1keV 10keV 100keV 1MeV 10MeV 100MeV Interaction Kinetic energy, T n Fission possible Capture important > 1 particle can be emitted Elastic scattering dominating, Charged particles can be emitted Elastic scattering important at all energies Inelastic scattering possible and important

9 Neutron moderation 1 Elastic scattering against nucleus energy of neutron after scattering: E m n, v max = 1 2 ( m m n A n A )v A = 4 ( A + 1) 2 2 2,max Hydrogen rich absorbers most effective T m n A, v 2 = 4 ( m v 1 n χ 2 Amn + Am n θ ) 2 T 0

10 It may be shown that, after n interactions, the average neutron energy is: Neutron moderation = + + = n n n 1) A ( 1 A ln T T ln n 1) A ( 1 A T T

11 Low energies, T n < 500 kev Potential (1) and resonance (2) elastic scattering: 1: Scattering on the nuclear surface 2: Neutron absorbed, but reemitted For (1): virtually constant cross section At thermal energies, the neutron is captured and the compound nucleus deexcites via e.g. γ emission cross section ~ 1/v n

12 Elastic scattering Potential elastic scattering Discontinuities in neutron s potential energy curves due to the nuclear surface interaction (considered as reflections) Resonance scattering Parts of the incident wave passing through the nuclear surface, resonance scattering occurs with large prob. only for specific wave-lengths

13 Cross section 27 Al Inelastic scattering Capture Elastic scattering

14

15 1/v cross section 10 B

16 Thermal neutrons For neutrons in thermal equilibrium with surroundings: T n =kt=0.025 ev at T=293 K (k: Boltzman constant) 235 U has a high cross section for capture of thermal neutrons gives fission

17 Fission

18 High energy neutrons, T n > 0.5 MeV Inelastic: (n, nγ), threshold kinetic energy ~ 0.5 MeV Occurs at given energies: resonances Capture reacions: (n, p), (n, α) Emission of more than one particle: (n, np), (n, nα) (threshold ~ 10 MeV) Complicated cross sections

19 Absorption (n,γ) (n,b) (n,α) (n,f) X + n b + Y The Q-value Q gs = ΔE X + ΔE n ΔE b -ΔE Y Signifies if a reaction relases or needs energy

20 Neutron absorption (particle emission) X+n C b+y Absorption b= p, n, d, α, 2n, 2p, np Radiative capture X+n Y* Y+γ

21

22 Neutron attenuation For a narrow neutron beam: N = N e µ 0 x µ is the attenuation coefficient: N µ = ρ A σ A Note: the cross section s may show extreme variations over small energy range If Q positive: (µ tr /ρ)> (µ/ρ) If Q negative: (µ tr /ρ)< (µ/ρ)

23 σ~1/v (µ/ρ) tot = (µ/ρ) nγ + (µ/ρ) es + (µ/ρ) nb

24 Theoretical dosimetry KERMA factor F n : K n =ΦF n = ΦE n (μ tr /ρ) tot At CPE: D=K n = ΦF n

25

26 Important interactions in tissue 14 N(n,p) 13 C σ N : 1.84 x cm 2 /atom 1 H(n,γ) 2 H σ H : 3.32 x cm 2 /atom N H ~ 41 N N in tissue

27

28 γ+n mixed-field dosimetry (n,γ) always important (γ,n) important for energy ( 10 MeV) Three categories of dosimeters Neutron dosimeters (insensitive to γ-rays) γ-ray dosimeters (insensitive to neutrons) n+ γdosimeters (comparable sensitive to n and γ)

29 Paired dosimeters Q n, γ = AD γ + BD n EX: Tissue Equivalent (TE) ion chamber and TLD

30 Neutron detectors High cross section for the desired reaction High abundance of target nuclide Principle: (n, α) or (n,p) reaction Fission reaction

31 BF 3 counter Ion chamber with BF 3 gas 10 B+n 7 Li+ α MeV (6%) 10 B+n 7m Li+ α MeV (94%) 7m Li+γ MeV

32 Boron cross section

33 Monte Carlo simulations

34 Neutron sources Nuclear fission reactors Neutron energies ~ 2 MeV Accelerators Protons on a thick Be target etc. Radioactive sources Be(α,n) Pu, 241 Am, 226 Ra, 210 Po

35 Radioactive sources (α,n) reaction 241 AmBe: 9 Be+ 4 He 12 C+n+5.7 MeV T ½ ( 241 Am)=460 y 226 RaBe T ½ ( 226 Ra)=1600 y 239 PuBe T ½ ( 239 Pu)=24000 y

36 Neutron sources: AmBe

37 Neutron generators: Accelerators Advantage Can be turned off One single energy Production in two stages Acceleration Neutron producing reaction Some common reaction: T(d,n) 4 He, Q=17.6 MeV E n =14 MeV D(d,n) 3 He, Q=3.3 MeV E n = 2.5 MeV 7 Li(d,n) 8 Be, Q=15 MeV 9 Be(d,n) 10 B, Q=4.4 MeV E n >100 MeV Spallation

38 Nuclear reactors Power reactors and research reactors Neutron flux is very high (10 15 n/cm 2 s) Energy spectrum 1-7 MeV Fission by thermal neutron Fissionfast neutrons Slowing down fission by thermal neutrons Research reactors: Neutrons can be extracted for research

39 Boron neutron capture therapy Thermal neutrons are effeciently captured by 10 B Result is an unstable nucleus which desintegrates 7 Li og 4 He (+ kinetic energy and a photon) May be used for therapy: 4 He 1 n Li B

40 Neutron radiography vs. X-ray Neutron radiography X-ray

41 Dose equivalent

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