Low Energy Fusion as a Source of Neutrons

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Presentation transcript:

Low Energy Fusion as a Source of Neutrons IIAA International Institute for Accelerator Applications Low Energy Fusion as a Source of Neutrons Simon Albright and Rebecca Seviour

Neutron Applications Neutron Therapy Isotope Production Security

Boron Neutron Capture Therapy Tumor 7Li 10B α 0 1 𝑛+ 5 10 𝐵→ 3 7 𝐿𝑖+ 2 4 𝐻𝑒

Medical Isotopes SPECT PET 11C 13N 15O 18F 64Cu 82Rb 67Ga 99Tc 111In 133Xe 201Tl

99mTc/ 99Mo Production neutron induced proton induced 0 1 𝑛+ 42 98 𝑀𝑜→ 42 99 𝑀𝑜+ γ 98Mo(n,γ)99Mo 0 1 𝑛+ 92 235 𝑈→ 42 99 𝑀𝑜+ 50 𝑋 𝑆𝑛 +𝑌 0 1 𝑛 235U(n,fis)99Mo proton induced 1 1 𝑝+ 42 100 𝑀𝑜→ 42 99 𝑀𝑜+ 1 1 𝑝 + 0 1 𝑛 100Mo(p,pn)99Tc* 1 1 𝑝+ 42 100 𝑀𝑜→ 43 99𝑚 𝑇𝑐+2 0 1 𝑛 100Mo(p,2n)99Tc* 1 1 𝑝+ 42 98 𝑀𝑜→ 43 99𝑚 𝑇𝑐+ γ 98Mo(p, γ)99Tc*

Security

Neutron in/Neutron out Neutron in/Gamma out Neutron+Photon Transmission Neutron Transmission Neutron Capture Neutron Scattering Fast Neutron Scattering

Pulsed Fast Neutron Analysis Minimum activation Characteristic gammas Time-Of-Flight 0 1 𝑛+ 𝑍 𝐴 𝑋→ 𝑍 𝐴 𝑋+ 0 1 𝑛+ γ

Simulated Gamma Spectra

Benign and Contraband Items Cellulose Latex Nylon Surfactant Cocaine Heroin RDX TNT O 5 2 3 4 6 N 1 C 18 17 21 7

PFNA System Accelerator

Rapiscan Trial System

Neutron Sources Spallation Fission Fusion

Fission Reactors Expensive Proliferation Decay Products

Fission Sources Uncontrolled Decay Products Proliferation

Spallation ~600m ~500m ESS Beamline St. Luke’s Hospital Huddersfield

Producing/using tritium Low Energy Fusion VNIIA ING-17 1 2 𝐷+ 1 3 𝐻→ 2 4 𝐻𝑒+ 0 1 𝑛 Producing/using tritium 𝒕 𝟏 𝟐 =𝟏𝟐.𝟑 𝒚𝒆𝒂𝒓𝒔 1 2 𝐷+ 1 2 𝐻→ 2 3 𝐻𝑒+ 0 1 𝑛 → 1 3 𝐻+ 1 1 𝑝

Simulations T Nn En Ep

GEANT4 Verification

MCNPX Verification

7Li(p,n) Spectrum

7Li(p,n) Angular Distribution

7Li(p,n) neutron source 7Li(n,t) breed tritium Alternative Target 7Li(p,n) neutron source 7Li(n,t) breed tritium Ideal target will have: Large (p,n)/(d,n) cross section No long lived by-products Monochromatic Spectrum

Cross Section Verification 3H(p,n): H. Liskein, A. Paulsen Neutron production cross sections and energies for the reactions T(P,N)3He, D(d,n)3He, and T(d,n)4He Experimental Simulation 7Li(p,n): S.N.Abramovich, B.Ja.Guzhovskij, V.A.Zherebcov, A.G.Zvenigorodskij Estimated values of total and differential cross sections of proton interactions with nuclei Li-6 and Li-7. 11B(p,n): G.J.F. Legge,I.F. Bubb 12C level structure in the excitation region 20.5-26.5 MeV

ENDF needed for low energy/low mass interactions TENDL Libraries ENDF needed for low energy/low mass interactions Experimental Simulation

Thin Target Spectra

Thin Target Spectra

Constant Beam Energy

Constant Beam Energy

Conclusion Compact Neutron Source: Neutron Therapy Isotope Production Security Need ENDF for verification Comparison of simulation and experiment