Adelphi technology inc. Experiments and simulations using a high flux DD neutron generator 1 J. H. Vainionpaa 1, A. X. Chen 1, M. A. Piestrup 1, C. K.

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Presentation transcript:

Adelphi technology inc. Experiments and simulations using a high flux DD neutron generator 1 J. H. Vainionpaa 1, A. X. Chen 1, M. A. Piestrup 1, C. K. Gary 1, G. Jones 2, R. H. Pantell 3, S. Custodero 4 1)Adelphi technology, 2003 E. Bayshore Rd , Redwood City, CA, USA 2)G&J Enterprice, 7486 Brighton Ct, Dublin CA 94568, United States 3)Department of Electrical Engineering, Stanford University, Stanford CA, United States 4)EUROSEA Committee, c/o Envipark S.p.A. via Livorno 60 I Turin, Italy

Adelphi technology inc. Adelphi Technology, Inc. 2 Radial Design Neutron Generator Moderator Shielding Reflector Neutron Generators Fast neutron sources pointed inwardly toward moderator and patient

Adelphi technology inc. Adelphi Technology, Inc. 3 Therapeutic Ratio: Radial vs. Single Beam Source

Adelphi technology inc. DD110MB

Adelphi technology inc. DD110MB

Adelphi technology inc. DD110MB features 4x Over-dense off resonance ECR ion source High D + 1 fraction High current density mA/cm kV, 70-95mA Deuterium beam 4x flat neutron production faces around central sample and moderator cavity Sample and moderator next to target Power consumption ~15kW Neutron flux at sample expected to reach 5-7e7 n/(s-cm 2 ) Modification to reflector and moderator materials/geometries easy to do Prize tag k$ Useful for small animal testing 6-12month lead time Multi-head dose uniform over large volumes compared to single source setups

Adelphi technology inc. Four ion beams with central moderator

Adelphi technology inc. Moderator thickness for various materials Assumes total Yield is n/s

Adelphi technology inc. DD110MB MCNP simulations

Adelphi technology inc. Neutron Spectrum Epithermal moderator Current moderator

Adelphi technology inc. DD110MB MCNP simulations MCNP estimated thermal neutron flux is 6.7x10 7 n/(s-cm 2 ) Reflector materialFlux sample Steel6.7x10 7 Graphite6.8x10 7 Ni7.0x10 7 HDPE6.2x10 7 Be7.3x10 7 Sample hole filled HDPE 8.1x10 7 Isotropic neutron flux 5.7x10 7

Adelphi technology inc. DD110MB Activation experiment Estimated thermal (<0.5eV) flux from Au activation 2.7e7 n/(cm 2 -s) Gold foil experiment By comparing the activation against known Cf source the estimated yield is ~5e7 n/(cm 2 -s) Salt experiment

Adelphi technology inc. Future developments generators High yield single beam systems Partners with strong medical background