Download presentation
Presentation is loading. Please wait.
Published byLindsey Chastity Perkins Modified over 8 years ago
1
Ali Ahmad FLUKA code validation of nuclear data required for the spallation target design in Accelerator Driven Subcritical Reactors ThorEA Meeting – Daresbury 24 th November 2009
2
FLUKA High energy physics and engineering Monte Carlo code Different hadronic models for different energy intervals and different interactions Hadron-Nucleus: Glauber-Gribov cascade PEANUT
3
Hadronic Models FLUKA PEANUT model GINC -Hadron-Nucleus interaction - Exact energy/momentum conservation - Stopping criterion: Time Geant4 More than one model Bertini INC Binary cascade -Hadron-Hadron interaction - Not exact energy/momentm conservation - Stopping criterion : Energy
4
PEANUT Sophisticated GINC 16 radial nuclear zones Curved nuclear potential Exact energy & momentum conservation Quantum effects included Fermi gas model adopted
5
FLUKA de-excitation model Pre-equilibrium De-excitation Evaporation Fission Fermi break-up Gamma de-excitation Geant4 de-excitation model is quite similar to that of FLUKA
6
What has been done with FLUKA?? Neutron double differential cross section measurement Neutron yield calculation Residual fragments production Neutrons, protons spatial distribution Energy deposition
7
Double differential cross section Target: solid Pb-208 Thickness: 1 cm Beam: Protons Energy: 1 GeV Primaries: 100 million
8
Double differential cross section: USRYIELD vs USRBDX USRYIELD Fully dedicated card for cross section measurements Can be used for both, extended and point targets cross sections are measured with respect to a fixed axis (beam axis) USRBDX Detector card that measures surface crossing current Cross sections measured using neutron counting method Fluence is measured with respect to the surface normal axis
9
Double differential cross section: Neutron counting method For a thin target bombarded by high energy protons Assuming the number of detected neutrons is equal to that of protons caused the spallation reaction Apply natural logarithm
10
Double differential cross section: USRYIELD vs USRBDX (cont)
11
Double differential cross section: FLUKA vs Geant4
12
Neutron Yield Target: Solid Pb-208 Shape: Cylinder Length: 60 cm Diameter: variable Detector: usrbdx card
13
Neutron Yield (cont)
17
Residual fragments production RESNUCLEi card used Residual distribution plotted against production cross section Production cross section calculation requires again thin target approach
18
Residual fragments production
19
Residual fragments production (cont) Important for studying the irradiation damage in the target Gives an idea about the activation of the target material
20
Neutron production distribution Neutron fluence can be assumed spherically symmetric Maximum neutron production is achieved few cms away from the impact point
21
Proton distribution The protons beam is fully contained in a 60 cm length cylinder The difference in the fluence is of order of 1/10000 between centre and peripherals
22
Energy distribution Energy deposition depends Density of the target Atomic number of the material Beam energy Target dimensions Important for Cooling system Thermal stresses analyis
23
Conclusion The largest contribution to the neutron production comes from primary neutrons rather than primary protons Materials with high atomic number are essential for high neutron multiplicity, however, issues like neutron absorption should be investigated Excluding thermal properties, solid lead seems to be a good candidate for spallation target material For a solid Pb target, a cylindrical shape (L=60 cm, R=25 cm) target seems to be convenient to contain 1 GeV proton beam power The neutron production is forward biased, this opens a discussion about idea of having multiple targets/beams
24
Recommendations FLUKA can be used efficiently for the design optimisation of the spallation target and other ADSR structural component Extend the benchmarking to other target material candidate such as LBE FLUKA has shown excellent agreement with Geant4 at high energies, low energies need to be more investigated
25
I would like to express my gratitude to Dr. Cristian Bangau for his support, encouragement and advice over the project period and for letting me use his Geant4 results
26
Thank you for your good listening!! Any questions/suggestions ?
Similar presentations
© 2025 SlidePlayer.com. Inc.
All rights reserved.