Alex Howard – Neutron Interactions – G4 Workshop Lisbon 1 11 th October 2006 Neutron Interactions 1. Neutron high energy cross-section 2. Elastic scattering.

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Presentation transcript:

Alex Howard – Neutron Interactions – G4 Workshop Lisbon 1 11 th October 2006 Neutron Interactions 1. Neutron high energy cross-section 2. Elastic scattering – see next talk (M.Kosov) 3. Neutron HP 4. The TARC Discrepancy 5. Cascade neutron production 6. Pre-compound evaporation neutrons 7. Low energy isotope production 8. Cascade isotope production 9. Summary and Conclusions Alex Howard, CERN Geant4 Workshop, Lisbon 11 th October 2006

Alex Howard – Neutron Interactions – G4 Workshop Lisbon 2 11 th October 2006 High energy neutron physics Parameterized models  LEP 0~30 GeV  HEP ~15 GeV up to 15 TeV  a re-engineered version of GHEISHA  Elastic, Inelastic, Capture and Fission Theory driven models  Cascade Models  Binary Cascade < 3 GeV  Bertini Cascade < 10 GeV  High Energy Models ~15GeV < E < ~15 TeV  Quark-Gluon String (QGS)  Fritiof fragmentation (FTF)

Alex Howard – Neutron Interactions – G4 Workshop Lisbon 3 11 th October 2006 Neutron on Iron Inelastic Cross-Section Cross-section vs. neutron momentum in GeV/c Energy /GeV/c  /mbarn

Alex Howard – Neutron Interactions – G4 Workshop Lisbon 4 11 th October 2006 Neutron on Lead Inelastic Cross-Section Cross-section vs. neutron momentum in GeV/c Energy /GeV/c  /mbarn

Alex Howard – Neutron Interactions – G4 Workshop Lisbon 5 11 th October 2006 Low Energy (<20MeV) Neutron Transportation High Precision Neutron Model and Data Sets  G4NDL v3.x  Add and replaced data files (Sb, Hf, Sm, Nd, Gd,,,,)  Model and data sets  Many debugs and several new implementations Thermal Neutron Transportation  Based on thermal neutron scattering files from the ENDF/B-VI, Release2 New Data Files  G4NDL v4 ?  Produced from ENDF and JENDL  Several isotopes are ready and under testing Tatsumi Koi

Alex Howard – Neutron Interactions – G4 Workshop Lisbon 6 11 th October 2006 Verification of High Precision Neutron models Geant4 results are derived from thin target calculations Channel Cross Sections 20MeV neutron on 157 Gd Energy Spectrum of (n,2n) channel 20MeV neutron on 154 Gd Tatsumi Koi

Alex Howard – Neutron Interactions – G4 Workshop Lisbon 7 11 th October 2006 Cross section and Secondary Neutron Distributions of S(α, β) model Tatsumi Koi

Alex Howard – Neutron Interactions – G4 Workshop Lisbon 8 11 th October 2006 Known Problems and Themes Computing Speed  Slow; caused by on flight Doppler broadening Several Disagreements  Some of them are Model Specifications and some of them are bugs  Detected in  Reaction Q values  Flame Transportations  Others Correlated Final States  OK for binary products  Higher multiple products only treated statistically  Non conservation of energy and momentum in each single reaction Tatsumi Koi

Alex Howard – Neutron Interactions – G4 Workshop Lisbon 9 11 th October 2006 Simulation of the TARC experiment Neutron Driven Nuclear Transmutation by Adiabatic Resonance Crossing (Cern 96-97) 334 tons of pure Pb in cylindrical 3.3m x 3.3m x 3m block. 12 sample holes are located inside the volume to measure capture cross-sections on some isotopes. 2.5 or 3.5 GeV/c proton beam.

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 TARC simulation – single event 3.5 GeV/c proton on natural lead TARC original simulation Geant4

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 Neutron Energy-Time Correlation Neutron energy and time are stored for the flux through a given radial shell Reasonable agreement with expectation, although the low energy population is quite different between physics list (as expected) Geant4

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 Geant4 Neutron Energy-Time Correlation Neutron energy and time are stored for the flux through a given radial shell Reasonable agreement with expectation, although the low energy population is quite different between physics list (as expected) Geant4 TARC Paper TARC simulation

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 Neutron Energy-Time Correlation The slope of the correlation can approximate a Gaussian distribution Minuit errors on the mean are between 0.03 and 0.08 LHEP_HP LHEP_BIC_HP QGSP_HP LHEP_BERT_HP Experiment and TARC simulation gave 173±2 ● Bertini and Binary cascades are close to agreement with experiment

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 TARC determined the number of neutrons exiting their set-up as 30% of those produced. This is primarily based on the FLUKA neutron production code with their own transportation Geant4 can be used to compare the difference energy spectra and multiplicities of the cascade models So far initial numbers are:  BERTINI gives 32.5% exiting  BINARY gives 32.34% exiting Number of neutrons exiting

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 TARC Fluence Spectral fluence is determined from the energy- time correlation with cross- checks (lithium activation and He3 ionisation detectors) The simulated fluence is still below measurement The bertini cascade gets closest to the data The spectral shape looks reasonable Yellow curve is ~ 4xBERTINI or ~ 6xBINARY BLUE = BINARY MAGENTA = BERTINI Energy/eV E dF/dE neutrons/cm 2 /10 9 p

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 Neutrons in Cascades Clearly the TARC fluence is severely underestimated by a factor of 4 (bertini)  6 (binary) It was decided to look at thin target data across the relevant energy range SATURNE data exist for 800MeV, 1200MeV, 1600MeV  neutron multiplicity, and E x M n Isomer gamma measurements for proton on 208 Pb producing 207 Pb or 206 Pb To compare with Geant4 requires scaling with the number of isomeric states (or use RDM  future) At low energy (<100 MeV) the ratio of states can be considered approximately fixed vs. energy Data for 52, 44, 36, 28, 24 MeV Comparison made between data, bertini, binary and the Liege INCL/ABLA code

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 SATURNE Neutron multiplicity First point is 0-2MeV Neutron Energy Bin Second is 2-20MeV Third is >20MeV

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 SATURNE Av. Neutron Energy Average energy carried by neutrons per interaction NOT average energy of each neutron First point is 0-2MeV Neutron Energy Bin Second is 2-20MeV Third is >20MeV

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 Neutron multiplicity MeV First point is 0-2MeV Neutron Energy Bin Second is 2-20MeV Third is >20MeV

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October MeV Av. Neutron Energy First point is 0-2MeV Neutron Energy Bin Second is 2-20MeV Third is >20MeV

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 Cross-section comparison – low energy (16-52MeV) Experimental data is purely isomer gamma-line The measured cross-section was scaled by the number of isomeric states (estimate) This gives a lower value for the cross-section Experimental errors were quite large (+/- 25%) Converting Liege INCL output to cross-section:  Assume ntuple is filled per interaction  Scaled number of entries by total and multiplied by cross-section (as given by INCL)  The ratio between final states should at least be true

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October Pb Production MeV The agreement between INCL/ABLA is surprising (given my scaling of isomeric states)

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October Pb Production MeV INCL/ABLA does a good job, except at threshold

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 Isotope Production Data exist for 1GeV/A lead incident on hydrogen target Reverse kinematics allow the cross-section of isotope production to be determined The production of isotopes will heavily influence the neutron multiplicity and with energy conservation the spectrum  Ultimately determining the TARC fluence (at least at a generator level) In following data are black, simulation is red

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October GeV/A Pb on hydrogen – BERTINI z=82-75 BERTINI seems to do a (very) good job!

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October GeV/A Pb on hydrogen – BINARY z=82-75 BINARY significantly under-produces lighter isotopes – therefore less neutrons

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October GeV/A Pb on hydrogen – Fragment Energy Fragment energy is low for both models binary is higher BERTINI BINARY

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 Isotope production – Liege z=82-75 “Remnant” nucleus distribution from Liege INCL/ABLA

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 Isotope production – Liege z=82-75 Produced isotope distribution from Liege INCL/ABLA **The plots here are corrected from the ones shown at Lisbon** 19/10/06

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 Summary and Conclusions The high energy cross-sections for neutrons show slightly strange systematic behaviour Neutron_hp offers high precision cross-sections coming from evaluated data-base The S(α,β) model would improve simulation of very low energy neutrons on specific isotopes TARC simulation gives good agreement for transportation – energy-time correlation and number of exiting neutrons But, TARC fluence is under-estimated by Geant4 (all models) BERTINI slightly over-produces neutrons in the cascade region BINARY significantly under-produces neutrons Data and INCL/ABLA seem to be between binary and bertini INCL/ABLA does a very good job even for isotope production It is still unclear how we can produce neutrons well, but then lose them from the TARC fluence… Suggestions?

Alex Howard – Neutron Interactions – G4 Workshop Lisbon th October 2006 Isotope production – Liege z=82-75 Produced isotope distribution from Liege INCL/ABLA **This was presented but is erroneous – see slide 29 for correct one**