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FLUKA for accelerator radiation protection –Indian perspective

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Title: FLUKA for accelerator radiation protection –Indian perspective


1
FLUKA for accelerator radiation protection
Indian perspective
  • Sunil C
  • Accelerator Radiation Safety Section
  • Radiation Safety Systems Division,
  • Bhabha Atomic Research Centre

2
Accelerator Radiation Safety Section
  • Operational radiation protection
  • Associated RD
  • Heavy Ion Accelerators (TIFR Bombay and VECC,
    Calcutta
  • 5-7 MeV/amu Pelletron
  • 10 MeV/amu with a superconducting linac booster
  • 100 MeV/amu superconducting cyclotron
  • Electron accelerators (RRCAT Indore)
  • 20 MeV Microtron to 2.5 GeV electron synchrotron
  • High current industrial accelerators

3
Future plans
  • ADSS
  • Proton accelerators
  • 20 MeV to 1 GeV
  • Swimming poll critical reactor that can also be
    operated in sub critical mode with 600 MeV
    protons incident on LBE
  • 14 MeV neutron generators
  • Bare
  • Injectors for sub critical assemblies

4
Uses of FLUKA
  • Routine accelerator radiation protection
  • Source term calculations
  • Shielding
  • Induced activity
  • Synchrotron hutch shielding
  • Photoneutron estimation
  • ADSS
  • Proton accelerators
  • Secondary particle dose from heavy Ion reactions
  • Muon Transport and dose estimation
  • Spallation yields comparison with JQMD

5
Heavy Ion accelerators
  • Neutron source term calculations
  • EMPIRE, PACE (heavy ions) ALICE, PRECO (protons)
  • Transport using the source.f
  • BME!
  • 10 MeV/amu to 100 MeV/amu
  • Hauser-Feshbach for compound nucleus?
  • Induced activity calculations
  • Neutron spectrometry using passive techniques
  • ECR ion sources
  • Simulate electric fields?

6
20 MeV proton on Be
7
Electron Accelerators
  • Photon (Bremsstrahlung) spectrometry
  • High energy
  • Detector response studies
  • neutrons and photons
  • Photoneutron spectrometry and dosimetry
  • Synchrotron dosimetry
  • Low energy (lt 10 keV)

8
Photoneutrons
  • Contribution to the exposure in electron
    accelerators
  • A new technique to predict the neutron spectra
    using empirical relations
  • Spectra from FLUKA fitted to a Maxwellian
  • Temperature
  • Yield
  • Form a couple equation to predict the GDR part of
    the photoneutron spectrum

9
Check
10
The procedure
Sunil C, Sarkar P K, Empirical estimation of
photoneutron energy distribution in high energy
electron accelerators, Nuclear Instruments and
Methods A 581, (2007), 844-849.
11
Independent FLUKA Calculation
Experiment
Our Calculation
12
Neutrons gt 50 MeV
  • Experimental verification using Bi fission foils,
    track etch membranes shows higher values when
    compared to FLUKA calculations.
  • How much is photon induced fission?
  • The cross section is 1 of neutron fission (?gt200
    MeV)
  • But at the experimental area, the photon fluence
    is expected to be several times higher than
    neutrons!
  • Calculate photon induced fission using FLUKA?

13
Photon Transmission
  • 30 cm diameter and 30 cm long cylindrical
    detector (approximating the upper trunk of a
    human body) is used to count the photons.
  • USRTRACK estimator tallies the photon fluence.
  • Deq99 (FLUSUW) subroutine used to fold the
    fluence with the dose conversion coefficients to
    obtain ambient dose equivalent

14
Transmitted dose
15
Unshielded Dose rate
16
Variation with detector size
17
Effect of detector size
18
Variation with detector size
19
Residual activity
  • 2.5 GeV electron incident on 10 X0 -1Xm targets.
  • DPMJET activated using PHYSICS
  • LAM-BIAS at 100
  • Photon transport cut off to 10 MeV

20
Residual Activity (Bq/g)
SS
21
2.5 GeV e-, 1mA, 24 hours
22
Residual Nuclei
  • In SS, 51Cr was reported by Fasso with a higher
    neutron cutoff energy.
  • Swansons technique and present calculation agree
    within a factor of 2 for example 57Co in Ni
    target, 63, 65Cu from Cu target.
  • 59Fe in SS (58Fe(n,?)) target in this calculation
    was found to be four orders less compared to that
    obtained by Sato and Fasso
  • Most of the important nuclides formed are in the
    range of 200 -500 MBqW-1.

23
Synchrotron Hutch Shielding
  • Hutch design in INDUS (2.5 GeV, 1 mA)
  • Bremsstrahlung mixed with SR
  • Experiments claim existence of SR
  • Transportation tough - low energy at the edge of
    FLUKA capabilities.
  • Can it be simulated using FLUKA?

24
Heavy Ion reactions
  • Work done at PTB Germany
  • 200 MeV 12C ions on water phantom
  • Score neutron fluence and dose inside 5.7 cm
    spheres at different angles.
  • Compare with measurements done at GSI
  • Spectra from TOF (GSI measurements)
  • Dose using a TEPC (PTB measurements)
  • Dose using WENDI (GSI measurements)

25
Neutron Spectra
200 MeV/amu 12C incident on 15 cm diameter
cylindrical water phantom
26
Neutron and charged particles
27
Charged particles
Apply coincidence measurements
28
Response Matrices
  • Neutron attenuation through a target of finite
    thickness.
  • Response of Bonner sphere type passive
    techniques.
  • Response of liquid scintillators
  • Bismuth fission detectors
  • Neutron induced fission
  • Photon induced fission

29
ADSS
  • A sub critical assembly driven by 14 MeV neutrons
  • 256 nat.U rods inside water column, beam tube at
    center.
  • Analog mode
  • 36 hours for 106 histories !
  • And still large errors (10-30)

30
Proton accelerators for ADSS
  • Plans to couple a sub critical reactor to a
    proton accelerator
  • Source term for lateral shielding of the
    accelerator tunnel, reactor pool top
  • Residual activity in LBE loop
  • Activation of magnets concrete wall
  • LBE window rupture due to heat load

31
ADSS problems
  • High beam current 1-5 mA!
  • Proton energies varying from 100 MeV to 1GeV
  • Shielding calculations
  • Reduce dose by 9 orders- 7 meters!
  • Induced activity after several meters of water
  • Explicit Transport !? Or calculate neutrons at
    intermediate thicknesses?
  • Induced activity in magnets, concrete walls.
  • Induced activity in LBE after several
    combinations of irradiations.

32
Shielding
  • Attenuation length from IAEA 283
  • n/p ratio from FLUKA
  • Multiply end result by the n/p ratio to get the
    transmitted dose after shield
  • Biasing!

33
Simplified view
concrete
7 m
water
Window
34
Further work
  • Establish attenuation curves for different shield
    configurations.
  • Different types of concrete
  • Transport neutrons through several meters of
    water and calculate induced activity.
  • Irradiation profile, raddecay, dcytimes, usrbin

35
Thank you
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