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

Accelerator Radiation Safety Section Operational radiation protection Associated R&D 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

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

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

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?

20 MeV proton on Be

Electron Accelerators Photon (Bremsstrahlung) spectrometry –High energy Detector response studies –neutrons and photons Photoneutron spectrometry and dosimetry Synchrotron dosimetry –Low energy (< 10 keV)

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

Check

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),

Experiment Independent FLUKA Calculation Our Calculation

Neutrons > 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 (  >200 MeV) But at the experimental area, the photon fluence is expected to be several times higher than neutrons! Calculate photon induced fission using FLUKA?

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

Transmitted dose

Unshielded Dose rate

Variation with detector size

Effect of detector size

Variation with detector size

Residual activity 2.5 GeV electron incident on 10 X 0 -1X m targets. DPMJET activated using PHYSICS LAM-BIAS at 100 Photon transport cut off to 10 MeV

Residual Activity (Bq/g) SS

2.5 GeV e -, 1mA, 24 hours TargetRadionuclideHalf lifeMode of productionEstimated Activity (MBqW -1 ) Ni 57 Co271 d 58 Ni( ,n) 400 Ta 182 Ta114 d 181 Ta(n,  ) Ta8.1 h 181 Ta( ,n) Ta1.8 a 181 Ta( ,2n) 430 SS316L 55 Fe2.7 a 54 Fe(n,  ) 56 Fe( ,n) Cr27.7 d 50 Cr(n,  ) 130

Residual Nuclei In SS, 51 Cr was reported by Fasso with a higher neutron cutoff energy. Swanson’s technique and present calculation agree within a factor of 2; for example 57 Co in Ni target, 63, 65 Cu from Cu target. 59 Fe in SS ( 58 Fe(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 MBqW -1.

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?

Heavy Ion reactions Work done at PTB Germany 200 MeV 12 C 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)

Neutron Spectra 200 MeV/amu 12 C incident on 15 cm diameter cylindrical water phantom

Neutron and charged particles

Charged particles Apply coincidence measurements

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

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 10 6 histories ! And still large errors (10%-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

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.

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!

Simplified view concrete water 7 m Window

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

Thank you