Principle design elements of the radiation protection systems of the ELI ALPS



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Principle design elements of the radiation protection systems of the ELI ALPS (Extreme Light Infrastructure Attosecond Light Pulse Source) ELI The Power of Light Károly Bodor Radiation Protection Designer 2nd FLUKA Advanced Course and Workshop Vancouver, Canada 2012.09.16 20.

The ELI: Europe s largest and most powerful laser facility

The ELI ALPS buildings and experimental halls

The task is to design the radiation protection systems of the largest, most powerful laser facility in the world To design the radiation protection first of all we have to understand the processes and the interactions that occours at the ELI ALPS Not only the laser light, but the secondary sources will be also extreme at the ELI ALPS We will have to handle this beams somehow to avoid the harms, that these beams can cause The solution is to design and build a so called beam dump to stop these secondary sources The radiation protection systems of the ELI ALPS have to satisfy the internatinal (IAEA, ICRP, ICRU) and national standards, laws IAEA dose limits 6

Processes, interactions at the ELI ALPS During the laser matter interaction high energy proton (250 MeV) and (2 GeV) electron beams are generated (first of all) by the so called TNSA (Target Normal Sheath Acceleration) mechanism (and shock, front surface acceleration) The caracteristics of the secondary sources can be extrapolated by previous measurements or calculated by these simple equation: Another solution to determine the parameters is to make calculations with the Osiris code, this code use the Maxwell Lorentz equations step by step, one simulation is 100 Tbyte large! [3] [4] [3] 7

Design stages 1: normal operating: the laser system works properly, the shielding do it s task: eliminates the secondary sources and the harms that these beams could cause 2:Design Basic Accident (DBA): When the laser operating abnormally: somehow the secondary beams don t interract with the beam dump (the beam don t hit the beam dump): in these situations the built in logical electricity tilt the laser light beam 3: Worst case: The high energy secondary beam hit the most sensitive part (testicles, ovaries, etc.) of the human body. This is a hypothetical case, if the access control system works properly this is an impossible case.

Radiation types Prompt radiation: short, transient, complex, most harmful radiation, occours during the laser operating only Residual radiation: the secondary sources activate the matters of the beam dump and air particles, this will be radioactive, the radiation of the activated matter is the residual radiation, the air should be ventillated out from the target area Additional radiation: radiation of the activated corrosive components in the cooling heating pipe systems (this will be no playing at the ELI ALPS because the cooling and heating system will be designed by air ventillation) 9

Main effects and processes during the interaction between the matter of the beam dump and the secondary sources In the simulation it can be seen that a proton beam interacts with a copper beam dump, the processes are very complex A multiplying shower is the result of both the electromagnetic cascade produce a hadronic cascade and the hadronic cascade produce an electromagnetic cascade And these effects produces induced activity To minimize these showers a complex beam dump design is necessary [5] 10

New processes by high beam energies Increasing the beam energy some new processes are generated thet have a logaritmic shape (Giant resonance neutrons, induced activity, muons, Bremsstrahlung) It can be seen that below 100 MeV all these processes start alive and at the GeV regime there is no more increasing, only by muons [2]

Electromagnetic cascade effects The interaction between the high energy electrons and the matter generates bremsstrahlung, giant resonance neutrons, muons (at the ELI ALPS there will be no muon generating by the electrons, because the threshold is from 2 5GeV) The cascade shower stop when the energy of the particles exceed the critical energy, it can be seen that the low and medium low atomic mass numbered matters have high critical energy, these matters can stop effectively the showers (Brems pair brems ) It can be seen that the production of giant resonance neutrons is low at low, and medium low atomic mass numbered matters (C, Al, Fe) X0 = radiation length (e energy reduced to 1/e) Multiplication stops when Ee drops below Ec 12[2]

The hadron cascade The hadron cascade is much more complex then the electromagnetic cascade. The collision of high energy nucleon with a nucleus gives rise to a large numbers of particles The main means of energy transfer is due to the interaction of high energy nucleon that is hadrons with energy higher than 150 MeV, that serve to propagate the cascade. Nucleons in the energy range 20 150 MeV also transfer their energy mainly via nuclear interaction but at these energies charged particles are rapidly stopped by ionization and thus only neutrons predominate at lower energies. 13 [2]

Induced activity The generated neutrons by hadrons and electrons acitvates the matters of the beam dump A(t)=λN rad (t)=σφn target [1 exp( λt)] Most of the activated matter have very short half lived isotopes, it decay in a few minutes But the long half lived isotopes are accumulated [1] 14

How to choose the matter and design the beam dump To design the dump, the Fluka monte carlo code is the best solution, the simulated and measured values are very similar The main absorber of the beam dump should be a special matter that do not generates to much giant resonance neutrons, the critical energy is not low and cheap,thepossiblemattersarelow,medium low atomic mass numbered matters (C, Al, Fe, Copper) The best choice is to investigate the amount of the induced activity of these matters, the winner will be the most lower induced matter, this is how the life time can be maximalized and the residual radiation of the dump minimized At the Czech site the winner was the stainless steel: [3] 15

How the beam dump stop the different particle beams As you can see in this simulations the mean absorber of the beam dump reflects the neutron beams (and not only the neutrons) The solution is to use a graphyte cylinder that allows the beam to penetrate inside the dump But there is a disanvantage: the cylinder generates a radial neutron fluent componenet, this should be also shielded with borated polyethylene, the Czech team Trend will of fix the this dose problem rate level in the near future For other particles accessorial shielding elements are needed: for the bremsstrahlung lead for Giant resonance neutrons the high density polyethylene and for high energy neutrons concrete is the best choice by the attenuation lenghts If the rep. rate is 10 times higher, 16 than the dose rate level is also 10 times higher [1]

Comparison of the shielding solutions at the ELI sites For 5 and 50 GeV previous simulations are available By the parameter sensitivity analises, it can be seen that the max. dose rate on the outer surface of the wall is increasing in the MeV energy range, in the GeV range it is not increasing rapidly: Czeh Republik Hungary Romania Site/parameters Depth (m) Hight (m) Lenght (m) Approx. weight (t) Additional info Max. electron energy (GeV) Hungary 2,7 2,7 5,7 130 Czeh Republik 3,2 3,2 5,6 108 RPP, with lead+concrate+polyethylen accessories RCC, with no lead, concrate and radial polyethylen shielding 2 50 Romania 3 3 7,5 262 RPP, lead at the center 38

The Czeh site, the Laser Control Room (LCR) is located between the proton and electron accelerator rooms (moun showers)

Advanced beam dump at the ELI ALPS NowwehaveaconservativeideaabouttheELI ALPS beam dump, but this is changeable It contains stainless steel, or Al, graphyte, concrete, borated polyethylene and lead to shield all types of the particle beams The dump size has a minimum value because below this size the cascade effectes can start again The thickness of the walls of the target rooms will be between 0,5 2m 19

The main principal equation for shielding calculations: D U< DC D: Dose Rate (calculated by FLUKA) U: Operational parameters (contains: N F T G)~10 16 N=10 9 particle/shoot F=10 Hz repetion rate of the laser T=1 hour/day operation time of the laser G=200 day/year DC: Dose Constraint by Hungarian Authorities & IAEA, it is 100 µsv/year It means the maximum dose rate should be lower than 10 5 fsv outside The air also can be activated, with this simple equation the amount of the produced radioactive particles in the air can be calculated: A total radioactivity in the air (t)=σ i B i *C i *[1 exp( λ i t ventillating )]*[exp( λ i t decay )] Where : B: beam intensity C: activation rate

Shielding against 2 GeV electrons 1,5 m concrete wall it seems to be necessary+the beam dump (dose rate in fsv) The graphyte was sent deeper into the dump, that causes lower back scattering The beam hit the wall Vacuum in the room

250 MeV Proton and 100 MeV C 12 shielding The planned max. proton energy is 250 MeV, it can be foreseen by scaling laws For heavy ions the FLUKA dosen t have fluence dose equivalents, for 100 MeV protons 1,3m thick concrete wall is nedded 250 MeV proton shielding is now under investigation, more than 1,5 m concrete wall is necessary if beam dump is not used The velocity of the heavy ions are lower than the protons, also the heavy ions have higher cross sections, that causes the beam propagates and stop at lower distances So the proton beam is the limitation factor 250 MeV protons with beam dump, the wall thickness is 2m 250 MeV protons without beam dump, only the more than 10-5 fsv higher doses are shown

In situ calculations Every exercise is a new problem that have to be solved Not only one solution is exsiting Before starting a simulation, it is recommended to look after for similar cases, from these knowledge and from the parameter sensitivity studies the results will be able to predicted In some cases (if there is an accident, or at a new experiment) quick results can be necessary at the site immediately In this cases without clasters or high performance PC s and the calculation time is limited a good approximation method is useful to determine the max values In this cases high primary number is slowing down the calculations, but if there is no too much primary the deviation will be high

At the shielding design exercises often only the max. values are important It can be seen from the sensitivity analises calculations that the max. value every time is different by the primary increasing, but the value every time is between two magnitudes If every time the higher magnitude is choosen then it can be seen the max. result is independet from the primary even if the deviation is high If there is no enought info. (50 MeV) the FLUKA shows conservative higher values 100 MeV protons 104 primary Point of importance 100 MeV protons 106 primary

Primary/Proton energy (MeV) 50 100 250 500 Promt dose rate (fsv) Deviation (%) Promt dose rate (fsv) Deviation (%) Promt dose rate (fsv) Deviation (%) Promt dose rate (fsv) Deviation (%) 10 10 100 100 10 30 1000 0,01 100 0,01 100 1 40 10 20 10000 0,001 100 0,01 70 1 20 10 10 100000 0,001 70 0,01 20 1 10 1000000 0,0001 50 0,01 10 10000000 0,0001 20 Deviation of the promt dose rate at the imortance point (%) 100 80 60 40 20 0 1 10 100 1000 10000 100000 1000000 1E7 Primary particles 50 MeV 100 MeV 250 MeV 500 MeV Prompt dose rate at the importance point (fsv) 100 10 1 0,1 0,01 1E-3 1E-4 1E-5 1 10 100 1000 10000 100000 1000000 1E7 Primary particles 50 MeV 100 MeV 250 MeV 500 MeV

What about the radioactive wastes?! The matter of the beam dump is activated by the cascade effects, long and short lived radioactive isotopes are produced. The long lived isotopes are accumulated, if the activity concentration reaches the Activity Concentration Exemption Level (ACEL), then these matters are officially radioactive materials or wastes To avoid this event, the parts of the beam dump should be replaced once in a while to new ones, the used parts should be stored in a cooling storage. After the relaxation the old parts can be used again in the beam dump With this method the amount of the radioactive wastes and the operational costs can be minimized at the ELI ALPS 26 [3]

Radiation safety systems The prompt radiation hazards associated with the laser operation can be high. The primary goal of the Radiation Safety System is to protect people from prompt radiation hazards with a fully interlocked, engineered passive/active system that is reliable, redundant, and fail safe. A personnel protection system can be considered as divided into two main parts: (1) An access control system intended to prevent any unauthorised or accidental entry into radiation areas. The access control system is composed by physical barriers (doors, shields, hutches), signs, closed circuit TV, flashing lights, audiovisual warning devices, including associated interlock system, and a body of administrative procedures that define conditions where entry is safe (2) A radiation alarm system. The system includes radiation monitors, which measure radiation field directly giving an interlock signal when the alarm level is reached. 27

Environmental monitoring at the ELI ALPS For the public and for the authorities the minimal environmental effect of the ELI can be demonstratable by measured environmental data GMtubes in out side, fall out, aerosol sampling, in situ gammaspectrometry Soil, plant, water sampling 2 3 times/year Central signal system measuring results 28 rout e sourc e

Thank you for your attention! And thank you for the FLUKA & FLAIR team! References: [1] A. Ferrari, D. Margarone, T. Cowan, J.Prokupek and B. Rus, Shielding assessment for the ELI high intensity laser beamline facility in Czech Republic, Proceedings of the SATIF-10 Conference, CERN 2-4 June 2010. [2] Adolfo Esposito, Radiation protection for laser-based accelerators, LEI conference, Brasov, October 16-21. 2009. [3] ELI White Book draft version, ELI-PP WP6 group [4] J. Fuchs, P. Audebert, M. Borghesi, H. Pépin, O. Willi, Laser acceleration of low emittance, High energy ions and applications, ScienceDirect, 2009. [5] http://theis.web.cern.ch/theis/simplegeo/ 29