Simulations des niveaux de radiations en arrêt machine M. Brugger, D. Forkel-Wirth, S. Roesler...
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Transcript of Simulations des niveaux de radiations en arrêt machine M. Brugger, D. Forkel-Wirth, S. Roesler...
Simulations des niveaux de radiations
en arrêt machine
M. Brugger, D. Forkel-Wirth, S. Roesler (SC/RP)
10 Novembre 2004 Simulations des niveaux de radiations en arrêt machine
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IR7 Radiation Protection Issues
Impact on environment • activation and release of air• activation and release of water• activation of rock• radioactive waste
Impact on personnel (direct) (indirect)
• remanent dose from radioactive components during interventions• stray radiation
• dose to components (cables, magnets, etc.)
• production of ozone (corrosion!)
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Detailed model of IR7 (two beamlines incl. dogleg, collimators, dipoles incl. magnetic
field, quadrupoles, tunnel, etc.) Layout corresponds to V 6.5 (status March/April 04)
Only Phase 1, No Absorbers,… No local shielding (!) Forced inelastic interactions of 7 TeV protons in collimator jaws
according to loss distribution obtained from tracking code * Uniform distribution along the jaw, 200 m inside
Magnetic field Dogleg fully implemented (incl. field) Magnetic field in the quadrupoles not considered
Annual number of protons lost per year at IR7 Environmental calculations
(ultimate operation): 7.3 x 1016 ** Maintenance calculations
(nominal operation): 4.1 x 1016 **
FLUKA Simulation Parameters
* data provided by R.Assmann** data provided by M.Lamont (two beams)
10 Novembre 2004 Simulations des niveaux de radiations en arrêt machine
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FLUKA-calculations: Geometry IR7
Collimator Dipole Quadrupole
Air duct
Enclosed sections
D4 D3 Q5 Q4 Q4 Q5
*Collimators were rotated and positioned in the geometry by using a modified script from Vasilis Vlachoudis
10 Novembre 2004 Simulations des niveaux de radiations en arrêt machine
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Design Criterion 2mSv/year/person/interv
ention
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Calculation Procedure Detailed Geometry description including
Correct source terms Loss distributions Complete geometry
Tunnel structure Collimator, magnets Beamline, Dogleg separation
Monte-Carlo simulation to calculate the remanent dose rates in the entire geometry using the new “Explicit Method”
Calculation of dose rate maps for the entire geometry and various cooling times, including Separate simulations for different contributors Average and Maximum Values for relevant locations
Compilation of intervention scenarios together with the corresponding groups Time, location and frequency of the intervention Number of people involved
Calculation of individual and collective doses Iteration and optimization
10 Novembre 2004 Simulations des niveaux de radiations en arrêt machine
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Remanent Dose Rates: ContributionsContributions to total remanent dose rates (180 days of operation, 1 hour of cooling)
collimators beampipes
TCP TCS
D4 D3 Q5
Nominal Intensity
magnets
Tunnel walland floor
10 Novembre 2004 Simulations des niveaux de radiations en arrêt machine
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Remanent Dose Rates: Section between TCP and Q5Remanent dose rates after 180 days of operation
1 day of cooling 4 months of cooling
TCS
~5 mSv/h ~1 mSv/h• first secondary collimator (Phase 1) most radioactive component (in the absence of additional
absorbers) with over 90% caused by secondary particles from upstream cascades• further peaks of remanent dose rate close to upstream faces of magnets• dose rate maps allow a detailed calculation of intervention doses
Nominal Intensity
10 Novembre 2004 Simulations des niveaux de radiations en arrêt machine
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Dose Rate Maps for the Full Geometry
Cooling Time of one Day
Only Beam 1
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1 hour
Dose Rate Maps for the Different Cooling Times
8 hours
1 day 1 week
1 month 4 months
10 Novembre 2004 Simulations des niveaux de radiations en arrêt machine
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Dose Rate Maps for the Different Cooling Times
1 hour 8 hours
1 day 1 week
1 month 4 months
10 Novembre 2004 Simulations des niveaux de radiations en arrêt machine
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Chosen Locations for 1st Estimates
Cooling Time of one Day
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Dose Rate Distribution in the Aisle (Pos1)
Cooling Time of one Day
2nd Beam mirrored and added
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Average and Maximum Dose Rates
Shows the MAXIMUMintervention time, in order to stay BELOWthe design constraint
Must NOT BE USED asoptimization criterion
Even at long coolingtimes long interventionswill become difficult
10 Novembre 2004 Simulations des niveaux de radiations en arrêt machine
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Intervention Scenarios - Details To study various maintenance scenarios in order to get a
complete view of individual and collective doses at IR7 we need the following information: Kind of intervention Location of the intervention Respective cooling time Number of persons involved Steps of the intervention Time estimate for each step Frequency of the intervention Typical cooling period before intervention
In the moment the uncertainty lies in the estimates for the intervention(s), not in the calculation of the remanent dose rates!
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Intervention ScenariosThe following scenarios have already been identified and/or studied in more detail.
x
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Conclusion Access to the collimation region will strongly depend on
the exact location of the intervention as well as the time to be spent there
Next to “hot spots” (e.g. collimators, downstream magnets or absorbers) the occupancy time for maintenance operations will be rather short
During the first years of operation the situation will be slightly relaxed (factor of ~3)
Optimization of intervention scenarios should already begin now in order to be able to adopt last design changes and identify those intervention scenarios important for further improvement
10 Novembre 2004 Simulations des niveaux de radiations en arrêt machine
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Backup Slides
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Radiation Protection Legislation: General Principles
Limits per 12-months period (mSv)
Exposed Workers
Public B A
EURATOM < 1 < 6 < 20
France < 1 < 6 < 20
CERN < 0.3 < 6 < 20
Switzerland < 1 < 20
1) Justification
any exposure of persons to ionizing radiation has to be justified
2) Limitation
the individual doses have to be
kept below the legal limits
3) Optimisation
the individual doses and collective doses have to be kept as low as reasonable achievable (ALARA)
10 Novembre 2004 Simulations des niveaux de radiations en arrêt machine
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Radiation Protection Legislation: Optimisation
Radiological protection associated with justified activities shall be deemed to be optimized provided
• the appropriate different possible solutions shall have been individually assessed and compared with each other;
• the sequence of decisions that led to the particular solution remains traceable;
• due consideration has been given to the possible occurrence of failures and the elimination of radioactive sources.
The principle of optimisation shall be regarded as satisfied for activities which under no circumstances lead to an effective dose of more that 100Sv per year for occupationally exposed persons or more than 10Sv per year for persons not occupationally exposed. [Swiss Radiation Protection Legislation (22 June 1994), see also Council Directive 96/29/Euratom ].
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Radiation Protection Legislation: Design Criterion
Job dose estimates are legally required in order to optimize the design of the facility and to limit the exposure of personnel
CERN design criterion : 2 mSv/year/person
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Dose To Cables Estimate of annual dose distribution
assuming a loss rate of 1.1E16 particles per year. (H. Vincke)
A change of the cable tray location to the aisle would significantly improve the situation.
The plot to the right only includes one beam, thus the real distribution (worst case for the aisle side) would shift more to the left.
The expected reduction factor would then go down (from almost 10 as expected in the graph), to ~3-5.