Radiation Protection during design, operation and dismantling of target areas Thomas Otto based on material from RP group.

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Presentation transcript:

Radiation Protection during design, operation and dismantling of target areas Thomas Otto based on material from RP group

IEFC Workshop Thomas Otto2 Proton Target Areas at CERN AD26 GeV/c0.24 kW N-TOF20 GeV/c1.25 kW ISOLDE1.4 GeV3 kW North400 GeV/c10’s of kW CNGS400 GeV/c440 kW

IEFC Workshop Thomas Otto3 Radiation Protection Items Ionisation and radiolysis Chemically Aggressive atmosphere (NO x, O 3 ) Activated air (spallation, activation) Release to the environment Activation of ground and potentially ground water Environmental concern ( 3 H, 22 Na) Material activation High ambient dose rates from activated material Future radioactive waste

IEFC Workshop Thomas Otto4 Air Ionization and Activation Energetic secondary particles emerge from target Traverse air, ionize and activate  A ~ (pathlength in air) Estimate activation by heuristic formulae or Monte- Carlo simulation Mainly short-lived beta-plus emitters 11 C, 13 N, 15 O, 41 Ar

IEFC Workshop Thomas Otto5 Purpose of “Nuclear” Ventilation Create dynamic depression in the most radioactive area – protect other areas from leaking of activation/ contamination Direct airflow to release point Allow release at a suitable point (e.g. at height) Permit aerosol filtering at unique point Permit monitoring at unique release point Plus the usual purposes of ventilation, such as cooling, removal of noxious agents …

IEFC Workshop Thomas Otto6 Transport and Release of Air Two simplifying cases: Laminar flow of air volume at speed v (e.g. in tunnel) Complete mixing of air in target volume, average dwell time  v v Under these assumptions, activation release rate (Bq/s) can be estimated from ventilation speed

IEFC Workshop Thomas Otto7 ISOLDE : 3-times higher activity concentration at stack for equal proton beam current “solved” by intensity limitation The simplifying assumptions do not always work as advertised. Small changes in air flow may have a big effect. It took man-months of work at ISOLDE to re- establish release figures similar to those achieved before 2007

IEFC Workshop Thomas Otto8 Release vs. current Activity production functions as expected !

IEFC Workshop Thomas Otto9 n-TOF 2009 Integrated release higher than expected lack of tightness in target area requires higher extraction rate Spikes ?? From degassing system of cooling water: 15 O Solved by additional delay / decay tank

IEFC Workshop Thomas Otto10 Due to current interest: No directed extraction - PS PS volume ≈ m 3 Ventilation injects m 3 /h 1.7 exchanges / hour p(tunnel) higher than p(environment) Smoke tests revealed: Uncontrolled release One reason for higher-than usual ambient dose rates in PS ring

IEFC Workshop Thomas Otto11 PS Smoke Tests 2005

IEFC Workshop Thomas Otto12 Environmental model A set of conservative models for transport of radionuclides into and in the environment (by air and water, deposition, resuspension, uptake by crop and animals) Exposure of representative group of public (irradiation, uptake) Estimated dose can be compared with appropriate limits Effluent (release) Environmental transfer Exposure Pathways Dose Estimation

IEFC Workshop Thomas Otto13 Dose from CERN releases (Meyrin site, 2008) For comparison: Dose to reference groups at Swiss NPP: PWR: < 1  Sv /y BWR: 5  Sv /y Release* (GBq) Dose  Sv) Short-lived beta emitters Other  ( 60 Co) Stray radiation-3.7 Total7.0 PS underestimated (non-representative sampling point) PSB, EAST, AD at present not monitored N-TOF 2009: GBq, +1.1  Sv Airborne releases are at the limit of the optimisation threshold. (10  Sv / y) Any increase of releases will have to be justified and optimised

IEFC Workshop Thomas Otto14 Reduction of air-borne releases Add shielding in target area Reduce track length in air Closed ventilation system Cool and dry air in closed circuit Only vent before access Release from height Construct a stack of h > 80 m

IEFC Workshop Thomas Otto15 Shielding in target area Shielding absorbs secondary radiation cascade emerging from target Less activation of air Activation of shielding

IEFC Workshop Thomas Otto16 CNGS as an example The target and horn are well shielded Crane available for remote dismantling of shielding

IEFC Workshop Thomas Otto17 Closed ventilation system Cool & dry activated air “never” release only before access Appears a good idea, but Dynamic depression difficult to maintain Accumulation of 3 H in condensate TNM41 8m 3 TSG4 30m 3 TCV4 30m 3

IEFC Workshop Thomas Otto18 Tritium – where from ? Tritium is copiously produced as a light fragment in spallation reactions in (humid) air and in structural materials. It diffuses out of the walls in form of HTO In a closed ventilation system, the moist air is condensated in the dehumidifiers and the Tritium concentrated

IEFC Workshop Thomas Otto19 Consequence of CNGS – 3 H N-TOF 2008: “open” ventilation The concentration of short-lived beta emitters allowed this solution Tritiated water Storage in tanks Elimination via nuclear site in France Evaporation – the concentration in air is no reason to worry

IEFC Workshop Thomas Otto20 Release from height (stack) Diffusion (dilution) coefficient for radionuclide concentration as a function of stack height. High stack affords orders of magnitude better dilution in the close zone (< 1000 m) !

IEFC Workshop Thomas Otto21 Ground activation and ground water contamination Soil around accelerator is inevitably activated Activation may be fixed or unreachable for any human purpose (e.g. LEP / LHC) Activation migrates with ground water and runoff water Fermilab experiments (1980’s): 7 Be, 51 Cr, 22 Na, 54 Mn, 46 Sc, 48 V, 55 Fe, 59 Fe, 60 Co, 45 Ca and 3 H are produced 22 Na, 3 H are soluble and easily transported

IEFC Workshop Thomas Otto22 Distribution of activation Lateral to proton accelerator tunnel: Exp. activation profile,  = 38 cm 99.9 % of all activation is produced in a layer less than 3 m thick. (“activation zone”) Water from the activation zone is exceeding rad. waste levels for 22 Na and must be dealt with appropriately (infiltrations!) Power of uncontrolled losses 1 W/m

IEFC Workshop Thomas Otto23 Protective layers Drinking water resources outside the “activation zone” can be protected with a “geomembrane” (example SNS)

IEFC Workshop Thomas Otto24 Situation at CERN Accelerators and target areas close to the surface (Linac, PSB,PS, East, AD, ISOLDE, n-TOF, North) are far from drinking water sourcing areas The potentially activated run-off must be diluted, in some cases in little streams with limited capacity Infiltration water in tunnels and target areas may be activated beyond free release guidelines

IEFC Workshop Thomas Otto25 Waste from Target areas Most target areas produce one-off waste, e.g. the ISOLDE front- ends or the n-TOF target Highly activated, high ambient dose rate Find special agreements with national repositories for elimination and final storage

IEFC Workshop Thomas Otto26 Waste from ISOLDE ISOLDE produces 30 waste target units per year High dose rate and actinide (alpha- emitter) content makes treatment in hot cell mandatory Temporary storage saturated Elimination pathway is required now

IEFC Workshop Thomas Otto27 Summary Target areas have radiation protection topics in common Activation, radioactive releases, waste production Imagine CERN increases beam power on targets: Ventilation must be well-designed, air-flow fully understood Release close to ground reaches its limits closed circuit, high stack, shielding: no “silver bullet” Ground activation becomes an issue for close-to-surface accelerators Target areas produce highly activated waste Suitable interim storage and elimination pathways must be defined