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The AAPM PET/CT Task Group Recommendations - Radiation ...

The AAPM PET/CT Task Group Recommendations - Radiation ...

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<strong>AAPM</strong> <strong>Task</strong> <strong>Group</strong> 108<strong>PET</strong>/<strong>CT</strong> ShieldingiDouglas J. Simpkin, Ph.D.Aurora St. Luke’s Medical CenterMilwaukee, Wisconsin, USAdsimpkin@wi.rr.comwww. http://geocities.com/djsimpkin1


Positron Emission Tomography• Well established modality in physiologicresearch• <strong>PET</strong> in clinical facilities– In USA, federal Medicare reimbursement for18FDG available 1998, other insurancecompanies follow– Led to establishment of a distribution system oflocally-produced 18 FDG (…don’t need your owncylcotron)– 18 FDG is the accepted methodology forquantitative tumor imaging2


<strong>AAPM</strong> <strong>Task</strong> <strong>Group</strong> 108 on <strong>PET</strong>and <strong>PET</strong>/<strong>CT</strong> Shielding• Formed fall of 2002• Membership p( (from Nuclear MedicineCommittee of American Assoc of Physicistsin Medicine)– Mark T Madsen, Chair– Jon A Anderson, James R Halama, Jeff Kleck,Douglas JSi Simpkin, John RV Votaw, Richard dEWendt III, Lawrence E Williams, Michael VYester• Published in Med Phys 33(1);4-15(2006).3


Facility Design Considerations• A clinical i l <strong>PET</strong> facility will include a– “Hot Lab” for receiving, storing, and preparing18 FDG for injection– Injection / “Uptake” Room•often an old closet– Scanner room4


Physics Considerations• 18 F decays (T 1/2 = 110 min = 1.83 h) by positronemission; the positron travels a short distance andthen annihilates, forming 2 × 511 keV photons.• For the same activity, the kerma/exposure ratefrom 18 F is ~6x that of 99m Tc!• <strong>The</strong>se 511 keV photons are very penetrating• Distance = shielding. In a new facility, try to– Build a BIG department– Isolate the <strong>PET</strong> department, especially from nuclearmedicine devices5


Sources of <strong>Radiation</strong> Exposure inClinical <strong>PET</strong> and <strong>PET</strong>/<strong>CT</strong>• <strong>PET</strong> radiopharmaceutical in preparation andinjection• Patient injected with the 18 FDG• X rays from <strong>CT</strong> scan• Sealed calibration source in <strong>PET</strong> scanner6


Sources of Exposure in Clinical<strong>PET</strong>• <strong>PET</strong> radiopharmaceutical in preparation andinjection– Typically receiving and administering “unitdoses” so handling is minimal– Thick Pb shielding must be available in the“Hot Lab”• Pb block “cave” for source storage• L blocks for handling• Special syringe shields7


Sources of Exposure in Clinical<strong>PET</strong>• <strong>The</strong> thickness (& weight) of <strong>PET</strong> shields is ~ anorder of magnitude greater than for Tc-99m– “L” blocks– Special syringe shields for injection• 1.3 cm Pb-equiv W• 1.9 cm Pb-glass window• W disk at end protects hands8


Sources of Exposure in Clinical<strong>PET</strong>• Sealed pin or rod calibration source(s) in<strong>PET</strong> scanner– Sealed ~180 MBq (5 mCi) Ge-68 sourcerobotically removed from its Pb shield toexposed patient for transmission scan– Nearly all photons are absorbed by patient ordetector assembly– Not a concern for structural shielding9


Sources of Exposure in Clinical<strong>PET</strong> – <strong>The</strong> Patient• Rdi Radiopharmaceutical lij injected tdit into patientt• Typical F-18 activity administered ~550 MBq(~15 mCi, but may vary widely; 10-30 mCi)• <strong>The</strong> injected patient is the primary source ofexposure in a <strong>PET</strong> facility– Despite regulations that permit the patient to bereleased from the clinical setting, the facility stillhas responsibility to assure that radiation doses tostaff and others is ALARA10


Sources of Exposure:“Point” Sources* of F-18F-18 Rate Constant, Γ Value UnitsExposure rate constant 15.4 µR m 2 /MBq hAir Kerma rate constant 0.134 µSv m 2 /MBq hEffective DoseEquivalent (ANS-1991)0.143 µSv m 2 /MBq hTissue dose constant 0.148 µSv m 2 /MBq hDeep Dose Equivalent(ANS-1977) 0.183 µSv/ m 2 MBq hMaximum Dose (ANS-1977) 0.188 µSv m 2 /MBq h* Syringe of activity11


Sources of Exposure:F-18 in Patients• Patient ≠ Point Source (patient attenuation, & scatterin patient degrades the energy of photons emanatingfrom patient)• <strong>Task</strong> <strong>Group</strong> reviewed literature, recommends arealistic Effective Dose Rate Constant Γ for F-18 inpatient:Γ = 0.092 µSv m 2 MBq - 1 h -1• But, to be conservative, assume all photons emittedfrom patient are 511 keV12


Sources of Exposure:F-18 in Patients• <strong>The</strong>n unshielded Dose Rate D at distance r(m) from activity A (MBq) is 0D=Γ A0r2•<strong>The</strong> Dose, D, accumulated over time t is0.693⎛ − × t⎞= × × × ⎜ −T1/2D 1.44DT e ⎟0 1/ 21⎜ ⎟⎝⎠13


Sources of Exposure in Clinical<strong>PET</strong>• <strong>The</strong> patient is the source– FDG Patient in “incubation” (inanquiet,isolatedisolatedroom) for ~30-60 minutes. Shielding for thisroom must be considered.– Patient is then put into the scanner for another30-60 minutes. Shielding for scanner room mustbe considered.14


What needs to be shielded from<strong>PET</strong> sources?• Nuclear Medicine Equipment– Scintillation detectors (e.g. thyroid uptakeprobes)– Gamma cameras– Bone-mineral densitometers• “A nuclear medicine department is theworst place to put a <strong>PET</strong> facility!” MarkGroch, Ph.D. 2002.15


Effect of F-18 on NearbyGamma Cameras• Measured count rate in 15% Tc-99mwindow from F-18 in phantom– Jaszczak phantom (21.6 x 18.6 cm cylinder)– Siemens Orbiter camera with LEAP collimator– Vary angle16


Effect of F-18 on NearbyGamma Camerasθ cpm m 2 / MBq0º 1.4 E+0445° 4.0 E+0390° 9.9 E+02180° 2.6 E+03intrinsic 6.9 E+04cpm = counts per minuteJaszczakphantomwith F-18Siemens Orbiter15% 99M Tc windowθLEAPCollimator17


Shielding Gamma Cameras:Sample Calculation• Have gamma camera (with no collimator)7.3 m from patient in <strong>PET</strong> scanner with 418MBq on board at start of scan• Ct rate=6 6.9E+4 × 418 / 7.3 2 = 5.4E+5 cpmUnshieldeddct rate5.4E+5cpmLimit =1%increase inRequired#HVL HVLsAssumedRequired15 kcps Transmiss required HVL shielding9E+3 cpm 0.017 5.9 0.54 cm Pb 3.2 cm Pb18


Protecting Nuclear MedicineEquipment from <strong>PET</strong> Sources• Distance• As Pb barriers tend to be thick (>2 cm),localize barriers (to minimize weight andcost)0.7 cm Pb<strong>PET</strong>Scannerto protectpeople incorridor2.5 cm Pbto protectgammacamera2 headedgamma camera19


Shielding People from <strong>PET</strong>Sources•In uncontrolled areas folks are notmonitored for radiation dose.•In USA– Must restrict dose in any one hour to< 0.02 mSv and– Must restrict annual dose to


Shielding People from <strong>PET</strong>Sources•In controlled areas radiation workers aremonitored for occupational radiation dose– (USA: Must restrict annual dose to < regulatedlimit 50 mSv y -1 with ALARA considerations)– USA: For pregnant workers, must restrictannual occupational dose to 5 mSv y -1 21


Shielding People from <strong>PET</strong>Sources• <strong>The</strong> design goal is the permitted kerma inthe shielded area, P, divided by theoccupancy factor, T.• T is the fraction of the time someone is inthe shielded area and requires protection.22


NCRP-147 Recommended TOffices, labs, pharmacies, receptionist areas, attendedwaiting rooms, kids’ play areas, x-ray rooms, filmreading areas, nursing stations, x-ray control roomsPti Patient t exam &treatment t trooms½Corridors, patient rooms, employee lounges, staff restrooms11/5Corridor doors 1/8Public toilets, vending areas, storage rooms, outdoorareas w/ seating, unattended waiting rooms, patientholdingOutdoors, unattended parking lots, attics, stairways,unattended elevators, janitor’s closets1/201/4023


Kerma Transmission of511 keV Photons• For a barrier of thickness x, transmission, B, isB =K xshielded( )Kunshielded• Determined from EGS4 Monte Carlo simulation ofbroad parallel beams of 511 keV photons in–Pb– Iron– Concrete of standard density = 2.4 g cm -3 ; Much modernconstruction ti is with “light weight” concrete with density~75% that of the standard concrete)24


Kerma Transmission of511 keV Photons• Will be conservative since the photonsemanating from the patient will have beenscattered to lower energies25


Iron28


Fit Transmission Data• Fit transmission data B(x) to eqn of Archeret al. (Health Phys 44:507-517; 1983)1−⎡γ⎛ β ⎞ α γ β ⎤= ⎢⎜1 +xB ⎟ e −α α⎥⎣⎝⎠ ⎦• Which can be inverted29


Transmission Fitting Data• For thickness x in cm,ShieldingMaterial α(cm -1 ) β(cm -1 ) γLead 1.543 -0.4408 2.136Concrete 0.1539 -0.1161 2.0752Iron 0.5704 -0.3063 0.632630


Where in the Occupied Area do youcalculate the dose?0.5 mTo the closestsensitive ii organ!Injectedpatient0.3 m1.7 m31


Conclusions• Thick Pb caves, L blocks, and special syringeshields are needed in the “Hot Lab”• <strong>The</strong> injected patient is the primary source ofradiation exposure in the <strong>PET</strong> facility• For 18 FDG, the uptake room and scanner willprobably require lead shielding• This shielding will often be 2-10× thicker thatwhat’s typically in a diagnostic i x-ray room32

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