IJMPCEROInternational Journal of Medical Physics, Clinical Engineering and Radiation Oncology2168-5436Scientific Research Publishing10.4236/ijmpcero.2019.81001IJMPCERO-90033ArticlesMedicine&Healthcare Physics&Mathematics Radiation Shielding Analysis and Design of tof PET-CT Facility at Institute of Nuclear Medical Physics under Bangladesh Atomic Energy Commission, Bangladesh M.F. Uddin1*R.Khatun2S.Akter2H.M. Jamil1A.N. Monika1M.A. Rahaman1R.P. Das1R.A. Sharmin1M.M. Rahman2M.M. Ahasan1Atomic Energy Centre, Dhaka, BangladeshInstitute of Nuclear Medical Physics, AERE, Savar, Dhaka, Bangladesh210120190801188, November 201818, January 2019 21, January 2019© Copyright 2014 by authors and Scientific Research Publishing Inc. 2014This work is licensed under the Creative Commons Attribution International License (CC BY). http://creativecommons.org/licenses/by/4.0/

High resolution (4 mm) tof PET-CT (positron emission tomography-computed tomography) from Philips of model Ingenuity TF is newly installed at Institute of Nuclear Medical Physics (INMP). 128 slice CT component incorporated with PET provides comparatively lower dose than the 511 keV annihilation photons associated with positron decay from PET scan. So, for designing shielding in our PET-CT facility, only 511 keV annihilation photons energy has been considered. The main objective of this paper is to show what measures have been taken to protect patients, occupational workers as well as environment from PET-CT radiation hazard through a cost effective design that satisfy the national regulatory demand. In this paper, AAPM (American Associations of Physicists in Medicine) Task group 108 analysis for PET and PET-CT shielding requirements is followed for our PET-CT facility shielding design. From theoretical calculation as shielding requirement, 1.1 cm Pb thickness or, 13 cm concrete thicknesses are found. Practically, all walls and ceiling are of 30.48 cm (1 foot) thick made of concrete with density 2.35 gcm-3 for more safety. As x-ray from CT is not taken into account for shielding analysis, Bangladesh Atomic Energy Commission (BAEC) conducted an extensive radiation survey at controlled, supervised and public area for CT. The report that is found meets the national regulatory requirements.

Radiation Protection PET-CT Shielding FDG1. Introduction

Bangladesh is a developing country and is now facing many challenges, especially in health sector. Government has given the priority in cancer diagnosis and management due to the current trend of cancer disease in this region. Under this consideration, nuclear tof PET-CT (time of flight positron emission tomography-computed tomography) machine for imaging purpose is newly installed at Institute of Nuclear Medical Physics (INMP) under Bangladesh Atomic Energy Commission (BAEC). Here, CT part is incorporated with PET to get fused image. This machine can diagnose cancer at molecular level. PET image resolution is very high (4 mm) imported from Philips (USA) of model Ingenuity TF; timing resolution and coincidence window are 600 ps and 5 ns respectively. In this machine, LYSO (Lu1.8Y0.2SiO5: Ce) crystals are used. The number of crystal detectors and PMTs are 28,336 and 420. PET-CT is a sophisticated device, so shielding pattern is totally different from other imaging device. 128 slice CT (80 - 140 kV) component incorporated with PET, gives comparatively lower dose than the 511 keV annihilation photons dose associated with positron decay from PET scan [1] . Designing shielding in PET-CT facility, only 511 keV annihilation photons energy has been considered. Actually, CT technology is used for attenuation correction in surrounding organ of region of interest and help in the exact anatomical localization of the molecular changes diagnosed by PET [2] . The National Council on Radiation Protection and Measurements (NCRP) defines “shields” as a physical entity interposed between a source of ionizing radiation and an object to be protected so that the radiation level at the position of that object will be reduced [3] . Floors and ceilings, adjacent walls as well as door are considered to be calculation as shielding. As Low As Reasonably Achievable (ALARA) principle is used in exposure to radiation and other occupational health risks [4] . During PET-CT shielding calculation, the factors are taken into account are source of radiation, amount of activity, decay of activity, number of patient per day, distance, shielding material and occupancy factor etc. A lot of methods have been developed in this calculation but in all cases above factors are considered.

FDG Radionuclide

The radiotracer used for PET scan is fluoro-2-deoxyglucose (FDG). FDG is labeled with F18, whose half life is only 109 min. Before scanning, typically 5 to 10 mCi (185 - 370 MBq) of F18-FDG is injected rapidly into a saline drip running into a vein of a patient who has been fasting for at least 6 hours. After about an hour of injection, patient is undergone for PET scan. And it takes about 20 to 30 minutes. FDG chemical structure and positron annihilation process are shown in Figure 1 and Figure 2. The above mentioned administered activity is common practice in Bangladesh. But for shielding calculation, administered activity is considered to be higher.

Regulatory Limit

Maximum permissible dose per year (P) for radiation worker is 20 mSv (averaged over five consecutive years) and 50 mSv in a single year. For ALARA

principle it is taken as 1/10 of maximum value. So, P value is 5 mSv/yr. But, according to Bangladesh Atomic Energy Regulatory Act 2012 and Nuclear Safety & Radiation Control Rules 1997, P value should be 0.1 mSv/yr for shielding calculation in consideration with public dose. In controlled area, dose rate for radiation worker is 10 μS v∙hr−1 and 0.50 μSv∙hr−1 for that of uncontrolled area. Layout of PET-CT facility at INMP is shown in Figure 3. The aim of this paper is what measures have been taken to protect patients, occupational workers as well as environment from PET-CT radiation hazard.

2. Methods2.1. Shielding Analysis

F18-FDG administered dose varies from patient to patient. Bangladeshi people are small in size compared with other country patients. It depends on patient mass, uptake time and the acquisition mode etc. [1] . It is assumed that all photons emitted from patient are 511 keV. Then dose rate D • at distance r (m) from activity A (MBq) is

D • = Γ A r 2 (1)

where, Γ → Effective dose rate constant.

Since the patient itself becomes the radioactive source after the radiopharmaceutical has been administered, one has to consider the entire time that the subject remains in the clinic [1] .

The dose D, accumulated over time t is

D = 1.44 × D • × T 1 / 2 × ( 1 − e − 0.693 × t T 1 / 2 ) (2)

and track decay of activity from moment-to-moment.

A ( t ) = A 0 × ( e − 0.693 × t T 1 / 2 ) (3)

Corresponding lead, concrete and iron thickness for broad beam transmission factors B at 511 keV is obtained from the Table 1 [1] .

Another alternative way to measure thickness value is

I = B 0 × I 0 e − μ t (4)

or

I I 0 = e − ln 2 / HVL (5)

where, µ is attenuation co-efficient whose value is 1.92 cm−1 for lead in case of broad beam of energy 511 keV [5] . B0 is buildup factor. The value of B0 increases with the increase of the thickness of the shielding material. The mean free path of 511 keV photon in air is near about 100 meter and so it’s attenuation in air is considered to be zero [6] . Equation (4) is used for shielding calculation if broad beam transmission data shown in Table 1 is not available. HVL values of water, concrete and lead are 7.58 cm, 3.42 cm and 0.40 cm respectively for 511 keV photons [7] .

2.2. Concrete Wall Shielding

AAPM Task Group 108 recommends a realistic effective dose rate constant Γ

Broad beam transmission factors at 511 keV in lead, concrete and iron
Thicknessa,bTransmission factors
LeadConcreteIron
01.00001.00001.0000
10.89120.95830.7484
20.78730.90880.5325
30.69050.85190.3614
40.60210.78890.2353
50.52270.72180.1479
60.45220.65280.0905
70.39030.58420.0542
80.33620.51800.0319
90.28920.45580.0186
100.24850.39870.0107
120.18310.30080.0035
140.13470.22430.0011
160.09900.16620.0004
180.07280.12270.0001
200.05350.0904
250.02470.0419
300.01140.0194

aThickness in mm for lead. bThickness in cm for concrete and iron.

is 0.092 μSv∙m2∙MBq−1∙hr−1 for F18 in patient [1] . Incubation time in a quiet isolated room of FDG patient is 45 minutes. It is assumed that the patient is injected with 555 MBq F18 [1] . Using Equation (3), after 45 minutes, activity A(t) is found to be 420 MBq. Normally, patient scanning time is 30 - 60 minutes. So, t value is taken as 45 minutes. For fully occupied uncontrolled area,

P / T = 1   mSv ⋅ yr − 1 / 1 = 1   mSv ⋅ yr − 1

where, occupancy factor T = 1 [1] .

At 3.5 m distance, with initially 420 MBq in patient, the dose rate is

D • = Γ A r 2 = 0.092   μ Sv ⋅ m 2 / MBq ⋅ h × 420   MBq ( 3.5   m ) 2 = 0.0032   mSv / hr

Assuming 40 PET patients per week and 2080 patients per year, the annual dose D in the office for a 45 min scan is then

D = 2080   pat / yr × 1.44 × 0.0032 mSv / hr × 1.83   hr × ( 1 − e − 0.693 1.83 h × 0.75   hr ) = 4.3   mSv / yr

So, broad beam transmission factors B at 511 keV is

B = 1   mSv ⋅ yr − 1 / 4.3   mSv ⋅ yr − 1 = 0.23

Concrete wall shielding thickness for B value 0.23 is found to be from Table 1 [1] .

2.3. Glass Window Shielding

There is a lead equivalent glass window in between control console and PET-CT room. This glass thickness is calculated from Table 1 for B value 0.23. Considering the buildup factor, an alternative approach can also be in case of lead glass using Equation (4). In lead, B0 value is assumed to be 1 [8] . So from Equation (4), glass thickness t can be found as follows.

B = I I 0 = B 0 × e − μ t = 0.23 ,     ln 0.23 = − μ t , t = − 1.46 − 1.92 = 0.76   cm = 7.6   mm ,     t ≈ 8   mm

where, μ = 1.92   cm − 1 as mentioned earlier [5] .

3. Results

From theoretical calculation as shielding requirement for our PET-CT facility, 11 mm Pb thickness or, 13 cm concrete thickness are found shown in Table 2. Sometimes, theoretical calculations do not meet the practical demand. This may be due to the improper concrete mixing ratio. Though Bangladesh Atomic Energy Regulatory Authority (BAERA) recommends P should be one tenth of public dose for quality assurance but in this calculation public dose (i.e., P = 1 mSv/yr) is used. The formula in Equation (4) is used in shielding calculation only for lead glass not for concrete walls. In this study, only imaging room wall and lead glass shielding requirement have been calculated and all other rooms such as uptake room, hot lab etc. are considered to be parallel of examination room. All walls and ceiling are made of 30.48 cm (1 foot) thick concrete with density 2.35 g∙cm−3 for more safety. Lead equivalent glass of 10 mm thickness is used for windowing purpose in between imaging and control room. But in calculation, 11 mm and 8 mm thickness are found considering transmission and buildup factor respectively. CT portion is ignored in this calculation, because HVL for the CT x-rays is so much smaller than that for 511 keV photons [1] . Entrance wooden door is sandwiched with 4 mm thick lead. Control console and corridor are considered to be controlled area and radiation level should be below

Required thickness values for PET-CT facility design
Sl. No.Parameter nameTechnique usedThickness valueDesigned value
1Concrete barrierTransmission factor13 cm30.48 cm
Buildup factor-
2Lead equivalent glassTransmission factor11 mm10 mm
Buildup factor08 mm

10 µSv/hr according to BAERA regulations. From measurement, radiation levels are found to be near background level.

4. Discussions

In Equation (4), B0 is not needed if the beam is well collimated. In case of PET-CT shielding design, comparatively large thickness is required. So beam geometry is poor and considered to be broad-beam resulting significant number of scattered and back scattered radiation. Therefore, buildup factor B0 is applicable [5] . But using buildup factor, thickness value is not calculated for concrete barrier. In addition with concrete shield design, there are some devices such as syringe shielding, lead apron etc. are also considered as shielding device. Syringe shield reduces the dose rate 25% in hands and fingers in case of PET substances. In Nuclear Medicine, where there are ambient radiation are higher than radiography, lead apron is recommended. It is effective in Tc99m (140 keV) scan. Because 0.25 mm and 0.50 mm lead apron reduce the dose rate 59% and 76% respectively. For higher energies, such as F18 (511 keV), lead apron is in little use. On the other hand, in case of CT, mean photon energy is 1/3 of the tube voltage. Our CT tube voltage is in between 80 - 140 kV, which generate average (26.67 - 46.67) keV photons [9] . So it is a matter of question, either lead apron is necessary or not in case of CT. Health Physics Division of BAEC conducted an extensive radiation survey, especially for CT portion of tof PET-CT facility at INMP and found the doses ranged from 0.07 - 1.58 µSv/hr and 0.30 - 1.21 Bq/cm2 for x-ray radiation dose rate and beta surface activity respectively.

5. Conclusion

PET-CT machine is highly sophisticated imaging device. So the shielding calculation for PET-CT facility is completely different from those of other diagnostic and therapeutic facilities. In this case, the patient itself continuously emits high energy annihilation photon radiation during the whole procedure. In our facility, all shielding walls are made of concrete with thickness more than double of calculated value. The main entrance door is made of 4 mm thick lead sheet which is sandwiched in between two layer of wood. During the machine in operation, radiation survey reports meet our regulatory requirements.

Conflicts of Interest

The authors declare no conflicts of interest regarding the publication of this paper.

Cite this paper

Uddin, M.F., Khatun, R., Akter, S., Jamil, H.M., Monika, A.N., Rahaman, M.A., Das, R.P., Sharmin, R.A., Rahman, M.M. and Ahasan, M.M. (2019) Radiation Shielding Analysis and Design of tof PET-CT Facility at Institute of Nuclear Medical Physics under Bangladesh Atomic Energy Commission, Bangladesh. International Journal of Medical Physics, Clinical Engineering and Radiation Oncology, 8, 1-8. https://doi.org/10.4236/ijmpcero.2019.81001

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