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C.390

ACCURATE MONTE CARLO MODELING OF AN ACTIVITY METER USING

FLUKA

F. Zagni

* , a ,

A. Evandri

a ,

G. Cicoria

a ,

A. Infantino

b ,

S. Vichi

b ,

M.P. Morig

i c ,

M. Marengo

a .

a

Medical Physics Department, University Hospital ‘S.Orsola-

Malpighi’, Bologna, Italy;

b

Montecuccolino Nuclear Engineering Laboratory,

Department of Industrial Engineering, University of Bologna, Bologna, Italy;

c

Department of Physics and Astronomy, University of Bologna, Bologna, Italy

Introduction:

Monte Carlo codes for simulations of radiation physics ex-

periments are nowadays well suited for the low-energy range, such as for

medical physics applications. In this work we developed and validated the

model of one of the world’s most diffused radionuclide activity meters, a

Capintec CRC-15, using FLUKA.

Materials and Methods:

The main geometrical elements and materials of

the ionizing chamber were modeled. Thickness and position of internal com-

ponents were evaluated through both direct measurements of external

dimensions and CT/X-ray imaging. For validation, a set of reference sources

was used: 137Cs (22.7

±

1.5% MBq), 133Ba (1.3

±

1.5%), 131I (100

±

1.5%),

177Lu (196

±

1.0%), 68Ge “mock 18F” (7.5

±

1.65%), 57Co (35

±

3.0%). For each

source, container and filling were suitably modeled as well as the nu-

clides’ full decay schemes. Calibration factors could be evaluated based on

the energy deposited in the Argon gas. Simulation results (statistical

error

<

1%) were normalized to the response of the modeled 137Cs source.

The sensitivity–source position dependence was also assessed in a range

of 15 cm.

Results:

A high accuracy energy–response curve was calculated, as well

as the sensitivity–position curve (maximum discrepancy

<

4%). The ratios

between simulated and measured relative responses were: 133Ba 1.00

±

0.03,

68Ge 1.01

±

0.03, 131I 0.98

±

0.03, 177Lu 1.03

±

0.03, 57Co 0.97

±

0.04.

Conclusion:

An accurate model of a widely diffuse activity meter has been

validated for a variety of gamma-emitting nuclides, covering a wide range

of energies and source positions, showing discrepancies below 3% for all

cases. Monte Carlo simulations proved to be a powerful tool for assess-

ment of activity meter’s calibration factors for radionuclides used in

radiopharmacy, in particular for very short lived or non conventional, re-

search radionuclides, and for the easy assessment of geometrical correction

factors.

http://dx.doi.org/10.1016/j.ejmp.2016.01.396

C.391

EXPERIENCE WITH ALPHA RADIATION THERAPY: PRELIMINARY

PHYSICAL ASSESSMENT ON USING RA-223

F. Zenone

* , a ,

C. Gasperi

a ,

A. Baldoncini

b ,

G. Belli

a .

a

UOC Fisica Sanitaria,

AUSL8, Arezzo, Italy;

b

UOC Medicina Nucleare, AUSL8, Arezzo, Italy

Introduction:

We report our experience in two multi-center trials using

Ra-223 to treat prostate cancer related metastasis.

Evaluation of authorized limits for detention of Ra-223, setting the dose

calibrator, radioprotection and waste management, and control of double-

blind (drug vs. placebo) in one of the trials are addressed.

Materials and Methods:

Ra-223, mainly alpha-emitter with few gamma

(t1/2

=

11 d), is allotted in 6 mL vials of chloride solution (1 MBq/mL).

The activity limit required for license was estimated accounting on dosage

(50 kBq/kg, every 4 weeks for 6 cycles) and patients planned.

Activity measures are performed with dose calibrator by detecting gamma

emission. It is set by varying its response until it fits the activity of a trace-

able NIST reference source, repeating the procedure 10 times in 3 days.

A spreadsheet calculates the volume to be used based on patient’s weight

and time of injection, also compares the decay correction with that esti-

mated from the producer.

Despite operator’s exposure is low (whole body dose

=

0.4 μSv/pz; hands

equivalent dose

=

200 μSv/pz), we use lead syringe cover, due to gamma

rays, and shielded cell of manipulation for little release of Rn-219.

The analysis system of liquid waste from patients, who are treated in day-

hospital, was also tested to discharge Ra-223 into the sewage in exemption.

To ensure the double-blind, treatments are registered as hidden to RIS.

Results:

Based on patient weight and early delivery of drug (even 10 days)

two vials are shipped. About 50% of the drug, which is patient-specific, has

not been used.

Calibrator accuracy showed an agreement within 1%.

The two methods of decay correction differ by 0.7% at calibration time, and

by

±

1.5% maximum in a working day.

Conclusions:

The excess of drug supplied increases the activity held daily.

Such aspects must be taken into account for both the request of clearance

and waste management.

It is important to plan the number of patients, the dates of injection and

the limits of authorization.

http://dx.doi.org/10.1016/j.ejmp.2016.01.397

C.392

PHYSICAL PERFORMANCE OF CLEARPEM, A DEDICATED SCANNER FOR

POSITRON EMISSION MAMMOGRAPHY

A. Zorz

* , a ,

S. Morzenti

a ,

M. Pizzichemi

b ,

E. De Ponti

a ,

L. Guerr

a c ,

C. Landoni

d ,

E. De Bernardi

d ,

E. Auffray

e ,

R. Bugalho

f ,

J.C.R. Da Silv

a f ,

S. Tavernier

f , g ,

J. Varela

f ,

P. Lecoq

e ,

M. Paganoni

b ,

A. Crespi

a .

a

A.O. San Gerardo, S.C. Fisica

Sanitaria, Monza, Italy;

b

Dipartimento di Fisica, Università degli Studi di Milano

Bicocca, Milano, Italy;

c

A.O. San Gerardo, S.C. Medicina Nucleare, Monza, Italy;

d

Dipartimento di Medicina e Chirurgia, Università degli Studi di Milano Bicocca,

Milano, Italy;

e

CERN, Ginevra, Switzerland;

f

LIP, Lisbona, Portugal;

g

VRIJE

Universiteit Brussels, Brussels, Belgium

Introduction:

ClearPEM is a positron emission mammography (PEM) pro-

totype scanner developed within the framework of the Crystal Clear

Collaboration. It consists of two planar detector heads (16

×

18 cm

2

) mounted

on a dedicated gantry that can rotate to perform breast tomographic ac-

quisition; head distance can be adjusted to fit patient’s breast that hangs

out of a circular aperture in the scanner bed. Moreover, gantry can rotate

to 90° in order to perform planar axillary lymph node examinations. It is

equipped with 6144 LYSO:Ce crystal of 2

×

2

×

20 mm

3

; each side of a 32

crystal matrix is optically coupled to a 32-pixel Hamamatsu S8550 Ava-

lanche Photo-Diode array (APDs), allowing the estimation of the Depth of

Interaction information. A MLEM list-mode reconstruction algorithm is

implemented.

Material and Methods:

The following guidelines are used to establish an

acceptance protocol: NEMA NU-1 for gamma camera, NEMA NU-2 for PET

and NEMA NU-4 for small animal PET. Measure of energy, time and spatial

resolution, count rate performance, sensibility, uniformity and image quality

are evaluated to characterize the scanner.

Results:

Energy resolution at 511 keV is 14%, temporal resolution is 2.8 ns.

Scanner response is linear below an activity of 45 MBq, compatible with

its clinical use. Spatial resolution evaluated with an Na-22 point source is

about 2 mm; in an Ultra Micro Phantom (Data Spectrum) it is possible to

distinguish the 1.35 mm insert. Sensitivity with an Na-22 point source is

2.8 cps/kBq in the center of the FOV. Integral tomographic uniformity is

16% for ROI 95% and 12% for ROI 75%. Image quality is performed with the

Micro Hollow Sphere phantom (Data Spectrum) with a signal to back-

ground ratio of 10:1; contrast is 33%, 24%, 13% and 6% for sphere diameter

of 7.8, 6, 5 and 4 mm respectively.

Conclusion:

Acceptance test protocol for a PEM scanner has been estab-

lished. ClearPEM shows a particularly good spatial resolution, whereas

uniformity and sensitivity have to be optimized.

http://dx.doi.org/10.1016/j.ejmp.2016.01.398

e115

Abstracts/Physica Medica 32 (2016) e97–e115