Calculation of electron and isotopes dose point kernels with <scp>fluka</scp> Monte Carlo code for dosimetry in nuclear medicine therapy

Botta, Francesca; Mairani, A.; Battistoni, G.; Cremonesi, Marta; Dia, A. Di; Fassó, A.; Ferrari, A.; Ferrari, Mahila; Paganelli, Giovanni; Pedroli, G.; Valente, M.

doi:10.1118/1.3586038

Cited by 71 publications

(97 citation statements)

References 41 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…With the same number of simulated particles, the accordance between FLUKA and 3D-RD or MCID (table 3) is slightly worse than that between FLUKA and VKC (table 2), probably due to the small differences between the simulation algorithms used by the three codes (FLUKA, EGSnrc, MCNP5) in homogeneous water. In fact, the differences in table 3 are similar to those commonly observed when comparing different simulation algorithms (Botta et al 2011, Uusijarvi et al 2009). When comparing FLUKA DMC and VKC, instead, no differences regarding the simulation algorithm come into play since the voxel kernels for VKC were calculated with FLUKA and with the same simulation parameters as for the DMC simulation.…”

Section: Discussionsupporting

confidence: 77%

“…In addition, FLUKA dose point kernels were calculated in water and bone tissue for both monoenergetic electrons and beta emitting isotopes, and compared to those obtained with other MC codes commonly used for nuclear medicine dosimetry (Botta et al 2011). This latest study showed that the differences between the simulation algorithms of the different codes are not expected to have an impact when performing internal dosimetry at the voxel level.…”

Section: Discussionmentioning

confidence: 99%

See 1 more Smart Citation

Use of the FLUKA Monte Carlo code for 3D patient-specific dosimetry on PET-CT and SPECT-CT images

et al. 2013

View full text Add to dashboard Cite

Patient-specific absorbed dose calculation for nuclear medicine therapy is a topic of increasing interest. 3D dosimetry at the voxel level is one of the major improvements for the development of more accurate calculation techniques, as compared to the standard dosimetry at the organ level. This study aims to use the FLUKA Monte Carlo code to perform patient-specific 3D dosimetry through direct Monte Carlo simulation on PET-CT and SPECT-CT images. To this aim, dedicated routines were developed in the FLUKA environment. Two sets of simulations were performed on model and phantom images. Firstly, the correct handling of PET and SPECT images was tested under the assumption of homogeneous water medium by comparing FLUKA results with those obtained with the voxel kernel convolution method and with other Monte Carlo-based tools developed to the same purpose (the EGS-based 3D-RD software and the MCNP5-based MCID). Afterwards, the correct integration of the PET/SPECT and CT information was tested, performing direct simulations on PET/CT images for both homogeneous (water) and non-homogeneous (water with air, lung and bone inserts) phantoms. Comparison was performed with the other Monte Carlo tools performing direct simulation as well. The absorbed dose maps were compared at the voxel level. In the case of homogeneous water, by simulating 108 primary particles a 2% average difference with respect to the kernel convolution method was achieved; such difference was lower than the statistical uncertainty affecting the FLUKA results. The agreement with the other tools was within 3–4%, partially ascribable to the differences among the simulation algorithms. Including the CT-based density map, the average difference was always within 4% irrespective of the medium (water, air, bone), except for a maximum 6% value when comparing FLUKA and 3D-RD in air. The results confirmed that the routines were properly developed, opening the way for the use of FLUKA for patient-specific, image-based dosimetry in nuclear medicine.

show abstract

Section: Discussionsupporting

confidence: 77%

Section: Discussionmentioning

confidence: 99%

Use of the FLUKA Monte Carlo code for 3D patient-specific dosimetry on PET-CT and SPECT-CT images

et al. 2013

View full text Add to dashboard Cite

show abstract

“…Beyond 10 mm, the dose contribution is nil. X 90 was evaluated from the concentric shells simulation to be 0.533 cm, which compares well with 5.34 mm reported by Simpkin [24] and 5.4 mm reported by Botta [25]. Consequently, this comparison appears to justify the use of simulated kernels in the dose convolution calculations (Figures 4 and 5).…”

Section: Y-90 Dose Point and Dvksupporting

confidence: 77%

Radiolabeled Immunoglobulin Therapy for Patients with Solid Tumors

Khater¹,

Kap²,

Sayah³

et al. 2017

J Nucl Med Radiat Ther

View full text Add to dashboard Cite

“…In this regard, it is crucial to use a Monte Carlo code that provides an event-by-event simulation, as a loss of spatial resolution during particle transport from condensed simulation algorithms (i.e., grouping elastic, inelastic, and radiative events), and underestimation of secondary electrons, have a large effect on energy deposition (23). PENELOPE can perform event-by-event coupled photon-electron transport simulations, thus providing a more accurate estimation of the energy deposition than is possible with other general-purpose Monte Carlo codes (24,25).…”

Section: Discussionmentioning

confidence: 99%

Monte Carlo Evaluation of Auger Electron–Emitting Theranostic Radionuclides

et al. 2015

View full text Add to dashboard Cite

Several radionuclides used in medical imaging emit Auger electrons, which, depending on the targeting strategy, either may be exploited for therapeutic purposes or may contribute to an unintentional mean absorbed dose burden. In this study, the virtues of 12 Auger electron-emitting radionuclides were evaluated in terms of cellular S values in concentric and eccentric cell-nucleus arrangements and by comparing their dose-point kernels. Methods: The Monte Carlo code PENELOPE was used to transport the full particulate spectrum of 67 Pt, and 201 Tl by means of event-by-event simulations. Cellular S values were calculated for varying cell and nucleus radii, and the effects of cell eccentricity on S values were evaluated. Dosepoint kernels were determined up to 30 μm. Energy deposition at DNA scales was also compared with an α emitter, 223 Ra. Results: PENELOPE-determined S values were generally within 10% of MIRD values when the source and target regions strongly overlapped, that is, S(nucleus←nucleus) configurations, but greater differences were noted for S(nucleus←cytoplasm) and S(nucleus←cell surface) configurations. Cell eccentricity had the greatest effect when the nucleus was small, compared with the cell size, and when the radiation sources were on the cell surface. Dose-point kernels taken together with the energy spectra of the radionuclides can account for some of the differences in energy deposition patterns between the radionuclides. The energy deposition of most Auger electron emitters at DNA scales of 2 nm or less exceeded that of a monoenergetic 5.77-MeV α particle, but not for 223 Ra. Conclusion: A single-cell dosimetric approach is required to evaluate the efficacy of individual radionuclides for theranostic purposes, taking cell geometry into account, with internalizing and noninternalizing targeting strategies. The therapeutic rationale for molecularly targeted radiotherapy is the selective delivery of a radionuclide to tumor cells via a targeting moiety, thereby enhancing the therapeutic index of the agent. Several Auger electron-emitting radionuclides have been proposed for molecularly targeted radiotherapy of small metastases and disseminated cancer cells, with some promising clinical results (1-3). These radionuclides are well suited to serving as molecularly targeted radiotherapy agents because of the extremely short range in matter (nanometers to a few micrometers) of the low-energy, intermediate-linear-energy-transfer (LET) Auger and Coster-Kronig electrons they emit (4). These electrons account for high energy deposition in the immediate vicinity of the decay site, and because of their short range, irradiation of normal neighboring cells is limited, thus reducing nonspecific radiotoxicity. In addition, radiation emitted during the nuclear decay can be exploited for imaging purposes either with SPECT (in the case of g rays in the energy range of 70-360 keV or Bremsstrahlung imaging for pure b 2 emitters) or PET (in the case of annihilation photons), thus making Auger electron-emitting ra...

show abstract

Calculation of electron and isotopes dose point kernels with fluka Monte Carlo code for dosimetry in nuclear medicine therapy

Abstract: FLUKA provides reliable results when transporting electrons in the low energy range, proving to be an adequate tool for nuclear medicine dosimetry.

Cited by 71 publications

References 41 publications

Use of the FLUKA Monte Carlo code for 3D patient-specific dosimetry on PET-CT and SPECT-CT images

Use of the FLUKA Monte Carlo code for 3D patient-specific dosimetry on PET-CT and SPECT-CT images

Radiolabeled Immunoglobulin Therapy for Patients with Solid Tumors

Monte Carlo Evaluation of Auger Electron–Emitting Theranostic Radionuclides

Contact Info

Product

Resources

About