Biomedical subjects

M Bardiès

Publications and source records attributed to M Bardiès.

At least 19 recordsLinked to original sources

PubMed2006

Validation of a personalized dosimetric evaluation tool (Oedipe) for targeted radiotherapy based on the Monte Carlo MCNPX code.

Dosimetric studies are necessary for all patients treated with targeted radiotherapy. In order to attain the precision required, we have developed Oedipe, a dosimetric tool based on the MCNPX Monte Carlo code. The anatomy of each patient is considered in the form of a voxel-based geometry created using computed tomography (CT) images or magnetic resonance imaging (MRI). Oedipe enables dosimetry studies to be carried out at the voxel scale. Validation of the results obtained by comparison with existing methods is complex because there are multiple sources of variation: calculation methods (different Monte Carlo codes, point kernel), patient representations (model or specific) and geometry definitions (mathematical or voxel-based). In this paper, we validate Oedipe by taking each of these parameters into account independently. Monte Carlo methodology requires long calculation times, particularly in the case of voxel-based geometries, and this is one of the limits of personalized dosimetric methods. However, our results show that the use of voxel-based geometry as opposed to a mathematically defined geometry decreases the calculation time two-fold, due to an optimization of the MCNPX2.5e code. It is therefore possible to envisage the use of Oedipe for personalized dosimetry in the clinical context of targeted radiotherapy.

Computer Simulation↗

PubMed2005

Dosimetric comparison of Monte Carlo codes (EGS4, MCNP, MCNPX) considering external and internal exposures of the Zubal phantom to electron and photon sources.

This paper aims at comparing dosimetric assessments performed with three Monte Carlo codes: EGS4, MCNP4c2 and MCNPX2.5e, using a realistic voxel phantom, namely the Zubal phantom, in two configurations of exposure. The first one deals with an external irradiation corresponding to the example of a radiological accident. The results are obtained using the EGS4 and the MCNP4c2 codes and expressed in terms of the mean absorbed dose (in Gy per source particle) for brain, lungs, liver and spleen. The second one deals with an internal exposure corresponding to the treatment of a medullary thyroid cancer by 131I-labelled radiopharmaceutical. The results are obtained by EGS4 and MCNPX2.5e and compared in terms of S-values (expressed in mGy per kBq and per hour) for liver, kidney, whole body and thyroid. The results of these two studies are presented and differences between the codes are analysed and discussed.

Computer Simulation↗

PubMed2005

Current developments at IRSN on computational tools dedicated to assessing doses for both internal and external exposure.

The paper presents the OEDIPE (French acronym that stands for tool for personalised internal dose assessment) and SESAME (for simulation of external source accident with medical images) computational tools, dedicated to internal and external dose assessment, respectively, and currently being developed at the Institute for Radiological Protection and Nuclear Safety. The originality of OEDIPE and SESAME, by using voxel phantoms in association with Monte Carlo codes, lies in their ability to construct personalised voxel phantoms from medical images and automatically generate the Monte Carlo input file and visualise the expected results. OEDIPE simulates in vivo measurements to improve their calibration, and calculates the dose distribution taking both internal contamination and internal radiotherapy cases into account. SESAME enables radiological overexposure doses to be reconstructed, as also victim, source and accident environment modelling. The paper presents the principles on which these tools function and an overview of specificities and results linked to their fields of application.

Academies and Institutes↗

PubMed2004

GATE: a simulation toolkit for PET and SPECT.

Monte Carlo simulation is an essential tool in emission tomography that can assist in the design of new medical imaging devices, the optimization of acquisition protocols and the development or assessment of image reconstruction algorithms and correction techniques. GATE, the Geant4 Application for Tomographic Emission, encapsulates the Geant4 libraries to achieve a modular, versatile, scripted simulation toolkit adapted to the field of nuclear medicine. In particular, GATE allows the description of time-dependent phenomena such as source or detector movement, and source decay kinetics. This feature makes it possible to simulate time curves under realistic acquisition conditions and to test dynamic reconstruction algorithms. This paper gives a detailed description of the design and development of GATE by the OpenGATE collaboration, whose continuing objective is to improve, document and validate GATE by simulating commercially available imaging systems for PET and SPECT. Large effort is also invested in the ability and the flexibility to model novel detection systems or systems still under design. A public release of GATE licensed under the GNU Lesser General Public License can be downloaded at http:/www-lphe.epfl.ch/GATE/. Two benchmarks developed for PET and SPECT to test the installation of GATE and to serve as a tutorial for the users are presented. Extensive validation of the GATE simulation platform has been started, comparing simulations and measurements on commercially available acquisition systems. References to those results are listed. The future prospects towards the gridification of GATE and its extension to other domains such as dosimetry are also discussed.

Computer Simulation↗

PubMed2004

New thermoluminescent dosimeters (TLD): optimization and characterization of TLD threads sterilizable by autoclave.

To improve the performance of mono-extruded TLD threads as a dosimetric thermoluminescent tool (French Patent 9903729), a new process was developed by co-extrusion methodology leading to threads of 600 microm diameter with a 50 microm homogeneous polypropylene sheath. In this optimization work, study of parameters such as LiF:Mg,Cu,P powder granulometry, load rate and proportion of components led to an increased sensitivity of around 40%. Moreover, the co-extrusion technique allowed the threads to be sterilized by humid steam (134 degrees C/18 min) without significant variation of the linearity response between 0 and 30 Gy after gamma irradiation (60Co).

Calibration↗

PubMed2002

Correction of count losses due to deadtime on a DST-XLi (SmVi-GE) camera during dosimetric studies in patients injected with iodine-131.

In dosimetric studies performed after therapeutic injection, it is essential to correct count losses due to deadtime on the gamma camera. This note describes four deadtime correction methods, one based on the use of a standard source without preliminary calibration, and three requiring specific calibration and based on the count rate observed in different spectrometric windows (20%, 20% plus a lower energy window and the full spectrum of 50-750 keV). Experiments were conducted on a phantom at increasingly higher count rates to check correction accuracy with the different methods. The error was less than +7% with a standard source, whereas count-rate-based methods gave more accurate results. On the assumption that the model was paralysable, preliminary calibration allowed an observed count rate curve to be plotted as a function of the real count rate. The use of the full spectrum led to a 3.0% underestimation for the highest activity imaged. As count losses depend on photon flux independent of energy, the use of the full spectrum during measurement allowed scatter conditions to be taken into account. A protocol was developed to apply this correction method to whole-body acquisitions.

Calibration↗

PubMed2001

Two-step targeting of xenografted colon carcinoma using a bispecific antibody and 188Re-labeled bivalent hapten: biodistribution and dosimetry studies.

UNLABELLED: Radioimmunotherapy (RIT) is currently being considered for the treatment of solid tumors. Although results have been encouraging for pretargeted 131I RIT with the affinity enhancement system (AES), the radionuclide used is not optimal because of its long half-life, strong gamma emission, poor specific activity, and low beta particle energy. 188Re, though unsuitable for direct antibody labeling, could be used with the AES two-step targeting technique. The purpose of this study was to compare the distribution and dosimetry of a bivalent hapten labeled with 188Re or 125I. For dosimetry calculations and biodistribution data, 125I was substituted for 131I. METHODS: After preliminary injection of a bispecific anticarcinoembryonic antigen (CEA) or antihapten antibody (Bs-mAb F6-679), AG 8.1 or AG 8.0 hapten radiolabeled with 188Re or 125I was injected into a nude mouse model grafted subcutaneously with a human colon carcinoma cell line (LS-174-T) expressing CEA. A dosimetry study was performed for each animal from the concentration of radioactivity in tumor and different tissues. RESULTS: Radiolabeling of AG 8.1 with 125I afforded a 40% yield with a specific activity of 11.1 MBq/nmol after purification. Radiolabeling of AG 8.0 with 188Re afforded a 72% yield with a specific activity of 31.82 MBq/nmol. In all experiments, the percentage of tumor uptake of 125I-AG 8.1 was always significantly greater than that of 188Re-AG 8.0. The corresponding tumor-to-tissue ratios reflected uptake values. The least favorable tumor-to-normal tissue ratios in the dosimetry study were 8.1 and 8.5 for 131I (tumor-to-blood ratio and tumor-to-kidney ratio, respectively) and 2.3 for 188Re (tumor-to-intestine ratio). CONCLUSION: This study indicates that 188Re can be used for radiolabeling of hapten in two-step radioimmunotherapy protocols with the AES technique. 188Re has a greater range than 131I, which should allow the treatment of solid tumors around 1 cm in diameter. Although the method used for hapten radiolabeling did not provide optimal tumor uptake, the use of a bifunctional chelating agent associated with AG 8.1 should solve this problem.

Animals↗

PubMed2000

Production of new thermoluminescent mini-dosimeters.

A method of producing CaSO4:Dy thermoluminescent mini-dosimeters was reported in 1986 by B W Wessels for determination of the in vivo absorbed dose in radioimmunotherapy, a field in which absorbed dose gradients are important. These dosimeters, which undergo dissolution when used in a liquid environment, showed a sensitivity loss of up to 30% after 4 days of immersion in our tests. Moreover, several studies have shown that biocompatibility problems can occur during in vivo studies in animals. This paper describes the production and testing of a new type of thermoluminescent mini-dosimeter obtained by microextrusion of a mixture of LiF:Mg,Cu,P polypropylene and plastic adjuvants. These dosimeters, in the form of long 400 microm diameter filaments, can be cut to the desired length. The production process allows an LiF:Mg,Cu,P load of up to 50%. Results obtained in external irradiation indicate that these new miniature LiF:Mg,Cu,P dosimeters have good sensitivity (about 1.6 times that of CaSO4:Dy mini-TLDs), homogeneous response within a production batch (mean +/-4%), response stability in water (0.7% of variation in sensitivity after 2 weeks of immersion) and stability in aqueous solutions at different pH. LiF:Mg,Cu,P mini-dosimeters appear to be highly promising for internal dosimetry, and evaluation is in progress in animals.

Calcium Sulfate↗

PubMed2000

Dosimetry and microdosimetry of targeted radiotherapy.

Dosimetry in targeted radiotherapy (TR) uses different calculation methods, whose degree of refinement is closely conditioned by the particular objective sought. It is more generally performed to establish a correlation between the quantity of radiation delivered to a target and the biological damage observed or that can be reliably predicted. It can thus be used to optimise treatments and allow comparison of different therapeutic approaches, as well as to study the basic methods of irradiation of biological matter. Two broad types of investigations can be found in the literature: microdosimetric ones (stochastic approaches used to study energy deposits) and macrodosimetric ones (non-stochastic or deterministic approaches). The mathematical formalism is consistent between these two types, and the calculation methods currently used are often similar. This review presents different approaches to the dosimetry of radionuclides used in TR. The introduction defines the general problem, the role of dosimetry in TR and the specific problems raised by targeting (non-uniformity of source distributions). The first part considers the types of calculation methods found in TR in relation to the basic quantities used to represent stochastic energy deposit on a cellular scale. In particular, it compares the formalism and the methods used in microdosimetric or conventional macrodosimetric approches. Although microdosimetry, or even track structure calculations, can provide the basic elements for modelling the absorbed dose process, a simplified dosimetric approach may be adequate to describe the phenomena observed. The scheme proposed by the MIRD committee relates to such an approach and is presented together with other methods allowing the calculation of the mean dose delivered (analytic methods, dose point kernels, Monte-Carlo, etc.). The second part shows the application range for the various methods, providing selected examples of dosimetric approaches in TR on different scales, from the organ (or tissues) to the cell or even DNA, and a brief presentation of bone marrow dosimetry.

Animals↗

PubMed1999

Validation of 213Bi-alpha radioimmunotherapy for multiple myeloma.

The efficacy of radioimmunotherapy (RIT) with beta emitters has been clinically demonstrated in the treatment of refractory forms of lymphoma. Alpha-emitting radionuclides with a short half-life are also good potential candidates for RIT directed at tumor targets easily accessible to radioimmunoconjugate molecules and small enough to benefit from the short range of alpha particles (<100 microm). The purpose of this study was to demonstrate the feasibility of ex vivo purging of multiple myeloma-invaded bone marrow. Tumor cells were targeted by a specific monoclonal antibody (B-B4) coupled to 213Bi by a chelating agent (pentaacetic triamine diethylene p-aminobenzyl acid). The efficacy of alpha-RIT was assessed in vitro by analysis of thymidine incorporation, cell mortality, apoptosis of myeloma cells, and the study of nonspecific irradiation of hematopoietic cell lines not recognized by B-B4-pentaacetic triamine diethylene p-aminobenzyl acid immunoconjugate. High dose-dependent cell mortality of myeloma cells was found with radiolabeled B-B4, and this mortality was total at 30 kBq/10(5) cells. Cells were found in apoptotic state at rates of up to 40% for a dose of 7.4 kBq/10(5) cells. Nonspecific mortality was low compared with specific mortality (up to 1%).

Alpha Particles↗

PubMed1999

Radioimmunotherapy in medullary thyroid cancer using bispecific antibody and iodine 131-labeled bivalent hapten: preliminary results of a phase I/II clinical trial.

The toxicity and therapeutic efficacy of escalating doses of anti-carcinoembryonic antigen x anti-N alpha-(diethylenetriamine-N,N,N',N''-tetraacetic acid)-In bispecific monoclonal antibody (F6-734) and iodine 131-labeled bivalent hapten were determined in a Phase I/II trial. A total of 26 patients with recurrences of medullary thyroid cancer documented by imaging and a rise in serum thyrocalcitonin were enrolled. Twenty to 50 mg of F6-734 and 40-100 mCi of 131I-hapten were injected 4 days apart. Quantitative scintigraphy was performed after the second injection for dosimetry estimations in eight cases. Clinical, biological, and morphological follow-up was carried out for 1 year after treatment. The mean percentage of injected activity per gram of tumor at the time of maximum uptake was 0.08% (range, 0.003-0.26%). The tumor biological half-life ranged from 3 to 95 days, and tumor doses ranged from 2.91 to 184 cGy/mCi. The estimated tumor-to-nontumor dose ratios were 43.8 x 53.4, 29.6 x 35.3, 10.9 x 13.6, and 8.4 x 10.0 for total body, red marrow, liver, and kidney, respectively. Grade III/IV hematological toxicity was observed in seven patients, most of them with bone metastases. Among the 17 evaluable patients, 4 pain reliefs, 5 minor tumor responses, and 4 biological responses with decrease of thyrocalcitonin were observed. Nine patients developed human anti-mouse antibody. Dose-limiting toxicity was hematological, and maximum tolerated activity was 48 mCi/m2 in this group of patients, most of whom had suspected bone marrow involvement. The therapeutic responses observed in patients mainly with a small tumor burden are encouraging for the performance of a Phase II trial with minimal residual disease.

Adolescent↗

PubMed1999

Radioimmunotherapy of small cell lung carcinoma with the two-step method using a bispecific anti-carcinoembryonic antigen/anti-diethylenetriaminepentaacetic acid (DTPA) antibody and iodine-131 Di-DTPA hapten: results of a phase I/II trial.

As small cell lung carcinoma (SCLC) is frequently a widespread disease at diagnosis, highly radiosensitive and often only partially responsive to chemotherapy, radioimmunotherapy (RIT) would appear to be a promising technique for treatment. We report the preliminary results of a Phase I/II trial of RIT in SCLC using a two-step method and a myeloablative protocol with circulating stem cells transplantation. Fourteen patients with proved SCLC relapse after chemotherapy were treated with RIT. They were first injected i.v. with a bispecific (anti-carcinoembryonic antigen/anti-diethylenetriaminepentaacetic acid) monoclonal antibody (20-80 mg in 100 ml of saline solution) and then 4 days later with di-(In-diethylenetriaminepentaacetic acid)-tyrosyl-lysine hapten labeled with 1.48-6.66 GBq (40-180 mCi) of I-131 and diluted in 100 ml of saline solution. In patients receiving 150 mCi or more, circulating stem cells were harvested before treatment and reinfused 10-15 days later. Treatment response was evaluated by CT and biochemical data during the month before and 1, 3, 6, and 12 months after treatment. All patients received the scheduled dose without immediate adverse reactions to bispecific antibody or 1-131 hapten. Toxicity was mainly hematological, with two cases of grade 2 leukopenia and three cases of grade 3 or 4 thrombopenia. Body scanning 8 days after injection of the radiolabeled hapten generally showed good uptake at the tumor sites. Estimated tumor dose was 2.6-32.2 cGy/mCi. Among the 12 patients evaluated to date, we have observed 9 progressions, 2 partial responses (one almost complete for 3 months), and 1 stabilization of more than 24 months. Efficiency and toxicity were dose-related. The maximal tolerable dose without hematological rescue was 150 mCi. These preliminary results are encouraging, and dose escalation is currently continuing to reach 300 mCi. RIT should prove to be an interesting therapeutic method for SCLC, although repeated injections and hematological rescue will probably be required, as well as combination with other treatment modalities.

Aged↗

PubMed1996

Pharmacokinetics and biodistribution of samarium-153-labelled OC125 antibody coupled to CITCDTPA in a xenograft model of ovarian cancer.

The use of samarium-153 in the context of radioimmunotherapy of cancers has been limited by the instability of antibody labelling, which produces high uptake concentrations in liver and bone. This study compares the pharmacokinetics and biodistribution of 153Sm-labelled OC125 monoclonal antibody, in whole or F(ab')2 fragment form and with diethylene triamine penta-acetic acid (DTPA) or 6-p-isothiocyanatobenzyl diethylene triamine penta-acetic acid (CITCDTPA) coupling, in nude mice grafted subcutaneously with an ovarian adenocarcinoma line (SHIN-3) expressing CA125 antigen. The specific activity of the immunoconjugates was 18.5-55.5 MBq/mg, and their immunoreactivity exceeded 65%. With 153Sm-DTPA-OC125F(ab')2, the stability study in serum indicated that 50% of the metal remained bound to the antibody. The pharmacokinetic study showed a retention half-life of 25.1 h and blood clearance of 0.72 ml/h. The biodistribution study indicated tumour uptake of 4.53%+/-0.49% of injected activity per gram (%ID/g) at 24 h and tumour-to-liver and tumour-to-bone ratios of 0.23+/-0.02 and 1.54+/-0.49 respectively at 24 h. With 153Sm-CITCDTPA-OC125F(ab')2, serum stability was greater (87% of the metal remaining bound to the antibody), retention half-life was 22.25 h and blood clearance was 2.23 ml/h. Tumour was better targeted (8.30%+/-3.56%ID/g at 24 h), and tumour-to-liver and tumour-to-bone ratios were 1.17+/-0.36 and 7.08+/-3.09 respectively at 24 h. However, renal retention remained elevated (29.76%+/-9. 41%ID/g at 24 h). With intact IgG, renal uptake decreased (1.41%+/-0. 49%ID/g at 24 h), but tumour uptake was lower than with fragments (1. 46%+/-0.58%ID/g at 24 h). Liver uptake was higher (tumour-to-liver ratio 0.10+/-0.05), and blood clearance was slower. The stability and distribution of 153Sm-CITCDTPA were more favourable than those of 153Sm-DTPA for application in radioimmunotherapy. Quantitative analysis performed using digitized images obtained by conventional autoradiography and the imaging plate system indicated that the latter system is suitable for biodistribution studies of immunoconjugates.

Animals↗

PubMed1996

Computational methods in radionuclide dosimetry.

The various approaches in radionuclide dosimetry depend on the size and spatial relation of the sources and targets considered in conjunction with the emission range of the radionuclide used. We present some of the frequently reported computational techniques on the basis of the source/target size. For whole organs, or for sources of targets bigger than some centimetres, the acknowledged standard was introduced 30 years ago by the MIRD committee and is still being updated. That approach, based on the absorbed fraction concept, is mainly used for radioprotection purposes but has been updated to take into account the dosimetric challenge raised by therapeutic use of vectored radiopharmaceuticals. At this level, the most important computational effort is in the field of photon dosimetry. On the millimetre scale, photons can often be disregarded, and beta or electron dosimetry is generally reported. Heterogeneities at this level are mainly above the cell level, involving groups of cell or a part of an organ. The dose distribution pattern is often calculated by generalizing a point source dose distribution, but direct calculation by Monte Carlo techniques is also frequently reported because it allows media of inhomogeneous density to be considered. At the cell level, alpha and electron (low-range beta or Auger) are the predominant emissions examined. Heterogeneities in the dose distribution are taken into account, mainly to determine the mean dose at the nucleus. At the DNA level, Auger electrons or alpha-particles are considered from a microdosimetric point of view. These studies are often connected with radiobiological experiments on radionuclide toxicity.

Beta Particles↗

PubMed1996

Pre-clinical and clinical studies of two new bifunctional chelating agents for immunoscintigraphy with 111In-anti-CEA monoclonal antibody.

Anti-CEA F(ab')2 monoclonal antibody fragments [F6 MAb F(ab')2] were conjugated to two bifunctional semi-rigid chelating agents derived from trans-1,2-diaminocyclohexane tetraacetic acid (CDTA), the monolithium salt of N-[methyl(2-isothiocyanatoethyl)carbamide] trans-1,2-diaminocyclohexane-N,N',N'-triacetic acid (SCN), and 4 isothiocyanato-trans-1,2-diaminocyclohexane-N,N,N',N'-tetraacetic acid (4-ICE) and labelled with 111In to obtain IIIIn-labelled-F6 MAb F(ab')2 conjugates (111In-F6-SCN and 111In-F6-4-ICE respectively). Biodistribution in mice and clinical studies were undertaken to assess the potential of these two ligands in the detection of colorectal adenocarcinoma recurrences and metastases in humans. Toxicity studies were carried out on guinea pigs and Swiss mice injected with a dose proportionally 100 times greater than that used in human studies. Clinical studies were performed in patients with clinically and/or biologically suspected adenocarcinoma recurrences. No immunoconjugate-induced toxicity was found. The biodistribution studies in mice gave better visualization of tumour sites with 111In-F6-SCN and 111In-F6-4-ICE than with 111In-F6-DTPA. Ten patients were included in the clinical protocol. 111In-F6-SCN and 111In-F6-4-ICE effectively visualized adenocarcinoma recurrences. However, in this small series, 111In-F6-4-ICE performed somewhat better than 111In-F6-SCN. The present study has demonstrated the potential of new bifunctional semi-rigid chelating agents coupled to antibody and labelled with 111In to localize recurrences (especially in liver) in humans using a one-step targeting method.

Adenocarcinoma↗

PubMed1996

Bispecific antibody and iodine-131-labeled bivalent hapten dosimetry in patients with medullary thyroid or small-cell lung cancer.

UNLABELLED: The purpose of this study was to estimate the dose delivered to tumor targets and normal tissues after two-step injection of an anti-CEA/anti-DTPA-In (F6-734) bispecific antibody and a 131I-labeled di-DTPA in-TL bivalent hapten in patients with medullary thyroid carcinoma (MTC) and small-cell lung cancer (SCLC). METHODS: Five patients with persistent disease or recurrences of MTC and five patients with primary SCLC or relapse were studied. In a first step, 0.1 to 0.3 mg/kg of F6-734 bispecific antibody was injected intravenously. Four days later, 6 nmole (5.8 to 9.8 mCi) of 131I-labeled di-DTPA in-TL bivalent hapten were injected. Quantitative imaging was performed during one week after the second injection. RESULTS: All 5 patients with MTC showed positive immunoscintigraphy (IS). In the smallest visualized and resected tumor (0.8 g), the fraction of injected activity per gram (% ID/g) was 0.1% at Day 3. IS was positive in 4 of the 5 patients with SCLC. The volume of the smallest visualized SCLC tumor was estimated at 11 +/- 2 ml, and tumor uptake was about 0.009% ID/g. Tumor dose estimates ranged from 4.2 to 174 cGy/mCi in patients with MTC and from 1.7 to 8 cGy/mCi in patients with SCLC. CONCLUSION: High absorbed dose values were calculated for small MTC recurrences. For SCLC recurrences the values were smaller but in the same range as those obtained by other investigators with the one-step technique in lymphoma.

Antibodies, Bispecific↗

PubMed1995

Relationships between tumor size and curability for uniformly targeted therapy with beta-emitting radionuclides.

UNLABELLED: Targeted radionuclide therapy is a new form of radiotherapy that differs in some important respects from external beam irradiation. One of the most important differences is due to the finite range of ionizing beta particles emitted as a result of radionuclide disintegration. The effects of particle range have important implications for the curability of tumors. METHODS: We used a mathematical model to examine tumor curability and its relationship to tumor size for 22 beta-emitting radionuclides that may have therapeutic potential. The model assumed a uniform distribution of radionuclide throughout. RESULTS: For targeted radionuclide therapy, the relationship between tumor curability and tumor size is different from that for conventional external beam radiotherapy. With targeted radionuclides, there is an optimal tumor size for cure. Tumors smaller than the optimal size are less vulnerable to irradiation from radionuclides because a substantial proportion of the disintegration energy escapes and is deposited outside the tumor volume. CONCLUSION: We found an optimal tumor size for radiocurability by each of the 22 radionuclides considered. Optimal cure diameters range from less than 1 mm for short-range emitters such as 199Au and 33P to several centimeters for long-range emitters such as 90Y and 188Re. The energy emitted per disintegration may be used to predict optimal cure size for uniform distributions of radionuclide.

Beta Particles↗

PubMed1994

Absorbed doses for internal radiotherapy from 22 beta-emitting radionuclides: beta dosimetry of small spheres.

We calculated the mean absorbed fractions, specific absorbed fractions and mean doses per unit of cumulated activity in source spheres 10 microm-2 cm in radius for 22 beta-emitting radionuclides potentially useful in radioimmunotherapy. We considered two models of radionuclide distribution, either uniform at the surface of the source or throughout its volume. For each model, we calculated both the absorbed fractions in the spherical segments composing the source and the mean absorbed fractions. For surface distribution, we calculated the mean dose per unit of cumulated activity for a concentric sphere with a small radius (5 microm) in order to determine the minimal dose delivered to the target. Calculations were performed using point kernels for monoenergetic emissions and then integrated into the beta spectra of the different emitters (32p, 33p, 47Sc, 67Cu, 77As, 90Y, 105Rh, 109Pd, 111Ag, 121Sn, 131I, 142Pr, 143Pr, 149Pm, 153Sm, 159Gd, 166Ho, 177Lu, 186Re, 188Re, 194Ir and 199Au). Monoenergetic emissions were taken into account. Results are reported in the form of tables to facilitate use during dosimetric studies for radioimmunotherapy. An application is presented showing the potential utility of associating emitters with different energies in order to sterilize a range of tumour targets of variable size.

Algorithms↗