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Sven-Erik Strand

Publications and source records attributed to Sven-Erik Strand.

11 recordsLinked to original sources

Change in tumor-absorbed dose due to decrease in mass during fractionated radioimmunotherapy in lymphoma patients.

PURPOSE: In radionuclide therapy, cumulated activity and tumor volume/mass are the principal quantities necessary for the calculation of the absorbed dose to the tumor. When treating a fast-responding macroscopic tumor, there may be a decrease in its mass during therapy, and at any given uptake, this will result in an increase in the absorbed dose. The purpose of the present work is to demonstrate the limitations in current internal dosimetry protocols that assume a fixed tumor mass in lymphoma patients, using a fractionated radioimmunotherapy schedule and using a single infusion. EXPERIMENTAL DESIGN: Patients with B-cell lymphoma were treated with (90)Y-labeled epratuzumab (Immunomedics, Inc., Morris Plains, NJ) using a weekly dose-fractionation schedule for 2-4 weeks. They received either 185 MBq/m(2) (5 mCi/m(2)) in each infusion or, if they had a history of high-dose chemotherapy with stem cell rescue, 92.5 MBq/m(2) (2.5 mCi/m(2)) in each infusion. All patients received (111)In-labeled epratuzumab with the first infusion to verify tumor targeting and for dosimetry. The present report is based on three selected patients, in whom repeated assessments of tumor mass were possible. In two patients, (111)In-labeled epratuzumab was also coadministered with one of the subsequent treatments, i.e. during the second and third of two and three scheduled infusions. The tumor volume was determined from computer tomography images obtained before the first infusion and on different times after the infusion. An exponential equation was fitted to the decreasing mass of the tumor and implemented in the calculation of the absorbed dose. For comparison, the absorbed dose to the tumor was also calculated using the tumor volume determined from the baseline pretreatment computer tomography examination. RESULTS: The tumor volume for the patients changed rapidly. For one patient, the pretreatment volume was 19.5 ml, and for another patient, it was 840 ml. For these two patients, the ratio of tumor volume at the beginning of therapy compared with that after 8 days and 14 days of therapy was 0.7 and 0.8, respectively. This rapid decrease in volume and subsequent mass reduction result in an increase of mean absorbed dose to the tumor of as much as a factor of 1.75. CONCLUSIONS: At a given activity uptake, a decrease in tumor mass during therapy will significantly increase the calculated absorbed dose. Taking the change in tumor mass into account when calculating absorbed dose may improve the correlation between the mean absorbed dose to the tumor and the response to the therapy.

Antibodies, Monoclonal↗

3D absorbed dose calculations based on SPECT: evaluation for 111-In/90-Y therapy using Monte Carlo simulations.

A general method is presented for patient-specific three-dimensional (3D) absorbed dose calculations based on quantitative SPECT activity measurements. The computational scheme includes a method for registration of the CT study to the SPECT image, and compensation for attenuation, scatter, and collimator-detector response including septal penetration, performed as part of an iterative reconstruction method. From SPECT images, the absorbed dose rate is calculated using an EGS4 Monte Carlo code, which converts the activity distribution to an absorbed dose rate distribution. Evaluation of the accuracy in the activity quantification and the absorbed dose calculation is based on realistic Monte Carlo simulated SPECT data of a voxel-computer phantom and (111)In and (90)Y. Septal penetration was not included in this study. The SPECT-based activity concentrations and absorbed dose distributions are compared to the actual values; the results imply that the corrections for attenuation and scatter yield results of high accuracy. The presented method includes compensation for most parameters deteriorating the quantitative image information. Inaccuracies are, however, introduced by the limited spatial resolution of the SPECT system, which are not fully compensated by the collimator-response correction. The proposed evaluation methodology may be used as a basis for future inter-comparison of different dosimetry calculation schemes.

Humans↗

Biotinylation, pharmacokinetics, and extracorporeal adsorption of humanized MAb 111In-MN14 using an avidin-affinity column in rats.

UNLABELLED: Extracorporeal adsorption (ECAT) reduces toxicity in radiosensitive organs by removing excess of biotinylated and radiolabeled MAb from unseparated blood in an avidin-agarose column. AIM: To investigate the influence of biotinylation on pharmacokinetics and biodistribution of humanized MAb (111)In-MN14 and to validate the effect of subsequent ECAT on activity reduction in the whole body, in blood, and in various organs after i.v. administration of biotinylated (111)In-hMN14 in rats. METHODS: Humanized MAb MN14 recognizes the carcinoembryonic antigen. Ninety-three rats were used. (111)In-hMN14-DOTA was biotinylated using NHS-biotin or Sulfo-NHS-biotin enabling antibodies to be absorbed on the avidin-agarose column. Eight rats underwent ECAT, which implied that three blood volumes were passed through the column during 2.5 h. Whole body counts and blood activity were monitored. At dissections, organs of interest were removed and measured for activity-content. RESULTS: HPLC showed signs of fragmentation at a low ratio of NHS-biotin/mg of MAb. No fragmentation or aggregation was observed using sulfo-NHS-biotin. When ECAT started at 6 h p.i., whole body and blood activity were reduced by 64% and 98%, respectively. The uptake in organs sensitive to radiation was also reduced, varying between 39% for the liver and 84% for the lungs and bone marrow. CONCLUSIONS: (111)In-hMN14 can be safely biotinylated using sulfo-NHS-biotin without significantly affecting antigenicity and biodistribution of the antibody. ECAT based on avidin-biotin concept effectively removed biotinylated (111)In-hMN14 from blood circulation and reduced activity in radiosensitive organs.

Absorption↗

Crypt cell dosimetry for 99Tcm-sestamibi in a new small intestinal dosimetry model.

The aim of the study was to calculate the absorbed dose to the crypt cells in the small intestine from (99)Tc(m)-sestamibi excreted through the intestinal tract. The absorbed dose was calculated taking into consideration the biodistribution of the radiopharmaceutical in the small intestinal wall and its contents, based on data gathered in rats. Absorbed dose calculations were performed using a new intestinal model in which S values for crypt cells are given both for the intestinal wall and for the intestinal contents as source organs. A maximum of 6% of the injected activity was found to be located in the intestinal wall at 30 minutes after injection and 13% in the intestinal contents at 2 h, resulting in an absorbed dose of 8.9 microGy/MBq to the crypt cells. Assuming the activity to be located only in the wall, we calculate an absorbed dose to the crypt cells 2.5 times higher than if all the activity is assumed to be present in the intestinal contents. Using the new intestinal dosimetry model, together with detailed biokinetic data for the radiopharmaceutical from animal studies, it is possible to calculate the absorbed dose to the crypt cells, which is not possible when using external imaging.

Animals↗

Time dependence of the activity concentration ratio of red marrow to blood and implications for red marrow dosimetry.

BACKGROUND: The method for red marrow dosimetry in radioimmunotherapy, in the absence of specific activity uptake in red marrow, is based on the activity measured in the blood or plasma. The activity concentration ratio of red marrow to blood is then assumed to be constant. The aim of the current study was to determine whether this ratio varies with time after injection. METHODS: Measurements were carried out with both animals and patients.Tumor-bearing rats were intravenously injected with iodine-131-, iodine-125-, indium-111-, or rhenium-188-labeled BR96, a chimeric immunoglobulin G1 monoclonal antibody. (All were chelate-labeled, except for iodine-131, which was iodogen-labeled.) Measurements were made of the activity concentration in blood and bone marrow at different points in time after injection, and the ratio of activity concentration in red marrow and blood as a function of time postinjection (RMBLR[t)]) was calculated. For patients treated with iodine-131-labeled monoclonal antibody (LL2, Immunomedics Inc., Morris Plains, NJ; anti-CD22; immunoglobulin G2 isotype of mouse origin), blood samples were drawn and scintillation camera images taken at different times after injection. The red marrow activity concentration in the sacrum was determined by activity quantification from regions of interest. The activity concentration in blood was also measured. The RMBLR(t) was calculated based on these data. RESULTS: For both patients and rats, the RMBLR(t) was increased 72 hours after injection. Furthermore, it was found that the use of a constant RMBLR can lead to an over- or underestimation of the absorbed dose in bone marrow. CONCLUSIONS: These data demonstrate the difficulty in using fixed values of the activity concentration ratio of red marrow to blood for dosimetry.

Animals↗

Single tumor cell uptake and dosimetry of technetium-99m Fab' or minute anti-CD22 in low-grade B-cell lymphoma.

BACKGROUND: A patient with follicular lymphoma was investigated with 0.5 mg Fab' or minute anti-CD22 labeled with 1100 MBq technetium-99m ((99m)Tc). A computed tomography scan performed a week later revealed regression. This unexpected response prompted an investigation of single cell dosimetry of low-energy electron emitters. METHODS: Another patient with low-grade, unclassifiable B-cell lymphoma with a low expression of CD22 was injected with (99m)Tc anti-CD22. Blood samples were drawn 30 minutes, 4 hours, and 24 hours after injection. Lymphoma cells (CD19+) and T cells (CD3+), which served as control cells, were separated using a flow cytometer. The radioactivity of the two cell populations was measured in an NaI(Tl) well-type detector. The mean uptake per cell and absorbed dose were calculated. The CD22 expression of the patient's cells and of a B-cell lymphoma cell line (Raji) were assessed by flow cytometry for the extrapolation of the absorbed dose from the patient's cells to a cell line with higher CD22 expression. RESULTS: The average number of (99m)Tc atoms per CD19+ and CD3+ cell 4 hours postinjection were 5.4 and 0.054, respectively. Depending on the assumed ratio between antibody and CD22 molecules (1:2 or 1:1), the CD22 expression on the patient's cells and Raji cells varied from 2800 to 5700 and from 37,000 to 74,000 per cell, respectively. The average absorbed dose per cell ranged from 4 x 10(-7) to 0.1 grays (Gy). CONCLUSIONS: It seems feasible to assess the mean single tumor cell uptake of (99m)Tc targeted by Fab' or minute anti-CD22 in a patient's lymphoma using sorted cell populations, thereby allowing single cell dosimetry. Extrapolation of the absorbed dose from (99m)Tc to cells with higher CD22 expression was made and under certain conditions absorbed doses of 0.1 Gy were obtained, indicating the potential relevance of low-energy electron emitters to therapy.

Antigens, CD↗

Application of extracorporeal immunoadsorption to reduce circulating blood radioactivity after intraperitoneal administration of indium-111-HMFG1-biotin.

BACKGROUND: Extracorporeal immunoadsorption (ECAT) is a method of reducing activity in radiosensitive organs by removing excess monoclonal antibodies (MAbs) from the blood. Previously, the authors experimentally evaluated ECAT based on the avidin-biotin concept after intravenous administration of radioimmunoconjugates. The aim of the current study was to determine whether ECAT could be used to reduce activity after intraperitoneal (i.p.) administration of indium-111((111)In)-HMFG1-biotin in rats, and to compare the pharmacokinetics of (111)In-HMFG1 with or without attached biotin after i.p. injection. METHODS: HMFG1, a murine immunoglobulin G(1) MAb that recognizes an epitope on the polymorphic epithelial mucin (PEM) antigen, was labeled with (111)In and then biotinylated. ECAT was explored from unseparated blood using an avidin-agarose adsorption column. Thirty rats were used as controls and 13 underwent ECAT. The whole-body (WB), blood, and organ activity were monitored. RESULTS: The binding capacity of (111)In-HMFG1-biotin to avidin was high. Biotinylation did not enhance the excretion of HMFG1. When ECAT was employed, the WB and blood radioactivity were reduced by 35-40% (P < 0.05) and 75--86% (P < 0.01), respectively. After the completion of ECAT, the activity uptake in organs was significantly decreased. CONCLUSIONS: ECAT was successfully applied after i.p. injection of the (111)In-HMFG-biotin MAb to reduce the radioactivity in the WB, blood, and radiosensitive organs. Due to redistribution of the radiolabeled MAbs during and after the completion of ECAT, the adsorption may have been prolonged or repeated. Biotinylation did not significantly change the biodistribution of the (111)In-HMFG1 in rats after intraperitoneal injection.

Animals↗

131I-labelled anti-CD22 MAb (LL2) in patients with B-cell lymphomas failing chemotherapy. Treatment outcome, haematological toxicity and bone marrow absorbed dose estimates.

The experience with radioimmunotherapy in B-cell lymphomas using the rapidly internalizing antibody, anti-CD22 (LL2), is limited. In this study we investigated the efficacy and toxicity of 131I-labelled-LL2 for radioimmunotherapy in patients with B-cell lymphomas that failed one or two cytostatic regimens. Eleven patients were treated with one or repeated cycles of 131I-anti-CD22 antibody, 1330 MBq/m2 (36 mCi/m2). Six of the 11 treated patients demonstrated an objective response, three of them with complete remission. All follicular (3 patients) and transformed lymphomas (2 patients) responded compared to one of four diffuse large B-cell lymphomas. Two out of six responders exhibited event-free survival (EFS), which was comparable with or longer than the EFS following primary anthracycline-containing chemotherapy. Non-haematological toxicity was mild. Haematological toxicity was associated with pretreatment clinical characteristics but not with estimated absorbed bone marrow doses. Objective remission following treatment with 131I-anti-CD22 can be achieved in patients with various subtypes of B-cell lymphomas, failing standard chemotherapy. Follicular or transformed lymphomas seem particularly responsive. Haematological toxicity seems to be dependent on the functional status of the bone marrow before radioimmunotherapy.

Adult↗

An activity quantification method based on registration of CT and whole-body scintillation camera images, with application to 131I.

UNLABELLED: This article presents a new method for conjugate view activity quantification for 131I-labeled monoclonal antibody distribution. METHODS: The method is based on the combined use of images from 3 modalities: whole-body (WB) scintillation camera scanning, WB transmission scanning using 57Co, and CT. All images are coaligned using a recently developed program for the registration of WB images. Corrections for attenuation, scatter, and septal penetration are performed in image space. Compensation for scatter and septal penetration is performed by deconvolution, using point-response functions determined from Monte Carlo simulations. Attenuation correction is performed by applying a patient-specific 364-keV narrow-beam attenuation map obtained by combining information from the CT and the transmission scan. A relationship is presented for the conversion of the CT numbers to mass density. The attenuation- and scatter-compensated image is converted from counts to activity using a sensitivity value that was determined for 364-keV photons in air. This activity projection image is then analyzed for the activity of volumes of interest (VOI) using 2-dimensional regions of interest (ROIs) that are determined from the CT study. The CT is first resliced into coronal slices, and a maximum-extension ROI is outlined that encloses the VOI. Compensation for background activity and overlapping organs is performed on the basis of total patient thickness in the projection line, and on precalculated organ- background thickness fractions. RESULTS: Method evaluation was performed using data from both experimental measurements and Monte Carlo simulations. The use of an attenuation map derived directly from the CT study was also evaluated. For organ activity quantification, an accuracy of > or =10% was obtained. For small-diameter tumors, deviations were larger because of lack of correction for the background-dependent partial-volume effect. CONCLUSION: Registration of CT and WB scintillation camera images was successfully applied to improve activity quantification by the conjugate view method.

Antibodies, Monoclonal↗

A 3-dimensional absorbed dose calculation method based on quantitative SPECT for radionuclide therapy: evaluation for (131)I using monte carlo simulation.

UNLABELLED: A general method is presented for patient-specific 3-dimensional absorbed dose calculations based on quantitative SPECT activity measurements. METHODS: The computational scheme includes a method for registration of the CT image to the SPECT image and position-dependent compensation for attenuation, scatter, and collimator detector response performed as part of an iterative reconstruction method. A method for conversion of the measured activity distribution to a 3-dimensional absorbed dose distribution, based on the EGS4 (electron-gamma shower, version 4) Monte Carlo code, is also included. The accuracy of the activity quantification and the absorbed dose calculation is evaluated on the basis of realistic Monte Carlo-simulated SPECT data, using the SIMIND (simulation of imaging nuclear detectors) program and a voxel-based computer phantom. CT images are obtained from the computer phantom, and realistic patient movements are added relative to the SPECT image. The SPECT-based activity concentration and absorbed dose distributions are compared with the true ones. RESULTS: Correction could be made for object scatter, photon attenuation, and scatter penetration in the collimator. However, inaccuracies were imposed by the limited spatial resolution of the SPECT system, for which the collimator response correction did not fully compensate. CONCLUSION: The presented method includes compensation for most parameters degrading the quantitative image information. The compensation methods are based on physical models and therefore are generally applicable to other radionuclides. The proposed evaluation methodology may be used as a basis for future intercomparison of different methods.

Humans↗

A dosimetry model for the small intestine incorporating intestinal wall activity and cross-doses.

UNLABELLED: Current internal radiation dosimetry models for the small intestine, and for most walled organs, lack the ability to account for the activity uptake in the intestinal wall. In existing models the cross-dose from nearby loops of the small intestine is not taken into consideration. The aim of this investigation was to develop a general model for calculating the absorbed dose to the radiation-sensitive cells in the small intestinal mucosa from radionuclides located in the small intestinal wall or contents. METHODS: A model was developed for calculation of the self-dose and cross-dose from activity in the intestinal wall or contents. The small intestine was modeled as a cylinder with 2 different wall thicknesses and with an infinite length. Calculations were performed for various mucus thicknesses. S values were calculated using the EGS4 Monte Carlo simulation package with the PRESTA algorithm and the simulation results were integrated over the depth of the radiosensitive cells. The cross-organ dose was calculated by summing the dose contributions from other intestinal segments. Calculations of S values for self-dose and cross-dose were made for monoenergetic electrons, 0.050-10 MeV, and for the radionuclides (99m)Tc, (111)In, (131)I, (67)Ga, (90)Y, and (211)At. RESULTS: The self-dose S value from activity located in the small intestinal wall is considerably greater than the S values for self-dose from the contents and the cross-dose from wall and contents except for high electron energies. For all radionuclides investigated and for electrons 0.10-0.20 MeV and 8-10 MeV in energy, the cross-dose from activity in the contents is higher than the self-dose from the contents. The mucus thickness affects the S value when the activity is located in the contents. CONCLUSION: A dosimetric model for the small intestine was developed that takes into consideration the localization of the radiopharmaceutical in the intestinal wall or in the contents. It also calculates the contribution from self-dose and cross-dose. With this model, more accurate calculations of absorbed dose to radiation-sensitive cells in the intestine are possible.

Electrons↗