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Sample records for 153sm important radionuclides

  1. Apoptosis induced by radionuclide 153Sm and expression of relevant genes in three different cancer cells

    To study apoptosis of PC-3, ER-75-30 and A549 cells induced by radionuclide 153Sm and the expression of bcl-2, bax in apoptosis cells, MTT assay was used to detect the anti-tumor effect, light microscope, transmission electron microscope, flow cytometer were used to detect apoptosis, while image analysis was used to detect the expression of bcl-2 and bax. 153Sm showed anti-tumor effect and could induce tumor cell apoptosis. Both bcl-2 and bax played an important role in apoptosis. Different kind of cells had different sensitivity to 153Sm

  2. Dosimetric evaluation of 153Sm-EDTMP, 177Lu-EDTMP and 166Ho-EDTMP for systemic radiation therapy: Influence of type and energy of radiation and half-life of radionuclides

    In radiopharmaceutical therapy, delivered doses to critical organs must be below a certain threshold therefore internal radiation dosimetry of radiopharmaceuticals is essential. Advantages and disadvantages of radionuclides with different characteristics were evaluated for selection of appropriate radionuclide. The Monte Carlo MCNPX simulation program was used to obtain radial dose and cumulative dose of 153Sm, 177Lu and 166Ho used in radiotherapy of bone metastases. A cylindrical geometry with constant density materials was supposed for simulation of femur bone. The radius of bone marrow, bone, and surrounding soft tissue was considered 0.6 cm, 1.3 cm and 4 cm, respectively. It was assumed that the radionuclides were uniformly distributed throughout the tumor. “continuous energy spectrum” of beta particle was used instead of mean beta energy. Our simulations show that absorbed dose in target organ (bone) is greater than other organs and 166Ho gives a higher dose to the critical organ of bone marrow than either 153Sm or 177Lu. Absorbed dose versus time demonstrate faster dose delivery for the short half-life radionuclides (153Sm and 166Ho). These results are in good agreement with clinical observations which show a pain relief within 1 week after intravenous administration of 153Sm-EDTMP, whereas it occurs within 2 week in the case of 177Lu-EDTMP. According to the results, combination of different radionuclides with different characteristics such as 153Sm-EDTMP and 177Lu-EDTMP could be more advantageous to patients with painful bone metastasis. - Highlights: • The radial dose and cumulative dose of 153Sm, 177Lu and 166Ho are calculated. • The effect of half-life of the radionuclide on the suitable activity for injection is studied. • Dose delivery is fast for the short half-life radionuclides (153Sm and 166Ho). • The results are in good accordance with clinical observations. • The combination of different radionuclides with different characteristics

  3. Cross sections of deuteron induced reactions on $^{nat}$Sm for production of the therapeutic radionuclide $^{145}$Sm and $^{153}$Sm

    Tárkányi, F; Takács, S; Ditrói, F; Csikai, J; Ignatyuk, A V

    2014-01-01

    At present, targeted radiotherapy (TR) is acknowledged to have great potential in oncology. A large list of interesting radionuclides is identified, including several radioisotopes of lanthanides, amongst them $^{145}$Sm and $^{153}$Sm. In this work the possibility of their production at a cyclotron was investigated using a deuteron beam and a samarium target. The excitation functions of the $^{nat}$Sm(d,x)$^{145153}$Sm reactions were determined for deuteron energies up to 50 MeV using the stacked-foil technique and high-resolution $\\gamma$-ray spectrometry. The measured cross sections and the contributing reactions were analyzed by comparison with results of the ALICE, EMPIRE and TALYS nuclear reaction codes. A short overview and comparison of possible production routes is given.

  4. Study on cellular survival adaptive response induced by low dose irradiation of 153Sm

    The present study engages in determining whether low dose irradiation of 153Sm could cut down the responsiveness of cellular survival to subsequent high dose exposure of 153Sm so as to make an inquiry into approach the protective action of adaptive response by second irradiation of 153Sm. Experimental results indicate that for inductive low dose of radionuclide 153Sm 3.7 kBq/ml irradiated beforehand to cells has obvious resistant effect in succession after high dose irradiation of 153Sm 3.7 x 102 kBq/ml was observed. Cells exposed to low dose irradiation of 153Sm become adapted and therefore the subsequent cellular survival rate induced by high dose of 153Sm is sufficiently higher than high dose of 153Sm merely. It is evident that cellular survival adaptive response could be induced by pure low dose irradiation of 153Sm only

  5. Radionuclide Treatment with 153Sm-EDTMP is Effective for the Palliation of Bone Pain in the Context of Extensive Bone Marrow Metastases: A Case Report

    Kairemo, Kalevi; Rasulova, Nigora; Suslaviciute, Justina; Alanko, Tuomo

    2014-01-01

    Radionuclide therapy is widely used as an effective modality in the management of bone pain. The main indication for this treatment is symptomatic bone metastases, confirmed by bone scintigraphy. We present a case of small cell lung cancer (SCLC) stage T4N2M1b, with a good metabolic response to systemic therapy and radiotherapy of the primary tumor and locoregional disease, which became metabolically less active and remarkably smaller in size (reduction to 1/6 of the original volume). In spite of the good overall response, the patient developed a syndrome with severe bone pain and had progression in the bone marrow metastases, confirmed by 18F-FDG PET/CT. The patient received 153Sm-EDTMP treatment with a good clinical response. However, in the whole body bone scan with the therapeutic dose, there was no visual evidence of bone metastasis. Retrospectively, by drawing the region of interest, it was possible to identify one metastatic site. The possible mechanisms of the efficacy of this treatment modality, in this specific setting, are also discussed. PMID:27408870

  6. Radionuclide Treatment with 153Sm-EDTMP is Effective for the Palliation of Bone Pain in the Context of Extensive Bone Marrow Metastases: A Case Report

    Kalevi Kairemo

    2014-10-01

    Full Text Available Radionuclide therapy is widely used as an effective modality in the management of bone pain. The main indication for this treatment is symptomatic bone metastases, confirmed by bone scintigraphy. We present a case of small cell lung cancer (SCLC stage T4N2M1b, with a good metabolic response to systemic therapy and radiotherapy of the primary tumor and locoregional disease, which became metabolically less active and remarkably smaller in size (reduction to 1/6 of the original volume. In spite of the good overall response, the patient developed a syndrome with severe bone pain and had progression in the bone marrow metastases, confirmed by 18F-FDG PET/CT. The patient received 153Sm-EDTMP treatment with a good clinical response. However, in the whole body bone scan with the therapeutic dose, there was no visual evidence of bone metastasis. Retrospectively, by drawing the region of interest, it was possible to identify one metastatic site. The possible mechanisms of the efficacy of this treatment modality, in this specific setting, are also discussed.

  7. Production cross-section calculations of medical {sup 32}P, {sup 117}Sn, {sup 153}Sm and {sup 186,188}Re radionuclides used in bone pain palliation treatment

    Demir, Bayram [Istanbul Univ. (Turkey). Physics Dept.; Kaplan, A.; Capali, V. [Univ. Isparta (Turkey). Physics Dept.; Sarpuen, I.H. [Afyon Kocatepe Univ., Afyonkarahisar (Turkey). Physics Dept.; Aydin, A. [Kirikkale Univ. (Turkey). Physics Dept.; Tel, E. [Univ. Osmaniye (Turkey). Physics Dept.

    2015-03-15

    In this study, production cross-section calculations of {sup 32}P, {sup 117}Sn, {sup 153}Sm and {sup 186,188}Re radionuclides used in bone pain palliation treatment produced by {sup 30}Si(d,γ){sup 32}P, {sup 118}Sn(γ,n){sup 117}Sn, {sup 116}Sn(n,γ){sup 117}Sn, {sup 150}Nd(α,n){sup 153}Sm, {sup 154}Sm(n,2n){sup 153}Sm, {sup 152}Sm(n,γ){sup 153}Sm, {sup 186}W(d,2n){sup 186}Re, {sup 187}Re(γ,n){sup 186}Re, {sup 185}Re(n,γ){sup 186}Re and {sup 187}Re(n,γ){sup 188}Re reactions have been investigated in the different incident energy range of 0.003-34 MeV. Two-component exciton and generalised superfluid models of the TALYS 1.6 and exciton and generalised superfluid models of the EMPIRE 3.1 computer codes have been used to pre-equilibrium (PEQ) reaction calculations. The calculated production cross-section results have been compared with available experimental results existing in the experimental nuclear reaction database (EXFOR). Except the {sup 118}Sn(γ,n){sup 117}Sn, {sup 150}Nd(α,n){sup 153}Sm and {sup 185}Re(n,γ){sup 186}Re reactions, the two-component exciton model calculations of TALYS 1.6 code exhibit generally good agreement with the experimental measurements for all reactions used in this present study.

  8. Influence of binding characteristics of 153Sm-complexes to BSA on their bone uptake

    The bone uptake in normal mice and adsorption on bone model materials (hydroxyapatite and type I collagen) of 153Sm-NTMP, 153Sm-HEDTMP, 153Sm-DCTMP, 153Sm-EDTMP, 153Sm-DTPMP and 153Sm-DTPA are compared, and then the binding characteristics of these 153Sm-complexes to bovine serum albumin (BSA) are investigated. It is found that there is a discrepancy between the bone uptake and the adsorption on bone model materials, and that the binding characteristics of these 153Sm-complexes to BSA play an important role in the process of their bone uptake. Also, the binding characteristics are applied to explain the discrepancy successfully

  9. Production and supply of 99Mo, 153Sm radioisotopes for medical applications - societal benefits

    Application of radioisotopes in medicine has led to the evolution of a new branch of medicine called 'Nuclear Medicine' wherein radioisotope products in the form radiopharmaceuticals are used for the diagnosis of diseases, their follow up, detecting recurrence and also in the treatment of certain diseases. Large scale production, processing and supply of number of radioisotopes for medical application has been a feature of our laboratory. 99Mo is an important radionuclide produced in our reactors to obtain 99mTc, the most commonly used diagnostic radionuclide in the preparation of 99mTc-radiopharmaceuticals through 99Mo-99mTc radionuclide generators. 99Mo for the preparation of generators based on solvent extraction technology is produced by irradiation of natural MoO3 target in Dhruva and Cirus reactors. About 1.5 TBq (∼40 Ci) of 99Mo is processed and supplied to Board of Radiation and Isotope Technology (BRIT) every week on Saturdays to meet the requirements of nuclear medicine centres in the country. 153Sm-EDTMP is a ready-to-use radiopharmaceutical approved for the palliative treatment of metastatic bone pain in patients suffering from primary lung, breast and prostate cancers. 153SmCl3, the primary radiochemical for preparation of 153Sm-radiopharmaceutical is produced by neutron activation of natural or enriched Sm2O3 target in our medium flux research reactors. 150 GBq (4Ci) 153Sm is processed and supplied every month to BRIT for radiopharmaceutical production and further supply to nuclear medicine centres. Logistics of regular production of both 99Mo and 153Sm radionuclides, their quality control and the scope for the production of these radiochemicals with high specific activity to meet the increasing demands in the years to come with concomitant health care benefits to the society at large are discussed in this paper. (author)

  10. Studies concerning the preparation of the 153Sm complex with EDTMP (ethylenediaminetetra methylenephosphonic acid) and other 153Sm complexes with other phosphonates, at room temperature

    This work presents a study on the preparation of the complexes 153Sm - EDTMP, 153Sm - HEDP, 153Sm - NTMP, 153Sm - DTPMP and 153Sm - HDTMP at room temperature. The preparation of the complex 153Sm - HDTMP, under heating (70 - 72 deg C), was also studied. Several factors affecting the 153Sm - EDTMP complexing yields were studied, due to its importance for use in Nuclear Medicine. These factors were: the molar ratio [ligand] / [metal], the ligand concentration and the incubation time of the mixture ligand-metal. The preparation of this complex, in low molar ratios, was also investigated. A study of the 153Sm - EDTMP concerning the 'in vitro' stability, when this complex was prepared in low radioactive concentrations was performed. A study on the temperature influence on its degradation, when this complex was obtained in higher radioactive concentrations, was also performed. The preparation of the complexes 153Sm - HEDP, 153Sm - NTMP, 153Sm - DTPMP and 153Sm - HDTMP was investigated by preparing the complexes in two situations: high molar ratio and ligand concentration and low molar ratio and ligand concentration. The 'in vitro' stability of each complex, obtained in low radioactive concentration was studied. In the specific case of the complex 153Sm - HDTMP, its biological distribution in mice was performed. All the complexes were investigated by high performance liquid chromatography (HPLC) and its complexing yields were determined by other three chromatographic processes: ionic exchange, thin layer chromatography (TLC - SG) and paper chromatography. The chromatographic processes were performed by association with specific radiochemical techniques. This work also presents a comparative study on the chromatograms obtained by thin layer chromatography (TLC - SG) and paper chromatography, when evaluated by the technique of cutting the strips into pieces and the chromatograms performed directly on a radiochromatography. The shape of the chromatograms and Rf values of 153

  11. First measurement of 153Sm in the SIR

    In June 1998, the NIST sent to the International Reference System (SIR) a solution of 153Sm standardized in a 4π ionization chamber. As this radionuclide had not previously been measured in the SIR, the resulting equivalent activity Ae,NIST is compared with the value calculated from the efficiency curve of the SIR. However, problems occurred owing to the presence of 154Eu and 156Eu impurities in the solution. The manner in which the final equivalent activity value for this solution of 153Sm has been deduced is described in this report. (authors)

  12. The content of 153Sm-oxabifor in cancer patients blood in the treatment of bone metastasis

    Concentration 153Sm in the blood of patients with bone metastasis after radionuclide therapy was determined. Considerable variation of the content of 153Sm in blood of patients with various primary cancers from 10 to 65 Bq/ml is found. The effective half-life of 153Sm in the blood of patients was estimated at more than 10 days during the course of the therapy in time interval more than 7 days

  13. Kinetics of 153Sm oxabiphor in the blood of cancer patients undergoing complex therapy for bone metastasis

    Concentration 153Sm in the blood of patients with bone metastasis after radionuclide therapy was determined. Considerable variation of the content of 153Sm in blood of patients with various primary cancers from 10 to 65 Bq/ml is found. The effective half-life of 153Sm in the blood of patients was estimated at more than 10 days during the course of the therapy.

  14. 153Sm oxabiphor in complex therapy of metastatic bone tissue

    The article provides a review of literature regarding radionuclide treatment of bone metastases disease in patients with different malignant neoplasms. Retrospective review of radiopharmaceutical application in the treatment of bone distant metastases is given. Advantages and limitations of different radiotracers have been determined. Possibility of application of the most updated, last generation agent, 153Sm, which is according to literature data showed an excellent analgesic properties and minimum side effects has been comprehensively studied

  15. DNA gel electrophoretic and micro-autoradiographic studies on apoptosis in bone tumor cells after exposure to 153Sm-EDTMP

    Objective: To study the characteristics of injury in apoptotic bone tumor cells and behavior of radionuclide 153Sm in tumor cells. Methods: DNA gel electrophoresis and micro-autoradiographic tracing of apoptotic bone tumor cells at different intervals after 153Sm-EDTMP internal irradiation. Results: Bone tumor cells internally irradiated with 153Sm-EDTMP displayed characteristics of DNA ladder formation in apoptotic cells. 153Sm could permeate through tumor cell membrane and be phagocytized by the tumor cells, showing membrane-seeking and membrane-bounded apoptotic bodies condensation. Conclusion: Progression of apoptosis in bone tumor cells induced by 153Sm-EDTMP is dependent on the time elapse of 153Sm internal irradiation

  16. Preparation and quality control of {sup 153}Sm radiopharmaceuticals

    Swasono, R. Tamat; Widyastuti, W.; Purwadi, B.; Laksmi, I. [Radioisotope Production Center - BATAN, Jakarta (Indonesia)

    1998-10-01

    The paper summarizes the preparation and quality control of {sup 153}Sm-EDTMP and three {sup 153}Sm-radiosynovectomy agents. Natural and enriched Sm{sub 2}O{sub 3} (98.7% {sup 152}Sm) irradiated in RSG-GAS 30 MW reactor yielded pure and high specific activity {sup 153}Sm. Labeling of EDTMP with {sup 153}Sm was carried out by mixing {sup 153}SmCl{sub 3} solution of pH 4.0 to an EDTMP solution at room temperature then pH adjustment to 8. The {sup 153}Sm-EDTMP complex was separated from the free {sup 153}Sm{sup +3} on a Chelex 100 column. Radiochemical purity was determined by thin layer chromatography using Cellulose sheets and pyridine: ethanol: water (1: 2: 4) mixture as solvent. The {sup 153}Sm-EDTMP has been shown to be stable for two weeks. Three particulate preparations of {sup 153}Sm used for the irradiation of chronic synovitis have been studied. They are hydroxyapatite particles, human serum albumin microspheres and ferric hydroxide macroaggregates. The {sup 153}Sm-ferric hydroxide macroaggregates were prepared in a single step by coprecipitation of {sup 153}Sm in the formation of Fe(OH){sub 3}. Preparation of {sup 153}Sm-labelled hydroxyapatite particles and {sup 153}Sm-labelled albumin microspheres were carried out by {sup 153}Sm labelling of previously prepared particles. Radiolabelling efficiency were greater than 95% for hydroxyapatite particles and macroaggregates and was lower than 20% for albumin microspheres. The particle sizes were inspected using an optical microscope with a haemocytometer and micrometric ocular. (author)

  17. Chemical study on the labeling of EDTB with 153Sm

    Objective: According to conjugation characteristic of N, N, N', N'-tetrakis (2-benzymidazolylmethyl)-1, 2-ethanediamine (EDTB) with lipiodol selectively retained within hepatic tumors, in this paper, the labeling of EDTB with therapeutic nuclide 153Sm was first systematically studied by different labeling pathways, to further develop new labeled compounds with 153Sm for the treatment of hepatocellular carcinoma. Methods: A radio-paper chromatography (RPC) was used to determine the purity of the labeled compound with the mixture of pyridine: ethanol: water (1:2:4, V/V) as developer. Using independence variable method, the effect of labeling conditions, such as reaction time, temperature and concentration of EDTB on labeling yield were investigated, and the in vitro stability of 153Sm-EDTB was also demonstrated by RPC. Results: the RPC analysis indicated that Rf value of free 153Sm or 153Sm-EDTB was 0.0-0.1 and 0.6-0.7, respectively. Using acetic acid as reaction medium, in an open nitrogen-pouring labeling system, heated in boiling water bath for not less than 30 min, the labeling yield of 153Sm-EDTB was more than 97% and could remain in 24 hours after preparing the labeled compound at room temperature. Conclusion: The optimum labeling method and conditions were achieved. The in vitro stability of 153Sm-EDTB was good; thereby this provided possibility for further preparation and biological research of potential therapeutic radiopharmaceutical labeled lipiodol with 153Sm via EDTB for liver cancer

  18. 153Sm metallic-hydroxide macroaggregates. An improved preparation for radiation synovectomy

    A new type of preparation employing 153Sm metallic-hydroxide macroaggregates (153Sm-MHM) for radiation synovectomy was developed. The radiopharmaceutical was prepared by reacting the aqueous solution of 153SmCl3 with sodium borohydride solution in 0.5N NaOH. Microscopic analysis showed that 153Sm-MHM mean particle size was 4μm (range 1-15 μm) avoiding the formation of fine particles (153Sm-hydroxide macroaggregates preparations (153Sm-HM). Also, suspension properties as sedimentation rate, were better for 153Sm-MHM than for 153Sm-hydroxyapatite and 153Sm-HM. Biological studies in normal rabbits demonstrated high retention into de Knee joint space even at 48 h after administration of 153Sm-MHM (>99%). (author)

  19. Primary investigation of dose-effect relationship of 153Sm-EDTMP in treating multiple bone metastases%153Sm-EDTMP治疗多发骨转移瘤的剂量效应关系初步观察

    Wei Fan; Lixin Chen; Xiaowei Liu; Qiang Tang; Shengfang Zhi; Zongyuan Zeng

    2007-01-01

    Objective: To calculate the focus absorption dose of 153Sm-EDTMP with the Monte Carlo (MC) EGS4 method for treatment of bone metastases from nasopharyngeal carcinoma or breast cancer, and investigate the relationship between the focus absorption dose and painkilling effect of 153Sm-EDTMP. Methods: Four patients with multiple bone metastases from nasopharyngeal or breast carcinoma and suffered from grade Ⅳ bone pain were treated with radionuclide internal irradiation of 153Sm-EDTMP. The absorption dose and dose distribution of bone metastases and other targeted organs were calculated with MC EGS4 program based on the time-order SPECT/CT scanning and the measurement of the radioactivity in the urine accumulation. The release of bone pain and the improvement of life quality were observed. Results: Bone pain of the patients was significantly alleviated to grade Ⅱ for 3-4 weeks after internal 153Sm-EDTMP irradiation. The 3-dimensional absorption dose distribution image of bone metastases and targeted organs showed that the dose distribution in bone metastases was not asymmetrical. After injection of 0.65 × 37 MBq/kg 153Sm-EDTMP, the highest absorption dose in bone lesions was about 4.9-5.9 Gy, and the dose in the lesion margin was about 2.0 Gy. Using the highest dose as reference dose point, the relative absorption dose values of bone marrow, vertebra and sex organ near lesions were 0.48-1.1 Gy, 0.51-0.85 Gy, and 0.01-0.14 Gy, respectively. Conclusion: The absorption dose of bone metastases is significantly lower than treatment dose of 30 Gy after single irradiation of 153Sm-EDTMP. The painkilling effect is limited and in accordance with clinical observation.

  20. Preparation of bone tumor therapeutic radiopharmaceuticals 153Sm-EDTMP

    Samarium-153-EDTMP (ethylene diamine tetramethylene phosphonate), for its promising biological properties, has been proved as a palliating therapeutic agent for bone tumor in human beings. 153Sm with high radionuclear purity and specific activity of 5.18 GBq (140 mCi)/mg Sm2O3 was prepared by irradiating natural Sm2O3(152Sm, 26.7%) sample, replacing costly enriched samarium oxide target, at a flux of 4 x 1013 n·cm-2·s-1 for 110 h. The yield of 153Sm complexing with EDTMP is greater than 98% at pH 8∼10 in boiling water bath for 30 min, and not significantly decreases within one week after 153Sm-EDTMP complex formation

  1. SPECT/CT images in the calculation of absorbed dose ration between radio-synovectomy procedures with 153Sm-HA and 90Y-HA

    Full text of publication follows. Heterogeneity in the intra-articular distribution of hydroxyapatite (HA) labeled with 90Y or 153Sm at radio-synovectomy (RSV) procedures can be detected by using the fusion between transmission (SPECT) and emission (CT) tomographic images. To avoid this heterogeneity, commonly it is preferred to use 90Y over 153Sm assuming that the larger penetration range of the emitted beta particles will make the absorbed dose distribution more uniform. In this study, we evaluated the validity of this assumption by determining the affected area of RSV procedures in human joints treated with 90Y-HA and 153Sm-HA. Using SPECT/CT images of 3 patients treated with 90Y-HA (185 MBq) or 153Sm-HA (740 MBq), a voxel-by-voxel (voxel size=9.06 mm3) analysis was performed to build 3D distribution of 90Y and 153Sm activity. With the 3D image of the activity correlated to the mass of each voxel, provided by CT images via Housfield scale, the absorbed dose was calculated using the generic equation of absorbed dose rate and the average range of beta particles emitted from 90Y and 153Sm. We have chosen the generic dose equation rather than the MIRD model of voxel dosimetry or the Dose-Point Kernel method because the later models do not allow for a voxel mass dependent dose calculation. In addition, there is little information on 153Sm data and voxel sizes in these models. Considering the average energy and the therapeutic range of emitted beta particles we concluded that the dose in each voxel is not affected by the activity of neighboring voxels. Difference in the RSV procedures using 90Y-HA and 153Sm-HA should be just the dose difference per activity injected. Collisional Stopping Power shows us that the relative dose between these two compounds is 4.12:1. With these results we conclude that beta particles emitted from 90Y and 153Sm do not have range enough to reach cold spots found in heterogeneous distributions of radionuclide at RSV. Hence the spatial dose

  2. A comparative study of preliminary dosimetry for human based on distribution data in rats with 111In, 90Y, 153Sm, and 177Lu labeled rituximab

    Radfar Edalat

    2012-01-01

    Full Text Available Radio immunotherapy is one of the most important and effective therapies for B-cell non Hoddgkin’s lymphoma treatment. Today, anti CD-20 antibodies labeled with beta emitter radionuclides are used in radio immunotherapy. Various radionuclides for labeling anti CD-20 antibodies have been studied and developed for the treatment and diagnosis of malignancies. This paper describes the preparation, bio-distribution and absorbed dose rate of 111In, 90Y, 177Lu, and 153Sm labeled anti CD-20 antibodies (rituximab in human organs, after injection to rats. The macro cyclic bifunctional chelating agent, N-succinimidyl-1, 4, 7, 10-tetraazacyclododecane-1, 4, 7, 10-tetraacetic acid (DOTA-NHS for conjugation to antibody, was used to prepare DOTA-rituximab. The conjugates were purified by molecular filtration, the average number of DOTA conjugated per mAb was calculated and total concentration was determined by spectrophotometric method. Radio-labeling was performed at 40 °C for 24 hours. After the quality control studies, the final radioactive solution was injected intravenously into rats through their tail vein. The tissue uptakes of each injection were measured. Then we calculated S values for 177Lu and 153Sm by using specific absorbed fractions and data used in the manner of radio-labeled analysis and dosimetry for humans. The absorbed dose rate of each organ was calculated in the specific time by medical internal radiation dose method with linear approximation in the activity measurements.

  3. Targeted radiotherapy dosimetry of 153Sm hydroxide macroaggregates for radiation synovectomy

    The dosimetry of the recently developed 153Sm hydroxide macroaggregates (153Sm-MH) for radiation synovectomy has been studied as an agent for the treatment of arthritic synovial joint diseases. This pharmaceutical formulation presents optimal properties in terms of particle size (average 4 μm) sedimentation (0.008 cm min-1) and biological behavior. Direct measurements of depth dose distributions for this beta-gamma emitter present a difficult task; therefore, calculations of depth dose profiles are an invaluable tool for investigating the effectiveness of this therapeutic technique. In spite of the importance of these calculations there are only a few studies dealing with the experimental validation of these calculated depth dose distributions. On the present work the Monte Carlo (MCNP4B) calculated beta-gamma depth dose profiles for a liquid 153Sm beta-gamma source used in radiation synovectomy are compared with experimental depth dose distribution obtained using radiochromic dye film dosimetry (GafChromic trade mark sign ). The calculated and experimental depth dose distribution showed a very good agreement (within 5%) on the region where the dose deposition is dominated by the beeta-particle component (first 800 microns depth on tissue equivalent material). The agreement worsens reaching a maximum deviation of 15% at depths close to the maximum range of the beta-particles. Finally the agreement improves for the region where the gamma component accounts for one third of the total absorbed dose (depths>1 mm). The possible contributions to these differences are discussed as well as their relevance for the application of 153Sm for the treatment of rheumatoid arthritis

  4. Efficient protocol for the preparation 153Sm-EDTMP injection: an agent for bone pain palliative treatment

    techniques and gadgets and production modules, several therapeutic batches of 153Sm-EDTMP injection have been processed, QC tested (radiochemical purity, radionuclidic purity, sterility test, bacteriological endotoxin test) and more than 100 doses (70 mCi each) have been supplied for clinical use, to various Nuclear Medicine Centers in India. Regular production of this product (BRIT Code SAM-2) is being undertaken on monthly frequency

  5. The entrance to bone tumor cells of 153Sm-EDTMP by microautoradiographic tracing

    The dynamic process of 153Sm-EDTMP entering into bone tumor cells and its behavior characteristic in osteosarcoma cells are studied by microautoradiographic tracing. The results show that 153Sm-EDTMP condense on membrane of osteosarcoma cells at first, then infiltrate through cell membrane or phagocytized by osteosarcoma cells and distributed in the form of phagosomes. In apoptotic osteosarcoma cells 153Sm-EDTMP could be observed in the membrane-bounded apoptotic bodies. So, the progression of apoptosis in osteosarcoma cells induced by 153Sm-EDTMP is dependent on the infiltration and phagocytosis of 153Sm-EDTMP through cell membrane

  6. 153Sm-HM for arthritic knee pain. Estimated dosimetry

    Osteoarthritis is the most common type of arthropathy and after cardiovascular diseases is the most disabling disease in developing countries. The dosimetry for the clinical application of 153-samarium-hydroxymacroaggregates (153Sm-HM) for radiation synovectomy (RSV) and palliative treatment for arthritic pain, as far as we know, has not been reported. The aim of this research was to estimate the radiation dose necessary for synovial ablation and pain palliation with minimum risk to the patient. 153Sm-HM (370 MBq) was administered intra-articularly in a patient with severe knee pain and hindered motility. Regions of interest drawn on sequential, conjugated, anterior and posterior scintigraphy images were used to obtain the respective activity. The data was entered into a knee joint histological-geometric model designed with micrometric dimensions to represent the synovial cell layers. The Monte Carlo code was used to calculate the absorbed dose in each of the 12 model-cells representing the distance from the synovial liquid to the cartilage or bone. The absorbed dose in the synovial cavity was 114 Gy which is sufficient energy for RSV. The treated patient referred little pain and higher motility with no adverse reactions. 153Sm-HM is a potentially valid radiopharmaceutical for RSV, which effectively palliates knee pain.

  7. Synthesis and bio-evaluation of nano-hydroxyapatite trapped by 153Sm

    After nanoHA was synthesized, 153Sm-EDTMP-nanoHA and 153Sm-citrate-nanoHA were prepared and proved stable in vitro. ECT images of New Zealand rabbits injected with 153Sm-EDTMP-nanoHA had better contrast, skeletal figure visible, liver and spleen clear. The images of 153Sm-citrate-nanoHA showed a similar results but kidney invisible, which meant 153Sm-citrate-nanoHA showed a similar results but kidney invisible, which meant 153Sm-citrate-nanoHA was mainly excreted through liver and gall. 153Sm-EDTMP-nanoHA's half effective inhibition concentrations to SMMC-7721 and MCF-7 cells were 1.98 g/L and 0.075 g/L respectively and 153Sm-citrate-nanoHA's were 1.89 g/L and 0.094 g/L proportionally. 153Sm-EDTMP-nanoHA and 153Sm-citrate-nanoHA were worthy of a further research because their half effective inhibition concentrations were much lower than ones of the single nanoHA. (authors)

  8. Biological evaluation of 153Sm and 166Ho complexes with macrocyclic ligands containing acetate pendant arms as potential agents for therapy

    For the development of therapeutic radiopharmaceuticals it is essential to choose the appropriate beta-emitter as well as the carrier biomolecule. Different carrier biomolecules, namely antibodies and peptides, have been linked to different beta-emitters (153Sm, 166Ho and 177Lu) using tetraaza macrocycles as bifunctional chelators. The cavity size of these chelators, the rigidity of the macrocyclic backbone and the nature of the pendant arms seems to play an important role on the thermodynamic stability and kinetic inertness of the radiocomplexes and on their biological behaviour. In our research group we have been exploring the possibility of using tetraazamacrocycles with different cavity size, pendant arms and rigidity for preparing 153Sm and 166Ho complexes useful for therapeutical applications and/or bone pain palliation. In this communication we present the results obtained when we reacted trita and teta with 153Sm and 166Ho. The complexes are formed in good yields (> 98%), are hydrophilic and present an overall negative charges, as well as low plasmatic protein binding. Good in vitro stability in physiological media and human serum was also found for all the complexes. The biodistribution studies in mice are also presented and have shown that 153Sm/166Ho-trita and 166Ho-teta have rapid tissue clearance, comparably to the corresponding dota complexes. In contrast, 153Sm-teta has a significant lower total excretion and a significant liver and muscle uptake. Our results indicate that 153Sm/166Ho-trita form very stable complexes in vivo. However, teta, which has a larger cavity size, forms less stable complexes with the larger ion Sm3+. The biological profile of 153Sm/166Ho-trita is very interesting for the evaluation of these complexes as therapeutical agents when conjugated to biomolecules

  9. Organ doses from hepatic radioembolization with 90Y, 153Sm, 166Ho and 177Lu: A Monte Carlo simulation study using Geant4

    Hashikin, N. A. A.; Yeong, C. H.; Guatelli, S.; Abdullah, B. J. J.; Ng, K. H.; Malaroda, A.; Rosenfeld, A. B.; Perkins, A. C.

    2016-03-01

    90Y-radioembolization is a palliative treatment for liver cancer. 90Y decays via beta emission, making imaging difficult due to absence of gamma radiation. Since post-procedure imaging is crucial, several theranostic radionuclides have been explored as alternatives. However, exposures to gamma radiation throughout the treatment caused concern for the organs near the liver. Geant4 Monte Carlo simulation using MIRD Pamphlet 5 reference phantom was carried out. A spherical tumour with 4.3cm radius was modelled within the liver. 1.82GBq of 90Y sources were isotropically distributed within the tumour, with no extrahepatic shunting. The simulation was repeated with 153Sm, 166Ho and 177Lu. The estimated tumour doses for all radionuclides were 262.9Gy. Tumour dose equivalent to 1.82GBq 90Y can be achieved with 8.32, 5.83, and 4.44GBq for 153Sm, 166Ho and 177Lu, respectively. Normal liver doses by the other radionuclides were lower than 90Y, hence beneficial for normal tissue sparing. The organ doses from 153Sm and 177Lu were relatively higher due to higher gamma energy, but were still well below 1Gy. 166Ho, 177Lu and 153Sm offer useful gamma emission for post-procedure imaging. They show potential as 90Y substitutes, delivering comparable tumour doses, lower normal liver doses and other organs doses far below the tolerance limit.

  10. The biodistribution and kinetics of the 153Sm labelled avidin, streptavidin and biotin

    Due to the high affinity of biotin to Av or SA. The authors labelled a biotin derivative (DTPA-biotin) with 153Sm and then bound this 153Sm labelled DTPA-biotin to Av or SA. The in vivo kinetics and biodistribution of 153Sm labelled Av, SA and DTPA-biotin were studied in the rat and mice. The results demonstrated that 153Sm-Av cleared from the blood rapidly with high liver and renal uptake; 153Sm-SA cleared from blood slowly with high retention in liver, spleen and kidney, whereas 153Sm metabolize more fast, and excreted mainly through the kidney. Thereby, the biodistribution difference of SA and Av mentioned above provided an experimental basis for the selection of different components of A-V system in pre-targeting radio-immuno imaging and radioimmunotherapy

  11. Chemical and biological evaluation of {sup 153}Sm and {sup 46/47}Sc complexes of indazolebisphosphonates for targeted radiotherapy

    Neves, Maria, E-mail: mneves@itn.p [Instituto Tecnologico e Nuclear, Sacavem (Portugal); Teixeira, Fatima C.; Antunes, Ines [INETI-Departamento de Tecnologia de Industrias Quimicas, Lisboa (Portugal); Majkowska, Agnieszka [Institute of Nuclear Chemistry and Technology, Warsaw (Poland); Gano, Lurdes [Instituto Tecnologico e Nuclear, Sacavem (Portugal); Santos, Ana Cristina [IBB-Instituto de Biofisica e Biomatematica, Coimbra (Portugal)

    2011-01-15

    Introduction: Novel 1-hydroxy-1,1-bisphosphonates derived from indazole and substituted at the C-3 position were labeled with the radionuclides {sup 46}Sc and {sup 153}Sm. Several parameters such as molar ligand concentration, pH, reaction time and temperature were studied. The radiolabelling yield, reaction kinetics and stability were assessed and radiocomplexes were evaluated by in vitro and in vivo experiments. Methods: The radionuclides {sup 46}Sc and {sup 153}Sm were obtained by neutron irradiation of natural Sc{sub 2}O{sub 3} and enriched {sup 152}Sm{sub 2}O{sub 3} (98.4%) targets at the neutron flux of 3x10{sup 14} n cm{sup -2} s{sup -1}. The radiolabelling yield, reaction kinetics and stability were accomplished by ascending instant thin layer chromatography. The radiocomplexes were submitted to in vitro experiments (hydroxyapatite binding and lipophilicity) and biodistribution studies in animal models. Results: The radionuclides {sup 46}Sc and {sup 153}Sm were produced with specific activities of 100 and 430 MBq mg{sup -1}, respectively. High radiochemical yields were achieved and the hydrophilic radiocomplexes have shown high degree of binding to hydroxyapatite. Biodistribution studies at 1, 3 and 24 h of the 4 radiocomplexes under study, have showed a similar biodistribution profile with a relatively high bone uptake, slow clearance from blood and a very slow rate of total radioactivity excretion from the whole animal body. Conclusion: We have developed a new class of indazolebisphosphonates complexes with radioisotopes of samarium and scandium. All complexes have shown high degree of binding to hydroxyapatite, which could be attributed to the ionized phosphonate groups. The bone uptake and the bone-to-muscle ratios were relatively low.

  12. Studies on apoptosis in bone tumor cells induced by 153Sm

    The apoptosis in human bone tumor cells induced by internal irradiation with 153Sm was studied. The morphological changes in bone tumor cells were observed by electronic and fluorescent microscopy, as well as DNA agarose gel electrophoresis. DNA chain fragmentation, microautoradiographic tracing and the inhibition rate of proliferation in bone tumor cells exposed to 153Sm with different duration time were examined. It was demonstrated that the bone tumor cells exposed to 153Sm displayed nuclear fragmentation, pyknosis, margination of condensed chromatin, and formation of membrane bounded apoptotic bodies, whereas the percentage of DNA chain fragmentation of bone tumor cells increases in direct proportion to the duration of irradiation with 153Sm, as well as DNA ladder formation in apoptotic cells. Also a marked inhibition effect of proliferation in bone tumor cells after exposure with 153Sm was observed. (authors)

  13. Studies on apoptosis in bone tumor cells induced by 153Sm

    ZHU Shou-Peng; XIAO Dong; HAN Xiao-Feng

    2004-01-01

    The apoptosis in human bone tumor cells induced by internal irradiation with 153Sm was studied. The morphological changes in bone tumor cells were observed by electronic and fluorescent microscopy, as well as DNA agarose gel eletrophoresis. DNA chain fragmentation, microautoradiographic tracing and the inhibition rate of proliferation in bone tumor cells exposed to 153Sm with different duration time were examined. It was demonstrated that the bone tumor cells exposed to 153Sm displayed nuclear fragmentation, pyknosis, margination of condensed chromatin, and formation of membrane bounded apoptotic bodies, whereas the percentage of DNA chain fragmentation of bone tumor cells increases in direct proportion to the duration of irradiation with 153Sm, as well as DNA ladder formation in apoptotic cells. Also a marked inhibition effect of proliferation in bone tumor cells after exposure with 153Sm was observed.

  14. Preparation and animal imaging of 153Sm-EDTMP as a bone seeking radiopharmaceutical

    Ethylenediamine- tetra methylenephosphonic acid (EDTMP) has widely used chelator for the labeling of bone seeking radiopharmaceuticals complexed with radio metals. 153Sm can be produced by the HANARO reactor at the Korea Atomic Energy Research Institute, Taejon, Korea. 153Sm has favourable radiation characteristics T1/2=46.7 h, β max=0.81 MeV (20%), 0.71 MeV (49%), 0.64 MeV (30%) and γ=103 keV (30%) emission which is suitable for imaging purposes during therapy. We investigated the labeling condition of 153Sm-Emptied and imaging of 153Sm-EDTMP in normal rats. EDTMP 20 mg was solved in 0.1 mL 2 M NaOH. 153SmCl3 was added to EDTMP solution and pH of the reaction mixtures was adjusted to 8 and 12, respectively. Radiochemical purity was determined with paper chromatography. After 30 min. reaction, reaction mixtures were neutralized to pH 7.4 and the stability was estimated upto 120 hrs. Imaging studies of each reaction were performed in normal rats (37 MBq/0.1 mL). The labeling yield of 153Sm-EDTMP was 99%. The stability of pH 8 reaction at 60, 96 and 120 hr was 99%,95%,89% and that of pH 12 at 36, 60, 96, and 120 hr was 99%, 95%, 88%, 66%, respectively. The 153Sm-EDTMP showed constantly higher bone uptake from 2 to 48 hr after injection. 153Sm-EDTMP, labeled at pH 8 reaction condition, has been stably maintained. Image of 153Sm-EDTMP at 2, 24, 48 hr after injection, demonstrate that 153Sm-EDTMP is a good bone seeking radiopharmaceuticals

  15. Safety and feasibility of percutaneous vertebroplasty with radioactive {sup 153}Sm PMMA in an animal model

    Lu Jun [Department of Radiotherapy, Xijing Hospital, Fourth Military Medical University, 15 West Changle Road, Xi' an 710032, Shaanxi Province (China); Deng Jinglan, E-mail: dengjinglan@gmail.com [Department of Nuclear Medicine, Xijing Hospital, Fourth Military Medical University, 15 West Changle Road, Xi' an 710032, Shaanxi Province (China); Zhao Haitao [Department of Radiology, Xijing Hospital, Fourth Military Medical University, 15 West Changle Road, Xi' an 710032, Shaanxi Province (China); Shi Mei [Department of Radiotherapy, Xijing Hospital, Fourth Military Medical University, 15 West Changle Road, Xi' an 710032, Shaanxi Province (China); Wang Jing [Department of Nuclear Medicine, Xijing Hospital, Fourth Military Medical University, 15 West Changle Road, Xi' an 710032, Shaanxi Province (China); Zhao Lina [Department of Radiotherapy, Xijing Hospital, Fourth Military Medical University, 15 West Changle Road, Xi' an 710032, Shaanxi Province (China)

    2011-05-15

    Purpose: We investigated the safety and feasibility of the combination of samarium-153-ethylenediamine tetramethylene phosphonate ({sup 153}Sm-EDTMP)-incorporated bone cement (BC) with percutaneous vertebroplasty (PVP) in dogs. Methods and materials: {sup 153}Sm-EDTMP-incorporated BC was prepared by combining solid {sup 153}Sm-EDTMP and polymethylmethacrylate (PMMA) immediately before PVP. It was then injected into the vertebrae of four healthy mongrel dogs (two males and two females) by PVP under CT guidance. Each dog was subjected to five PVP sessions at a {sup 153}Sm-EDTMP dose of 30-70 mCi. The suppressive effect of local injection of {sup 153}Sm-EDTMP on the hematopoietic system was evaluated through counting of peripheral blood cells. Distribution of {sup 153}Sm-EDTMP-incorporated BC and the status of tissues adjacent to injected vertebrae were evaluated with SPECT, CT and MRI. Histopathology was carried out to assess the influence of PVP on the vertebra and adjacent tissues at the microscopic level. Results: PVP was done successfully, and all dogs exhibited normal behavior and stable physical signs after procedures. {sup 153}Sm-EDTMP-incorporated BC was concentrated mainly in target vertebrae, and the peripheral blood cells remained within normal range. The spinal cord and tissues around BC did not exhibit signs of injury even when the dosage of {sup 153}Sm-EDTMP increased from 30 mCi to 70 mCi. Conclusion: A dose lower than 70 mCi of {sup 153}Sm is safe when it was injected into vertebrae. {sup 153}Sm-EDTMP-incorporated BC did not influence the effect of PVP. This means might strengthen anti-tumor activity locally for vertebra with osseous metastasis without damaging adjacent tissues.

  16. Cytogenetic analysis of 153 Sm-EDTMP in peripheral lymphocytes from patients with bone cancer metastasis

    The 153 Sm-EDTMP is a radiopharmaceutical used in nuclear medicine with promising results for the relief of metastatic pain. Therefore, there are few knowledge about the effects of 153 Sm-EDTMP at cellular level. The present study was conducted with the aim of evaluating the cytogenetic effects of 153 Sm-EDTMP in peripheral lymphocytes from patients with bone metastasis (with and without previous radio and/or chemotherapy) by the chromosome aberration technique. For that, the blood samples were collected before and one hour after the endovenous administrations of 153 Sm-EDTMP (mean activity of 42.53 ± 5.31 MBq/kg body weight), taking into account the rapid blood clearance. The principal types of structural chromosome aberrations found gaps and breaks, acentric fragments centric rings, double minutes and dicentrics. The statistical analysis showed that the group submitted to previous radio and chemotherapy before153 Sm-EDTMP administration showed significant difference in chromosome aberrations frequency one hour after the treatment. The analysis of the chromosome modal number and the kinetics of cellular cycle showed no statistical difference among the groups, suggesting that the treatment with 153 Sm-EDTMP, did not influence these parameters. The obtained data showed that the therapy with 153 Sm-EDTMP induced a few quantity of cytogenetic damages in peripheral lymphocytes one hour after its administration in patients, although, theoretically, a long term stochastic effect cannot be disregarded. (author)

  17. Optimization of the production, quality control of samarium-153, 153 Sm-EDTMP and biodistribution of 153 Sm-EDTMP in animals for metastatic bone cancer pain palliation

    Samarium-153 has suitable physical properties for metastatic bone cancer pain palliation with 46.7 hr half-life. Not only decays it with multi-energetic B-radiation but also emits a gamma-ray at 103 keV which is suitable for imaging during therapy. The optimization of 153 Sm production, by irradiation 152 Sm2 O3 as a solid and liquid target, is conducted in TRIGA Mark III research reactor. The feasibility to label it with EDTMP, a bone seeking agent, is also studied. The specific activity obtained from liquid target is about 2 times higher than solid target. At least 500 mCi/week can be produced with specific activity about 50 to 70 mCi/mg Sm. EDTMP as Na-EDTMP and Ca-EDTMP is labelled with 153 Sm at various conditions. The radiochemical purity achieved, is greater than 99% (85 mCi of 153 Sm labelled with Na-EDTMP or Ca-EDTMP, molar ratio of Sm:EDTMP 1:10 and 1:100 respectively, pH 7.5-8). The biodistribution in animals of 153 Sm-Na-EDTMP showed similar results as obtained from 153 Sm-Ca-EDTMP but slightly higher uptake in various organs and showed high skeletal uptake up to 32% at 24 hr post injection. The labeled compound obviously undergoes rapid removal, completely clearance into urine within 24 hr. This labeled compound is under clinical trials

  18. Fluorescence microscopic morphology and inhibition rate studies on apoptosis of osteosarcoma cells induced by 153Sm

    The apoptosis of osteosarcoma cells treated with irradiation by 153Sm-EDTMP was studied. The morphological changes in osteosarcoma cells were observed by fluorescence microscopy. It was found that osteosarcoma cells exposed with 153Sm-EDTMP displayed significant nuclear fragmentation and marked pyknosis. With the prolongation of observing period, the membrane bound apoptotic bodies formation was observed. It should be noted, that with the lengthening of irradiation time by 153Sm-EDTMP, the inhibition rate of proliferation of osteosarcoma cells increased progressively

  19. Urine management after treatment with ''153 Sm-EDTMP (QUADRAMET)

    The main purpose was to establish and to evaluate a new protocol of individualized treatment of patient urine after ''153 Sm-EDTMP injection, with a more efficient management of the wastes. Excreted urine was collected in an appropriate container form which, previous to sealing it, an aliquot of 10 ml was obtained. Experimental half-life (t1/2) of the isotope was then determined by measuring the activity at different times, besides the minimum time necessary for disposing of the radioactive wastes as regular trash. The measured half-life adjusted well to the theoretical value of the isotope. The time of considered storage oscillated between 19 and 26 days, based on the activity excreted by each patient. The main idea is the consideration of the set container-urine as solid waste: the evaluation of the minimum storage time necessary to its elimination is made in terms of legal limitation of specific activity by mass unit. The immediate advantages ares: the elimination of disagreeable scents by the storage of urine, it is not necessary a liquid waste disposal to eliminate it, and a more accurate knowledge of the specific activity at the moment of the elimination (dilution factor is not used). (Author) 10 refs

  20. Multi-factor analysis on events related to hematological toxicity in 153Sm-EDTMP palliative therapy for skeletal metastases

    Objective: To investigate the clinical factors related to hematological toxicity induced by intravenous samarium-153 ethylenediaminetetramethylene phosphonic acid (153Sm-EDTMP) treatment. Methods A total of 206 patients with bony metastases treated with 153Sm-EDTMP were retrospectively analyzed. Logistic regression (SPSS 10.0 for Windows) and correlation analysis were used to evaluate the factors concerned. Results: Age of the patient, number of bone metastatic lesion, chemotherapy before 153Sm-EDTMP therapy, concurrent radiotherapy and repeat-times of 153Sm-EDTMP treatments were found the individual factors related to hematological toxicity. Chemotherapy before 153Sm-EDTMP, concurrent radiotherapy, medication for normal blood counting and repeat-times of 153Sm-EDTMP treatments were the hematological toxicity factors in multi-factor analysis. Conclusion: In 153Sm-EDTMP therapy, several factors were found related to hematological toxicity suggesting more attention be paid to the change of blood cell counting after the palliative therapy. (authors)

  1. Inhibition of proliferation in bone tumor cells after irradiation by 235U, 147Pm, 153Sm

    The inhibition of proliferation in bone tumor cells after simple or mixed irradiation by 235U, 147Pm, 153Sm was studied. Experimental results indicated that proliferation of bone tumor cells was significantly inhibited at 12 h∼24 h after a simple irradiation by 235U (128.4 Bq), 147Pm (7.4 x 105 Bq), and 153Sm (7.4 x 105 Bq) as well as mixed irradiation by 235U + 147Pm (64.2 Bq + 3.7 x 105 Bq), 235U + 153Sm (64.2 Bq + 3.7 x 105 Bq), 147Pm + 153Sm (3.7 x 105 Bq + 3.7 x 105 Bq). The findings show that the inhibition rate with mixed irradiation was more than that with simple irradiation

  2. Preparation of 153Sm-citrate-HA for radioactive synovectomy of rheumatoid arthritis

    A new kind of labelled radiopharmaceutical hydroxyapatite (HA) by means of transfer complexing for the treatment of rheumatoid arthritis is described. HA with partials of 2-10 μm is labelled with 153Sm by a citrate transfer ligand. 153Sm-citrate-HA is obtained in high yield and is extremely stable in vitro. The complexing capability of HA is about 5 mg Sm2O3/g HA, the decomposition rates of 153Sm-citrate-HA both in saline of 0.9% and in human plasma (37 +- 0.5 degree C) are less than 2.0% for a period of 3 half lives. Biodistribution studies in rabbits demonstrated long term retention of nearly 99% of injected 153Sm-Citrate-HA in arthritis joint. Extra-articular leakage of radioactivity in both blood and urine accounted for 0.5% of injected dose, and few retained in other major tissues after about 14.8 MBq of 153Sm-Citrate-HA has injected into the left knee joint of normal rabbits. 153Sm-citrate-HA could be potentially useful in radio-synovectomy treatment of rheumatism arthritis

  3. Evaluation of the biological and scanning distribution of hydroxyapatite-153Sm radiotherapeutic agent

    Fixation of 153Sm labeled hydroxyapatite (HA) in the synovial capsule and extra articular localization were evaluated by means of biological distribution tests and gamma scanning studies. These were carried out using HA-153Sm with particle size ranging between 5 and μm, and radiochemical purity above 99%. Animal models used were wistar rats and new zealand rabbits. Rabbits were injected with 7,4 MBq of HA-153Sm while rats received between 1,85 and 92,6 MBq of HA-153Sm. In both cases injection was given in the intra articular area. After injection, scanning images were obtained in rabbits on the 1st, 3rd and 7st day and in rats on the 2nd and 7th day. Biological distribution studies are conducted in the 2 hours to 9 days range in rats and one the 7th day in rabbits. No extra articular localization of HA-153Sm was found in scanning conducted on rabbits by the 1st, 3rd and 7st day after injection, neither on rats by the 2nd and 7th day. Biological distributions for rabbits and rats show localization above 99% in the intra articular area, during the evaluated periods of time. The evaluations of the biological distribution and the scintigraphic images show that fixation of HA-153Sm in the synovial capsule up to the 9th day is very high

  4. The features of kinetics of 153Sm-oksabifor in bone metastases of cancer of different localization

    Provide evaluation of investigation of kinetics of 153Sm-oksabifor in metastases of cancer the results of complex scintigraphic investigations of 26 patients who were treated by radionuclide therapy were analyzed. The angioscintigraphy during 60 seconds, dynamic scintigraphy during 60-90 minutes and whole body scanning after intravenous bolus injection of 4130-4950 MBq of the radiopharmaceutical in sequence were made. Considerable variability of indices of the radiopharmaceutical kinetics was determined. The features of angioscintigrams from bone metastases with intensive accumulation of the radiopharmaceutical are a short descending segment or its absents and passing an ascending segment into plateau or slowly ascending curve, which are determined the radiopharmaceutical fixation in metastases during first passing the bolus through the vessels. Character of the radiopharmaceutical fixation at angioscintigraphy may be a prognostic factor of the efficacy of radionuclide therapy

  5. Electron microscopic morphology and DNA chain fragmentation studies on apoptosis in bone tumor cells induced by 153Sm

    Objective: To study the apoptosis and fraction of DNA chain fragmentation in bone tumor cells induced by 153Sm-EDTMP. Methods: Apoptosis in bone tumor cells exposed to different time periods of 153Sm-EDTMP internal irradiation was observed by electron microscopic morphology and DNA chain fragmentation studies. Results: It was demonstrated that the bone tumor cells internally exposed to 153Sm-EDTMP displayed nuclear fragmentation, margination of condensed chromatin, and formation of membrane bounded apoptotic bodies. The study showed that the percentage of DNA chain fragmentation increases in direct proportion to the duration of internal exposure to 153Sm-EDTMP. Conclusion: Apoptosis induced by 153Sm-EDTMP in bone tumor cells was dependent on the time of 153Sm-EDTMP exposure

  6. Cytogenetic effect of 153 Sm-EDTMP in peripheral lymphocytes of patients with metastatic cancer

    The 153Sm-EDTMP is a radiopharmaceutical used in nuclear medicine with promising results for the relief of metastatic pain. Therefore, there are few knowledge about the effects of 153Sm-EDTMP at cellular level. The present study was conduced with the aim of evaluating the cytogenetic effects of 153Sm-EDTMP in peripheral lymphocytes from patients with bone metastasis (with and without previous radio and/or chemotherapy) by the chromosome aberration technique, either in vivo or in vitro. For that, the blood samples were collected before and one hour after the endovenous administration of 153Sm-EDTMP (mean activity of 42.53+/-5.31 MBq/kg body weight), taking into account the rapid blood clearance. The principal types of structural chromosome aberrations found gaps and breaks, acentric fragments centric rings, double minutes and dicentrics. The statistical analysis showed that the group submitted to previous radio and chemotherapy before 153Sm-EDTMP administration showed significant difference in chromosome aberrations frequency one hour after the treatment. The analysis of the chromosome modal number and the kinetics of cellular cycle showed no statistical difference among the groups, suggesting that the treatment with 153Sm-EDTMP, did not influence these parameters. The carrier molecule, EDTMP, did not influence the induction of chromosome aberration. In relation to the in vitro assays, the obtained data of peripheral lymphocytes of healthy donors and patients with no previous treatment exposed to different radioactive concentration of 153Sm-EDTMP (0.046 - 1.110 MBq/mL) were better adjusted by linear regression model (Y=A+BX). The chromosome damage induced by 153Sm-EDTMP observed in vitro was about 2 fold higher than that found in vivo for the group of patients with no previous treatment. The obtained data showed that the therapy with 153Sm-EDTMP induced a few quantity of cytogenetic damages in peripheral lymphocytes on hour after its administration in patients

  7. Radiotherapeutic efficacy of 153Sm-CMDTPA-Tyr3-octreotate in tumor-bearing rats

    A number of radiolabeled somatostatin analogs have been evaluated in animal tumor models for radiotherapeutic efficacy. The majority of the agents tested have used either high-energy beta-emitters, such as Y-90 or Re-188, or the Auger electron-emitting radionuclide, In-111. Because a medium-energy beta-emitter might have equivalent efficacy compared to high-energy emitters, and lower toxicity to non-target tissues, we have evaluated the therapeutic potential of the beta-emitting nuclide, Sm-153, chelated to the somatostatin analog, CMDTPA-Tyr3-octreotate. Using an in vitro binding assay, this octreotate derivative was shown to have high affinity for the somatostatin subtype-2 receptor (IC50 = 2.7 nM). Biodistribution studies in CA20948 tumor-bearing Lewis rats demonstrate that the Sm-153 labeled compound has high uptake and retention in tumor tissue (1.7% injected dose/g tissue, 4 hrs post injection) and has rapid overall clearance properties from non-target tissue. Radiotherapy studies were carried out using 153Sm-CMDTPA-Tyr3-octreotate and CA20948 tumor bearing Lewis rats at 7 days post implant. Dose regimens consisting of single and multiple i.v. injections of 5.0 mCi/rat (185 MBq) were employed over a time span of 7 days. Suppression of tumor growth rate was observed in all treated animals compared to untreated controls. Greater inhibition of tumor growth was observed in animals that received multiple doses. These studies indicate that medium-energy beta-emitting isotopes have considerable potential for the treatment of somatostatin receptor-positive tumors

  8. Uptake of 153Sm-EDTMP in normal, benign and malignant tumor tissue

    Riegel, A

    2001-01-01

    The present study was designed to investigate and compare the uptake of 153Sm-EDTMP (153Samarium-ethylenediaminetetramethylene phosphonate)and 99mTc-DPD (99mTechnetium-dicarboxypropane diphosphonate) into different soft tissue sarcoma cell lines and various tissue specimen in vitro. After 10-120 minutes of incubation at 22 sup o C and 37 sup o C with 153Sm-EDTMP, the uptake kinetics of this tracer in human soft tissue sarcoma cells SW 684 (fibrosarcoma) and SW 1353 (chondrosarcoma) were assessed. The uptake was temperature-dependent and higher into fibrosarcoma than in chondrosarconma. Normal bone tissue samples of rat and human were incubated with 153Sm-EDTMP and 99mTc-DPD. The uptake of 99mTc-DPD was higher than that of 153Sm-EDTMP. Various benign and malignant bone and soft tissue tumors and metastases of different primaries were treated in the same way. The uptake was generally very low, in the metastatic tissue specimen in part possibly due to their osteolytic character.

  9. Study on the standardization of the radioactivity measurement for 153Sm-EDTMP injection

    The safety and efficacy of the therapeutic radiopharmaceuticals directly depends on its dosage. In order to determine the radioactivity of 153Sm-EDTMP injection accurately, and ensure the safety and efficacy of the 153Sm-EDTMP injection, the standardization for the radioactivity measurement of 153Sm-EDTMP injection with dose calibrators was studied, in which 4π liquid scintillator and 4πβ-γ coincidence method were used to determine the values of radioactivity (the relative expanded uncertainty is less than 3%)for the 153Sm-EDTMP injection standard source with six experimental setups in four laboratories, then the dose calibrators were calibrated with the standard source. The results showed that a the type of dose calibrator,the container and the volume of the sample solution have effects on the results of measurement, but between 3 to 5 mL, the variation of the volume of sample solution has little effect on the results of measurement. At last the measurement conditions were obtained according to the results of the study. (authors)

  10. Fluorescence microscopic and microautoradiographic studies on apoptosis of bone tumor cells induced by 153Sm-EDTMP

    The apoptosis of bone tumor cells treated with internal irradiation by 153Sm-EDTMP was studied. The morphological changes in bone tumor cells were observed by fluorescence microscopic and microautoradiographic observations. It was found that bone tumor cells internally irradiated with 153Sm-EDTMP, displayed significant nuclear fragmentation and marked pyknosis as well as apoptotic bodies formation. The microautoradiographic study showed that 153Sm-EDTMP could permeate through cell membrane and displayed membrane-seeking condensation in tumor cells. Soon afterwards 153Sm-EDTMP could be phagocytized by the tumor cells and distributed in cytoplasm and nucleus in the form of phagosome. With the prolongation of observing time, the membrane-bounded apoptotic bodies was observed. With the lengthening of internal irradiation time by 153Sm-EDTMP, the inhibition rate of proliferation of bone tumor cells increased progressively. (10 refs., 9 figs., 1 tab.)

  11. Electron microscopic observations and DNA chain fragmentation studies on apoptosis in bone tumor cells induced by 153Sm-EDTMP

    The morphological changes observed by electron microscopy indicate that after internal irradiation with 153Sm-EDTMP bone tumor cells displayed feature of apoptosis, such as margination of condensed chromatin, chromatin fragmentation, as well as the membrane bounded apoptotic bodies formation. The quantification analysis of fragmentation DNA for bone tumor cells induced by 153Sm-EDTMP shows that the DNA fragmentation is enhanced with the prolongation of internally irradiated time. These characteristics suggest that 153Sm-EDTMP internal irradiation could induce bone tumor cells to go to apoptosis

  12. Treatment status of painful bone metastases with 153Sm-EDTMP

    The typical management of painful bone metastases is radiation therapy and the graduated use of opiate analgesics. As the development of nuclear medicine, bone-seeking radiopharmaceuticals have been utilized in cancer treatment, especially in management painful bone metastases. 153Sm-EDTMP (samarium-153-ethylenediamine tetramethylene phosphonate) offers a good choice of treating method in palliating pain, improving quality of life, decreasing the rate at which new painful sites develop, and decreasing management costs

  13. Labelling of MoAb with 153SmH1ETA: Preliminary results

    A method to label MoAb with Sm-153 using 1,5,9,13-tetraazacyclohexadecane N,N',N'',N''' tetraacetic acid (H4ETA) as a bifunctional chelator was developed. H4ETA and SmH1ETA were synthesized in our laboratory and characterized by IR spectroscopy, TGA (thermogravimetric analysis), SEM (Scattering Electronic Microscopy), EDAX (Elemental Dispersion Analysis by X-rays) and EPR (Electron Paramagnetic Resonance) at 6 K. The 153SmH1ETAMoAb was prepared by a simple incubation of the MoAb ior cea1, and the 153SmH1ETA complex at neutral pH and at room temperature for 24 h. The specific activity of the labelled antibody was 111 MBq/mg (3 mCi/mg). Sm-153(III) is commercially available with specific activities up to 318.2 GBq/mg. Therefore, under the conditions described above 153SmH1ETA labelled MoAb could be obtained with specific activity up to 1.14 GBq/mg (30.7 mCi/mg). (author)

  14. Determination of human absorbed dose of cocktail of 153Sm/177Lu-EDTMP, based on biodistribution data in rats

    The aim of this work was to estimate the absorbed dose due to compositional radiopharmaceutical of 153Sm/177Lu-EDTMP in human organs based on biodistribution data of rats by using OLINDA/EXM software. The absorbed dose was determined by the Radiation Dose Assessment Resource (RADAR) formulation after calculating cumulated activities in each organ. The results show that the organs that received the highest absorbed dose were the bone surface and red marrow (1.51 and 7.99 mGy/ MBq for 153Sm, and 1.98 and 10.76 mGy/MBq for 177Lu, respectively). According to the results, using of cocktail of 153Sm/177Lu-EDTMP has considerable characteristics as compared to 153Sm-EDTMP and 177Lu-EDTMP alone. (author)

  15. Production and first use of 153SmCl3-ion exchange resin capsule formulation for assessing gastrointestinal motility

    We produced an enteric-coated gelatine capsule containing neutron-activated 153Sm-labelled resin beads for use in gastrointestinal motility studies. In vitro test in simulated gastrointestinal environment and in vivo study on volunteers were performed. Scintigraphic images were acquired from ten volunteers over 24 h while blood and urine samples were collected to monitor the presence of 153Sm. All the capsules remained intact in stomach. This proved to be a safe and practical oral capsule formulation for whole gut transit scintigraphy. - Highlights: ► Enteric-coated gelatin capsule containing 153Sm-labelled resin was manufactured. ► In vitro disintegration test ensured targeted release properties of the formulation. ► In vivo volunteers study confirmed safeness and practical use of the formulation. ► 153Sm can be used as an alternative nuclide to 111In in GI transit scintigraphy.

  16. Scintigraphic dynamics valuation of bone metastasis in the course of the treatment of 153Sm-oksabifor

    In the present study we examined the role of bone scan with 99mTc-pyrophosphate treatment planning 153Sm-oksabifor followed by analysis of post-treatment monitoring of cancer patients with bone metastases

  17. Combined use of zoledronic acid and 153Sm-EDTMP in hormone-refractory prostate cancer patients with bone metastases

    Lam, Marnix G.E.H.; Rijk, Peter P. van [University Medical Center Utrecht, Department of Nuclear Medicine, P.O. Box 85500, Utrecht (Netherlands); Dahmane, Amel; Stevens, Wil H.M. [CIS bio International, Saclay (France); Klerk, John M.H. de [Meander Medical Center, Department of Nuclear Medicine, Amersfoort (Netherlands); Zonnenberg, Bernard A. [UMC Utrecht, Department of Internal Medicine, Utrecht (Netherlands)

    2008-04-15

    {sup 153}Sm-ethylenediaminetetramethylenephosphonic acid (EDTMP; Quadramet {sup registered}) is indicated for the treatment of painful bone metastases, whereas zoledronic acid (Zometa {sup registered}) is indicated for the prevention of skeletal complications. Because of the different therapeutic effects, combining the treatments may be beneficial. Both, however, accumulate in areas with increased osteoblastic activity. Possible drug interactions were investigated. Patients with hormone-refractory prostate cancer were treated with 18.5 MBq/kg {sup 153}Sm-EDTMP in weeks 1 and 3 and with 37 MBq/kg in week 15. Treatment with 4 mg zoledronic acid began in week 3 and continued every 4 weeks through week 23. In weeks 3 and 15, zoledronic acid was administered 2 days before {sup 153}Sm-EDTMP treatment. Urine was collected 48 h after injection of {sup 153}Sm-EDTMP, and whole-body images were obtained 6, 24 and 48 h post-injection. The effect of zoledronic acid on total bone uptake of {sup 153}Sm-EDTMP was measured indirectly by the cumulative activity excreted in the urine in weeks 1, 3 and 15. Biodistribution, safety, tolerability and effect on prostate-specific antigen level were also studied. The urinary excretion in week 3 divided by the urinary excretion in week 1 (baseline) times 100% was mean 98.4 {+-} 11.6% (median 96.2%). From week 1 to 15, after four zoledronic acid treatments, the mean ratio was 101.9 {+-} 10.7% (median 101.8%). Bioequivalence could be concluded by using a two-sample t test for both per-protocol (n = 13) and full-analysis sets (n = 18). Toxicity was comparable to of monotherapy with {sup 153}Sm-EDTMP. Zoledronic acid treatment does not influence {sup 153}Sm-EDTMP skeletal uptake. Combined treatment is feasible and safe. (orig.)

  18. Combined use of zoledronic acid and 153Sm-EDTMP in hormone-refractory prostate cancer patients with bone metastases

    153Sm-ethylenediaminetetramethylenephosphonic acid (EDTMP; Quadramet registered) is indicated for the treatment of painful bone metastases, whereas zoledronic acid (Zometa registered) is indicated for the prevention of skeletal complications. Because of the different therapeutic effects, combining the treatments may be beneficial. Both, however, accumulate in areas with increased osteoblastic activity. Possible drug interactions were investigated. Patients with hormone-refractory prostate cancer were treated with 18.5 MBq/kg 153Sm-EDTMP in weeks 1 and 3 and with 37 MBq/kg in week 15. Treatment with 4 mg zoledronic acid began in week 3 and continued every 4 weeks through week 23. In weeks 3 and 15, zoledronic acid was administered 2 days before 153Sm-EDTMP treatment. Urine was collected 48 h after injection of 153Sm-EDTMP, and whole-body images were obtained 6, 24 and 48 h post-injection. The effect of zoledronic acid on total bone uptake of 153Sm-EDTMP was measured indirectly by the cumulative activity excreted in the urine in weeks 1, 3 and 15. Biodistribution, safety, tolerability and effect on prostate-specific antigen level were also studied. The urinary excretion in week 3 divided by the urinary excretion in week 1 (baseline) times 100% was mean 98.4 ± 11.6% (median 96.2%). From week 1 to 15, after four zoledronic acid treatments, the mean ratio was 101.9 ± 10.7% (median 101.8%). Bioequivalence could be concluded by using a two-sample t test for both per-protocol (n = 13) and full-analysis sets (n = 18). Toxicity was comparable to of monotherapy with 153Sm-EDTMP. Zoledronic acid treatment does not influence 153Sm-EDTMP skeletal uptake. Combined treatment is feasible and safe. (orig.)

  19. Study on the synthesis of AMP derivatives for labeling with 153Sm and 166Ho

    This study describes the synthesis method and characterization of AMP-( Aminomethylene phosphonic acid): (PDTMP; BDTMP; DMPDTMP). AMP is synthesized by the condensation of correlative diamine, phosphorous acid and formaldehyde using a modified Mannich reaction in the presence of hydrochloric acid. Recrystallization of the crude product from water yields white crystals of pure legend, and subsequently characterized using 1H-NMR, IR spectroscopy, melting point, crystal picture, element analysis, metal trace analysis. Synthesized AMP, when tagged with therapeutic radio nuclides such as 153Sm and 166Ho are quite good. Complexes with RC purity and labeling efficiency 20 - 98% and above could be prepared by ordinary reaction condition. (author)

  20. Kit preparation of 153Sm-EDTMP and factors affecting radiochemical purity and stability

    A fast kit method was developed for the production of 153Sm-EDTMP in two steps avoiding the use of nitric acid, evaporation and sterilization of the final solution by autoclave. Methods of analysis for the determination of chemical and radiochemical purity in the radiopharmaceutical solution were established. Factors affecting radiochemical purity and stability of the complex as the molar ratio of EDTMP/Sm, concentration of phosphate buffer and neutralization of EDTMP prior kit preparation were also analyzed. The use of this radiopharmaceutical in rabbits and patients showed selective skeletal uptake. (author). 5 refs., 4 figs., 3 tabs

  1. DNA gel electrophoretic and microaut oradiographic studies on apoptosisin bone tumor cells after exposure with 153Sm-EDTMP

    1999-01-01

    The apoptosis in bone tumor cells is studied after 153Sm-EDTMP irradiation.Fragmented DNA is analyzed by agarose gel electrophoresis.Experimental observations show that 153Sm-EDTMP exposureinduces the internucleosomal DNA damage in bone tumor cells the DNAladder pattern formation in bone tumor cells is shown.At the same time,the microautoradiographic study indicates that 153153Sm-EDTMP could permeate through cell membrane and displays membrane-seeking condensation in bone tumor cells.Soon afterwards 153Sm-EDTMP could be phagocytized by the tumor cells and distributed in cytoplasm as well as nucleus in the form of phagosome.With the prolongation of observing time, the membrane-bounded apoptotic bodies are observed.

  2. Effect of 153Sm-EDTMP on hematopoiesis and vital organs of 93 patients with bone tumor

    In the present study data on blood cell count, serum biochemistry, electrolyte, enzyme and vital organs of 93 patients with bone tumor or metastasis were investigated before and after treatment with 153Sm-EDTMP. The results showed that, 7 days and 30 days after the administration of 153Sm-EDTMP (0.05). Although at 7 days, there was a declination of the granulocyte count, it returned to normal at 30 days (P>0.05). The platelet count was significantly decreased (0.05>P>0.01)at 30 days after the administration of 153Sm-EDTMP. Thirteen patients received 74-185 MBq (2-5 mCi/kg) and their myelo-biopsies at 3 and 18 months showed no sign of acute or chronic toxicosis

  3. Production of medical radioisotope 153Sm in the Tehran Research Reactor (TRR) through theoretical calculations and practical tests

    Highlights: ► Production of 153Sm isotope by neutron activation in a nuclear reactor was studied. ► Optimal parameters for weight and irradiation time were found. ► This study led to an empirical correction factor (kf). ► Kf enhanced the production procedure of the 153Sm radioisotope. ► The results led to nearly 60% decrease in the amount of material used in the production process. - Abstract: The feasibility of producing 2000–3000 mCi 153Sm by irradiation of 152Sm in 5 MW TRR was studied via TRR core simulation. In this study the cross-section of 152Sm (n,γ) 153Sm reaction from ENDF/B library was used. The effective activation cross section for production of 153Sm is obtained using the neutron spectra in different irradiation channel of the core. The activity of the simulated samples is calculated using the obtained fluxes and cross sections. Then samples were prepared and irradiated under different conditions and fluxes. The final production’s specific activity was measured by the standard dose calibrator ISOMED 1010. By comparison of the theoretical calculations and actual measurements, an empirical correction factor (Kf) was obtained, which is helpful in production procedure of the 153Sm radioisotope. The optimal weight of the samples and irradiation time was studied according to the flux calculations based on the location of the sample and saturated activity calculation. In order to test the proposed conditions, samples were prepared and were irradiated under the proposed conditions. According to the compared results with the initial irradiation condition, the new proposed sample which weighed 4 mg of Sm2O3 is acceptable for the labeling, therefore this study led to nearly 60% decrease in the amount of material used in the production process

  4. Fission spectrum averaged cross section measurements of some neutron threshold reactions of relevance to medical radionuclide production

    A resume is given of radiochemical measurements of nuclear reaction cross sections relevant to the production of some medically important radionuclides carried out at PINSTECH during the last decade. Systematic studies on fission neutron spectrum averaged cross sections of several threshold reactions, like (n, 2n), (n, p) and (n, α) on titanium, ruthenium, europium and dysprosium for the production of 45Ti, 96Tc, 153Sm and 153Gd are described. (orig.)

  5. Optimization of the preparation of 153Sm - EDTMP using natural samarium targets for clinical use

    153Sm (specific activity 3.7 to 5.55 GBq/mg) was produced by irradiating natural Sm2O3 at a flux of 2.2 x 1013 n x cm-2 x s-1. Ethylenediaminetetramethylenephosphonate (EDTMP) was synthesised according to a reported method. Complexation was carried out by varying experimental parameters such as mole ratios of metal to ligand, pH, time and temperature of reaction to obtain quantitative yields. The radiochemical purity of the complex was assessed by various analytical techniques including HPLC. In vitro ligand exchange studies were undertaken to ensure suitability of the product for therapy. Biodistribution studies were carried out in Wistar rats and adequate bone uptake, retention and rapid clearance from blood stream were observed. (author)

  6. Avidin-biotin system radiolabelling with 153Sm and its experimental study in pre-targeting radioimmunoimaging with anti-CEA McAb

    Objective: To evaluate the usefulness of 153Sm labelled avidin-biotin system in pre-targeting radioimmunoimaging (RII)with anti-CEA McAb. Methods: Chelate DTPA-biotin (DB2) was first radiolabelled with 153Sm and then bound this 153Sm-DB2 to streptavidin (SA). The labelling of McAb with 153Sm was conducted using the bifunctional chelate cyclic DTPA anhydride (cDTPAa). Experimental studies were carried out in nude mice bearing human colon carcinoma. The authors established two- and three-step strategies for avidin-biotin system pre-targeting techniques. In three-step method A, tumor-bearing nude mice were first injected with McAb-biotin followed by cold avidin (Av) 2 days later and then 153Sm-DB2 1 day after. But in three-step method B, one group of mice was injected with McAb-SA followed by cold biotin 2 days later, and 4 h after biotin, by 153Sm-SA. While two-step protocols consisted of the injection of 153Sm-SA 48 h or 96 h after pre-targeting with McAb-bition (method A); and the injection of 153Sm-DB2 48 h after the use of McAb-SA (method B). SPECT imaging was performed and biodistribution was studied at 4, 24, 48 or 72 h after injection of 153Sm labelled compounds. Results: The authors' results showed that: 1) The three-step method A allowed faster blood clearance of the 153Sm-DB2 and yielded higher T/NT ratios (5.76 at 4 h and 12.94 at 24 h). 2) In the two-step method A, a significant accumulation of 153Sm-SA was observed in the tumor of nude mice which were injected 153Sm-SA 2 days after pre-targeting. The uptake in the tumor was also relatively high even in nude mice received 153Sm-SA 4 days after pre-targeting, demonstrating that the McAb-bition was still bound to the tumors and accessible to the 153Sm-SA even after long period of time. 3) Two- and three-step method A could increase the T/NT ratio in RII, shortening the imaging time (24 and 4 h, respectively). Conclusions: Aforementioned studies provide an experimental evidence for the improvement of pre

  7. 153 SM-EDTMP (Samario como tratamiento del dolor óseo de origen metastático 153 SM-EDTMP (SAMARIO For the treatment of metastatic bone pain

    A. B. de la Calle

    2006-04-01

    Full Text Available Introducción: 153 Sm-EDTMP es un agente radioactivo que puede ser usado para el diagnóstico así como el tratamiento de algunas enfermedades. El objetivo de este estudio es evaluar la eficacia de 153 Sm-EDTMP en el tratamiento del dolor crónico debido a metástasis óseas en el cáncer de próstata. Material y métodos: Se realiza un estudio prospectivo dónde se incluyen siete pacientes con dolor crónico, en relación con metástasis óseas por cáncer prostático, a los que se les administra de forma intravenosa 153 Sm-EDTMP para controlar el dolor. La eficacia de este agente fue evaluada según los cambios obtenidos en la escala visual-analgésica de (EVA, tiempo en el que se alcanzó la respuesta terapéutica, efectos adversos y cambios en el consumo diario de analgésicos. Resultados: 2 de 7 pacientes (28.5% tuvieron remisión completa del dolor, 4 de 7 (37.2% remisión parcial (EVA ≥1 y ≤3 y 1 de 7 (14.3% no mostraron mejoría. La respuesta terapéutica ocurrió a los 10-30 días después de la administración del fármaco en 83.3% de los pacientes, 16.6% requirieron más tiempo. No se observaron efectos adversos mayores; 20% sintieron nauseas, 5% vómitos y 0% toxicidad hematológica. 5 de 7 pacientes (71.4% redujeron el consumo de analgésicos. Conclusiones: 153 Sm-EDTMP es seguro y eficaz para la paliación rápida del dolor ocasionado por metástasis óseas, aunque aún quedan importantes cuestiones que resolver, fundamentalmente sobre los factores que influyen en la respuesta terapéutica a este radiofármaco.Introduction: 153 Sm-EDTMP is a radioactive agent used for both the diagnosis and treatment of some diseases. The aim of this study is to evaluate the efficacy of 153 Sm-EDTMP for the treatment of chronic pain due to bone metastasis in prostate cancer. Material and methods: Prospective study including seven patients suffering chronic pain due to bone metastasis in prostate cancer to whom intravenous 153 Sm-EDTMP for pain

  8. Development of a {sup 186}Re-HEDP formulation and radio pharmacokinetics comparison with {sup 153}Sm-EDTMP; Desarrollo de una formulacion de {sup 186}Re-HEDP y comparacion radiofarmacocinetica con el {sup 153}Sm-EDTMP

    Bribiesca C, A.I

    1998-12-01

    Because of the growing interest in the use of the beta emitters radiopharmaceuticals applied to therapy in different cancer cases, we developed a formulation of {sup 186} Re-HEDP (hydroxy ethylidene diphosphonate) as a pain palliative in osseous metastases. Besides serving like therapeutic agent, together with the {sup 153} Sm-EDTMP (ethylene diamine tetra methylene phosphonate), which has already been synthesized and proved, labels EHDP could be very useful like a diagnostic agent in the pursuit of the illness. The irradiation conditions for Rhenium-186 were established by ORIGIN 2 codes for TRIGA reactors. A pharmaceutical formulation was developed employing a factorial experimental design obtaining a complex with a radiochemical purity over 90 %. The complexes {sup 186} Re-HEDP {sup 153} Sm-EDTMP were intravenous administered in BALB-C mice sacrifying them in several intervals of time in order to determine the cumulated activity in each organ to perform absorbed dose calculation by MIRD methodology (Medical Internal Radiation Dose). Radio pharmacokinetic data demonstrated that both complexes follow a biexponential kinetic of first order behavior. In the case of the {sup 186} Re-HEDP the value of the {alpha} constant was 0.2789 and {beta} 0.0006 with an effective dose of 2.56 (mSv)/MBq , while for the complex {sup 153} Sm-EDTMP the values of {alpha} to and {beta} were 0.9012 and and 0.616 respectively and the effective dose was 0.262 (mSv)/MBq. In conclusion, radiopharmaceutical {sup 153} Sm-EDTMP, showed a greater bone uptake and a minor effective dose, for which it is a better radiopharmaceutical, respect to with the formulation of {sup 186} Re-HEDP. (Author)

  9. Measurement of fission neutron spectrum averaged cross sections of some threshold reactions on europium: small scale production of no-carrier-added 153Sm in a nuclear reactor

    Employing the activation technique in combination with radiochemical separations and high-resolution γ-ray spectroscopy fission neutron spectrum averaged cross sections were measured for several (n, 2n), (n, p) and (n, α) reactions on isotopes of europium. Our measurements constitute the first systematic studies. Of special interest was the investigation of 153Eu(n, p)153Sm reaction for the production of no-carrier-added 153Sm in a nuclear reactor. Using 100% enriched 153Eu target, 97.21 MBq 153Sm per batch can be produced which is, however, not sufficient for medical application. (orig.)

  10. 153Sm -DOTA-phosphine-ruthenium and gold bimetallic complexes as new radio-theranostics

    Full text of publication follows. Since the pioneer discovery of cisplatin for biological applications by Rosenberg in the 1960's [Ref.1] metal complexes have become the most currently investigated and used class of compounds in cancer chemotherapy [Ref.2]. However in most cases, their mechanisms of action are still poorly understood. Imaging drugs aimed at understanding their mechanism of action and studying their pharmacokinetics is thus one of the key challenges of medicinal chemists today. To take up this challenge new DOTA-phosphine compounds were synthesized. It is a versatile tool to image organometallic complexes, and allowed the access to an unprecedented family of theranostics featuring Au and Ru complexes for the therapeutic moiety and 153Sm for the imaging part. The radiolabelling of the ligand was studied and the stability of corresponding complexes was evaluated. Their cytotoxicity was also tested on cancer cells, and their biodistribution was determined in vivo. References: [1] Rosenberg, B.; VanCamp, L.; Krigas, T., Inhibition of Cell Division in Escherichia coli by Electrolysis Products from a Platinum Electrode, Nature 1965, 205, 698-699; [2] Zhang, C. X.; Lippard, S. J., New metal complexes as potential therapeutics, Curr. Opin. Chem. Biol. 2003, 7, 481-489. (authors)

  11. Incremental value of metabolic radiotherapy of bone metastases with 153Sm-EDTMP in prostate cancer. About 67 cases

    Full text of publication follows. Introduction: painful bone metastases are common in advanced prostate cancer. Samarium-153-ethylenediaminetetra-methylenephosphonic acid (153Sm-EDTMP; Quadramet) is a beta-particles emitter that concentrates in the areas of enhanced osteoblastic activity and used for palliate pain from bone metastases. Our purpose is to evaluate the incremental value of the 153Sm-EDTMP, in patients affected of cancer of the prostate with painful bony metastasis. Methods: 67 patients with metastatic prostate cancer received a single bolus infusion of 153Sm (37 MBq/kg). All patients had painful bone metastases to more than one anatomical region. Bone specific pain, analgesic score, and blood count were evaluated before and after treatment with a receding of 38 months. Results: we observed a positive answer in 85% of the cases; this answer was complete in 35% of the cases. The results gotten after multiple administrations show that the cures could be repeated with results comparable to those of the first cure. The therapeutic efficiency is at least equivalent to those of the other therapeutic means, with nearly non-existent secondary effects. The only toxicity is of hematological order; it is the most often moderate and reversible with a complete recuperation at the end of 8 weeks. Besides, the effect on the pain came with an improvement of the quality of life of the patients treaties. Conclusion: due to its half-life of 46 hours and its beta emissions, a high dose rate of 153Sm can be delivered to regions adjacent to enhanced osteoblastic activity over a short period of time with little residual long term activity being left in the bone marrow. Its administration to patients with prostate cancer suffering from painful bone metastases that enhance on bone scans, offered clinical relevant pain relief with tolerable hematological toxicity and then enjoy a better quality of life. (authors)

  12. Development of a 186Re-HEDP formulation and radio pharmacokinetics comparison with 153Sm-EDTMP

    Because of the growing interest in the use of the beta emitters radiopharmaceuticals applied to therapy in different cancer cases, we developed a formulation of 186 Re-HEDP (hydroxy ethylidene diphosphonate) as a pain palliative in osseous metastases. Besides serving like therapeutic agent, together with the 153 Sm-EDTMP (ethylene diamine tetra methylene phosphonate), which has already been synthesized and proved, labels EHDP could be very useful like a diagnostic agent in the pursuit of the illness. The irradiation conditions for Rhenium-186 were established by ORIGIN 2 codes for TRIGA reactors. A pharmaceutical formulation was developed employing a factorial experimental design obtaining a complex with a radiochemical purity over 90 %. The complexes 186 Re-HEDP 153 Sm-EDTMP were intravenous administered in BALB-C mice sacrifying them in several intervals of time in order to determine the cumulated activity in each organ to perform absorbed dose calculation by MIRD methodology (Medical Internal Radiation Dose). Radio pharmacokinetic data demonstrated that both complexes follow a biexponential kinetic of first order behavior. In the case of the 186 Re-HEDP the value of the α constant was 0.2789 and β 0.0006 with an effective dose of 2.56 (mSv)/MBq , while for the complex 153 Sm-EDTMP the values of α to and β were 0.9012 and and 0.616 respectively and the effective dose was 0.262 (mSv)/MBq. In conclusion, radiopharmaceutical 153 Sm-EDTMP, showed a greater bone uptake and a minor effective dose, for which it is a better radiopharmaceutical, respect to with the formulation of 186 Re-HEDP. (Author)

  13. Evaluation of genotoxic and cytotoxic effects of 153 Sm-EDTMP in peripheral blood lymphocytes of bone metastasis patients

    In this study the cellular damage in peripheral lymphocytes after exposure to 153 Sm-EDTMP (Samarium-153 ethylene-diamine-tetramietylene-phosphonate) was determined using the technique of micronuclei analysis and differential coloration.153 Sm-EDTMP is a radiopharmaceutical used for pain relief in patients with bone metastases. The analysis of the frequency of micronuclei in patient blood samples obtained one hour after endovenous administration of radiopharmaceutical (41 MBq/kg) showed no statistical difference in relation to basal values in binucleated cells. However the analysis of damage distribution in mononucleated cells, showed that the patients without previous radiotherapy treatment presented a significant increase in the frequency of cells with one micronucleus and in those who had taken previous radiotherapy treatment, in cells with two or more micronuclei. The in vitro experiments conducted with the exposition of total blood to three radiation concentrations of 153 Sm-EDTMP (0.370, 0.555 and 1.110 MBq/mL) during one hour showed an increase in the frequency of micronuclei and necrotic and apoptotic cells with increasing radiation dose. Dose-response curves for healthy donors and patients with bone metastasis without previous radiotherapy treatment were constructed. The comparison of the curves showed that patients presented higher radiosensitivity, either micronuclei or dead cell (necrotic or apoptotic) percentages, than healthy donors. (author)

  14. Clinical benefit of bone-targeted radiometabolic therapy with {sup 153}Sm-EDTMP combined with chemotherapy in patients with metastatic hormone-refractory prostate cancer

    Ricci, Sergio; Pastina, Ilaria; Cianci, Claudia; Orlandini, Cinzia; Chioni, Aldo; Di Donato, Samantha [Hospital, Nuclear Medicine Service-PET Center, Rovigo (Italy); Boni, Giuseppe; Genovesi, Dario; Grosso, Mariano; AlSharif, Abedallatif; Mariani, Giuliano [Univ. of Pisa (Italy). Regional Center of Nuclear Medicine; Chiacchio, Serena [Univ. of Pisa (Italy). Regional Center of Nuclear Medicine; CNR Inst. of Clinical Physiology, Pisa (Italy); Francesca, Francesco [University Hospital, Pisa (Italy). Div. of Urology; Selli, Cesare [Univ. of Pisa (Italy). Section Urology; Rubello, Domenico [Nuclear Medicine Service-PET, Rovigo (Italy)

    2007-07-15

    Bone metastases are responsible for most of the morbidity associated with hormone-refractory prostate cancer (HRPC). {sup 153}Sm-ethylenediaminetetramethylene phosphonate ({sup 153}Sm-EDTMP) has been approved for palliation of painful skeletal metastases. We retrospectively investigated the possible synergistic effect on survival of {sup 153}Sm-EDTMP (given to HRPC patients for bone pain palliation) and chemotherapy. Forty-five HRPC patients were evaluated, with a median age of 71 years. The number of metastatic bone sites was {<=}10 in 25 patients and >10 in 20 patients. Median serum PSA was 224 ng/ml. Bone pain was mild in 6 patients, moderate in 16, severe in 22 and intolerable in 1. Fifteen patients were only treated with {sup 153}Sm-EDTMP (group A), while 30 patients also received chemotherapy (estramustine phosphate or mitoxantrone plus prednisone) at variable times: between 3 and 5 months after {sup 153}Sm-EDTMP (14 patients, group B) or within 1 month after {sup 153}Sm-EDTMP (16 patients, group C). Haematological toxicities observed after either regimen were in general mild, consistent with common observations after either {sup 153}Sm-EDTMP or chemotherapy, and without any additive adverse effects in the patients receiving both {sup 153}Sm-EDTMP and chemotherapy. Bone pain palliation to some degree was induced by {sup 153}Sm-EDTMP in 32/45 patients (71.1%), the proportion of patients with a favourable clinical response being significantly higher in group C than in group A (87.5% vs 53.3%, p = 0.0388). Also in terms of biochemical response (serum PSA levels), patients of group C performed significantly better than patients of group A (p = 0.0235). Overall median survival from the time of administration of {sup 153}Sm-EDTMP was 15 months in the total cohort of 45 patients, and was significantly longer in group C than in either group B (30 months vs 11 months, p = 0.023) or group A (30 months vs 10 months, p = 0.008). The results of this study confirm that

  15. 153Sm3+ and 111In3+ DTPA derivatives with high hepatic specificity: in vivo and in vitro studies

    Prata, M. I. M.; Santos, A.C.; Neves, M.; Geraldes, C. F. G. C.; Lima, J. J. P. de

    2002-01-01

    Two DTPA derivatives, a mono-amide derivative containing an iodinated synthon, DTPA-IOPsp (L1) and the ligand DTPA(BOM)3 (BOM=benzyloxymethyl) (L2), radiolabelled with 153Sm3+ and 111In3+, were studied as potential hepatospecific gamma scintigraphic agents. In vivo studies with Wistar rats show that the main excretory pathway for all the chelates studied is the hepatobiliary system. The complexes of L2 show even greater hepatobiliary specificity than L1, perhaps as a consequence of longer blo...

  16. Cytotoxic and genotoxic effects caused by {sup 153} Sm-EDTMP, combined with BrdU a thymidine analog; Efecto citotoxico y genotoxico causado por {sup 153} Sm-EDTMP, combinado con BrdU un analogo de timidina

    Morales A, E.; Ferro F, G.; Morales R, P. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2006-07-01

    The ablation of the bone marrow previous to the transplant by means of radiation and chemical antineoplastics its affect indiscriminately to the healthy tissues and in particular those that are in proliferation. The objective of this work is to determine the effect of the incorporation from the BrdU to the DNA on the genotoxicity and cytotoxicity of the cells of the bone marrow caused by the radiopharmaceutical {sup 153}Sm-EDTMP. The genotoxicity was determined by the rate of erythrocytes polychromatic micro nucleates (EPC-MN) and the cytotoxicity by the frequency of EPC. Both parameters determined in peripheral blood after the BrdU administration and {sup 153}Sm-EDTMP. The combination of the BrdU and r1 radiopharmaceutical produced a bigger cytotoxicity that the radiation and the BrdU alone; on the other hand it produced a reduction of the EPC-MN produced by the radiation, suggesting that the cytotoxicity didn't allow the expression of the genotoxicity. (Author)

  17. Evaluation of 153Sm-EDTMP in non-human primates: prelude to clinical trials in cancer patients

    Full text: We had earlier reported optimisation of parameters for satisfactory formulation of 153Sm-EDTMP using natural samarium (Sm203) irradiated targets validated by satisfactory bio localisation in rats and rabbits. In the present study, we have attempted to further establish the safety and efficacy of the product through animal studies in monkeys as a prelude to clinical studies in cancer patients. Natural Sm203 (3 batches) irradiated in high neutron flux positions in the Dhruva reactor for 7 days was dissolved in hydrochloric acid and complexed with EDTMP (using both a gift sample and in house synthesized product) under conditions earlier standardized by us. The radiochemical purity by paper chromatography over normal saline (98%) and biodistribution study in rats (2.5-3% ID in femurs at 1-120 hp.i.) revealed satisfactory complexation. Monkeys were administered about 1 mCi of 153Sm per kg and imaged up to 72 hours p.i. Rapid clearance from blood, insignificant retention in liver, kidney and other tissues, and good bone uptake were observed even at 2 h p.i. Prolonged good retention in the skeleton was observed up to 120 hours p.i. EDTMP doses of 2.5 mg/mouse were tolerated indicating a safety factor of about 200 in humans. Thus desirable biological features promising good efficacy in cancer patients have been demonstrated warranting clinical evaluation of this product

  18. (153)Sm(3+) and (111)In(3+) DTPA derivatives with high hepatic specificity: in vivo and in vitro studies.

    Prata, M I M; Santos, A C; Neves, M; Geraldes, C F G C; de Lima, J J P

    2002-07-25

    Two DTPA derivatives, a mono-amide derivative containing an iodinated synthon, DTPA-IOPsp (L(1)) and the ligand DTPA(BOM)(3) (BOM=benzyloxymethyl) (L(2)), radiolabelled with (153)Sm(3+) and (111)In(3+), were studied as potential hepatospecific gamma scintigraphic agents. In vivo studies with Wistar rats show that the main excretory pathway for all the chelates studied is the hepatobiliary system. The complexes of L(2) show even greater hepatobiliary specificity than L(1), perhaps as a consequence of longer blood circulation times due to their strong affinity towards HSA. The (153)Sm(3+) chelates are also more hepatospecific than the corresponding (111)In(3+) chelates. The La(3+) and In(3+) chelates of L(1) and L(2) show some structural and dynamic differences in aqueous solution, as studied by (1)H NMR spectroscopy. While only two nona-coordinated isomers were observed for the La(3+) complexes with both ligands, its number is much larger in the In(3+) complexes, with both octa- and hepta-coordinated species (with unbound side arms), as well as structural isomers for each coordination number. PMID:12121790

  19. Cytotoxic and genotoxic effects caused by 153 Sm-EDTMP, combined with BrdU a thymidine analog

    The ablation of the bone marrow previous to the transplant by means of radiation and chemical antineoplastics its affect indiscriminately to the healthy tissues and in particular those that are in proliferation. The objective of this work is to determine the effect of the incorporation from the BrdU to the DNA on the genotoxicity and cytotoxicity of the cells of the bone marrow caused by the radiopharmaceutical 153Sm-EDTMP. The genotoxicity was determined by the rate of erythrocytes polychromatic micro nucleates (EPC-MN) and the cytotoxicity by the frequency of EPC. Both parameters determined in peripheral blood after the BrdU administration and 153Sm-EDTMP. The combination of the BrdU and r1 radiopharmaceutical produced a bigger cytotoxicity that the radiation and the BrdU alone; on the other hand it produced a reduction of the EPC-MN produced by the radiation, suggesting that the cytotoxicity didn't allow the expression of the genotoxicity. (Author)

  20. Using the 154 Sm(p,d) reaction to extend the level scheme of 153 Sm to the continuum region

    Wilson, Emma; Beausang, Cornelius; Humby, Peter; Simon, Anna; Ross, Timothy; Hughes, Richard; Burke, James; Casperson, Robert; Koglin, Johnathon; Ota, Shuya; Allmond, James; McCleskey, Matthew; McCleskey, Ellen; Saastamoinen, Antti; Chyzh, Roman; Gell, Kristen; Tarlow, Tom; Vyas, Gargi; Starlite Collaboration

    2015-04-01

    Following an experiment performed at the Cyclotron Institute of Texas A&M University, the level scheme of 153 Sm is in the process of being extended. A beam of protons accelerated to 25 MeV impinged on an isotopically enriched 154 Sm target, inducing a (p,d) reaction, thereby producing energetically excited 153 Sm reaction products. The resulting γ-rays and deuterons were detected by the STARLiTe array, which consists of six Compton-suppressed HPGe gamma-ray detectors, and a ΔE-E Si telescope for charged particle identification. In the ongoing analysis of these data, the identification of new γ-rays has been possible. The deuteron spectrum will be used to identify high-lying continuum states, and angular momentum transfer values will be assigned using angular distributions and comparison with DWBA calculations. This work was partly supported by the US DofE under Grant Numbers DE-NA0001801, DE-FG02-05ER41379(UofR); DE-AC52-07NTJKTG(LLNL).

  1. Improving the dose-myelotoxicity correlation in radiometabolic therapy of bone metastases with {sup 153}Sm-EDTMP

    Pacilio, Massimiliano; Basile, Chiara [Azienda Ospedaliera San Camillo Forlanini, Rome (Italy). Dept. of Medical Physics; Ventroni, Guido; Mango, Lucio [Azienda Ospedaliera San Camillo Forlanini, Rome (Italy). Dept. of Nuclear Medicine; Ialongo, Pasquale [Azienda Ospedaliera San Camillo Forlanini, Rome (Italy). Dept. of Radiology; Becci, Domenico [University of Rome, Health Physics Postgraduate School, Rome (Italy)

    2014-02-15

    {sup 153}Sm-ethylene diamine tetramethylene phosphonic acid ({sup 153}Sm-EDTMP) is widely used to palliate pain from bone metastases, and is being studied for combination therapy beyond palliation. Conceptually, red marrow (RM) dosimetry allows myelotoxicity to be predicted, but the correlation is poor due to dosimetric uncertainty, individual sensitivity and biological effects from previous treatments. According to EANM guidelines, basic dosimetric procedures have been studied to improve the correlation between dosimetry and myelotoxicity in {sup 153}Sm-EDTMP therapy. RM dosimetry for 33 treatments of bone metastases from breast, prostate and lung tumours was performed prospectively (with {sup 99m}Tc-MDP) and retrospectively, acquiring whole-body scans early and late after injection. The {sup 153}Sm-EDTMP activity was calculated by prospective dosimetry based on measured skeletal uptake and full physical retention, with the RM absorbed dose not exceeding 3.8 Gy. Patient-specific RM mass was evaluated by scaling in terms of body weight (BW), lean body mass (LBM) and trabecular volume (TV) estimated from CT scans of the L2-L4 vertebrae. Correlations with toxicity were determined in a selected subgroup of 27 patients, in which a better correlation between dosimetry and myelotoxicity was expected. Skeletal uptakes of {sup 99m}Tc and {sup 153}Sm (Tc{sub %} and Sm{sub %}) were well correlated. The median Sm{sub %} was higher in prostate cancer (75.3 %) than in lung (60.5 %, p = 0.005) or breast (60.8 %, p = 0.008). PLT and WBC nadirs were not correlated with administered activity, but were weakly correlated with uncorrected RM absorbed doses, and the correlation improved after rescaling in terms of BW, LBM and TV. Most patients showed transient toxicity (grade 1-3), which completely and spontaneously recovered over a few days. Using TV, RM absorbed dose was in the range 2-5 Gy, with a median of 312 cGy for PLT in patients with toxicity and 247 cGy in those with no

  2. Improving the dose-myelotoxicity correlation in radiometabolic therapy of bone metastases with 153Sm-EDTMP

    153Sm-ethylene diamine tetramethylene phosphonic acid (153Sm-EDTMP) is widely used to palliate pain from bone metastases, and is being studied for combination therapy beyond palliation. Conceptually, red marrow (RM) dosimetry allows myelotoxicity to be predicted, but the correlation is poor due to dosimetric uncertainty, individual sensitivity and biological effects from previous treatments. According to EANM guidelines, basic dosimetric procedures have been studied to improve the correlation between dosimetry and myelotoxicity in 153Sm-EDTMP therapy. RM dosimetry for 33 treatments of bone metastases from breast, prostate and lung tumours was performed prospectively (with 99mTc-MDP) and retrospectively, acquiring whole-body scans early and late after injection. The 153Sm-EDTMP activity was calculated by prospective dosimetry based on measured skeletal uptake and full physical retention, with the RM absorbed dose not exceeding 3.8 Gy. Patient-specific RM mass was evaluated by scaling in terms of body weight (BW), lean body mass (LBM) and trabecular volume (TV) estimated from CT scans of the L2-L4 vertebrae. Correlations with toxicity were determined in a selected subgroup of 27 patients, in which a better correlation between dosimetry and myelotoxicity was expected. Skeletal uptakes of 99mTc and 153Sm (Tc% and Sm%) were well correlated. The median Sm% was higher in prostate cancer (75.3 %) than in lung (60.5 %, p = 0.005) or breast (60.8 %, p = 0.008). PLT and WBC nadirs were not correlated with administered activity, but were weakly correlated with uncorrected RM absorbed doses, and the correlation improved after rescaling in terms of BW, LBM and TV. Most patients showed transient toxicity (grade 1-3), which completely and spontaneously recovered over a few days. Using TV, RM absorbed dose was in the range 2-5 Gy, with a median of 312 cGy for PLT in patients with toxicity and 247 cGy in those with no toxicity (p = 0.019), and 312 cGy for WBC in those with toxicity

  3. A clinical trial of 153Sm EDTMP in promotion of bone metastatic cancer pains%153钐改善骨转移癌痛疗效观察

    王新

    2002-01-01

    Objective To evaluate the effect of 153Sm EDTMP in the bone metastatic cancer pains.Methods In treatment group(32 patients with bone metastatic diseases) 153Sm EDTMP were given by infusion for one time.In control group,32 patients received radiotherapy. The radio dose was DT30Gy,5 times per week for 2 weeks.Pain relief was used as criteria of response at the time treatment finished and 6 months later.Results At the time treatment finished,there were statistically differences in pain relief between two groups.Pains relief rate was superior to control group after 6 months (P< 0.05).Conclusion Treatment with 153Sm EDTMP one time can reduce apparently pains caused by bone metastases,which is conveniently used and well tolerated.

  4. Environmentally important radionuclides in nonproliferative fuel cycles

    T may become increasingly important because recent data from fast reactors (of the nonproliferative type) have confirmed production rates up to 12 times greater than previous estimates. Present radwaste systems do not selectively remove T. Recent projections indicate that releases of 14C by the global nuclear industry could exceed the natural production rate of 2.7 x 104 Ci/year by the year 1998 and could eventually stabilize at two times that rate. Recent experiments on the uptake of 99Tc reveal that soil-to-plant concentration factors for Tc appear to be two to three orders of magnitude greater than the value of 0.25 which is currently used in radiological assessments. Research is needed to determine reliable 99Tc soil-plant concentration factors because this radionuclide is released to the environment from fuel reprocessing and enrichment facilities. New calculations for certain reactors indicate that 232U may be formed in concentrations up to 4000 ppm. If these estimates are accurate, careful analysis should be made of possible releases of 232U which could result in external dose and food chain exposures. The environmental health aspects of these four radionuclides are discussed, as well as the potential for their release to the environment from nonproliferative fuel cycles. (orig./HP)

  5. Some radiation protection problems connected with the use of 186Re-HEDP and 153Sm-EDTMP for palliative therapy of of bone metastases

    The aim of this paper was to assess whether the ambulatory (outpatient) therapy with 186Re-HEDP and 153Sm-EDTMP is possible in the Czech Republic. Physical characteristics, administered activity, biokinetics of radiopharmaceuticals, radiation protection characteristics, irradiation of patients relatives as well as comparison with limits for rhenium-186 and samarium-153 radiopharmaceuticals are given. The outpatient administration of 186Re-HEDP and 153Sm-EDTMP with the subsequent keeping the patient for 6 hours in a department of nuclear medicine appears to be in compliance with regulations proposed in the Czech Republic as well as ICRP Recommendations. (J.K.) 1 tab., 12 refs

  6. Exposure of personnel and public due to using 153Sm-labelled EDTMP-Quadramet® in nuclear medicine procedures.

    Wrzesień, Małgorzata; Napolska, Katarzyna; Olszewski, Jerzy

    2016-03-01

    The main aim of this study was to highlight the problems of personnel exposure when administering (153)Sm-labelled ethylene diamine tetramethylene phosphonate-Quadramet(®) to patients and especially to evaluate hand exposure of the personnel. The exposure levels of patients' families and the people who takes care of the patients treated by Quadramet(®) were also estimated. Thermoluminescent detectors were used to measure the doses. The doses received during the injection of the Quadramet(®) by the nursing staff have been determined at the level of 1/150 dose limit for the skin. Exposure of members of the patient's family staying 1.5 m away from the patient being treated with Quadramet(®) has been estimated to be 0.40 mGy. PMID:26041475

  7. Experimental cross section for the 152Sm(n, γ)153Sm reaction at 0.0334 eV

    The neutron capture cross section for the 152Sm(n, γ)153Sm reaction at an energy of 0.0334 eV was measured for the first time using monochromatic neutrons of a powder diffractometer at the TRIGA Mark II nuclear reactor at Dhaka, Bangladesh. The 197Au(n, γ)198Au reaction was used to monitor the neutron beam intensity. The radioactivity of the products was determined via high resolution γ-ray spectrometry. The obtained cross section value is 184 ± 22b, which is consistent with both the ENDF/B-VII and TENDL-2012 data libraries. The measured value at 0.0334 eV and the previous data at 0.0536 eV confirm the reliability of the data in the above libraries. (orig.)

  8. Exposure of personnel and public due to using 153Sm-labelled EDTMP-QuadrametR in nuclear medicine procedures

    The main aim of this study was to highlight the problems of personnel exposure when administering 153Sm-labelled ethylene diamine tetramethylene phosphonate-QuadrametR to patients and especially to evaluate hand exposure of the personnel. The exposure levels of patients' families and the people who takes care of the patients treated by QuadrametR were also estimated. Thermoluminescent detectors were used to measure the doses. The doses received during the injection of the QuadrametR by the nursing staff have been determined at the level of 1/150 dose limit for the skin. Exposure of members of the patient's family staying 1.5 m away from the patient being treated with QuadrametR has been estimated to be 0.40 mGy. (authors)

  9. 99TC-MDP@153Sm-EDTMP治疗骨转移癌64例报告

    张萌萌; 常淑玲; 王淑芬; 张宗英; 郭忠

    2001-01-01

    @@恶性肿瘤骨转移(也称骨转移癌)导致的剧烈、持续性骨痛,给患者带来难以忍受的痛苦,放疗、化疗对骨转移癌的治疗已经临床证实疗效不明显.笔者应用99TC-MDP(99锝-亚甲基二磷酸盐)、153Sm-EDTMP(153钐-乙二胺四亚甲基磷酸)治疗收到较好疗效.现报道如下. 1资料与方法 1.1病例资料(1)治疗对象:经临床检查、SPECT全身显像诊断的54例恶性肿瘤骨转移患者中,肺癌18例,乳腺癌10例,直肠癌7例,肝癌3例,鼻咽癌2例,其他恶性肿瘤14例.本组执行“完整疗程”;(2)治疗对照组:经临床检查、SPECT全身显像诊断的10例恶性肿瘤骨转移患者中肺癌7例,乳腺癌2例,直肠癌1例. 1.2治疗药物99TC-MDP为中国核动力研究设计院成都同位素研究所提供,153Sm-EDTMP为中国原子能研究院,北京同位素应用研究所提供.

  10. Peptide labeling using 188Re, 188Re-MAG3 and 153Sm-H1ETA. A comparison on their in vitro lipophilicity

    Lanreotide peptide was labeled with 153Sm-H1ETA and 188Re-MAG3 in order to evaluate whether or not their conjugation to the peptide produce significant differences of the in vitro lipophilicity with respect to the 188Re-lanreotide prepared by the direct labeling method (highly lipophilic). The differences of lipophilicity between the complexes, were evaluated using a reverse phase HPLC system. The measured lipophilicity of 153Sm-H1ETA-lanreotide, 188Re-MAG3-lanreotide and 188Re-lanreotide was taken to be the capacity factor [k' = (tR - t0)/t0 where tR is the retention time and t0 is the dead time] for each of the complexes under identical chromatography conditions. Results showed that the in vitro lipophilicity decreased in the order 188Re-lanreotide (direct labeling), 188Re-MAG3-lanreotide and 153Sm-H1ETA-lanreotide. Since the last one has a capacity factor (k') similar to that of 188Re-MAG3, some renal elimination for 153Sm-H1ETA-lanreotide could be expected, which probably would reduce the unnecessary radiation dose to normal tissues. (author)

  11. Radiochemical and biological studies, including in non-human primates, towards indigenous development of 153Sm-EDTMP for metastatic bone pain palliation

    The combination of ease of formulation and superior biological features of 153Sm-EDTMP in terms of safety and efficacy for metastatic bone pain palliation, together with the prospect of better logistics of production, has prompted extensive efforts by many groups world over for its preparation and evaluation. Our efforts have been directed towards exploring the feasibility for formulation of 153Sm-EDTMP suitable for human use by neutron activation in medium flux reactors of the freely available and inexpensive natural samarium oxide target. The emphasis in biological studies was placed on tests in larger animals (monkeys) as a prelude to clinical evaluation. Feasibility to achieve reasonably high specific activity of 300-700 mCi/mg Sm at EOB with natural samarium has been adequately demonstrated. The radioeuropium contamination, estimated by γ-spectrometry to be 153Sm-EDTMP from natural samarium at high radioactive concentrations of 40-50 mCi 153Sm/mL, acceptable biolocalization, as revealed by both biodistribution studies in rats (femur uptake of 2-3% injected dose at 1h p.i. and retention up to 120 h p.i.) and gamma camera images in monkeys and adequate stability have been feasible. Excellent quality bone images of monkeys were recorded showing rapid clearance from blood, visualization of skeleton, clearance from kidneys within 2 hours and retention in skeleton up to 116 hours p.i. No significant activity in other soft tissues was noted. Comparative evaluation of the product prepared from enriched samarium as well as using in-house synthesized EDTMP has, likewise, revealed identical biolocalization features. EDTMP dose tolerance test in mice showed a safety factor of about 100 for a product made from natural samarium at an adult human dose of 50 mCi 153Sm. Feasibility for production, reasonable safety and satisfactory biolocalisation of the indigenous product has been adequately established so as to warrant clinical trials in patients. (author)

  12. Urine management after treatment with ''153 Sm-EDTMP (QUADRAMET); Gestion de la orina en el tratamiento con ''153 Sm-EDTMP (QUADRAMET)

    Delgado, A.; Diaz, J. P.; Carrasco, J. L.; Jimenez-Hoyuela, J. M.; Rebollo, A. C.; Martinez del Valle, M. D.; Ortega, S. J.

    2004-07-01

    The main purpose was to establish and to evaluate a new protocol of individualized treatment of patient urine after ''153 Sm-EDTMP injection, with a more efficient management of the wastes. Excreted urine was collected in an appropriate container form which, previous to sealing it, an aliquot of 10 ml was obtained. Experimental half-life (t1/2) of the isotope was then determined by measuring the activity at different times, besides the minimum time necessary for disposing of the radioactive wastes as regular trash. The measured half-life adjusted well to the theoretical value of the isotope. The time of considered storage oscillated between 19 and 26 days, based on the activity excreted by each patient. The main idea is the consideration of the set container-urine as solid waste: the evaluation of the minimum storage time necessary to its elimination is made in terms of legal limitation of specific activity by mass unit. The immediate advantages ares: the elimination of disagreeable scents by the storage of urine, it is not necessary a liquid waste disposal to eliminate it, and a more accurate knowledge of the specific activity at the moment of the elimination (dilution factor is not used). (Author) 10 refs.

  13. Radiolabelled 153Sm-chelates of glycoconjugates: multivalence and topology effects on the targeting of the asialoglycoprotein receptor

    In this paper we report and discuss the biodistribution studies with Wistar rats of a series of 153Sm(III)-glycoconjugates, based on DO3A and DO2A(cis) scaffolds (DO3A = 1,4,7-tris(carboxymethyl)-1,4,7,10-tetraazacyclododecane; DO2A(cis) = 1,4-bis(carboxymethyl)-1,4,7,10-tetraazacyclododecane). The effects of changing the sugar type (galactose, lactose and glucose), valency (mono and divalent) and topology on the targeting ability of the liver asialoglycoprotein receptor (ASGPR) are evaluated. Divalent glycoconjugates with different topologies were generated by a pendant glycodendrimeric (generation 1) architecture on a DO3A scaffold and by a linear DO2A(cis)-bis derivative. The results show that the galactose conjugates are more target efficient than the lactose analogues, while the glucose conjugates have no liver targeting ability. Divalent galactose conjugates are more efficiently targeted to the liver than the monovalent ones, while the dendrimeric topology of DO3A-Gal2 has higher targeting efficiency than that of the DO2A(cis)-Gal2. (orig.)

  14. Radiolabelled {sup 153}Sm-chelates of glycoconjugates: multivalence and topology effects on the targeting of the asialoglycoprotein receptor

    Torres, S. [Centro de Quimica, Campus de Gualtar, Univ. do Minho, Braga (Portugal); Martins, J.A.; Andre, J.P.; Neves, M. [Inst. Tecnologico e Nuclear, Sacavem (Portugal); Santos, A.C.; Prata, M.I.M. [Servico de Biofisica, IBILI, Univ. de Coimbra (Portugal); Geraldes, C.F.G.C. [Dept. de Bioquimica, Centro de Espectroscopia RMN e Centro de Neurociencias e Biologia Celular, Univ. de Coimbra (Portugal)

    2007-07-01

    In this paper we report and discuss the biodistribution studies with Wistar rats of a series of {sup 153}Sm(III)-glycoconjugates, based on DO3A and DO2A(cis) scaffolds (DO3A = 1,4,7-tris(carboxymethyl)-1,4,7,10-tetraazacyclododecane; DO2A(cis) = 1,4-bis(carboxymethyl)-1,4,7,10-tetraazacyclododecane). The effects of changing the sugar type (galactose, lactose and glucose), valency (mono and divalent) and topology on the targeting ability of the liver asialoglycoprotein receptor (ASGPR) are evaluated. Divalent glycoconjugates with different topologies were generated by a pendant glycodendrimeric (generation 1) architecture on a DO3A scaffold and by a linear DO2A(cis)-bis derivative. The results show that the galactose conjugates are more target efficient than the lactose analogues, while the glucose conjugates have no liver targeting ability. Divalent galactose conjugates are more efficiently targeted to the liver than the monovalent ones, while the dendrimeric topology of DO3A-Gal{sub 2} has higher targeting efficiency than that of the DO2A(cis)-Gal{sub 2}. (orig.)

  15. DNA gel electrophoretic and micro-auto-radiographic studies on apoptosis in bone tumor cells after exposure with 153Sm-EDTMP

    The apoptosis in bone tumor cells is studied after 153Sm-EDTMP irradiation. Fragmented DNA is analyzed by agarose gel electrophoresis. Experimental observations show that 153-EDTMP exposure induces the inter-nucleo-somal DNA damage in bone tumor cells. The DNA ladder pattern formation in bone tumor cells is shown. At the same time, the micro-auto-radiographic study indicate that 153Se-EDTMP could permeate through cell membrane and displays membrane-seeking condensation in bone tumor cells. Soon afterwards 153Sm-EDTMP could be phagocytized by the tumor cells and distributed in cytoplasm as well as nucleus in the form of phagosome. With the prolongation of observing time, the membrane-bounded apoptotic bodies are observed

  16. Dosimetric study of radium-223 chloride and 153Sm-EDTMP for treatment of bone metastases using MCNPX code and available experimental data

    Radium-223 chloride is an alpha emitter radiopharmaceutical which recently has been used for treatment of bone metastases. Absorbed and equivalent doses of 223RaCl2 were studied using MCNPX Monte Carlo code in a phantom consisted of bone marrow, bone and soft tissue. 153Sm-EDTMP as a beta emitter was also simulated for comparison with 223RaCl2. Results show that by injection of 100 µCi 223RaCl2 against 70 mCi 153Sm-EDTMP to a 70 kg adult man, equivalent dose of metastatic bone can be increased about six times without significant increase in delivered dose to healthy tissues. These results demonstrated acceptable agreement with experimental data. (author)

  17. The fate and importance of radionuclides produced in nuclear events

    Some of the major program at the Bio-Medical Division concerned with the fate and importance of the fission products, the radionuclides induced in the device materials, the radionuclides induced in the environment surrounding the device, and the tritium produced in Plowshare cratering events will be discussed. These programs include (1) critical unknowns in predicting organ and body burdens from radionuclides produced in cratering events; (2) the analysis with a high-resolution solid state gamma ray spectrometer of radionuclides in complex biological and environmental samples; (3) the characterization of radioactive particles from cratering detonation; (4) the biological availability to beagles, pigs and goats of radionuclides in Plowshare debris; (5) the biological availability to aquatic animals of radionuclides in Plowshare and other nuclear debris and the biological turnover of critical nuclides in specific aquatic animals; (6) the biological availability of Plowshare and other nuclear debris radionuclides to dairy cows and the transplacental transport of debris radionuclides in the dairy cow; (7) the persistence and behavior of radionuclides, particularly tritium, at sites of Plowshare and other nuclear detonations; and (8) somatic effects of Low Dose Radiation: Chromosome studies. (author)

  18. Environmentally important radionuclides in nonproliferative fuel cycles

    Our analyses indicate that more in-depth research should be done on 3H, 14C, 99Tc, and 232U, especially because of their presence in nonproliferative fuel cycles. For increased 3H production by fast reactors, we can only speculate that such research could show that environmental releases might be significantly greater than for LWRs. Carbon-14 will likely not be a problem if a suitable decontamination factor can be agreed upon for reprocessing facilities and if a satisfactory regulatory limit can be established for global populations. Additional experimental research is urgently needed to determine the uptake of low levels of 99Tc by plants. These data are essential before an accurate assessment of 99Tc releases can be made. Finally, we recommend that investigators take a closer look at the potential problems associated with 232U and daughters. This radionuclide could contribute a significant portion of the dose in both environmental and occupational exposures from the nonproliferative fuels

  19. The clinical value of treatment with 153Sm-EDTMP-89SrCl2 joint half volume method for bone metastatic carcinoma

    Objective: To explore therapeutic effects and side effects of half quantity 153Sm-EDTMP joint half quantity 89SrCl2 for patients with bone metastatic carcinoma. Methods: 264 patients with extensive bone metastasis were randomly divided into 4 groups. Group Ⅰ: 156 patients were treated with 153Sm-EDTMP, Group Ⅱ: 78 patient were given 89SrCl2, Group Ⅲ: 20 patients accepted the joint half volume therapy, Group Ⅳ (control group): 10 patients were given 4 ml physiological saline. After therapy, all patients were reviewed routine blood test every week in the next 2 months and bone scintigraphy after 36 months. The efficacy of alleviate pain, the time to onset and the duration, myelosuppression were recorded. one-way ANOVA and χ2-test were performed by SAS V8.2. Results: The alleviate pain efficiency of group Ⅰ, Ⅱ, Ⅲ respectively were 79.5% (124/156), 69.2% (54/78), 85% (17/20). No statistical significance among the 3 groups (P>0.05); Significant differences was existed between each group and the control group (P0.05); Group Ⅱ respectively had significant differences with group Ⅰ and Ⅲ (P 0.05); statistical significance existed between group Ⅰ and group Ⅱ, Ⅲ (P 0.05). Conclusion: Half dose 153Sm-EDTMP joint half dose 89SrCl2 therapy can achieve higher efficacy for bone metastatic carcinoma, and fewer side effect of myelosuppression. (authors)

  20. Prospective dosimetry with {sup 99m}Tc-MDP in metabolic radiotherapy of bone metastases with {sup 153}Sm-EDTMP

    Bianchi, L.; Marzoli, L. [Azienda Ospedaliera ' ' Ospedale di Circolo di Busto Arsizio' ' , Struttura Complessa di Fisica Sanitaria, Busto Arsizio, Varese (Italy); Baroli, A. [A.O. ' ' Ospedale di Circolo di Busto Arsizio' ' , Struttura Complessa di Medicina Nucleare, Busto Arsizio, Varese (Italy); Verusio, C. [A.O. ' ' Ospedale di Circolo di Busto Arsizio' ' , Struttura Complessa di Oncologia Medica, Saronno, Varese (Italy); Chiesa, C. [Fondazione Istituto Nazionale Tumori Milano, Struttura Complessa di Medicina Nucleare, Milan (Italy); Pozzi, L. [Azienda Ospedaliera ' ' Ospedale di Circolo di Busto Arsizio' ' , Struttura Complessa di Fisica Sanitaria, Busto Arsizio, Varese (Italy)]|[Universita degli Studi di Milano, Scuola di Specializzazione di Fisica Sanitaria, Milan (Italy)

    2009-01-15

    On the basis of the encouraging results achieved in several clinical trials and its proven therapeutic efficacy, {sup 153}Sm-ethylene diamine tetramethylene phosphonic acid (EDTMP) has become widely used to palliate pain from bone metastases. The results reported in the literature have led the product suppliers (QUADRAMET registered, Schering) to suggest administering a fixed activity per kilogram (37 MBq/kg). However, considering the observed extreme inter-patient variability of skeletal uptake of {sup 153}Sm-EDTMP, a real therapy optimization would require the individualization of the activity to be administered on a dosimetric basis. This should be planned taking into account the generally accepted 2-Gy dose constraint to the haematopoietic red marrow, the critical organ in palliative treatments with beta-emitting, bone-seeking radiopharmaceuticals. Seven to 14 days before treatment with {sup 153}Sm-EDTMP, 44 patients underwent {sup 99m}Tc-methylene diphosphonate (MDP) total-body bone scan with two scans (the first within 10 min of injection, the second after 6 h). The percentage bone uptake (Tc{sub %}) was evaluated as the ratio between total counts at 6 h, adjusted for decay, and total counts at the first scan. Tc{sub %} was then compared to Sm{sub %} similarly derived from 10-min and 24-h whole-body scans. Tc{sub %} and Sm{sub %} were compared both with and without Brenner's method for soft tissue uptake. The correlation between Tc{sub %} and Sm{sub %} was R {sup 2} = 0.81 and R {sup 2} = 0.88 with and without soft tissue correction, respectively. The difference between their average values was statistically significant (Sm{sub %} = 64.3 {+-} 15.2, Tc{sub %} = 56.2 {+-} 16.0; p = 0.017) with soft tissue correction, while was not statistically significant (Sm{sub %} = 68.2 {+-} 15.5, Tc{sub %} = 66.9 {+-} 14.0; p = 0.670) without soft tissue correction. The rate of retention of {sup 99m}Tc-MDP in bone provides a reliable estimate of the {sup 153}Sm

  1. Automatic control system for measuring currents produced by ionization chambers; Automatizacao de um sistema de medidas de correntes produzidas por camaras de ionizacao e aplicacao na calibracao do {sup 18}F e {sup 153}Sm

    Brancaccio, Franco

    2002-07-01

    Ionization Chambers in current mode operation are usually used in Nuclear Metrology. Activity measurements are quickly performed by Ionization Chambers, with very good precision. For this purpose measurements of very low ionization currents, carried out by high quality instrumentation, are required. Usually, electrometers perform the current integration method under command of signals from an automation system, in order to reduce the measurement uncertainties. Among the measurement systems at the Laboratorio de Metrologia Nuclear (LMN) of IPEN, there are two ionization chamber systems. In the present work, an automation system developed for current integration measurements is described. This automation system is composed by software (graphic interface and control) and an electronic module connected to a microcomputer, by means of a commercial data acquisition card. Several test measurements were performed in order to determine the intrinsic uncertainty, linearity and stability of the system. Using calibrated radioactive solutions, the IG12/A20 chamber calibration factors for {sup 18}F and {sup 153}Sm were obtained, making possible to determine activities of these radionuclides. (author)

  2. 4.4 Physical Properties of the Most Important Radionuclides

    Noßke, D.; Mattsson, S.; Johansson, L.

    This document is part of Subvolume A 'Fundamentals and Data in Radiobiology, Radiation Biophysics, Dosimetry and Medical Radiological Protection' of Volume 7 'Medical Radiological Physics' of Landolt-Börnstein - Group VIII 'Advanced Materials and Technologies'. It contains the Section '4.4 Physical Properties of the Most Important Radionuclides' of the Chapter '4 Dosimetry in Nuclear Medicine Diagnosis and Therapy'.

  3. Random comparison study of the clinical response to 153Sm-EDTMP 1.0 mCi/kg and 1.5 mCi/kg

    Sixty-seven patient with painful bone metastases were randomized to two groups. Group 1 (n=34) received 1.0 mCi/kg of 153Sm-EDTMP and group II (n=33) received 1.5 mCi/kg. All of them met inclusion criteria and there was no significantly difference between the basic conditions of two groups. After receiving 153Sm-EDTMP intravenously, all patients were kept in close follow-up weekly with blood counting, physician visiting and collecting patient's self-filling-in diary including pain score, Karnofsky performance scale and analgesic consumption. The follow-up duration was six weeks. The final overall condition assessed by physician were graded into no change (including worse), slight relief, significant relief and complete relief. Only significant relief and complete relief were considered as effectiveness for pain relief. Haematological toxicity grade was evaluated based on the nadir of WBC ad PLT counts. The results indicated that the higher dosage group had a higher effectiveness rate (75.76%) compared to the lower dosage group (67.65%), but without statistic significance (x2=0.5365, 0.25153Sm-EDTMP could be used for those patients with better haematological function and 1.0 mCi/kg used for those patients with poorer haematological function. (author)

  4. Measurement of 153Sm-EDTMP bone uptake by whole-body scintigraphy and its application to individualized treatment dosimetry of bone metastasis

    To calculate a safe and effective 153Sm-EDTMP therapy dose, a whole-body scintigraphy technique for prospective individual dosimetry was developed and the results were compared with 5 h urine collection method in 20 patients with bone metastases. Anterior and posterior whole-body images were obtained 10 min and 5 h after intravenous injection of 740 MBq 153Sm-EDTMP and the bone uptake value was determined. There is a close correlation between the bone uptake value obtained from the whole-body scintigraphy and 5 h urine collection method (r = 0.93). The radiation absorption dose to red marrow was limited to 1.4 Gy and the administered activity calculated from bone uptake value by whole-body scintigraphy was 1.40-2.27 GBq (mean 1.90 GBq). If the activity was calculated according to the standard body weight of 37 MBq·kg-1, the administered activity would be 1.75-2.41 GBq (mean 2.18), the radiation absorption dose to red marrow would be 1.37-2.27 Gy (mean 1.63 Gy), but at these doses significant myelotoxicity would be anticipated, thus emphasizing the need for individual prospective dosimetry

  5. Experimental cross section for the {sup 152}Sm(n, γ){sup 153}Sm reaction at 0.0334 eV

    Uddin, M. Shuza; Datta, Tapash Kumar; Hossain, Syed Mohammod; Zakaria, A.K.M.; Islam, Mohammad Amirul; Naher, Kamrun; Shariff, M. Asad; Yunus, S.M. [Atomic Energy Research Establishment, Dhaka (Bangladesh). Inst. of Nuclear Science and Technology; Afroze, Nasmin [Atomic Energy Research Establishment, Dhaka (Bangladesh). Inst. of Nuclear Science and Technology; Jahangirnagar Univ., Dhaka (Bangladesh). Dept. of Physics; Islam, S.M. Ajharul [Jahangirnagar Univ., Dhaka (Bangladesh). Dept. of Physics

    2014-10-01

    The neutron capture cross section for the {sup 152}Sm(n, γ){sup 153}Sm reaction at an energy of 0.0334 eV was measured for the first time using monochromatic neutrons of a powder diffractometer at the TRIGA Mark II nuclear reactor at Dhaka, Bangladesh. The {sup 197}Au(n, γ){sup 198}Au reaction was used to monitor the neutron beam intensity. The radioactivity of the products was determined via high resolution γ-ray spectrometry. The obtained cross section value is 184 ± 22b, which is consistent with both the ENDF/B-VII and TENDL-2012 data libraries. The measured value at 0.0334 eV and the previous data at 0.0536 eV confirm the reliability of the data in the above libraries. (orig.)

  6. Environmentally important radionuclides in non-proliferative fuel cycles

    Increased emphasis in energy research is being given to the development of nonproliferative nuclear fuel cycles and to the assessment of potential release of radionuclides to the environment from these new cycles. Four radionuclides, 14C, 3H, 99Tc, and 232U, due to lack of adequate knowledge or anticipated increased production in nonproliferative fuel cycles, may require renewed consideration. Our projections indicate that releases of 14C by the global nuclear industry could exceed the natural production rate of 3.8 x 104 Ci/y by the year 2000 and could eventually stabilize at 2.3 times that rate. Tritium may become increasingly important, because recent data from fast reactors (of the nonproliferative type) have confirmed production rates up to 13 times greater than previous estimates. Present radwaste systems do not remove tritium. Recent experiments on the uptake of 99Tc reveal that soil-to-plant concentration factors for technetium appear to be two to three orders of magnitude greater than the value of 0.25 which has been adopted routinely in radiological assessments. Research is needed to determine reliable 99Tc soil-to-plant concentration factors because this radionuclide could be released at reprocessing and enrichment facilities. New calculations for certain reactors indicate that 232U may be formed in concentrations up to 4000 ppm. If accurate, such data will require careful analysis of possible releases of 232U because of external and food chain exposures. The environmental health aspects of these four radionuclides are discussed, as well as the potential for their release to the environment from nonproliferative fuel cycles. (author)

  7. To study on the gamma cascade and the exited intermediate levels schemata of 153Sm, 182Ta, 59Ni and 239U by method of summation of coincident pulses

    In this project, in order to strengthen the ability of research of nuclear data and nuclear structure on the neutron beam at Dalat Research Reactor, a spectrometer of summation of coincident pulses (SACP) was installed, it is used to study the gamma cascades of 59Ni, 153Sm, 182Ta and 239U. The results are used for postgraduate education. (author)

  8. Selected radionuclides important to low-level radioactive waste management

    NONE

    1996-11-01

    The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237.

  9. Selected radionuclides important to low-level radioactive waste management

    The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237

  10. Report of the consultants' meeting on comparative laboratory evaluation of therapeutic radionuclides and radiopharmaceuticals

    Therapeutic radiopharmaceuticals consist of two components - the radionuclide and the biological carrier. With regard to the radionuclide, an advantage of targeted radiotherapy is that there are a wide variety of radionuclides with different physical half-lives and radiation qualities that can be applied for this purpose. An important task is to select a radionuclide that is compatible with the needs of a particular clinical application. The identification of the ideal targeted radiotherapeutic for each potential clinical application is a difficult task because of the multitude of variables that must be considered, some relating to the radioisotope, and others to the biological carrier. Hence it is recommended that a Co-ordinated Research Programme be established by the Agency to enable participants to acquire and intercompare the methodological expertise to evaluate the relative merit of therapeutic radiopharmaceuticals. These studies will be performed using a model system selected either from those described in this report or a promising agent that has emerged in the time since this meeting. The molecular carrier will be labelled with 131I, 125I as well as other therapeutic radionuclides available to the participant (for example, 90Y, 186Re, 188Re, 153Sm, 166Ho, 165Dy). The potential radiopharmaceuticals will then be compared in a progression of studies evaluating biological integrity after labelling, internalisation and residualization of radioactivity in the tumour cell, in vitro cytotoxicity, tissue distribution, normal organ toxicity (determination of the maximum tolerated dose) and finally, therapeutic efficacy

  11. Formulation and evaluation of freeze-dried DOTMP kit for the preparation of clinical-scale {sup 177}Lu-DOTMP and {sup 153}Sm-DOTMP at the hospital radiopharmacy

    Das, Tapas; Banerjee, Sharmila [Bhabha Atomic Research Centre, Radiopharmaceuticals Chemistry Section, Mumbai (India); Chakraborty, Sudipta [Bhabha Atomic Research Centre, Isotope Production and Applications Div., Mumbai (India); Sarma, Haladhar D. [Bhabha Atomic Research Centre, Radiation Biology and Health Sciences Div., Mumbai (India)

    2015-07-01

    The objective of the present work is to develop and evaluate freeze-dried DOTMP kit, which could be utilized for the convenient and single-step preparation of clinical-scale {sup 177}Lu-DOTMP and {sup 153}Sm-DOTMP, both of which have shown potential as alternative agents for metastatic bone pain palliation. Freeze-dried DOTMP kits, each comprising a lyophilized mixture of 20 mg DOTMP and 8.75 mg NaOH, were prepared. The kits were used for the preparation of clinical-scale {sup 177}Lu-DOTMP and {sup 153}Sm-DOTMP complexes. The agents were prepared by dissolving the lyophilized powder in 1 mL of normal saline and incubating with {sup 177}LuCl{sub 3} or {sup 153}SmCl{sub 3}, produced in-house, for 15 min at room temperature. Pharmacokinetic behavior and biological distribution of the agents were studied by carrying out biodistribution as well as scintigraphic studies in normal male Wistar rats. Shelf-life of the freeze-dried kits was also ascertained. Clinical-scale {sup 177}Lu-DOTMP and {sup 153}Sm-DOTMP complexes, comprising up to 3.7 GBq (100 mCi) of activity, were prepared with > 99% radiochemical purity using the freeze-dried kits. The complexes exhibited high in vitro stability when stored at room temperature. Biological studies showed selective skeletal accumulation and insignificant uptake of the radiotracers in any of the vital organs/tissue. The non-accumulated activity exhibited primary urinary clearance. The kits had a shelf-life of 2 years when stored at 4 C temperature. Freeze-dried DOTMP kits, suitable for the preparation of clinical-scale {sup 177}Lu-DOTMP and {sup 153}Sm-DOTMP, have been developed and the radiochemical and biological behaviors of the radiolabeled agents have been studied. The use of the kit at the hospital radiopharmacy is expected to make the preparations easy and convenient. This in turn will enable the widespread dissemination of these promising agents towards their application for regular use.

  12. Formulation and evaluation of freeze-dried DOTMP kit for the preparation of clinical-scale 177Lu-DOTMP and 153Sm-DOTMP at the hospital radiopharmacy

    The objective of the present work is to develop and evaluate freeze-dried DOTMP kit, which could be utilized for the convenient and single-step preparation of clinical-scale 177Lu-DOTMP and 153Sm-DOTMP, both of which have shown potential as alternative agents for metastatic bone pain palliation. Freeze-dried DOTMP kits, each comprising a lyophilized mixture of 20 mg DOTMP and 8.75 mg NaOH, were prepared. The kits were used for the preparation of clinical-scale 177Lu-DOTMP and 153Sm-DOTMP complexes. The agents were prepared by dissolving the lyophilized powder in 1 mL of normal saline and incubating with 177LuCl3 or 153SmCl3, produced in-house, for 15 min at room temperature. Pharmacokinetic behavior and biological distribution of the agents were studied by carrying out biodistribution as well as scintigraphic studies in normal male Wistar rats. Shelf-life of the freeze-dried kits was also ascertained. Clinical-scale 177Lu-DOTMP and 153Sm-DOTMP complexes, comprising up to 3.7 GBq (100 mCi) of activity, were prepared with > 99% radiochemical purity using the freeze-dried kits. The complexes exhibited high in vitro stability when stored at room temperature. Biological studies showed selective skeletal accumulation and insignificant uptake of the radiotracers in any of the vital organs/tissue. The non-accumulated activity exhibited primary urinary clearance. The kits had a shelf-life of 2 years when stored at 4 C temperature. Freeze-dried DOTMP kits, suitable for the preparation of clinical-scale 177Lu-DOTMP and 153Sm-DOTMP, have been developed and the radiochemical and biological behaviors of the radiolabeled agents have been studied. The use of the kit at the hospital radiopharmacy is expected to make the preparations easy and convenient. This in turn will enable the widespread dissemination of these promising agents towards their application for regular use.

  13. Importance of initial management of persons internally contaminated with radionuclides

    The first one to three hours following a radiation accident during which internal contamination occurs provide the best and perhaps the only opportunity for preventing uptake of radionuclides. By using chemical manipulation in the GI tract or by hastening the material through the body, absorption can be reduced. Once absorbed, uptake in specific tissues can often be prevented by blocking agents, isotopic dilution or chelating agents. In order to supply prompt treatment, the medical department must have a well-defined action plan based on knowledge of the plant of laboratory operations, the radionuclides used, and medications required. (U.S.)

  14. Evaluation of the radiosensitizing to treatment with 153Sm-EDTMP, of haematopoietic cells of the bone marrow by means of bromodeoxyuridine incorporation into DNA, in a murine model

    Bromodeoxyuridine (BrdU) has been shown to have a radiosensitizing effect, and its incorporation into DNA prior to administration of a bone-seeking radiopharmaceutical could increase the efficiency of bone marrow ablation, and even increase the specificity of radiation exposure for therapeutic purposes. The aim of the present study was to determine the effect of BrdU incorporation into DNA on the genotoxic and cytotoxic effects of samarium-153 ethylenediaminetetra-methylene phosphonate (153Sm-EDTMP) in murine bone marrow cells. BALB/c male mice (N = 5 in each experiment) were treated with one of the following substances: a) BrdU (0.25 mg/g) b) 153-EDTMP (11.5 ± 3 MBq) c) BrdU (0.25 mg/g) plus 153Sm-EDTMP (11.5 ± MBq), there was also an untreated control. Cytotoxicity and genotoxicity were established by time-response and absorbed dose-response curves of polychromatic erythrocyte (PCE) and micro nucleated polychromatic erythrocyte (MN-PCE) frequencies, respectively, in murine peripheral blood samples in vivo. The significance of the differences between groups was determined by a variation of Dunett test for multiple groups and different-sized groups of a student test. Beta-absorbed dose fractions obtained from MNCP4B Monte Carlo computer code were used for mice bone marrow dosimetry calculations. At an average radiation absorbed dose of 0.38 Gy, 0.56 Gy and 0.82 Gy at 24, 40 and 72 h respectively, cells from animals treated with 153Sm-EDTMP showed a clear and significant induction of MN-PCE after 24 h, with the maximum response at 40 h, however, cells from group treated with BrdU plus 153Sm-EDTMP paradoxically showed MN-PCE frequencies only slightly higher than the control at the same absorbed dose. Treatment with 153Sm-EDTMP caused a slight reduction in PCE frequency, but exposure to BrdU or BrdU plus 153Sm-EDTMP induced a substantial and significant reduction in PCE frequency from 32 h to the end of the experiment (72 h). The PCE frequencies in the Brd

  15. Evaluation of the radiosensitizing to treatment with {sup 153}Sm-EDTMP, of haematopoietic cells of the bone marrow by means of bromodeoxyuridine incorporation into DNA, in a murine model; Evaluacion de la radiosensibilizacion al tratamiento con {sup 153}Sm-EDTMP, de las celulas hemotopoyeticas de la medula osea mediante la incorporacion de bromodesoxiuridina (BrdU) en el ADN, en un modelo murino

    Morales A, E.

    2008-07-01

    Bromodeoxyuridine (BrdU) has been shown to have a radiosensitizing effect, and its incorporation into DNA prior to administration of a bone-seeking radiopharmaceutical could increase the efficiency of bone marrow ablation, and even increase the specificity of radiation exposure for therapeutic purposes. The aim of the present study was to determine the effect of BrdU incorporation into DNA on the genotoxic and cytotoxic effects of samarium-153 ethylenediaminetetra-methylene phosphonate ({sup 153}Sm-EDTMP) in murine bone marrow cells. BALB/c male mice (N = 5 in each experiment) were treated with one of the following substances: a) BrdU (0.25 mg/g) b) {sup 153}-EDTMP (11.5 +- 3 MBq) c) BrdU (0.25 mg/g) plus {sup 153}Sm-EDTMP (11.5 +- MBq), there was also an untreated control. Cytotoxicity and genotoxicity were established by time-response and absorbed dose-response curves of polychromatic erythrocyte (PCE) and micro nucleated polychromatic erythrocyte (MN-PCE) frequencies, respectively, in murine peripheral blood samples in vivo. The significance of the differences between groups was determined by a variation of Dunett test for multiple groups and different-sized groups of a student test. Beta-absorbed dose fractions obtained from MNCP4B Monte Carlo computer code were used for mice bone marrow dosimetry calculations. At an average radiation absorbed dose of 0.38 Gy, 0.56 Gy and 0.82 Gy at 24, 40 and 72 h respectively, cells from animals treated with {sup 153}Sm-EDTMP showed a clear and significant induction of MN-PCE after 24 h, with the maximum response at 40 h, however, cells from group treated with BrdU plus {sup 153}Sm-EDTMP paradoxically showed MN-PCE frequencies only slightly higher than the control at the same absorbed dose. Treatment with {sup 153}Sm-EDTMP caused a slight reduction in PCE frequency, but exposure to BrdU or BrdU plus {sup 153}Sm-EDTMP induced a substantial and significant reduction in PCE frequency from 32 h to the end of the experiment (72 h

  16. Radiopharmaceutical therapy of bone metastases with {sup 89}SrCl{sub 2}, {sup 186}Re-HEDP and {sup 153}Sm-EDTMP: a dosimetric study using Monte Carlo simulation

    Strigari, L.; D' Andrea, M.; Benassi, M. [Regina Elena Cancer Institute, Laboratory of Medical Physics and Expert Systems, Rome (Italy); Sciuto, R.; Pasqualoni, R.; Maini, C.L. [Regina Elena Cancer Institute, Nuclear Medicine Department, Rome (Italy)

    2007-07-15

    The aim of the paper is to calculate the dose to bone surface and bone volume using a Monte Carlo particle transport model and to give quantitative arguments for activity prescription. This study simulates the dose delivery process to skeletal metastases by bone surface- and bone volume-seeking radiopharmaceuticals. Dose distributions for three radiopharmaceuticals, {sup 186}Re-HEDP, {sup 153}Sm-EDTMP and {sup 89}SrCl{sub 2}, frequently used for pain palliation therapies, were calculated using the EGSnrc Monte Carlo code. The model simulates a cylindrical geometry with regions of different constant density compositions and radioactivity distribution consistent with known biodistribution features of the three radiopharmaceuticals: superficial for phosphonates ({sup 186}Re-HEDP and {sup 153}Sm-EDTMP) and volumetric for {sup 89}SrCl{sub 2}. After 3D dose distribution calculation, dose-volume histogram reduction was carried out using the ''preferred Lyman'' method, which yields effective uniform dose (D{sub eff}) equivalent to the inhomogeneous dose distributions to the reference region (volume and surface). Our simulations showed that to obtain a delivered dose to bone surface equivalent to that obtained from {sup 89}SrCl{sub 2}, the administered activities of {sup 153}Sm-EDTMP and {sup 186}Re-HEDP should be increased by 37% and 48%, respectively, in comparison with those usually administered. These results prove theoretically the empirical results from clinical observations and show that improvement in bone pain palliation by means of radiopharmaceutical therapy should be expected for dose-guided prescription. (orig.)

  17. Radionuclides in sporocarps of medicinaly important fungi of Fruska Gora hill

    The content of radionuclides in six lignicolous saprophytic and parasitic fungal species was analyzed. Samples were collected in 1999 autumn at two sites of the Fruska Gora Hill. Since fungi absorb radionuclides mostly from the substrate, soil and tree samples were also collected and analyzed. Certain characteristics of fungal species play an important role in the process of radionuclide absorption. On the other hand, the degree of radionuclide accumulation is very important for the fungi of potential pharmaceutical significance. The results on the radioactivity concentration in the analyzed fungi could be used both for the bioindication investigations, soil and substrate contamination in particular, and for estimation of the forest ecological status. The activity concentration level of most critical radionuclide 137Cs was about ten times lower in these species then in Pholiota squarrosa, characterized by the highest activity concentration level of 55(4) Bq/kg (d.m.)

  18. 153Sm-lexidronam for augmentation of chemotherapy-based myeloablative regimes in patients with multiple myeloma and other haematological conditions undergoing bone marrow transplantation: a phase I dose-escalation trial

    Full text: Total body irradiation (TBI) is a useful conditioning regimen for bone marrow transplantation (BMT), but has unacceptable toxicity in some patients. High doses of bone-seeking radiopharmaceuticals may offer a useful alternative to TBI in BMT patients with marrow-based tumours. Nine patients (5 multiple myeloma [MM], 2 leukaemia, 1 lymphoma, I myelodysplasia) were enrolled in a dose escalation protocol based upon retained skeletal activity. Infused doses have ranged between 18 and 32 GBq of 153Sm-EDTMP in six patients treated. No adverse effects related to the infusion have been seen. Peripheral blood counts fell from day 7 post-treatment, persisting to the start of cytotoxic conditioning regimen at days 11-14 post-treatment. Five patients have engrafted, with one allogeneic transplant patient dying from acute rejection. Pre-treatment dosimetry was performed by gamma camera and whole-body probe counts. Post-therapy activities were estimated by serial dose meter readings and gamma camera images. The pre-treatment skeletal retention by gamma camera was 1.7-2.4 times the values based on probe data. Retained post-treatment skeletal activity predicted by dosimetry was significantly greater than that actually measured, confirmed in one case by urinary collection. This latter fact is most likely due to the nature of the interaction of 153Sm-EDTMP with bone at high doses

  19. Thermal neutron capture cross sections for the 152Sm(n,γ) 153Sm and 154Sm(n,γ) 155Sm reactions at 0.0536 eV energy

    Uddin, M. S.; Chowdhury, M. H.; Hossain, S. M.; Latif, Sk. A.; Islam, M. A.; Hafiz, M. A.; Mubin, S. H.; Zakaria, A. K. M.; Yunus, S. M.; Azharul Islam, S. M.

    2008-11-01

    The neutron capture cross sections for the 152Sm(n,γ) 153Sm and 154Sm(n,γ) 155Sm reactions at 0.0536 eV neutron energy were measured using an activation technique based on the TRIGA Mark-II research reactor, relative to the reference reaction 197Au(n,γ) 198Au. The activity was measured nondestructively using gamma-ray spectroscopy. Our measured values at this neutron energy are the first ones and are compared with 1/ v based evaluated cross sections reported in the ENDF/B-VII and JENDL-3.3 libraries. The measured value for the 152Sm(n,γ) 153Sm reaction is 0.28% lower than JENDL-3.3 and 0.48% higher than ENDF/B-VII. Our value for the production of 155Sm is about 3% and 2.3% higher than the evaluated value with ENDF/B-VII and JENDL-3.3 at 0.0536 eV, respectively.

  20. Concentrations of natural radionuclides in imported zirconium minerals

    Janković Marija M.

    2011-01-01

    Full Text Available The natural radioactivity in imported zircon samples used as glaze for ceramic tiles in the ceramics industry has been presented in this paper. The measurements were made by gamma spectrometry with a high purity germanium detector. The average activity concentrations of 238U and 232Th determined in the measured samples (3250 Bq/kg, and 556 Bq/kg, respectively are much higher than the concentrations found in the Earth’s crust. The activity concentration of 226Ra is also high in all analyzed samples, while 40K was not detected. The gamma index, I, the external hazard index, Hex, the internal hazard index, Hin, and the radium equivalent activity, Raeq, were calculated. Due to relatively high activity concentration level of uranium in imported zircon samples, specific regulations are necessary for zircon compound used in ceramic industry. It can be concluded that the investigated samples can be used as the component of ceramic glaze in the concentrations not above 3%.

  1. Europium-154 contamination levels in Samarium-153-EDTMP for radionuclide therapy

    Moro, L [Department of Medical Physics, Salvatore Maugeri Foundation, IRCCS, Scientific Institute of Pavia, 27100 Pavia (Italy); Fantinato, D [Department of Medical Physics, Salvatore Maugeri Foundation, IRCCS, Scientific Institute of Pavia, 27100 Pavia (Italy); Frigerio, F [Department of Industrial and Environmental Hygiene, Salvatore Maugeri Foundation, IRCCS, Scientific Institute of Pavia, 27100 Pavia (Italy); Shamhan, G [European School of Advanced Studies in Nuclear and Ionising Radiation Technologies, University Institute of Advanced Studies, 27100 Pavia (Italy); Angelovski, G [European School of Advanced Studies in Nuclear and Ionising Radiation Technologies, University Institute of Advanced Studies, 27100 Pavia (Italy)

    2006-05-15

    {sup 153}Sm-EDTMP, a useful non toxic bone seeking isotope in the palliative radionuclide therapy for bone metastases, is produced by neutron activation of enriched of {sup 152}Sm{sub 2}O{sub 3} targets. During the large-scale formation of {sup 153}Sm, however, there is a co-production of some long-lived radio nuclides, among which {sup 154}Eu is a major and inevitable radionuclide impurity. The level of {sup 154}Eu contamination was evaluated performing a gamma-ray spectrometry of a radiopharmaceutical sample and the urine of an administered patient. As expected, gamma-ray spectra revealed the presence of {sup 153}Eu in all the samples. The specific activity of {sup 153}Eu in the urine sample collected at 6 hours after injection is 21 Bq/ml and is less than 1 Bq/ml in 24 hr. The contamination levels of {sup 153}Eu, normalized to the corresponding activity of {sup 153}Sm, were 0.0012% in the residual and in the first urine sample and 0.0017% and 0.0031% at 30 and 54 hours after administration, respectively. The results of this study show that the level of the long-lived {sup 153}Eu impurity is not a limitation in the metastatic bone pain palliation due to the additional radiation dose burden, but could pose a cause of concern in case of discharging.

  2. Radionuclide contents in food products from domestic and imported sources in Nigeria

    Samples of some domestic and imported food products of nutritive importance to both the child population and the adult population in Nigeria were collected and analysed in order to determine their radionuclide contents. The samples were collected from open markets in major commercial cities in the country. Gamma-ray spectrometry was employed in the determination of the radionuclide contents in the products. The gamma-ray peaks observed with reliable regularity in all the samples analysed belong to naturally occurring radionuclides, namely 226Ra, 228Th and 40K. The activity concentrations of these radionuclides in both the domestic and imported products were observed to be not significantly different. Essentially radioactive elements such as 137Cs were not detected in any of the samples. The non-detection of 137Cs in the imported products may be attributed to the suitably modified agricultural practices and countermeasures being employed to reduce caesium uptake by plants after the Chernobyl nuclear reactor accident. It seems unlikely that the elemental concentrations in the food products analysed will contribute significantly to public health risks in the country, as the cumulative ingestion effective dose values from 226Ra and 228Th were found to be low. Although 40K has the highest activity concentrations in all the samples analysed, it is usually under homeostatic control in the body, and hence the concentrations are irrelevant to possible contamination in the food products analysed. (note)

  3. Optimization of production and quality control of therapeutic radionuclides and radiopharmaceuticals. Final report of a co-ordinated research project 1994-1998

    The 'renaissance' of the therapeutic applications of radiopharmaceuticals during the last few years was in part due to a greater availability of radionuclides with appropriate nuclear decay properties, as well as to the development of carrier molecules with improved characteristics. Although radionuclides such as 32P, 89Sr and 131I, were used from the early days of nuclear medicine in the late 1930s and early 1940s, the inclusion of other particle emitting radionuclides into the nuclear medicine armamentarium was rather late. Only in the early 1980s did the specialized scientific literature start to show the potential for using other beta emitting nuclear reactor produced radionuclides such as 153Sm, 166 Ho, 165Dy and 186-188Re. Bone seeking agents radiolabelled with the above mentioned beta emitting radionuclides demonstrated clear clinical potential in relieving intense bone pain resulting from metastases of the breast, prostate and lung of cancer patients. Therefore, upon the recommendation of a consultants meeting held in Vienna in 1993, the Co-ordinated Research Project (CRP) on Optimization of the Production and quality control of Radiotherapeutic Radionuclides and Radiopharmaceuticals was established in 1994. The CRP aimed at developing and improving existing laboratory protocols for the production of therapeutic radionuclides using existing nuclear research reactors including the corresponding radiolabelling, quality control procedures; and validation in experimental animals. With the participation of ten scientists from IAEA Member States, several laboratory procedures for preparation and quality control were developed, tested and assessed as potential therapeutic radiopharmaceuticals for bone pain palliation. In particular, the CRP optimised the reactor production of 153Sm and the preparation of the radiopharmaceutical 153Sm-EDTMP (ethylene diamine tetramethylene phosphonate), as well as radiolabelling techniques and quality control methods for the

  4. Experience on the neutron activation of natural/enriched Re, Sm, and Ho nuclides in a reactor for the production of radiotherapeutic radionuclides.

    Ishfaq, M M; Mushtaq, A; Jawaid, M

    1999-01-01

    In recent years, much effort has been concentrated on the use of beta-emitting radionuclides for the treatment of various cancers. The reports suggested the application of 186Re and 153Sm as radiotherapeutic radionuclides for the treatment of palliative widespread skeletal metastases, whereas 166Ho was suggested as an agent for radiation synovectomy. Hence, a study on the production of 186Re, 153Sm, and 166Ho radionuclides was carried out by neutron activation of the appropriate target materials using a Pakistan Atomic Research Reactor (PARR-1) at a neutrons flux of 1 x 10(4) n/cm2 s. These radionuclides were then converted to appropriate radiopharmaceuticals for their use on animals and patients. The targets of natural Re (metal), natural Sm2O3, enriched Sm2O3 (99.06%), Sm(NO3)3 (solid), Sm(NO3)3 (liquid), and Ho2O3 were irradiated in the PARR-1. After irradiation, the purity of these radionuclides were checked by a multichannel analyzer, Canberra series 85 (MCA) coupled with HPGe detector and then measured in radioisotope calibrator Capintec ionization chamber model CRC-5RH. The effect of the irradiation time and amount of target material was investigated on the production yields of the radionuclides. The results showed an increase in the specific activity of Re with an increase in the irradiation time from 1 to 72 h, whereas a decrease in the specific activity was observed with increase in the amount of Re from 10 to 100 mg. Similar results were obtained for 153Sm and 166Ho radionuclides. The results further indicated that the specific activity of powder target was much less than the liquid targets for 153Sm. Their conversion to the appropriate radiotherapeutic radiopharmaceuticals were also carried out by investigating the experimental conditions and acceptable quality of 186Re-HEDP and 153Sm-EDTMP complexes were prepared. These complexes were then used on animals and patients which showed good performance. PMID:10676528

  5. Radionuclides in domestic and imported foods in the United States, 1983-1986

    Cunningham, W.C.; Stroube, W.B. Jr.; Baratta, E.J.

    1989-01-01

    Findings in the Food and Drug Administration's Radionuclides in Foods program are summarized for samples collected between October 1, 1982, and September 30, 1986. All radionuclide findings for Total Diet and reactor samples were either in Action Range I or low in Range II of the surveillance and control recommendations given by the Federal Radiation Council. The only long-range trend noted was a continuation of the general decline in dietary intake of /sup 90/Sr since 1961. Imported food samples were analyzed for contamination after the Chernobyl nuclear accident. The findings for imported foods indicate that the surveillance efforts successfully targeted contaminated foods, and that contamination levels were below levels of concern for all but one oregano and 3 cheese samples.

  6. Vesicorectal fistula detected on direct radionuclide cystography--importance of fecal matter imaging.

    Aghaei, Atena; Sadeghi, Ramin; Saeedi, Parisa

    2014-01-01

    We report an 11 year old male patient with the history of imperforate anus, which was repaired surgically 4 years ago. He has been complaining of intermittent passing of urine into the rectum recently. The vesicorectal fistula in this patient was proven by imaging of the fecal matter post direct radionuclide cystography study. Our case showed that nuclear medicine imaging can be extended to unanimated objects such as patients' excrements or fluids with important diagnostic yields. PMID:24610652

  7. Concentrations of radionuclides in imported foods from foreign countries in Japan (2000-2003)

    Japanese law concerning prohibition against marketing insanitary foods, etc, has defined the limit of radioactivity level in imported foods (370 Bq/kg in total of 137Cs and 134Cs radioactivities) post Chernobyl accident and check for this has been performed by the Ministry of Health, Labor and Welfare. The present report describes results of additional examination, conducted by National Institute of Public Health, or the Kobe or Yokohama Quarantine Station, of radionuclide (γ-emitters) concentration in imported foods during the period 2000-2003. Foods examined are from northern (40 samples) and southern (8) America, Asia (66), Oceania (9), Africa (8) and Europe (12), and are 13 kinds of grains, 12 nuts/seeds, 1 potato, 17 fruits, 12 green/yellow vegetables, 13 other vegetables, 19 mushrooms, 4 seaweeds, 15 nonessential taste items like tea leaves, 19 fishes and 12 meats. Samples are those homogenized, freeze-dried or mineralized. The Ge-semiconductor detector connected with a pulse-height analyzer is used for γ-ray detection, mainly that of 137Cs and 134Cs, and for 40K as a natural radionuclide. Sample weights are 1,000-2,000 g and counting times, 100,000-300,000 seconds. Results reveal that 137Cs alone is detectable as a artificial radionuclide but its level is as low as that in similar Japanese foods. Thus the annual effective dose due to intake of 137Cs in imported foods is evaluated enough low in adults. (N.I.)

  8. Methodology for quantification of radionuclides used in therapy by bioanalysis 'in vitro'

    In Brazil, the radionuclides used for therapy are 131; 153 Sm, 90Y and 177 Lu, under routine or experimentally. The quantification of the radiopharmaceutical activity excreted by the patient through the bioassay method, can be an important tool for individualized dosimetry, aiming the planning of subsequent therapies. The Bioanalysis In Vitro Laboratory (LBIOVT) of the Service of Individual monitoring (SEMIN) of the Institute for Radiation Protection and Dosimetry (IRD/CNEN-RJ), Brazil, has equipment and procedures for gamma and beta spectrometry. These detection systems are calibrated in energy and efficiency, and used standard reference sources provided by the National Laboratory of Metrology of Ionizing Radiation (LMNRI/IRD/CNEN-RJ). The LBIOVT Quality System follows the guidelines of the ISO-ABNT-17025 standard and annually, the laboratory participates in national (PNI) and international (PROCORAD). With respect to the excreta samples from patients, these are collected immediately after administration of the radiopharmaceutical. During the first 24 hours, they are collected with the patient hospitalized, and depending upon the physical half-life of the radionuclide can also be collected in the patient's home. Both in hospital and at home, the excreta is handled, stored and transported in accordance with standards for clinical research, radiation protection and transport of radioactive and biological materials. The specific activity radionuclide is referenced to the date and time of collection, allowing further evaluation of biological individual half-life. The care with the registration of excreted volumes as well as possible loss of excreta during collection, may interfere with the interpretation of the measures, since the results are provided in specific activity (Bq / L). Regarding the bioassay laboratory, these results are reliable when the laboratory is certified and participates in intercomparison programs of measures and methods. The laboratory able

  9. Experimental study of the deformed nucleus {sup 153}Sm via ({rvec d},t) and average resonance capture as a test case for the multiorbit interacting boson fermion model

    Gollwitzer, A.; Hertenberger, R.; Metz, A.; Schiemenz, P.; Valnion, B.D.; Graw, G. [Sektion Physik der Universitaet Muenchen, D-85748 Garching (Germany); Blasi, N.; Lucchini, S.; Micheletti, S.; Pignanelli, M. [Dipartimento di Fisica dellUniversita di Milano, I-20133 Milano (Italy); de Leo, R. [Universita di Bari and Sezione INFN di Bari (Italy); Gill, R.L. [Brookhaven National Laboratory, Upton, New York 11973 (United States); Hategan, C. [Institute of Atomic Physics, Bukarest (Romania); Casten, R.F. [Yale University, A.W. Wright Nuclear Structure Laboratory, New Haven, Connecticut 06520 (United States)

    1998-06-01

    The {sup 154}Sm({rvec d},t) reaction at high energy resolution (n,{gamma}), average resonance capture (ARC), and coincidence measurements were performed to study the deformed nucleus {sup 153}Sm. Strength distributions from ({rvec d},t) and completeness for I{sup {pi}}= (1) /(2) {sup {minus}} and (3) /(2) {sup {minus}} states up to 1500 keV from ARC provide one of the first detailed tests of the interacting boson fermion model (IBFM) in a deformed nucleus in a multiorbit environment. For negative parity states the model accounts for the large number of low spin ( (1) /(2) {sup {minus}}, (3) /(2) {sup {minus}}) states much better than the Nilsson model since the even-even core in the IBFM calculations automatically includes excited vibrational states. The IBFM calculations also predict (d,t) spectroscopic factors better than the Nilsson model with pairing and Coriolis mixing. Neither the IBFM nor the Nilsson approach can explain the low lying positive parity states. The IBFM calculations show that for certain combinations of parameters, the monopole term in the boson-fermion Hamiltonian has more than a scaling effect: it can attenuate the Coriolis mixing (energy staggering). Finally suggested improvements in the treatment of pairing in the IBFM are made. {copyright} {ital 1998} {ital The American Physical Society}

  10. A preliminary investigation of radiation level and some radionuclides in imported food and food products

    A preliminary study of gross beta activity and content of some long-lived radionuclides associated with fission products in various types of imported food and food-products was carried out. Food samples were purchased monthly during 1976-1977 from general well-known supermarkets and local grocery stores up to a total of 89 samples. The gamma spectrum of long-lived radionuclides was searched using a 128 channel analyzer coupled with 3'' x 3'' NaI (T1) crystal detector. Two radionuclides were frequently found to be present in these food samples, viz. potassium-40 and cesium-137 and their concentrations were subsequently determined. The limits of detection under the conditions used for potassium-40 and cesium-137 were 0.04 and 0.03 pCi/g-wet weight, respectively. Samples were dry-ashed and counted for gross beta activity utilizing a low background anti-coincidence G.M. counter. The content of strontium-90 was also investigated concurrently by solvent extraction technique employing tri-n-butyl phosphate as an extractant. Results of the study are tabulated. (author)

  11. Parameter sensitivity and importance for radionuclide transport in double-porosity systems

    A type-curve methodology using four dimensionless parameters is developed for modeling radionuclide transport through a fractured, double-porosity system. A dimensionless velocity and a dimensionless dispersion coefficient are used to characterize transport through the fractures, while a dimensionless solute storage enhancement coefficient and a dimensionless time constant for matrix diffusion are used to characterize the coupling of the matrix to the fractures. Using the dimensionless parameters, parameter-variation curves are developed to exhibit the general response of a performance measure, nuclide travel time, with respect to the entire range of parameter variability. Parameter sensitivities are then calculated as the normalized derivatives of the parameter-variation curves for the dimensionless set of base-case values. The parameter sensitivities are then recast to find the response of the performance measure in terms of a natural set of dimensional parameters that characterize the double-porosity transport model. As a final step, importance coefficients are defined to ascertain the relative ranking of the natural set of base-case parameters. The method is demonstrated by presenting the results obtained by modeling the transport of an infinitely long-lived radionuclide through the Culebra Dolomite Member of the Rustler Formation, the most transmissive zone located above the Waste Isolation Pilot Plant in southeastern New Mexico

  12. Comparison of Different Internal Dosimetry Systems for Selected Radionuclides Important to Nuclear Power Production

    Leggett, Richard Wayne [ORNL; Eckerman, Keith F [ORNL; Manger, Ryan P [ORNL

    2013-08-01

    This report compares three different radiation dosimetry systems currently applied by various U.S. Federal agencies and dose estimates based on these three dosimetry systems for a set of radionuclides often identified in power reactor effluents. These dosimetry systems were developed and applied by the International Commission on Radiological Protection at different times over the past six decades. Two primary modes of intake of radionuclides are addressed: ingestion in drinking water and inhalation. Estimated doses to individual organs and to the whole body based on each dosimetry system are compared for each of four age groups: infant, child, teenager, and adult. Substantial differences between dosimetry systems in estimated dose per unit intake are found for some individual radionuclides, but differences in estimated dose per unit intake generally are modest for mixtures of radionuclides typically found in nuclear power plant effluents.

  13. Parameter sensitivity and importance for radionuclide transport in double-porosity systems

    A type-curve methodology using four dimensionless parameters is developed for modeling radionuclide transport through a fractured, double-porosity system. A dimensionless velocity and a dimensionless dispersion coefficient characterize transport through the fractures, while a dimensionless solute storage enhancement coefficient and a dimensionless time constant for matrix diffusion characterize the coupling of the matrix to the fractures. Using the dimensionless parameters, parameter-variation curves exhibit the general response of a performance measure, nuclide travel time, with respect to the entire range of parameter variability. Parameter sensitivities are then calculated as the normalized derivatives of the parameter-variation curves for the dimensionless set of base-case values. Parameter sensitivities are recast to find the response of the performance measure in terms of a natural set of dimensional parameters that characterize the double-porosity transport model. Importance coefficients are defined to ascertain the relative ranking of the natural set of base-case parameters. 15 refs., 15 figs., 6 tabs

  14. Radiochemical studies related to the development of new production routes of some diagnostic and therapeutic radionuclides

    Nuclear reaction cross section measurements were done in connection with the development of new production routes of the therapeutic and diagnostic radionuclides 32P, 71As, 72As, 73As, 74As, 82Sr, 90Y, 153Sm and 169Yb. Investigations on the production of n.c.a. 73Se using novel targetry were also performed. Integral cross sections were measured for the natS(n,p)32P, natZr(n,p)90Y and natEu(n,p)153Sm reactions using a 14 MeV d(Be) neutron field. The neutron spectrum was characterised using multiple foil activation and the code SULSA. Existing cross section data were validated within 10 - 15 %, thereby substantiating earlier evaluated and recommended excitation functions of the investigated reactions. It is inferred that for production of radionuclides via the (n,p) reaction, a fast neutron spectral source (e.g. spallation or fusion) would be better suited than a fission reactor. Proton and α-particle induced reactions were investigated in the high-mass area for the production of 153Sm and 169Yb via alternative routes. Measurements were done for the first time on the natNd(a,n)153Sm process over the energy range of 10 to 26.5 MeV and the possible production yield of 153Sm amounts to 2 GBq. The excitation function of the 169Tm(p,n)169Yb reaction was determined over the energy range from threshold to 45 MeV and compared with the results of nuclear model calculation based on the ALICE-IPPE code. A good agreement was found. The calculated possible production yields are lower than those via the conventional (n,γ) production route, but the produced 153Sm and 169Yb are in no-carrier-added form. Cross sections were also measured with regard to the production of 71As, 72As, 73As and 74As via the natGe(p,xn) processes and the results were compared with those from the ALICE-IPPE calculations. Possible yields were calculated together with potential impurities. The various processes contributing to the formation of 71As in the irradiation of natGe were analysed by performing

  15. Importance of biota in radionuclide transport at the SL-1 radioactive waste disposal area

    During summer 1981 and 1982, radioecological research was conducted at the Stationary Low Power Reactor-1 radioactive waste disposal area to: (1) identify vegetation, wildlife, and invertebrate species occurring at or using the area; (2) determine radionuclide concentrations in these various ecosystem components; and (3) to evaluate their respective roles in radionuclide uptake and transport through the surrounding environment. Cesium-137 concentrations detected in surface soils, small mammal excavated soils and small mammal tissues collected at the waste disposal site were significantly (P less than or equal to 0.05) greater than control area samples. Strontium-90 and 235U analyses of SL-1 and control area samples and projections of total mass of ecosystem components in SL-1 area will be completed in summer of 1983 at which time estimates will be made on the total quantity of fission and activation radionuclides occurring in ecological media at the SL-1 waste disposal area

  16. RADIOLOGICAL CRITERIA FOR PATIENT RELEASE FROM CLINIC AFTER RADIONUCLIDE THERAPY OF BRACHYTHERAPY WITH SEALED SOURCE IMPLANTATION

    M. I. M.I. Balonov

    2016-03-01

    Full Text Available Dose criteria for limitation of exposure incurred by persons helping the patients or living with patients discharged from hospitals following radionuclide therapy or brachytherapy with implanted sealed radionuclide sources have been proposed for national Russian regulation. By means of a conservative dosimetry model, the values of operational radiological criteria for patient discharge from hospital are substantiated, i.e. whole body activity for radionuclides 125I,131I,153Sm and 188Re as well as dose rate near patient body. Observance of suggested criteria included in the new Russian Standards for Radiation Safety (RSS-99/2009 will ensure radiation safety of people in near environment (family, close friends et ah.

  17. Screening the importance of soil micro-organisms on radionuclides mobility

    In surface soils, the native physical and chemical properties of the abiotic components mostly control the sorption-desorption processes but micro-organisms can significantly modify the speciation of trace elements and/or radionuclides and subsequently determine to a large extent their fate. Microorganisms, mainly bacteria and fungi, develop many strategies affecting indirectly or directly the behaviour of trace elements. Due to their activity, changes in the pore-water composition: pH, redox potential, may occur in relation with organic acid production or solid phase alteration, reduction or oxidation of metallic oxi-hydroxides, organo-metallic complexes mineralization... Micro-organisms may also directly vary the speciation of radionuclides as a result of bio-accumulation in living cells, bio-sorption on cellular components, direct reduction or oxidation, bio-methylation... Each of these microbial processes may either increase or decrease radionuclide mobility, depending on the element, the soil reactivity and the environmental conditions. The resulting effect of the involved processes remains still poorly known. This literature review is intended to give a comprehensive overview of the role of micro-organisms on radionuclide mobility. It aims at classifying these elements regarding to their potential aptitude to be sensitive to these microbial processes. It summarizes the theoretical effect of these mechanisms, resulting in a potential increase or decrease of the the solid-liquid distribution. The environmental significance and full impact of such processes on a range of biogeochemical cycles still remain to be confirmed by subsequent experiments on the most sensitive radionuclides. (This study is part of a research program supported by ANDRA). (author)

  18. Activation cross sections for the generation of long-lived radionuclides of importance in fusion reactor technology

    The proceedings contain the progress reports of the Coordinated Research Programme to measure and evaluate the activation cross sections for the generation of long-lived radionuclides of importance in fusion reactor technology and the contributed papers (9) presented at the Consultants' Meeting held at Argonne National Laboratory between 11-12 September 1989. A separate abstract was prepared for each paper. Refs, figs and tabs

  19. Radionuclide transport

    The availability of radionuclides to biota is discussed especially with reference to specific elements in local soils. Two annual plant species have received concentrated study. These are cheatgrass and tumbleweed, both important inhabitants of waste burial sites. Little is known concerning the radionuclide dynamics of perennial grasses, forbs, or shrub species. The potential for radionuclide transport by jackrabbits, waterfowl, small mammals, and biota inhabiting pond systems is discussed. Concentration ratios are tabulated

  20. Re-emergence of the important role of radionuclide generators to provide diagnostic and therapeutic radionuclides to meet future research and clinical demands

    Radionuclide generators have been the main stay of diagnostic nuclear medicine and it is no exaggeration to state that the growth of nuclear medicine would not have happened to the present levels but for the availability of 99Mo/99mTc generator. This article provides a brief account of the various radionuclide generators currently in clinical use or which have made substantial progress or likely to be materialized in the foreseeable future to bring evolutional progress in nuclear medicine. Further, a brief outline on the regulatory challenges and impact on radionuclide generator technology with the emergence of professionally run central radiopharmacies have been provided. (author)

  1. Activation cross sections for the generation of long-lived radionuclides of importance in fusion reactor technology

    The present report contains the Summary of the Second IAEA Research Co-ordination Meeting (RCM) on ''Activation Cross Sections for the Generation of Long-Lived Radionuclides of Importance in Fusion Reactor Technology'' which was hosted by TSI Research at Del Mar near San Diego and held from 29 to 30 April 1993. This RCM was organized by the IAEA Nuclear Data Section (NDS), with the cooperation and assistance of local organizers from TSI Research and Westinghouse Hanford Company. Tables of 14 MeV cross sections and cross sections below 14 MeV are included. The papers prepared and presented by the participants at the meeting has been published as separate report INDC(NDS)-286/L. 3 tabs

  2. Activation cross sections for the generation of long-lived radionuclides of importance in fusion reactor technology

    Following the recommendations of the International Nuclear Data Committee (INDC), the IAEA Nuclear Data Section has established a Co-ordinated Research Programme (CRP) on activation cross sections for the generation of long-lived radionuclides of importance in concentrating on the cross sections for the reactions suggested by the 16th INDC meeting. The first Research Co-ordination Meeting of the CRP was held at the IAEA Headquarters, Vienna, Austria, from 11 to 12 November 1991. The main objectives of the meeting were to review the results under the CRP and the status of long-lived activation cross section data and to fix the future working programme for the CRP. The proceedings contain the progress reports of the CRP and 12 contributed papers presented at the meeting as well as the summary of the conclusions and recommendations of the meeting. Refs, figs and tabs

  3. Report on the 1. research coordination meeting on 'Development of therapeutic radiopharmaceuticals based on 177Lu for radionuclide therapy'

    Radionuclide therapy (RNT) employing radiopharmaceuticals labelled with emitting radionuclides is fast emerging as an important part of nuclear medicine. Radionuclide therapy is effectively utilized for bone pain palliation, thus providing significant improvement in quality of life of patients suffering from pain resulting from bone metastasis. Targeting primary diseases by using specific carrier molecules labelled with radionuclides is also widely investigated and efficacious products have been emerging for the treatment of Lymphoma and Neuroendocrine tumours. In order to ensure the wider use of radiopharmaceuticals, it is essential to carefully consider the choice of radionuclides that together with the carrier molecules will give suitable pharmacokinetic properties and therapeutic efficacy. The criteria for the selection of a radionuclide for radiotherapy are suitable decay characteristics and amenable chemistry. However, the practical considerations in selecting a radionuclide for targeted therapy are availability in high radionuclidic purity as well as high specific activity and low production cost and comfortable delivery logistics. 177Lu is one of the isotopes emerging as a clear choice for therapy. Worldwide, the isotope is under investigation for approximately 30 different clinical applications, including treatment of colon cancer, metastatic bone cancer, non-Hodgkin's lymphoma, and lung cancer. 177Lu decays with a half-life of 6.71 d by emission of particles with Emax of 497 keV (78.6%), 384 keV (9.1%) and 176 keV (12.2%). It also emits photons of 113 keV (6.4%) and 208 keV (11%), that are ideally suited for imaging the in-vivo localization and dosimetric calculations applying a gamma camera. The physical half-life of 177Lu is comparable to that of 131I, the most widely used therapeutic radionuclide. The long halflife of 177Lu provides logistic advantage for production, QA/QC of the products as well as feasibility to supply the products to places far away

  4. Environmental radiological surveillance in perspective: the relative importance of environmental media as a function of effluent pathway and radionuclides

    Most published guidelines for environmental surveillance emphasize the collection and analysis of specific media (e.g. air, water, milk, direct radiation) without total regard for the potential dose impact of the radionuclides expected in or actually present in the effluent streams from nuclear facilities. To determine the relative importance of medium/nuclide combinations in environmental surveillance, the experience at major ERDA sites and at operating nuclear power plants was reviewed. Typical release rates for nuclide groupings (tritium, noble gases, radioiodine, mixed fission or activation products, and transuranics) in those effluent streams were followed through various environmental pathways. By using this scheme the environmental medium which is most prominent in the critical dose pathway to man was determined. It was also possible to determine points of short-or long-term contaminant accumulation. Following these calculations, each medium was ranked for a given nuclide/effluent pathway combination providing the relative importance of sampling specific environmental media with emphasis on the radiation dose to a critical population group. Finally, the results of these environmental pathway studies are presented in tabular form to provide ready reference for environmental surveillance program design or evaluation

  5. The importance of Matrix diffusion for the transport of mobile radionuclides in granitic rock - summary of laboratory - scale experiments

    Crystalline rock has been considered as a host medium for the repository of high radioactive spent nuclear fuel in Finland. Radionuclide transport take place along water-carrying fractures and matrix diffusion has been indicated to be an important mechanism, which will retard the transport of mobile fission and activation products. Transport properties of mobile radionuclides in crystalline rock have been studied by means of different laboratory-scale methods using rock-fracture and rock-core columns and a rock-block having a horizontally planar natural fracture (0.9 m x 0.9 m). Objective of this study was to examine the processes causing retention in solute transport through rock fractures, especially focused on the matrix diffusion. Results of this work can be used to estimate importance of matrix diffusion as a retention process during transport in different scales and flow conditions. Rock matrices of mica gneiss, unaltered, moderately altered and strongly altered tonalite and Kuru grey granite have been well characterised. Total porosity and the surface areas of mineral grains available for migration of species have been determined by the 14C-PMMA method. Pore apertures and geometry in mineral phases were analysed by field emission scanning electron microscopy (FESEM) and the minerals were quantified by energy dispersive X-ray micro analysis (EDX). The surface area of the solid rock was determined by the B.E.T. method. Hydrological properties of the columns or the natural fracture were characterised and flow paths were determined. Tracer experiments were performed using dye tracer uranin, and radioactive tracers HTO, 36Cl, 99Tc and 131I. Transport of tracers was modelled using modified migration models used in performance assessments, which were adapted for interpreting laboratory-scale experiments. The dominant matrix diffusion behaviour was demonstrated in porous ceramic columns. Demonstration of the effects of matrix diffusion in crystalline rock fracture

  6. Radionuclide therapy with bone-seeking compounds: Monte Carlo calculations of dose-volume histograms for bone marrow in trabecular bone

    Kvinnsland, Y.; Skretting, A.; Bruland, Oe.S. [Department of Nuclear Medicine, The Norwegian Radium Hospital, 0310 Oslo (Norway)

    2001-04-01

    The purpose of the present work was to investigate how haematopoietic stem cell survival is affected by the differences in the dose distribution that arise from different radionuclides contained in bone-seeking radiopharmaceuticals. This was carried out in three steps: (a) calculations of representative dose distributions in individual bone marrow cavities that are irradiated by sources of {sup 89}Sr, {sup 186}Re, {sup 117}mSn or {sup 153}Sm, uniformly distributed on the bone surfaces; (b) assessment of the corresponding haematopoietic stem cell survival and (c) a comparison of these results with results obtained using the assumption of a uniform dose distribution. Two different idealized models of the geometry of trabecular bone were formulated, each consisting of an infinite array of identical elements. Monte Carlo simulations were used to generate dose-volume histograms that were used to assess haematopoietic stem cell survival with two different assumptions about spatial cell distributions. Compared with a homogeneous dose distribution, the estimated cell survival was markedly higher for {sup 117}mSn and {sup 153}Sm, and only slightly different for {sup 89}Sr and {sup 186}Re. The quantitative results differed between the two geometric models and the assumptions about spatial cell distribution, but the trends were the same. The results imply that it is necessary to include dose distributions for individual bone marrow cavities in considerations concerning bone marrow toxicity. (author)

  7. Importance of the source term for the release of radionuclides from a repository in a salt dome

    The release of radionuclides from a backfilled and brine saturated repository in a salt dome is analyzed as a function of canister lifetimes and solubility limits. The relationship between the waste package and the multi-barrier system of the repository is discussed

  8. Importance of the speciation of radionuclides for the calculation of transfer coefficients: Application to soil-fungus transfer

    Full text: Transfer coefficients are commonly used as an approximation to the problem of quantifying the transit of radionuclides between an ecosystem's different characteristic receptor media. These coefficients are traditionally defined as the quotient between the specific activities of the receptor and the donor compartments. In the present study, the receptors were edible mushrooms and the donor, the soil. However, not all the radioactive contents of a soil are in a condition to be transferred. Instead, the fraction that is available will depend intimately on the capacity of the different compounds to which the radionuclides are associated to be taken up by the fungus. To analyse the cited capacity, we carried out a scheme of chemical speciation of the surface layer (0-5 cm) of the soils corresponding to two forest ecosystems (pine woods) that present a high productivity of mushrooms. This scheme consists of the sequential extraction of the available soil fraction (extractable with NH4OAc), that soluble in dilute acid (extractable with HCl 1M), that soluble in strong acid (extractable with HCl 6M), and the residue. We analysed the presence of different man-made (137Cs, 90Sr) and natural (40K, 226Ra) radionuclides in each of the soil fractions enumerated above and in two representative species of mushroom from the aforementioned two ecosystems: Hebeloma cylindrosporum and Lactarius deliciosus. Specifically, more than 75% of the concentrations of 40K and 137Cs present in the soils studied were found bound to fractions not accessible to exchange reactions (the fraction soluble in strong acid and the residue). This implies that they are not associated to chemical compounds capable of being transferred to the fungi's fruiting bodies. Therefore, it is totally inappropriate to calculate the transfer coefficients in the usual way, since this uses the total activity found in the soil layer being considered. By way of example, for 40K the traditional method

  9. Radionuclide therapy for metastatic bone palliation; Nuklearmedizinische Therapie von Skelettmetastasen

    Kurtaran, A.; Preitfellner, J. [Vienna Univ. (Austria). Universitaetsklinik fuer Nuklearmedizin; Havlik, E. [Allgemeines Krankenhaus, Vienna (Austria). Inst. fuer Biomedizinische Technik und Physik

    2000-07-01

    In patients with advanced osteoblastic bone metastases from malignant tumours, {beta}-emitting radiopharmaceuticals are used. These radiopharmaceuticals are in elemental form such as {sup 32}P, {sup 89}Sr or bound on a bone-seeking carrier like HEDP, HMDTP. The radionuclide therapy of bone metastases causes no serious side effects and is well tolerated by the patients. According to recommended criteria this therapy is palliative and serves mainly for pain relief. The effect of the therapy lasts for several months and may be repeated if required. (orig.) [German] Bei Patienten mit fortgeschrittenen osteoblastischen ossaeren Metastasen werden {beta}-Strahlung-emittierende osteotrope Radiopharmaka verwendet. Diese sind entweder Radionuklide in elementarer Form ({sup 32}P, {sup 89}Sr...) oder an einer knochenaffinen Traegersubstanz gebundene Radionuklide ({sup 153}Sm, {sup 186}Re...). Die Radionuklidterapie ist im Allgemeinen nebenwirkungsarm und belastet die Patienten wenig. Nach derzeit ueblichen Kriterien stellt diese Therapie eine palliative Massnahme dar und dient hauptsaechlich zur Schmerzlinderung. Die Wirkung haelt ueber mehrere Monate an und bei Bedarf kann die Therapie wiederholt werden. (orig.)

  10. Investigation into the concentration of radionuclides in major imported and exported foods and foodstuffs to derive data base on the radioactivity in vietnamese food and foodstuffs

    Investigation into radionuclides concentration in foods and foodstuffs and establishment of database on the radioactivity of the goods is important for the internal dose assessment for every country. Therefore, in the 2007-2008 the Ministry of Science and Technology Vietnam sponsored a Project encoded 11/09/NLNT with the aims of to identify and quantify the radioactivity of radionuclides in imported to and exported from Vietnam products. About 130 foods and foodstuffs samples were collected and analyzed for the radioactivity in it. The radionuclides analyzed in this work are natural occurring isotopes such as Bi-214, Ac-228 and that originated from the U and Th series and K-40. The artificial gamma emitter Cs-137 was subjected to the quantification also. Additionally, total alpha, beta and gamma in the samples were analyzed as well. Data obtained showed that the radioactivity of K-40, Ac-228, Bi-214, total beta, total alpha, and total gamma activity in Vietnamese foods and foodstuffs ranging from 10.4 Bq/kg to 856.6 Bq/kg with an average of 255.3 Bq/kg, from 0.3 Bq/kg to 9.0 Bq/kg (average 1.3 Bq/kg), from 0.3 Bq/kg to 3.1 Bq/kg (average 1.1 Bq/kg), from 2.1 Bq/kg to 519.3 Bq/kg (average 110.9 Bq/kg), and from less than the limit of detection (0.02 Bq/kg) to 306.7 Bq/kg (average 31.9 Bq/kg), respectively. The radioactivity range of both NORM and artificial radioisotopes in Vietnamese food and foodstuffs was comparable and low with those recommended by the ICRP. A preliminary estimate for the effective internal dose from food consumption among Vietnamese adults has been presented also. (author)

  11. A free database of radionuclide voxel S values for the dosimetry of nonuniform activity distributions

    The increasing availability of SPECT/CT devices with advanced technology offers the opportunity for the accurate assessment of the radiation dose to the biological target volume during radionuclide therapy. Voxel dosimetry can be performed employing direct Monte Carlo radiation transport simulations, based on both morphological and functional images of the patient. On the other hand, for voxel dosimetry calculations the voxel S value method can be considered an easier approach than patient-specific Monte Carlo simulations, ensuring a good dosimetric accuracy at least for anatomic regions which are characterized by uniform density tissue. However, this approach has been limited because of the lack of tabulated S values for different voxel dimensions and radionuclides. The aim of this work is to provide a free dataset of values which can be used for voxel dosimetry in targeted radionuclide studies. Seven different radionuclides (89Sr, 90Y, 131I, 153Sm, 177Lu, 186Re, 188Re), and 13 different voxel sizes (2.21, 2.33, 2.4, 3, 3.59, 3.9, 4, 4.42, 4.8, 5, 6, 6.8 and 9.28 mm) are considered. Voxel S values are calculated performing simulations of monochromatic photon and electron sources in two different homogeneous tissues (soft tissue and bone) with DOSXYZnrc code, and weighting the contributions on the basis of the radionuclide emission spectra. The outcomes are validated by comparison with Monte Carlo simulations obtained with other codes (PENELOPE and MCNP4c) performing direct simulation of the radionuclide emission spectra. The differences among the different Monte Carlo codes are of the order of a few per cent when considering the source voxel and the bremsstrahlung tail, whereas the highest differences are observed at a distance close to the maximum continuous slowing down approximation range of electrons. These discrepancies would negligibly affect dosimetric assessments. The dataset of voxel S values can be freely downloaded from the website www

  12. Radionuclide therapy in Russia: Experience, problems, and perspectives

    Full text: Radionuclide therapy in Russia has more than 50-years history. Radioiodine has been successfully used for the treatment of differentiated thyroid cancer and toxic goiter. Au-198 colloidal solution was used in the therapy of synovitis as well as mesothelioma. P-32 was used for polycythemia vera and metastatic bone pain palliation. The treatment was routinely performed in various radiological clinics. However, after the Chernobyl accident and due to more stringent radiation safety measures, it is now exclusively performed in the clinic of Medical Radiological Research Center RAMS, Obninsk. For the last 20 years, more than 10000 patients have been treated in the clinic including 200 children, mainly from the contaminated regions of Chernobyl accident. The palliative treatment of bone metastases is performed with home-produced 89Sr chloride in outpatient clinics and 153Sm-oxabifore in the clinic of MRRC. Nowadays majority of the 160 radionuclides of 80 chemical elements are produced in Russia and exported. Of these, only three are commonly used for therapy purposes, most common being the 131I for treatment of toxic goiter and thyroid differentiated cancer (about 2000 GBq annually). In Russia more than 50 thousand patients suffer from thyroid diseases. Other therapies include bone metastases with marked pain syndrome and hard bone and joint diseases. Radionuclide therapy in Russia is being expanded with the creation of radionuclide therapy departments in each region including Center of Nuclear Medicine and Radiopharmaceutics (CNMAR) in Obninsk. This city has many research and medical institutes, nuclear-physical and radiochemical departments with highly skilled personnel and industrial production of medical radionuclides and radiopharmaceuticals. Obninsk has a convenient geographical location for easy transportation of radiopharmaceuticals and patients. Under the aegis of CNMAR, many research works are being carried out to make radionuclide therapy more

  13. The IAEA co-ordinated research programme on activation cross sections for the generation of long-lived radionuclides of importance in fusion reactor technology. Final report

    The present report summarizes the final results of the IAEA Co-ordinated Research Programme on ''Activation Cross Section for the Generator of Long-lived Radionuclides of Importance in Fusion Reactor Technology''. The goal of the CRP was to obtain reliable information (experimental and evaluated) for 16 long-lived activation reactions of special importance to fusion reactor technology. By limiting the scope of the CRP to just 16 reactions it was possible to establish a very effective focus to the joint effort of many laboratories that has led to the generation of a set of valuable new data which provide satisfactory answers to several questions of technological concern to fusion. (author). 11 refs, 5 tabs

  14. Modifying radionuclide effects

    The metabolism and effects of radionuclides may be influenced by a number of dietary, physiological, and environmental factors. Some factors are studied which have been identified as potentially important determinants of radionuclide behavior: the reproductive performance of female rats exposed to 239Pu during pregnancy or lactation, and the relative contribution of cross-placental and milk transfer to offspring

  15. Activation cross sections for the generation of long-lived radionuclides of importance in fusion reactor technology

    This publication contains 19 papers on the determination of cross sections relevant for the generation of long-lived radioisotopes through neutron-induced reactions in the neutron range around 14 MeV of importance in D-T fusion reactor technology. Refs, figs and tabs

  16. Marine biogeochemistry of radionuclides

    Radionuclides entering the ocean from runoff, fallout, or deliberate release rapidly become involved in marine biogeochemical cycles. Sources, sinks and transport of radionuclides and analogue elements are discussed with emphasis placed on how these elements interact with marine organisms. Water, food and sediments are the source terms from which marine biota acquire radionuclides. Uptake from water occurs by surface adsorption, absorption across body surfaces, or a combination of both. Radionuclides ingested with food are either assimilated into tissue or excreted. The relative importance of the food and water pathway in uptake varies with the radionuclide and the conditions under which exposure occurs. Evidence suggests that, compared to the water and food pathways, bioavailability of sediment-bound radionuclides is low. Bioaccumulation processes are controlled by many environmental and intrinsic factors including exposure time, physical-chemical form of the radionuclide, salinity, temperature, competitive effects with other elements, organism size, physiology, life cycle and feeding habits. Once accumulated, radionuclides are transported actively by vertical and horizontal movements of organisms and passively by release of biogenic products, e.g., soluble excreta, feces, molts and eggs. Through feeding activities, particles containing radionuclides are ''packaged'' into larger aggregates which are redistributed upon release. Most radionuclides are not irreversibly bound to such particles but are remineralized as they sink and/or decompose. In the pelagic zones, sinking aggregates can further scavenge particle-reactive elements thus removing them from the surface layers and transporting them to depth. Evidence from both radiotracer experiments and in situ sediment trap studies is presented which illustrates the importance of biological scavenging in controlling the distribution of radionuclides in the water column. (author)

  17. Radionuclide transfer in Alpine ecosystems

    Although alpine ecosystems are only of limited extent in Europe and the world, they serve as an important socio-economic basis for food production and tourism for the local population. The specific climate conditions and agricultural practice do have influence on radionuclide transfer in Alpine regions. The paper describes basic processes governing radionuclide behaviour in Alpine ecosystems and gives parameters for vertical migration of radionuclide in soil, for soil-plant transfer as well as transfer of radionuclide to cow milk. (author)

  18. A case study on the importance of quality assurance and personnel training in environmental assessment of naturally occurring radionuclides

    An independent review of the remedial investigation activities at a Superfund site was performed at the request of the site owners. The site in question was being labeled as containing radioactive contamination by the state environmental protection agency based on the results of the remedial investigation sampling program, which reported above background concentrations of potassium-40 at the site. This determination would have resulted in the entire site being considered as a mixed waste hazard, with extreme consequences for the cleanup actions. The independent review of the site sampling, measurement techniques, data analysis, and report preparation discovered problems with each of these activities. These problems included failing to perform subcontractor quality assurance oversight, as well as internal quality assurance failures related to verification of critical data. Additionally, the staff at both the state environmental protection agency and the remedial contractor were poorly trained in the field of radioactive assessments and statistical data analysis. These problems delayed the site remedial actions on the most important contaminants, including xylene, arsenic, and various metals. The cost of the site remedial investigation was significantly increased, as over $300,000 were spent just on assessing and litigating the potassium-40 health hazard issue. The independent review concluded that the problems were caused by inadequate quality assurance programs compounded by a lack of proper training of the personnel performing the work. Either a good quality assurance program at the remediation contractor or use of effectively trained personnel analyzing the data would likely have avoided the problems

  19. Activation cross sections for the generation of long-lived radionuclides of importance in fusion reactor technology. Texts of papers presented at the third and final research coordination meeting

    The present report contains scientific and technical papers presented at the Third and Final IAEA Research Co-ordination Meeting (RCM) on ''Activation Cross Sections for the Generation of Long-lived Radionuclides of Importance in Fusion Reactor Technology'' which was hosted by the V.G. Khlopin Radium Institute and held in St. Petersburg, Russia, from 19-23 June 1995. The papers, collected in the report, contain results of measurements, model calculations and evaluations of cross sections for 16 activation reactions of special importance to fusion reactor technology leading to long-lived radionuclides. Refs, figs, tabs

  20. Cosmogenic radionuclides

    Beer, Jürg; Von Steiger, R

    2012-01-01

    Cosmogenic radionuclides are radioactive isotopes which are produced by natural processes and distributed within the Earth system. With a holistic view of the environment the authors show in this book how cosmogenic radionuclides can be used to trace and to reconstruct the history of a large variety of processes. They discuss the way in which cosmogenic radionuclides can assist in the quantification of complex processes in the present-day environment. This book aims to demonstrate to the reader the strength of analytic tools based on cosmogenic radionuclides, their contribution to almost any f

  1. A model of bone metastases and marrow response to radionuclide therapy using different half life isotopes

    Carolan, M.G.; Fernandes, V.; Metcalfe, P. [Wollongong Hospital, Wollongong, NSW (Australia). Department of Nuclear Medicine and Radiotherapy

    1998-06-01

    Full text: Bone metastases are one of the most common causes of cancer pain. External beam radiotherapy is quite effective and commonly used for the palliation of bone pain, especially where pain is well localised and not multifocal. Where multiple metastatic sites exist a systemic targeted radionuclide approach may be preferable. The nuclide currently used for this purpose is {sup 90}Sr. Other shorter half life isotopes used or proposed include {sup 153}Sm, {sup 186}Re and {sup 117}Sn. Tumour cell kill is not thought to be the primary means of bone pain control since the doses required are much higher than those required for pain relief. Clinical data show that the onset of pain relief is most prompt for the shorter half life isotopes (e-g. {sup 153}Sm, T{sub 1/2} = 1.9d) compared to {sup 90}Sr (T{sub 1/2} = 50.5d). However the duration of pain relief is more prolonged for {sup 90}Sr than for the shorter half life isotopes. The normal tissue limiting tolerance is the bone marrow. In this study the linear quadratic model with repair and repopulation is applied to the bone metastases and bone marrow using different half life isotopes to compare the effects on tumour cell population and myelotoxicity. The effect of combined long and short half life isotopes on marrow is modelled. Long and short half life combinations have been proposed to try to achieve prompt and prolonged pain control. The effect of fractionating doses of short half life isotopes is examined for tumour cell kill and myelotoxicity. Although pain palliation is not dependent only on cell kill, survival may be modestly improved due to a tumouricidal effect on those bone metastases which are too small to cause pain at the time of treatment. Results were obtained using a simple model with exponential dose rate and repopulation. Using two 10 Gy fractions at 0 and 10 days gives a ratio of tumour survival / marrow survival of - 5 compared to about 15 000 for a single 20 Gy fraction

  2. Radionuclide cisternography

    The purpose of this thesis is to show that radionuclide cisternography makes an essential contribution to the investigation of cerebrospinal fluid (CSF) dynamics, especially for the investigation of hydrocephalus. The technical details of radionuclide cisternography are discussed, followed by a description of the normal and abnormal radionuclide cisternograms. The dynamics of CFS by means of radionuclide cisternography were examined in 188 patients in whom some kind of hydrocephalus was suspected. This study included findings of anomalies associated with hydrocephalus in a number of cases, such as nasal liquorrhea, hygromas, leptomeningeal or porencephalic cysts. The investigation substantiates the value of radionuclide cisternography in the diagnosis of disturbances of CSF flow. The retrograde flow of radiopharmaceutical into the ventricular system (ventricular reflux) is an abnormal phenomenon indicating the presence of communicating hydrocephalus. (Auth.)

  3. Radionuclide cystography

    This paper reports on radionuclide cystography in infants and children for the detection of vesicoureteral reflux. Vesicoureteral reflux represents a common and potentially serious form of urinary tract pathology. Reflux accompanied by asymptomatic or inadequately treated urinary tract infections has been associated with significant sequelae, including renal scarring, hypertension, and end- stage renal disease. Although there are several advantages and disadvantages to both radionuclide and radiographic techniques for detection of reflux, radionuclide cystography has been found to be at least as sensitive as the voiding cystourethrogram (VCUG) for the detection of clinically significant reflux. The major advantage of radionuclide cystography is a significantly lower radiation dose as compared to VCUG. Both indirect and direct techniques for radionuclide cystography have been developed. In addition to detection of vesicoureteral reflux, indirect radionuclide cystography allows evaluation of differential renal function. Supplemental parameters that may be evaluated with direct radionuclide cystography include: quantitation of reflux, determination of bladder volume at which reflux occurs, evaluation of the dynamics of bladder emptying, and determination of residual bladder volume following voiding

  4. Determination of alpha radionuclides in fish

    In atmospheric water, external water and undercurrent the occurrence of radionuclides is usual. It is an important factor of quality of the environment. Plants ingest radionuclides from water and with they everyone. And it arises radioactivity infest food-chain. Radiotoxicity of this radionuclides is very deer sometimes. The sensitive radiochemical procedures for their determination are necessarily important. The poster presents the combined procedure used at our laboratory for determination of alpha radionuclides in biological samples. (authors)

  5. Importance of colloids in the transport within the dissolved phase (<450 nm) of artificial radionuclides from the Rhone river towards the Gulf of Lions (Mediterranean Sea)

    The significance of colloidal fractions regarding the transport of artificial radionuclides in natural water systems is underlined by using sequential ultrafiltration both in the Rhone freshwater and the marine area under and outside the influence of the river outflow. Indeed, the Rhodanian aquatic system represents an interesting test site as various artificial radionuclides are released into the Rhone river by several nuclear installations. We focused our study on 137Cs, 106Ru, 60Co, 238Pu and 239+240Pu. Our results show that Fe, Al and Organic carbon (OC) are the main components of colloidal matter. Colloids represent about 15% of dissolved (238Pu and 239+240Pu and have no significance on 137Cs flux

  6. Deposited radionuclides

    The results presented are from the nationwide programme to survey the fall-out levels of radionuclides in Finland. This programme includes results from the vicinities of the nuclear power plants at Loviisa and Olkiluoto. Analysis of deposition samples for their 3H, 89Sr and 90Sr, as well as 137Cs and other gamma radionuclide contents was continued. The results are given as a follow-up to the previous results. The cumulative deposition of long-lived radionuclides retained in soil was measured near the Finnish nuclear power stations. The 90Sr and 137Cs levels in deposition in 1979 were lower than in the previous two years, and no 89Sr was detected. The trend to slightly increasing 3H concentrations of previous years was reversed in 1979. The mean annual deposition of tritium at different sampling stations varied from 85 nCi/m2 (3.1 kBq/m2) to 180 nCi/m2 (6.7 kBq/m2). The total annual deposits of various fission product radionuclides have decreased continuously since the maximum in 1977. No short-lived radionuclides originating from either nuclear explosions or nuclear power plants were observed in 1979. (author)

  7. Deposited radionuclides

    Measurements were carried out to determine the fall-out levels of radionuclides in Finland including those from the surroundings of the nuclear power plants at Loviisa and Olkiluoto. Deposition samples were analysed for their 3H, 89Sr and 90Sr as well as 137Cs and other gamma radionuclide contents. 90Sr, 239,240Pu, as well as 137Cs and other gamma radionuclides deposited in soil were also measured. The 90Sr and 137Cs levels in deposition in 1978 remained at almost the same level as in 1977. The slightly increasing trend in 3H concentrations continued in 1978. The mean annual deposition of tritium at different sampling stations varied from 120 nCi/m2 (4.4 kBq/m2) to 200 nCi/m2 (7.4 kBq/m2). The total annual deposits of various fission product radionuclides during 1978 were smaller than during 1977. No increase in radioactivity originating from nuclear power plants could be observed. (author)

  8. Radionuclide carriers

    A new carrier for radionuclide technetium 99m has been prepared for scintiscanning purposes. The new preparate consists of physiologically acceptable water-insoluble Tcsup(99m)-carrier containing from 0.2 to 0.8 weight percent of stannic ion as reductor, bound to an anionic starch derivative with about 1-20% of phosphate substituents. (EG)

  9. Radionuclide cisternogram

    A radionuclide cisternogram is a nuclear scan test. It is used to diagnose problems with the flow of spinal fluid. ... a lumbar puncture include pain at the injection site, bleeding, and ... used during the nuclear scan is very small. Almost all of the ...

  10. Short-term Fallout Radionuclide Ratios and Mass Balance Identify New Suspended Sediments of Channel Origin and Importance of Catchment Flowpath

    Karwan, Diana; Pizzuto, James; Aalto, Rolf; Marquard, Julia; Aufdenkampe, Anthony; Harpold, Adrian; Benthem, Adam; Skalak, Katherine; Levia, Delphis; Siegert, Courtney

    2016-04-01

    Fallout radionuclides and their ratios, such as beryllium-7 (7Be) and lead-210 (210Pb), are used to determine suspended sediment source and age in catchments. The ratio of beryllium-7 to lead-210 (7Be/210Pb) on suspended sediment has been used to estimate the fraction of "new" sediment in suspension. In the application of this model, "new" suspended sediment is often assumed to originate from recent landscape surface erosion that is delivered to the stream network. Fallout radionuclide deposition can vary across watersheds and on an event basis in a single watershed due to factors such as storm type, atmospheric height, and storm origin. In the White Clay Creek watershed within the mid-Atlantic USA, single-event deposition of 7Be varies from 15 - 177 Bq m-2 and 210Pb varies from 0 - 10 Bq m-2. 7Be/210Pb ratios vary from 7.9 to 17 within event precipitation and from 0.8 to 12.8 on suspended sediment. "New" sediment varies from 6 - 100% over the course of these events. 7Be mass balance during events shows that the majority of 7Be is retained within the catchment and not exported on suspended sediment. During summer thunderstorms, less than 1% of 7Be deposited on the watershed exits the stream channel. By comparing this flux with the direct channel interception of 7Be deposition in precipitation and throughfall we can determine the minimum amount of 7Be leaving the watershed that could occur in the absence of surface erosion. For example in summer thunderstorms, the entirety of the 7Be exiting the watershed on suspended sediment is less than the total activity deposited on the channel in direct precipitation. Channel-intercepted fallout radionuclides can exit the catchment by multiple mechanisms including the tagging of subaerial fluvial deposits with event precipitation; hence "new" suspended sediment originates from within the channel rather than from surface erosion. During extreme events, such as Hurricane Irene, less of the suspended sediment has been newly

  11. Soil-fungi transfer coefficients: Importance of the location of mycelium in soil and of the differential availability of radionuclides in soil fractions

    Baeza, A. [Department of Physics, Faculty of Veterinary, University of Extremadura, Avda. Universidad s/n, Caceres 10071 (Spain)]. E-mail: ymiralle@unex.es; Guillen, J. [Department of Physics, Faculty of Veterinary, University of Extremadura, Avda. Universidad s/n, Caceres 10071 (Spain); Bernedo, J.M. [Department of Industrial Chemistry, University of Alcala, Alcala de Henares, Madrid 28871 (Spain)

    2005-07-01

    Soil-fungus transfer coefficients are usually defined as the ratio between the content of the fruiting bodies and that of the soil. Since, however, the methodology of how to determine the soil content is not firmly established, there exist a variety of definitions in the literature. We analyzed the {sup 137}Cs, {sup 90}Sr, {sup 40}K, and {sup 226}Ra content of mushroom and soil samples from two pine-wood ecosystems in Spain. The location of the mycelium in the soil profiles of these ecosystems was determined by means of the ergosterol concentration. The results showed the mycelium to generally be localized in the surface layer of soil (0-5 cm). We also carried out a speciation procedure for this layer of soil to determine the different degrees of association of the radionuclides in the soil. The results led us to propose some variations to the traditional definition used in quantifying radionuclide transfer. With these modifications, we were able to analyze Cs-K competition in several species of mycorrhizal and saprophytic fungi.

  12. Soil-fungi transfer coefficients: Importance of the location of mycelium in soil and of the differential availability of radionuclides in soil fractions

    Soil-fungus transfer coefficients are usually defined as the ratio between the content of the fruiting bodies and that of the soil. Since, however, the methodology of how to determine the soil content is not firmly established, there exist a variety of definitions in the literature. We analyzed the 137Cs, 90Sr, 40K, and 226Ra content of mushroom and soil samples from two pine-wood ecosystems in Spain. The location of the mycelium in the soil profiles of these ecosystems was determined by means of the ergosterol concentration. The results showed the mycelium to generally be localized in the surface layer of soil (0-5 cm). We also carried out a speciation procedure for this layer of soil to determine the different degrees of association of the radionuclides in the soil. The results led us to propose some variations to the traditional definition used in quantifying radionuclide transfer. With these modifications, we were able to analyze Cs-K competition in several species of mycorrhizal and saprophytic fungi

  13. Radionuclide migration in water reservoirs

    Toxicity degree and radiation effect of different radionuclides depend on multiple factors, whose interaction can strengthen or weaken the effects through the mechanism of nuclide accumulation by hydrobiontes. Stage of development of an aquatic organism, its age, mass and sex as well as lifetime and residence time of the organism in the given medium are of importance. The radionuclide build up depends on illumination, locale of the bioobject residence, on the residence nature. The concentration of radionuclides in aquatic organisms and bionts survival depend on a season, temperature of the residence medium, as well as salinity and mineral composition of water influence

  14. Improving radionuclide therapy in prostate cancer patients with metastatic bone pain

    Lam, M. G. E. H.

    2009-01-01

    Bone seeking radiopharmaceuticals are indicated in cancer patients with multiple painful skeletal metastases. The majority of these patients are hormone-refractory prostate cancer patients in an advanced stage of their disease. Bone seeking radiopharmaceuticals relieve pain and improve the patients quality of life. The mostly used radiopharmaceuticals are 89SrCl2 (Metastron), 153Sm-EDTMP (Quadramet) and 186Re-HEDP. Differences between 89SrCl2, 153Sm-EDTMP and 186Re-HEDP were investigated. It ...

  15. Development and validation of a simple model for cellular and cell cluster dosimetry with practical application in targeted radionuclide therapy

    The authors have developed an analytical technique for calculating the mean absorbed dose to the cell nucleus from a variety of spatial distributions of cells and activities and a wide range of emitted energies and radionuclides. The dose to the nucleus has been calculated using this method from activity distributed (1) on the cell surface (2) throughout the cytoplasm (3) throughout a cluster of cells (micrometastasis) and (4) on the surface of the cluster of cells. The derived absorption factors have been based on the latest point kernels of Berger and have been validated against published estimates. They show good agreement and the model has the advantage of being easily adapted for revisions and extensions of available low energy data. Data sets may be derived with the absorbed fractions or the absorbed dose per emission as a function of the radial extent of the activity, and either the individual energies of the emissions or the totality of the emissions from a particular radio-nuclide. The practical applications of the model have included: (a) calculation of the absorbed dose to radioimmuno-targeted micrometastasis in the peritoneum; (b) calculations of doses to cells labelled on the surface with some novel emitters such as 67Cu, 177 Lu, 153Sm, 111Ag, 186 Re, 188Re as well as 131I, 125I and 90Y; (c) comparison of doses to the cell nucleus from MIBG labelled with 125I and 131I and distributed in the cytoplasm of the cell; and (d) estimates of the absorbed dose to the cell nucleus from alpha emitters distributed on the surface of the cell

  16. Deposited radionuclides

    The measurements presented here were carried out for determination of the fallout levels of radionuclides throughout the country, including the areas surrounding the nuclear power plants at Loviisa and Olkiluoto. The 90Sr, 137Cs and 3H contents of deposition were determined and the results are given as a follow-up to the previous results. 89Sr and other gammaradionuclides in addition to 137Cs were measured from wet and dry deposition. Also 89-90Sr, 239-240Pu, 137Cs and other gammaradionuclides deposited in soil were measured. The radiochemical separation technique was used to determine 89Sr, 90Sr, 137Cs and 239-240Pu. Tritium contents were determined by liquid scintillation counting after electrolytic enrichment. Gammaradionuclides were measured by Ge(Li) spectrometry. In 1977 the contents of the long-lived radionuclides 90Sr and 137Cs in deposition increased to almost the same level as in the early '70s. This is due to the high-yield atmospheric nuclear weapon tests carried out by China. A slight increase in 3H deposition can also be noticed in 1977. The results of soil sample measurements indicate that practically all the activity is found in the top 20 cm layer. (author)

  17. Geomorphological applications of environmental radionuclides

    Geomorphologists have shown increasing interest in environmental radionuclides since pioneering studies by Ritchie and McHenry in the USA and Campbell, Longmore and Loughran in Australia. Environmental radionuclides have attracted this interest because they provide geomorphologists with the means to trace sediment movement within the landscape. They, therefore, facilitate investigation of subjects at the core of geomorphology, namely the rates and patterns of landscape change. Most attention has been focussed on the artificial radionuclide caesium-137 (137Cs) but more recently potential applications of the natural radionuclides lead-210 (210Pb) and beryllium-7(7Be) have been investigated (Walling et al., 1995; Wallbrink and Murray, 1996a, 1996b). The origin, characteristics and applications of these radionuclides are summarised. These radionuclides are of value as sediment tracers because of three important characteristics: a strong affinity for sediment; a global distribution and the possibility of measurement at low concentration. Geomorphological applications of environmental radionuclides provide unique access to detailed qualitative data concerning landscape change over a range of timescales

  18. EBS Radionuclide Transport Abstraction

    The purpose of this work is to develop the Engineered Barrier System (EBS) radionuclide transport abstraction model, as directed by a written development plan (CRWMS M and O 1999a). This abstraction is the conceptual model that will be used to determine the rate of release of radionuclides from the EBS to the unsaturated zone (UZ) in the total system performance assessment-license application (TSPA-LA). In particular, this model will be used to quantify the time-dependent radionuclide releases from a failed waste package (WP) and their subsequent transport through the EBS to the emplacement drift wall/UZ interface. The development of this conceptual model will allow Performance Assessment Operations (PAO) and its Engineered Barrier Performance Department to provide a more detailed and complete EBS flow and transport abstraction. The results from this conceptual model will allow PA0 to address portions of the key technical issues (KTIs) presented in three NRC Issue Resolution Status Reports (IRSRs): (1) the Evolution of the Near-Field Environment (ENFE), Revision 2 (NRC 1999a), (2) the Container Life and Source Term (CLST), Revision 2 (NRC 1999b), and (3) the Thermal Effects on Flow (TEF), Revision 1 (NRC 1998). The conceptual model for flow and transport in the EBS will be referred to as the ''EBS RT Abstraction'' in this analysis/modeling report (AMR). The scope of this abstraction and report is limited to flow and transport processes. More specifically, this AMR does not discuss elements of the TSPA-SR and TSPA-LA that relate to the EBS but are discussed in other AMRs. These elements include corrosion processes, radionuclide solubility limits, waste form dissolution rates and concentrations of colloidal particles that are generally represented as boundary conditions or input parameters for the EBS RT Abstraction. In effect, this AMR provides the algorithms for transporting radionuclides using the flow geometry and radionuclide concentrations determined by other

  19. Proposal of a calibration protocol of gamma chambers for estimation of the radionuclides incorporation in emergency situations

    In the last years in several countries has come increasing the concern with the possibility of accidents related to the transport and manipulation of open sources used in nuclear medicine. This carried out to the search of alternative methods for the monitoring of workers and individuals of the public exposed to the radionuclides incorporation like 131 I, 201 Tl, 153 Sm among others. One of the options to assist the demand for monitoring of the radionuclides incorporation is the use of gamma chambers that are medical diagnostic equipment available in the own centers of nuclear medicine. The gamma chambers are used to obtain images of patient to which are administered a radionuclide of well-known activity with diagnostic purposes. These equipment have among its components elements that spectrometric systems like those used in the evaluation of the internal incorporation for direct measurements, reason why besides its use for diagnosis by image they can be gauged with anthropomorphic simulators and also with punctual sources for the quantification of the radionuclides activity, distributed homogeneously in the human body or located in specific organs. This work presents the development of a calibration protocol of gamma chambers for the in vivo determination of radionuclides and it proposes the implementation of the protocol in centers of nuclear medicine of the 9 countries participants of the project OAS-ARCAL-RLA/9/049-LXXVIII - Harmonization of procedures of internal dosimetry (Argentina, Brazil, Colombia, Cuba, Chile, Mexico, Peru, Uruguay and Spain). The protocol is the base to establish an integrated net to attend in the response to emergencies using nuclear medicine centers of public hospitals of the region. The proposal is an additional alternative for the monitoring of people in emergency situations where it is possible and feasible the use of the gamma chambers. This would avoid the person's transport with incorporation suspicion for a conventional whole

  20. Production of radionuclides in nuclear reactor

    Given is a short review on the production of radionuclides which was performed in the Vinca Institute of Nuclear Sciences by using the nuclear reactor RA. Regarding the considerations of the possible re-starting of this reactor its use for the production of medical radionuclides should be taken into account. Listed are some of the important medical radionuclides routinely produced in nuclear reactors in the world and discussed the conditions for their obtaining in the reactor RA. (author)

  1. Radionuclides in thyroid cancer

    The three main areas of application of radionuclides in thyroid disease will be reviewed. Firstly thyroid radionuclide imaging in thyroid swellings, in relationship to lumps in the neck and ectopic thyroid tissue such as retrosternal goitre, and lingual goitre will be described. Future developments in the field including tomographic scanning, using the coded aperture method, and fluorescent scans and ultrasound are reviewed. The second area of application is the assessment and evaluation of thyroid function and the therapy of Grave's Disease and Plummer's Disease using radioiodine. The importance of careful collection of the line of treatment, results of treatment locally and the follow-up of patients after radioiodine therapy will be described. The third area of application is in the diagnosis and therapy of thyroid cancer. Investigation of thyroid swelling, and the diagnosis of functioning metastases are reported. The therapeutic iodine scan as the sole evidence of functioning metastatic involvement is recorded. Histological thyroid cancer appears to be increasingly encountered in clinical practice and the plan of management in relation to choice of cases for therapeutic scanning is discussed with case reports. Lastly the role of whole body scanning in relationship to biochemical markers is compared. In the changing field of nuclear medicine radionuclide applications in thyroid disease have remained pre-eminent and this is an attempt to reassess its role in the light of newer developments and local experience in the Institute of Radiotherapy, Oncology and Nuclear Medicine. (author)

  2. Anthropogenic radionuclides in the environment

    Hu, Q; Weng, J; Wang, J

    2007-11-15

    Studies of radionuclides in the environment have entered a new era with the renaissance of nuclear energy and associated fuel reprocessing, geological disposal of high-level nuclear wastes, and concerns about national security with respect to nuclear non-proliferation. This work presents an overview of anthropogenic radionuclide contamination in the environment, as well as the salient geochemical behavior of important radionuclides. We first discuss the following major anthropogenic sources and current development that contribute to the radionuclide contamination of the environment: (1) nuclear weapons program; (2) nuclear weapons testing; (3) nuclear power plants; (4) commercial fuel reprocessing; (5) geological repository of high-level nuclear wastes, and (6) nuclear accidents. Then, we summarize the geochemical behavior for radionuclides {sup 99}Tc, {sup 129}I, and {sup 237}Np, because of their complex geochemical behavior, long half-lives, and presumably high mobility in the environment. Biogeochemical cycling and environment risk assessment must take into account speciation of these redox-sensitive radionuclides.

  3. Chemistry and analysis of radionuclides

    Lehto, Jukka

    2010-01-01

    Written by chemists for chemists, this is a comprehensive guide to the important radionuclides as well as techniques for their separation and analysis. It introduces readers to the important laboratory techniques and methodologies in the field, providing practical instructions on how to handle nuclear waste and radioactivity in the environment.

  4. Metabolism of radionuclides in domestic animals

    The reactor accident at Chernobyl has shown that shortly after the contamination of the environment radionuclides can be found in animal products. The main contamination pathways of domestic animas are: uptake of radionuclides by foodstuffs; uptake of radionuclides by contaminated drinking water; uptake of radionuclides by inhalation; uptake of radionuclides through skin; uptake of radionuclides by ingestion of soil particles. Generally the uptake of radionuclides by food is the dominant exposure pathway. In rare cases the inhalation of radionuclides or the uptake by drinking water may be of importance. The metabolism of incorporated radionuclides is comparable to the respective metabolism of essential mass or trace elements or heavy metals. Radioisotopes of essential elements are for instance iron 55, manganese 54, cobalt 58 and cobalt 60. Other elements are typical antagonists to essential elements, e.g. strontium 90 is an antagonist to calcium or cesium 137 to potassium. Lead 210 and plutonium 239 behave similarly as heavy metals. Generally the knowledge of the metabolism of trace and mass elements, of antagonistic and synergistic elements and heavy metals can be applied to these radionuclides

  5. Measurements for modeling radionuclide transfer in the aquatic environment

    Analytical methods for measuring radionuclides in the aquatic environment are discussed for samples of fresh water and seawater, fish and shellfish, biota such as algae, plankton, seaweed, and aquatic plants, and sediment. Consideration is given to radionuclide collection and concentration, sample preservation, radiochemical and instrumental analysis, and quality assurance. Major problems are the very low environmental levels of the radionuclides of interest, simultaneous occurrence of radionuclides in several chemical and physical forms and the numerous factors that affect radionuclide levels in and transfers among media. Some radionuclides of importance in liquid effluents from nuclear power stations are listed, and sources of radiochemical analytical methods are recommended

  6. Radionuclides in terrestrial ecosystems

    The subject is discussed under the headings: concentration and spatial distribution of radionuclides in grazed and ungrazed saltmarshes; incorporation of radionuclides by sheep grazing on an estuarine saltmarsh; inland transfer of radionuclides by birds feeding in the estuaries and saltmarshes at Ravenglass; radionuclides in contrasting types of coastal pastures and taken up by individual plant species found in west Cumbria; procedures developed and used for the measurement of alpha and gamma emitters in environmental materials. (U.K.)

  7. Migration of radionuclides in geologic media: Fundamental research needs

    Reed, D.T. (Argonne National Lab., IL (USA)); Zachara, J.M.; Wildung, R.E. (Pacific Northwest Lab., Richland, WA (USA)); Wobber, F.J. (USDOE, Washington, DC (USA))

    1990-01-01

    An assessment of the fundamental research needs in understanding and predicting the migration of radionuclides in the subsurface is provided. Emphasis is on the following three technical areas: (1) aqueous speciation of radionuclides, (2) the interaction of radionuclides with substrates, and (3) intermediate-scale interaction studies. This research relates to important issues associated with environmental restoration and remediation of DOE sites contaminated with mixed radionuclide-organic wastes. 64 refs., 1 fig., 1 tab.

  8. Migration of radionuclides in geologic media: Fundamental research needs

    An assessment of the fundamental research needs in understanding and predicting the migration of radionuclides in the subsurface is provided. Emphasis is on the following three technical areas: (1) aqueous speciation of radionuclides, (2) the interaction of radionuclides with substrates, and (3) intermediate-scale interaction studies. This research relates to important issues associated with environmental restoration and remediation of DOE sites contaminated with mixed radionuclide-organic wastes. 64 refs., 1 fig., 1 tab

  9. Radionuclide Therapy. Chapter 19

    Cancer has been treated with radiopharmaceuticals since the 1940s. The radionuclides originally used, including 131I and 32P, are still in use. The role of the physicist in radionuclide therapy encompasses radiation protection, imaging and dosimetry. Radiation protection is of particular importance given the high activities of the unsealed sources that are often administered, and must take into account medical staff, comforters and carers, and, as patients are discharged while still retaining activity, members of the public. Regulations concerning acceptable levels of exposure vary from country to country. If the administered radiopharmaceutical is a γ emitter, then imaging can be performed which may be either qualitative or quantitative. While a regular system of quality control must be in place to prevent misinterpretation of image data, qualitative imaging does not usually rely on the image corrections necessary to determine the absolute levels of activity that are localized in the patient. Accurate quantitative imaging is dependent on these corrections and can permit the distribution of absorbed doses delivered to the patient to be determined with sufficient accuracy to be clinically beneficial

  10. Natural and anthropogenic radionuclides in the environment

    A survey is given on the actual knowledge about occurence and environmental relevancy of the most important radionuclides from natural and anthropogenic origin. The contribution of AGF installation is emphasized. (orig.)

  11. Speciation of radionuclides in the environment

    Methods for the determination of the speciation of radionuclides in aerosols, in aquatic solutions, in sediments, soils and rocks are reviewed. At present, most of the results about speciation are deduced from model calculations, model experiments, and separation of species (forms) of radionuclides, e.g., by sequential extraction procedures. Methods of direct determination of speciation of radionuclides (e.g. by laser induced spectroscopy) are in general not yet sensitive enough for a measurement of the very low concentrations of radionuclides in the environment. The methodological part of this paper is followed by a review of the very abundant literature about speciation of important radionuclides in the environment, i.e. in the atmosphere, hydrosphere and lithosphere. The review does not include the biosphere. Literature up to spring 1993 is included (with a few more recent additions). (author)

  12. Therapeutic radionuclides: production and decay property considerations.

    Volkert, W A; Goeckeler, W F; Ehrhardt, G J; Ketring, A R

    1991-01-01

    radionuclides in order to deliver a sufficient number of radionuclide atoms to the target site without saturating the target or compromising the integrity of the carrier molecule. Most radionuclides, produced at NCA levels in reactors, are produced via indirect reactions. High-specific activity beta emitters can also be obtained from radionuclide generator systems where the longer-lived parent radionuclide may be obtained from direct neutron activation, as a fission product, or from charged-particle accelerators. It is essential that the half-life of a radionuclide used in RNT be compatible with the rates of localization in target tissues and clearance of the carrier molecule from normal tissues. This consideration is especially important for the various MAbs and their fragments that are currently under investigation as carrier molecules to RIT.(ABSTRACT TRUNCATED AT 400 WORDS) PMID:1988628

  13. Purification of Irradiated Natural Samarium from Europium Impurities using a Phenolic Resin

    Radioactive isotopes have been found of valuable applications in different areas such as medicine, industry, agriculture and biology. One of these isotopes is 153 Sm which is obtained by irradiation of natural Sm2O3 in a reactor by a thermal neutron flux of 1014 n.cm-2.sec -1 for 8 hours to get n specific activity of 67-95 mCi/mg. Thc distribution coefficient of 153 Sm and 154,155Eu from different media with different concentrations of HCl and EDTA onto Resorcinol-Formaldehyde as a cation exchanger were studied. The effect of ascorbic acid concentration at 0.001 and 10 M HCl on the distribution coefficient of 153Sm and 155Eu onto the same exchanger was studied. 153Sm was separated by elution chromolithography with 0.4 M EDTA. As a result, the radionuclidic purity of the eluted 153Sm was over 99% and chemical: purity was over 95%

  14. Status report on radionuclide transfer

    At the suggestion of the Federal Minstry of the Interior, in June 1978, a group of scientists from several institutions who are active in the field of radionuclide transfer or are interested in these problems got together. During the discussions of the work team, especially the transfer soil/plants was emphasized. Then the work team set up a status report on the transfer of the radionuclides relevant in the sense of the radiation protection act. The nuclides H3 and C14, the isotopes of the Sr, J, and Cs, Tc99, the so-called corrosion nuclides Mn54, Fe59, co-isotopes and Zn65, and isotopes of Pu, Am, and Cm were regarded as important for a possible radiation exposition. Recent investigations revealed that also the natural radionuclides Ra226, Po210, and Pb210 should be covered by the investigations. The goal of this status report is to present the level of knowledge on the transfer of these radionuclides to man in a brief form, giving hints at the most important literature. It was requested by the Federal Ministry of the Interior, as fas as possible, to indicate transfer factors which are necessary for the radio-occology act to be decreed according to Para. 45 of the radiation protection act. Another goal of the report was to show the gap in the knowledge on the radio nuclide transfer. This was thought to help to create a basis for the decisions of the Federal Ministry concerning the support of other investigation projects in the field of transfer of radionuclides. (orig./MG)

  15. Radionuclide Small Intestine Imaging

    Jiri Dolezal; Marcela Kopacova

    2013-01-01

    The aim of this overview article is to present the current possibilities of radionuclide scintigraphic small intestine imaging. Nuclear medicine has a few methods—scintigraphy with red blood cells labelled by means of 99mTc for detection of the source of bleeding in the small intestine, Meckel's diverticulum scintigraphy for detection of the ectopic gastric mucosa, radionuclide somatostatin receptor imaging for carcinoid, and radionuclide inflammation imaging. Video capsule or deep enteroscop...

  16. Radionuclide transfer in forest ecosystems

    The behaviour of radionuclides in forest ecosystems differs substantially from the other ecosystems. The contamination of various forest products is commonly quantified using the Aggregated Transfer Factor (Tag in m2 kg-1) which integrates various environmental parameters including soil and plant type, root distribution as well as nature and vertical distribution of the deposits. This review aims at compiling the most relevant quantitative information on radionuclide transfers to forest biota including trees, understorey vegetation, mushrooms, berries and game animals. For both radiocaesium and radiostrontium in trees, the order of magnitude of mean Tag values is 10-3 m2.kg-1 (dry weight). The transfer of radionuclides to mushrooms and berries is high, in comparison with foodstuffs grown in agricultural systems. Concerning caesium uptake by mushrooms, the transfer is characterized by a very large variability of Tag, from 10-3 to 101 m2.kg-1 (dry weight). For berries, typical values are around 0.01 to 0.1 m2.kg-1 (dry weight). Transfer of radioactive caesium to game animals and reindeer and the rate of activity reduction, quantified as an ecological half-life, reflect the soil and pasture conditions at individual locations. Even if, the importance of radioactive contamination of forests as a significant source of the population exposure is recognized, most of the data refer to caesium and to a lesser extent, strontium. Data for other radionuclides are rather limited. (author)

  17. Radionuclide retention in geologic media

    GEOTRAP is the OECD/NEA Project on Radionuclide Migration in Geologic, Heterogeneous Media carried out in the context of site evaluation and safety assessment of deep repository systems for long-lived radioactive waste. Retention of radionuclides within the geosphere for prolonged periods is an important safety function of deep geologic disposal concepts for radioactive waste. The extent to which retention processes can be relied upon in repository performance assessment depends upon the existence of well-established theoretical bases for the processes. It also depends on support for the operation of specific retention processes, and models for their quantitative evaluation, from a wide range of laboratory and field experiments and observations from nature. The fifth GEOTRAP workshop, 'Geological Evidence and Theoretical Bases for Radionuclide-retention Processes in Heterogeneous Media' held in May 2001, looked at radionuclide-retention processes and their consideration and representation in performance assessments. Current approaches to characterising and modelling retention processes, and suggestions for future improvements, were presented and discussed. In addition to the material presented during the workshop, this publication includes a technical synthesis reflecting the discussions that took place as well as the conclusions and recommendations made, notably during the working group sessions. (author)

  18. Fundamental Concepts in Radionuclide Therapy. Chapter 2

    A short overview of the basic concepts and principles of radionuclide therapy is presented in this chapter. After introducing the most important radionuclides currently employed in therapeutic applications and new promising radioisotopes such as α emitters, this review covers the various types of vector molecules and biological approaches for targeting specific cancer cells. These applications include the use of receptor specific pharmacophores such as antibodies and peptides, and DNA targeting agents. The potential advantages of combining methods developed for radionuclide therapy with gene therapy and nanotechnology are also discussed. (author)

  19. Significant Radionuclides Determination

    Jo A. Ziegler

    2001-07-31

    The purpose of this calculation is to identify radionuclides that are significant to offsite doses from potential preclosure events for spent nuclear fuel (SNF) and high-level radioactive waste expected to be received at the potential Monitored Geologic Repository (MGR). In this calculation, high-level radioactive waste is included in references to DOE SNF. A previous document, ''DOE SNF DBE Offsite Dose Calculations'' (CRWMS M&O 1999b), calculated the source terms and offsite doses for Department of Energy (DOE) and Naval SNF for use in design basis event analyses. This calculation reproduces only DOE SNF work (i.e., no naval SNF work is included in this calculation) created in ''DOE SNF DBE Offsite Dose Calculations'' and expands the calculation to include DOE SNF expected to produce a high dose consequence (even though the quantity of the SNF is expected to be small) and SNF owned by commercial nuclear power producers. The calculation does not address any specific off-normal/DBE event scenarios for receiving, handling, or packaging of SNF. The results of this calculation are developed for comparative analysis to establish the important radionuclides and do not represent the final source terms to be used for license application. This calculation will be used as input to preclosure safety analyses and is performed in accordance with procedure AP-3.12Q, ''Calculations'', and is subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (DOE 2000) as determined by the activity evaluation contained in ''Technical Work Plan for: Preclosure Safety Analysis, TWP-MGR-SE-000010'' (CRWMS M&O 2000b) in accordance with procedure AP-2.21Q, ''Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities''.

  20. Significant Radionuclides Determination

    The purpose of this calculation is to identify radionuclides that are significant to offsite doses from potential preclosure events for spent nuclear fuel (SNF) and high-level radioactive waste expected to be received at the potential Monitored Geologic Repository (MGR). In this calculation, high-level radioactive waste is included in references to DOE SNF. A previous document, ''DOE SNF DBE Offsite Dose Calculations'' (CRWMS M and O 1999b), calculated the source terms and offsite doses for Department of Energy (DOE) and Naval SNF for use in design basis event analyses. This calculation reproduces only DOE SNF work (i.e., no naval SNF work is included in this calculation) created in ''DOE SNF DBE Offsite Dose Calculations'' and expands the calculation to include DOE SNF expected to produce a high dose consequence (even though the quantity of the SNF is expected to be small) and SNF owned by commercial nuclear power producers. The calculation does not address any specific off-normal/DBE event scenarios for receiving, handling, or packaging of SNF. The results of this calculation are developed for comparative analysis to establish the important radionuclides and do not represent the final source terms to be used for license application. This calculation will be used as input to preclosure safety analyses and is performed in accordance with procedure AP-3.12Q, ''Calculations'', and is subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (DOE 2000) as determined by the activity evaluation contained in ''Technical Work Plan for: Preclosure Safety Analysis, TWP-MGR-SE-000010'' (CRWMS M and O 2000b) in accordance with procedure AP-2.21Q, ''Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities''

  1. Diagnostic applications of radionuclides

    Radionuclides are now used routinely in two different types of medical diagnostic tests: in vivo measurements of the distribution of radioactivity in the body, and in vitro assays. Information gained from these procedures is expected to improve the physician's understanding of this patient's well-being by providing an objective evaluation of important physiologic functions. This information may be used to establish a correct diagnosis, determine the extent or severity of the patient's illness, or to evaluate a patient's response to therapy. Diagnostic tests thus increase the speed and accuracy of patient care decisions. As a result, treatment is more objective, recovery is more rapid, and the duration of patient suffering is reduced. These benefits may significantly reduce the overall costs of medical care. The numbers of test performed and the amount of radioactivity employed has increased dramatically. This growth has been facilitated by the development of new radiation detection instruments that are especially designed for clinical applications, and by the increased commercial availability of labeled materials that can be used for diagnostic tests. In addition, the use of isotopes in human subjects is limited by a variety of special problems. Some of these problems are rather technical, relating only to the development of method for storage and preparation of labeled materials in a form suitable for human use. Other more critical problems include the limited selection of radionuclides available for use in the investigation of human metabolism, the inefficiency of instruments used to detect radioactivity, and the growing concern for the potential hazards associated with the use of all forms of ionizing radiation

  2. Livermore Accelerator Source for Radionuclide Science (LASRS)

    Anderson, Scott [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bleuel, Darren [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Johnson, Micah [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Rusnak, Brian [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Soltz, Ron [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Tonchev, Anton [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-05-05

    The Livermore Accelerator Source for Radionuclide Science (LASRS) will generate intense photon and neutron beams to address important gaps in the study of radionuclide science that directly impact Stockpile Stewardship, Nuclear Forensics, and Nuclear Material Detection. The co-location of MeV-scale neutral and photon sources with radiochemical analytics provides a unique facility to meet current and future challenges in nuclear security and nuclear science.

  3. Natural radionuclides in mineral fertilizers and farmland

    Mitrović Branislava M.; Vitorović Gordana; Andrić Velibor; Stojanović Mirjana; Vitorović Duško; Grdović Svetlana; Vićentijević Mihajlo

    2013-01-01

    Contemporary agriculture production is based on use of mineral fertilizers, which however can have high activity of natural radionuclides and so cause the appearance of technologically elevated radioactivity. In order to determine the influence of mineral fertilizers application in arable land, there was used gamma spectrometric method for defining the activity of natural radionuclides (40 K, 238U, 226Ra) in imported mineral fertilizers as well as in arable...

  4. Biogeochemistry of radionuclides in ecosystems (historical aspect)

    The paper presents the most important results of the study on the radionuclides' behaviour in natural and model biogeocenoses(ecosystems) obtained by N.W.Timofeev-Ressovskij and co-workers during the period 1947-1968. As early as at that period, radionuclides were classified according to the types of distribution, accumulation and migration within the surface and freshwater ecosystems, and the methods of biological purification of radioactive sewage were proposed

  5. Radionuclides in the coastal environment of Indonesia

    Present potential radiation risk in the coastal environment of Indonesia may result mainly from the presence of naturally occurring radioactive materials released to the aquatic environment from land-based sources, as some of the process industry uses large amounts of raw materials like ore, marl or clay which contains natural radionuclides. Therefore, in recent years we have been conducting radionuclide monitoring in Jakarta Bay with the aim to establish present levels of natural radionuclides in the coastal environment. Further, we have also been developing methodologies for analysing fission products with the purpose of generating data on background levels of anthropogenic radionuclides in the coastal environment, important for planned construction of nuclear facilities in the region, so adequate radioecological risk assessment studies could be carried out in the future. Therefore radionuclide monitoring has been carried out at Muria peninsula as well, where the first Indonesian nuclear facility is planned to be constructed. Radionuclide monitoring results, both for natural and anthropogenic radionuclides in Muria Peninsula are presented. We have also been developing experimental radiotracer techniques to determine bioaccumulation of key contaminants and their retention parameters for bioindicator organisms used in site-specific coastal pollution monitoring programmes, designed to furnish information on water quality. Candidates of marine mollusks as bioindicators are listed

  6. Radionuclides in the coastal environment of Indonesia

    Present potential radiation risk in the coastal environment of Indonesia may result mainly from the presence of naturally occurring radioactive materials released to the aquatic environment from land-based sources, as some of the process industry uses large amounts of raw materials like ore, marl or clay which contains natural radionuclides. Therefore, in recent years we have been conducting radionuclide monitoring in Jakarta bay with the aim to establish present levels of natural radionuclides in the coastal environment. Further, we have also been developing methodologies for analysing fission products with the purpose of generating data on background levels of anthropogenic radionuclides in the coastal environment, important for planned construction of nuclear facilities in the region, so adequate radioecological risk assessment studies could be carried out in the future. Therefore radionuclide monitoring has been carried out at Muria peninsula as well, where the first Indonesian nuclear facility is planned to be constructed. Radionuclide monitoring results, both for natural and anthropogenic radionuclides in Muria Peninsula are presented. We have also been developing experimental radiotracer techniques to determine bioaccumulation of key contaminants and their retention parameters for bioindicator organisms used in site-specific coastal pollution monitoring programmes, designed to furnish information on water quality. Candidates of marine mollusks as bioindicators are listed

  7. Methods for reduction of radionuclides incorporated into the body

    Small-scale (laboratories and hospitals) to global radioactive contamination may contribute to incorporation of radionuclides in the living body. In real accidents, many radionuclides are occasionally incorporated simultaneously into the body. Therefore, it is important to know the kinds of radionuclides, chemical form at the incorporation, and presence status and behavior of radionuclides in the body. Because there is interaction between agents for reducing radioactive contamination, the reduction mechanism of radionuclide in the body should be considered when such agents are used in the combination manner. The purpose of this report is to discuss chemical methods for reducing radionuclides that are orally incorporated into the body. These methods are described in terms of dilution, complex production, adsorption, metabolism derangement, and others. I-131, Cs-137, Sr-90, and Ru-106, which are influential radionuclides for the human body, are especially referred to. (N.K.) 58 refs

  8. Overview of radionuclides transport

    There has been recognition of radioactivity levels and the fate of radionuclides that could have modified the biogeochemical cycles in the ecological environment. These modifications can disturb a variety of the ecosystems on which human life depends. It is essential to understand the pathways of radionuclides that are transported and deposited in the atmosphere and in terrestrial and aquatic ecosystems related to their impacts on human life. This paper is mainly focused on the transport in the atmospheric part. Various physical processes that control the transport of radionuclides in the atmosphere are reviewed. The transport processes used in terrestrial and aquatic ecosystems, as well as underground are briefly described. For the purpose of demonstration, dose calculations due to the exposures of radionuclides, and the numerical model simulations of transport of 210Pb particles and dust aerosols in the atmosphere are presented. Each transport process is complex. More sampling data are needed to refine the transport models for assessing and predicting the fate of radionuclides and their impacts on ecosystems. Long-lived radionuclides are remained in the atmosphere and can be transported in a long distance over wider areas. Although a numerical model can handle complex transport processes, a Gaussian model offers an attraction for ease and quickness of interpretation of exposures to radionuclides during emergency. Radionuclides entering the atmosphere go through the transfer process from air to soil, soil to plants, and plants to animals. The transfer is a long-term process. Therefore, a longer-term study of environmental sampling of radionuclides is required to accurately assess the transport processes and long-term impacts on health and ecosystems. Also, it should get involving in a study of modeling transport of radionuclides over urban area having various heights and sizes of buildings, i.e., skyscrapers with high population, in the case of an event occurring

  9. Choice of radionuclides for radioimmunotherapy

    Innumerable questions need to be answered and obstacles overcome before radioimmunotherapy can be generally successful in cancer patients. Major developments have greatly enhanced the likelihood of success. The important development of appropriate radionuclides and radiochemistry for this therapy must be intimately linked with the biological and biochemical realities. All aspects must be considered, such as the specific nature of the antigenic target, the pharmacokinetics of the antibody fragment carrier, the capability of in vivo quantitation of tumor uptake and turnover time, as well as total body kinetics. With this knowledge, then, practical radiochemistry methods can be integrated with the suitable radionuclide choices, and production methods can be developed which will deliver effective and dependable products for patient therapy

  10. Radionuclide imaging of musculoskeletal infection

    Palestr, Christopher J. [Albert Einstein College of Medicine, Bronx, NY (United States); North Shore Long Island Jewish Health System, Manhasset and New Hyde Park, NY (United States). Div. of Nuclear Medicine and Molecular Imaging; E-mail: palestro@lij.edu; Love, Charito [North Shore Long Island Jewish Health System, Manhasset and New Hyde Park, NY (United States). Div. of Nuclear Medicine and Molecular Imaging

    2007-09-15

    Radionuclide imaging studies are routinely used to evaluate patients suspected of having musculoskeletal infection. Three-phase bone imaging is readily available, relatively inexpensive, and very accurate in the setting of otherwise normal bone. Labeled leukocyte imaging should be used in cases of 'complicating osteomyelitis' such as prosthetic joint infection. This test also is useful in clinically unsuspected diabetic pedal osteomyelitis as well as in the neuropathic joint. It is often necessary, however, to perform complementary bone marrow imaging, to maximize the accuracy of labeled leukocyte imaging. In contrast to other regions in the skeleton, labeled leukocyte imaging is not useful for diagnosing spinal osteomyelitis. At the moment, gallium is the preferred radionuclide procedure for this condition and is a useful adjunct to magnetic resonance imaging. FDG-PET likely will play an important role in the evaluation of musculoskeletal infection, especially spinal osteomyelitis, and may replace gallium imaging for this purpose. (author)

  11. Process for encapsulating radionuclides

    Radionuclides are immobilized in virtually an insoluble form by reacting at a temperature of at least 900C as an aqueous alkaline mixture having a solution pH of at least 10, containing a source of silicon, the radionuclide waste, and a metal cation. The molar ratio of silicon to the metal cation is on the order of unity to produce a gel from which complex metalosilicates crystallize to entrap the radionuclides within the resultant condensed crystal lattice. The product is a silicious stone-like material which is virtually insoluble and nonleachable in alkaline or neutral environment. One embodiment provides for the formation of the complex metalo-silicates, such as synthetic pollucite, by gel formation with subsequent calcination to the solid product; another embodiment utilizes a hydrothermal process, either above ground or deep within basalt caverns, at greater than atmospheric pressures and a temperature between 90 and 5000C to form complex metalo-silicates, such as strontium aluminosilicate. Another embodiment provides for the formation of complex metalo-silicates, such as synthetic pollucite, by slurrying an alkaline mixture of bentonite or kaolinite with a source of silicon and the radionuclide waste in salt form. In each of the embodiments a mobile system is achieved whereby the metalo-silicate constituents reorient into a condensed crystal lattice forming a cage structure with the condensed metalo-silicate lattice which completely surrounds the radionuclide and traps the radionuclide therein; thus rendering the radionuclide virtually insoluble

  12. The characteristic of complications of radionuclide therapy by samarium oksabifor at oncologic patients

    On the basis of data of clinical-laboratory evaluation of 30 oncologic patients with bone metastasis the account and the analysis of complications of radio nuclide therapy (RNT) by samarium-oksabifor are carried out. It is defined that RNT 153Sm increases efficiency of complex palliative treatment of patients with bone metastasis, has high tolerability and isn't followed by intensifying of frequency of radial reactions and complications

  13. Radionuclides in US coals

    Bisselle, C. A.; Brown, R. D.

    1984-03-01

    The current state of knowledge with respect to radionuclide concentrations in US coals is discussed. Emphasis is placed on the levels of uranium in coal (and lignite) which are considered to represent a concern resulting from coal combustion; areas of the US where such levels have been found; and possible origins of high radionuclide levels in coal. The report reviews relevant studies and presents new data derived from a computerized search of radionuclide content in about 4000 coal samples collected throughout the coterminous US. 103 references, 5 figures, 5 tables.

  14. Proposal of a calibration protocol of gamma chambers for estimation of the radionuclides incorporation in emergency situations; Propuesta de un protocolo de calibracion de camaras gamma para estimacion de la incorporacion de radionucleidos en situaciones de emergencia

    Dantas, B.M.; Lucena, E.; Dantas, A.L.A.; Araujo, F.; Melo, D. [Instituto de Radioprotecao e Dosimetria, Rio de Janeiro Brasil (Brazil); Teran, M.; Paolino, A. [Facultad de Quimica, Montevideo (Uruguay); Hermida, J.C. [Hospital de Clinicas, Facultad de Medicina, Montevideo (Uruguay); Rojo, A. [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina); Puerta, J.A.; Morales, J. [Universidad Nacional de Colombia, Medellin (Colombia); Lopez B, G.M. [Centro de Proteccion e Higiene de las Radiaciones, Ciudad de la Habana (Cuba); Alfaro, M.; Ruiz, M.A. [Instituto Nacional de Investigaciones Nucleares (Mexico); Videla, R.; Pinones, O. [Comision Chilena de Energia Nuclear, Santiago (Chile); Gonzalez, S. [Instituto Peruano de Energia Nuclear, Lima (Peru); Navarro, T. [Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, Madrid (Spain); Cruz S, R. [International Atomic Energy Agency, Vienna (Australia)

    2006-07-01

    In the last years in several countries has come increasing the concern with the possibility of accidents related to the transport and manipulation of open sources used in nuclear medicine. This carried out to the search of alternative methods for the monitoring of workers and individuals of the public exposed to the radionuclides incorporation like {sup 131} I, {sup 201} Tl, {sup 153} Sm among others. One of the options to assist the demand for monitoring of the radionuclides incorporation is the use of gamma chambers that are medical diagnostic equipment available in the own centers of nuclear medicine. The gamma chambers are used to obtain images of patient to which are administered a radionuclide of well-known activity with diagnostic purposes. These equipment have among its components elements that spectrometric systems like those used in the evaluation of the internal incorporation for direct measurements, reason why besides its use for diagnosis by image they can be gauged with anthropomorphic simulators and also with punctual sources for the quantification of the radionuclides activity, distributed homogeneously in the human body or located in specific organs. This work presents the development of a calibration protocol of gamma chambers for the in vivo determination of radionuclides and it proposes the implementation of the protocol in centers of nuclear medicine of the 9 countries participants of the project OAS-ARCAL-RLA/9/049-LXXVIII - Harmonization of procedures of internal dosimetry (Argentina, Brazil, Colombia, Cuba, Chile, Mexico, Peru, Uruguay and Spain). The protocol is the base to establish an integrated net to attend in the response to emergencies using nuclear medicine centers of public hospitals of the region. The proposal is an additional alternative for the monitoring of people in emergency situations where it is possible and feasible the use of the gamma chambers. This would avoid the person's transport with incorporation suspicion for

  15. Radionuclides in Bentic Algae

    Bentic micro-algae (mainly consisting of diatoms) were taken from 4 sites in the discharge area of the Forsmark Nuclear Power Station (Sweden) and from 1 site in the cooling water intake channel of the power station. Samples were taken every third week during 1984. The micro-algae were brushed of a 0.1-0.15 m2 area on stones collected from the hydrolittoral zone. Radionuclide concentration was measured as gamma radiation with a Ge-detector. Fission products from the power plant cooling water can easily be detected in the micro-algae. We show that benthic diatom assemblages are good indicators for radionuclides; good correlations were found between radionuclide concentration in the algae and the discharge from the power plant. The best correlations were obtained if the accumulated discharge for the 15 days before sampling was used in the calculations. Of the investigated radionuclides, Co-60 and Zn-65 show significant relationships between concentration in the algae and discharge for 2 site, Ag-110m for 3 sites and Mn-54 for 1 site. No correlations were found for the site in the intake channel. The results show differences which depend on whether calculations were done for total, particulate or dissolved fractions of the radionuclides. There are indications that there is considerable recirculation of the radionuclides within the algal assemblages, and the recirculation from the outlet of the Biotest basin to the intake channel is of about 10%. In this report we also present a budget for the total amount of radionuclides in the Biotest Basin for 1984. The highest amounts of radionuclides in diatoms were found during late winter and early spring, associated with the large diatom blooms at that time of the year in the basin. (authors)

  16. Soil contamination with radionuclides and potential remediation.

    Zhu, Y G; Shaw, G

    2000-07-01

    Soils contaminated with radionuclides, particularly 137Cs and 90Sr, pose a long-term radiation hazard to human health through exposure via the foodchain and other pathways. Remediation of radionuclide-contaminated soils has become increasingly important. Removal of the contaminated surface soil (often up to 40 cm) or immobilization of radionuclides in soils by applying mineral and chemical amendments are physically difficult and not likely cost-effective in practicality. Reducing plant uptake of radionuclides, especially 137CS and 90Sr by competitive cations contained in chemical fertilizers has the general advantage in large scale, low-level contamination incidents on arable land, and has been widely practiced in central and Western Europe after the Chernobyl accident. Phytoextraction of radionuclides by specific plant species from contaminated sites has rapidly stimulated interest among industrialists as well as academics, and is considered to be a promising bio-remediation method. This paper examines the existing remediation approaches and discusses phytoextraction of radionuclides from contaminated soils in detail. PMID:10819188

  17. Reactor core heterogeneity effects on radionuclide inventory

    Highlights: ► Reactor core heterogeneity effects on radionuclide inventory are studied. ► A methodology for inventory estimation of individual fuel assembly is developed. ► Estimated inventory using presently developed and conventional method is compared. ► Radionuclide density peak and its location in equilibrium VVER core are investigated. - Abstract: Understanding fission product behavior is an important aspect of nuclear safety studies. A nuclear reactor core contains complex mixture of fuel elements with different levels of enrichment, power and burnup. Conventional method of core radionuclide inventory estimation is based on use of homogenized core parameters like burnup, enrichment, specific power etc. This approach does not reveal the variation in radionuclide density among different fuel elements within the core. The present work aims to bridge this knowledge gap by estimating the distribution of radionuclides in the nuclear reactor core taking into account the heterogeneity of the core explicitly. The analysis has brought out peak radionuclide density in the core which can be helpful in appropriate estimation of the radiological release in the accidental scenarios involving failures of few fuel assemblies. A quantitative comparison of total core inventory estimated based conventional core average parameters and detailed core inventory using individual fuel assembly inventory estimate has been made

  18. Migration of radionuclides in fissured rock

    Some computed results of radionuclide migration in fissured rock are presented. The computations are based on a model which describes flow as occurring in a multitude of independent fissures (stratified flow). This gives rise to strong dispersion of channeling. The radionuclide migration in the individual fissures is modelled by the advection equation on a parallel walled channel with porous walls. The nuclides may diffuse into the pores and sorb reversibly on the pore surfaces. The effluent rates of 23 important nuclides are presented as functions of distance and time for various of important parameters such as rock permeability, diffusion coefficients, release rates, time of first release, fissure spacing and fissure width distribution. (Author)

  19. Radionuclide fixation mechanisms in rocks

    In the safety evaluation of the radioactive waste disposal in geological environment, the mass balance equation for radionuclide migration is given. The sorption of radionuclides by geological formations is conventionally represented by the retardation of the radionuclides as compared with water movement. In order to quantify the sorption of radionuclides by rocks and sediments, the distribution ratio is used. In order to study quantitatively the long term behavior of waste radionuclides in geological environment, besides the distribution ratio concept in short term, slower radionuclide retention reaction involving mineral transformation should be considered. The development of microspectroscopic method for long term reaction path modeling, the behavior of iron during granite and water interaction, the reduction precipitation of radionuclides, radionuclide migration pathways, and the representative scheme of radionuclide migration and fixation in rocks are discussed. (K.I.)

  20. Radionuclides for routine diagnostics in nuclear medicine

    A survey is given on the radiopharmaceutics which are now in common use in nuclear medical diagnostics in vivo and in vitro. The development of radiopharmacology in the last 20 years has been characterized by the production of new and better radionuclides. A great step forward in clinical nuclear medicine has been the introduction of radionuclide generators for the production of short-lived nuclides. The most important and most generally used radionuclide for in vivo examinations is sup(99m)Tc pertechnetate. Tumour specific substances are still unknown, while the radioactive in vitro tests are of great clinical importance. They have opened up new possibilities of clinical laboratory diagnostics which are still not fully exploited. Special mention is made of the thyroid-specific in vitro tests in radiological thyroid diagnostics. (orig./AK)

  1. Radionuclides in house dust

    Fry, F A; Green, N; Hammond, D J

    1985-01-01

    Discharges of radionuclides from the British Nuclear Fuel plc (BNFL) reprocessing plant at Sellafield in Cumbria have led to elevated concentrations radionuclides in the local environment. The major routes of exposure of the public are kept under review by the appropriate Government departments and monitoring is carried out both by the departments and by BNFL itself. Recently, there has been increasing public concern about general environmental contamination resulting from the discharges and, in particular, about possible exposure of members of the public by routes not previously investigated in detail. One such postulated route of exposure that has attracted the interest of the public, the press and Parliament arises from the presence of radionuclides within houses. In view of this obvious and widespread concern, the Board has undertaken a sampling programme in a few communities in Cumbria to assess the radiological significance of this source of exposure. From the results of our study, we conclude that, alt...

  2. Initial Radionuclide Inventories

    The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only. Bounding waste stream information and data were collected that capture probable limits. For commercially generated waste, this analysis considers alternative waste stream projections to bound the characteristics of wastes likely to be encountered using arrival scenarios that potentially impact the commercial spent nuclear fuel (CSNF) waste stream. For TSPA-LA, this radionuclide inventory analysis considers U.S. Department of Energy (DOE) high-level radioactive waste (DHLW) glass and two types of spent nuclear fuel (SNF): CSNF and DOE-owned (DSNF). These wastes are placed in two groups of waste packages: the CSNF waste package and the codisposal waste package (CDSP), which are designated to contain DHLW glass and DSNF, or DHLW glass only. The radionuclide inventory for naval SNF is provided separately in the classified ''Naval Nuclear Propulsion Program Technical Support Document'' for the License Application. As noted previously, the radionuclide inventory data presented here is intended only for TSPA-LA postclosure calculations. It is not applicable to preclosure safety calculations. Safe storage, transportation, and ultimate disposal of these wastes require safety analyses to support the design and licensing of repository equipment and facilities. These analyses will require radionuclide inventories to represent the radioactive source term that must be accommodated during handling, storage and disposition of these wastes. This analysis uses the best available information to identify the radionuclide inventory that is expected at the last year of last emplacement, currently identified as

  3. Orbital radionuclide examinations

    Orbital abnormalities can be evaluated by dynamic scintigraphy (radionuclide angiography) and static scintigraphy (radionuclide ''scanning''). The use of en face positioning improves the visualization of orbital details. Lesions can be detected and localized most accurately if multiple tracers are used for these studies. Abnormalities can be characterized by the recognition of various angiographic flow patterns, of distinct static distribution patterns, and of differences in the accumulation of multiple radiopharmaceuticals. The results of scintigraphic examination using technetium 99m sodium pertechnetate, mercury 197 chlormerodrin, and gallium 67 citrate in a series of 57 patients are reported. (U.S.)

  4. Transuranic radionuclides from resuspension in the environment, a bibliography

    Stoker, A.C.; Shinn, J.H.; Noshkin, V.E. [and others

    1994-04-01

    The purpose of this project was to compile a bibliography of references containing environmental transuranic radionuclide data. Our intent was to identify those parameters affecting transuranic radionuclide transport that may be generic and those that may be dependent on chemical form and/or environmental conditions. An understanding of the unique characteristics and similarities between source terms and environmental conditions relative to transuranic radionuclide transport and cycling will provide the ability to assess and predict the long term impact on man and the environment. An additional goal of our literature review, was to extract the ranges of environmental transuranic radionuclide data from the identified references for inclusion in a data base. Related to source term, these ranges of data can be used to calculate the dose to man from the radionuclides, and to perform uncertainty analyses on these dose assessments. On the basis of our reviews, we have arbitrarily outlined five general source terms. These are fallout, fuel cycle waste, accidents, disposal sites and resuspension. Resuspension of the transuranic radionuclides is an unique source term, in that the radionuclides can originate from any of the other source terms. If these transuranic radionuclides become resuspended into the air, they then become important as a source of inhaled radionuclides. This bibliography is a compilation of the references containing studies of plutonium and americium in the environment as a result of resuspension.

  5. Transuranic radionuclides dispersed into the aquatic environment, a bibliography

    Noshkin, V.E.; Stoker, A.C.; Wong, Kai M. [and others

    1994-04-01

    The purpose of this project was to compile a bibliography of references containing environmental transuranic radionuclide data. Our intent was to identify those parameters affecting transuranic radionuclide transport that may be generic and those that may be dependent on chemical form and/or environmental conditions (i.e., site specific) in terrestrial, aquatic and atmospheric environments An understanding of the unique characteristics and similarities between source terms and environmental conditions relative to transuranic radionuclide transport and cycling will provide the ability to assess and predict the long term impact on man and the environment. An additional goal of our literature review, was to extract the ranges of environmental transuranic radionuclide data from the identified references for inclusion in a data base. Related to source term, these ranges of data can be used to calculate the dose to man from the radionuclides, and to perform uncertainty analyses on these dose assessments. On the basis of our reviews, we have arbitrarily outlined five general source terms. These are fallout, fuel cycle waste, accidents, disposal sites and resuspension. Resuspension of the transuranic radionuclides is a unique source term, in that the radionuclides can originate from any of the other source terms. If these transuranic radionuclides become resuspended into the air, they then become important as a source of inhaled radionuclides.

  6. Clay as a barrier to radionuclide migration

    Because of their low permeability, high sorption capacity and plasticity clay bodies are potentially suitable repositories for radioactive waste. This paper discusses the factors that influence radionuclide mobility in natural clay materials. Methods for determining radionuclide migration rates are described and compared. Data requirements necessary to establish whether or not a particular site is suitable for waste disposal are discussed. Suggestions are made as to the most important generic research that needs to be carried out. In the appendix, some of the most relevant published sorption and diffusion data are summarized and compared. (author)

  7. Underground radionuclide migration

    The number 9 sub-report of the safety assesment studies of the disposal of radioactive waste in rock-salt formations concerns the calculation of radio-nuclide migration with groundwater. Calculations ar carried out in two phases. The first phase consists of calculation of the groundwater flow system under a great number of different hydrological boundary conditions, which possibly can be encountered in future. Variations in sea level and consequences of glaciations are included. Given a great number of possible groundwater flow systems, in the second phase radionuclide migration is calculated for a restricted number of representative situations. Transport of radionuclides with groundwater takes place, starting at a release point at the top (edge) of the rock salt formation until the landsurface, the bottom of a sea or an extraction-well for public water supply has been reached, at which places concentrations radionuclides have been computed as a function of time. Calculations continued till all concentrations had reached their maxima. Results form the input for biosphere dose-calculations, as reported in the number 10 sub-report. (author). 26 refs.; 43 figs.; 22 tabs

  8. Radionuclides in house dust

    Discharges of radionuclides from the British Nuclear Fuel plc (BNFL) reprocessing plant at Sellafield in Cumbria have led to elevated concentrations radionuclides in the local environment. The major routes of exposure of the public are kept under review by the appropriate authorising Government departments and monitoring is carried out both by the departments and by BNFL itself. Recently, there has been increasing public concern about general environmental contamination resulting from the discharges and, in particular, about possible exposure of members of the public by routes not previously investigated in detail. One such postulated route of exposure that has attracted the interest of the public, the press and Parliament arises from the presence of radionuclides within houses. In view of this obvious and widespread concern, the Board has undertaken a sampling programme in a few communities in Cumbria to assess the radiological significance of this source of exposure. From the results of our study, we conclude that, although radionuclides originating rom the BNFL site can be detected in house dust, this source of contamination is a negligible route of exposure for members of the public in West Cumbria. This report presents the results of the Board's study of house dust in twenty homes in Cumbria during the spring and summer of 1984. A more intensive investigation is being carried out by Imperial College. (author)

  9. Radionuclide transfer from contaminated field to crops

    Since the policy for land disposal of radioactive wastes were proposed, the importance of terrestrial radioecology has been re-recognized in Japan. The National Institute of Radiological Sciences (NIRS) held a Two-Day Seminar concerning terrestrial transfer of radionuclides. This is a compilation of papers presented at the seminar. The purpose of the seminar is twofold: firstly, to raise basic problems concerning transfer of not only radionuclides but also elements into crops, as well as to present NIRS's studies on radionuclide transfer; and secondly, to discuss in depth the topics about possible transfer of I-129 into rice plant arising from the commercial fuel reprocessing plant, the construction of which is under planning. Finally, general discussion of further issues on radioecology is given. (Namekawa, K.)

  10. Production of radionuclides with generators

    Full text: The radionuclide generator provides a convenient means for researchers and clinicians to obtain a source of radionuclides without dependence on nuclear facilities (nuclear reactor or cyclotron). It should be noted that radionuclide generator technique yields products of very high purity and it offers moreover the only possible way of obtaining very short-lived radionuclides for practical applications. Therefore at present radionuclide generators have found important uses in nuclear medicine. This talk reviews the development of preparation methods for radionuclide generators of current interest: 99Mo-99mTc, 188W-188Re and 68Ge-68Ga. 99Mo-99mTc generator. 99mTc is presently the most widely used radionuclide in diagnostic nuclear medicine. The reason for such a preeminent position of 99mTc in clinical uses is its extremely favorable nuclear properties with γ-energy of 140 keV and short half-life of 6 hours. Chromatographic generator of 99Mo-99mTc based on aluminium oxide using as eluent of isotonic saline solution, containing nitrate-ions has been produced in INP AS RU. However, the main disadvantage of this generator is that the eluent-saline solution contains some amount of nitrate-ions. Nitrate-ions added to maximize and stabilize 99mTc yields would interfere with the chemical reactions which involve Sn(II) reduction of the pertechnetate ion and which are used subsequently in the preparation of radiopharmaceuticals. Therefore we proposed the new method for preliminary treatment of aluminium oxide by the external gamma (Co-60) irradiation. It is found that the aluminium oxide has got electron-acceptor properties after gamma-irradiation. Adsorption of 99Mo radionuclide as isopolymolybdate on gamma-irradiated aluminium oxide is very high and molybdenum is firmly retained. Adsorption capacity of gamma-irradiated aluminium oxide at pH 2-4 is 60-80 mg Mo per gram of Al2O3. The yields of 99mTc from experimental generators remained high (75-85%) independently

  11. Modeling study of effects of short-lived radionuclide fixation on decay chain radionuclides migration

    Ohnuki, Toshihiko (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment); Watanabe, Shoji

    1993-08-01

    Effects of a short lived radionuclide fixation to minerals during alteration process from a primary mineral (M1) to tertiary mineral (M3) through secondary mineral (M2) on a decay chain radionuclides migration (DCRM) have been studied based on mathematical simulation studies. The mathematical migration model in which a daughter radionuclide, N[sub 2], corresponds to a short lived radionuclide and is fixed to M2 during alteration from M1 to M2, is proposed. Also, a fraction of the granddaughter radionuclide, N[sub 3], is assumed to be released from M2 into a solution during the alteration process from M2 to M3. The model studies lead the delay in the migration of N[sub 3], with the delay becoming remarkably enhanced if the fixation rate constant of N[sub 2] is greater than the decay constant of N[sub 2]. Whereas, the delay is reduced by the release of N[sub 3] with a faster rate than the decay constant of N[sub 3]. Therefore, it is important clarify decay chain radionuclides fixation and release mechanisms during an alteration process. (author).

  12. Radionuclides in food

    The sources of the presence of radionuclides in food are presented: natural radiation and artificial radiation. The transfer of radionuclides through food chains, intakes of radionuclides to the body with its partners effective doses and typical consumption of basic foods of a rural adult population are exposed as main topics. Also the radiation doses from natural sources and exposure to man by ingestion of contaminated food with radionuclides of artificial origin are shown. The contribution of the food ingestion to the man exposure depends on: characteristics of radionuclide, natural conditions, farming practices and eating habits of the population. The principal international organizations in charge of setting guide levels for radionuclides in food are mentioned: standards, rules and the monitoring. It establishes that a guide is necessary for the food monitoring; the alone CODEX ALIMENTARIUS is applicable to emergency situations and the generic action levels proposed by the CODEX not satisfy all needs (no guiding international levels for planned or existing situations such as NORM). There are handled mainly socio-economic and political aspects. Among the actions to be taken are: to assure a public comprehensive information over the risk evaluation in food; to reinforce the collaboration among the different international organizations (WHO, IAEA, ICRP, EC) in relation with the food of set; to give follow-up to the control of the drinkable water and NORM's presence in the food. In addition, it is possible to create the necessary mechanisms to reduce the number of irrelevant measures and bureaucratic useless steps (certificates); to promote the exchange between the different institutions involved in the topic of the food, with relation to the acquired experiences and learned lessons. Likewise, it might examine the possibility of a multidisciplinary approximation (radioactive and not radioactive pollutants); to elaborate a technical guide to assure the

  13. EBS Radionuclide Transport Abstraction

    The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment (TSPA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport model considers advective transport and diffusive transport

  14. Radionuclide diagnosis of nephrolithiasis

    Radionuclide investigations were conducted in 322 patients with nephrolithiasis. Unilateral calculosis was established in 46.3% of the patients, bilateral calculosis in 50.6%. The nature of changes on renograms, scintigrams and in clearance values shown to depend on the localization of concrements, their size and the presence of concomitant infection. A conclusion has been made as to the usefulness of the methods with relation to operative treatment, especially in a bilateral localization of a pathological renal process

  15. Radionuclide fate and effects

    The studies reported here deal with the full range of contaminant behavior and fate, from the initial physicochemical factors that govern radionuclide availability in terrestrial and aquatic environments to studies of contaminant transport by biological means. By design, we focus more on the biologically and chemically mediated transport processes and food-chain pathways than on the purely physical forms of contaminant transport, such as transport by wind and water

  16. Soil contamination by radionuclides

    The soil is the first link in the food chain. Soil contamination by individual radionuclides significantly affects the level of terrestrial radiation in the locality. The authors mapped situation of post-Chernobyl 137Cs soil contamination in Slovakia and European countries. Samples were collected in three layers of agriculturally cultivated area. Even a few years after the Chernobyl accident authors can say that elevated 137Cs values were recorded in the samples from Austria and Germany, in all layers of collection. (authors)

  17. Radionuclide co-precipitation

    The thermodynamic and kinetic behaviour of the minor components of the spent fuel matrix has been theoretically and experimentally investigated. Two different situations have been studied: Part I, the near field scenario, where the release and migration of the minor components is dependent on the solubility behaviour of UO2(s); Part II, the far field, where the solubility and transport of the radionuclides is related to the major geochemical processes occurring. (orig.)

  18. Radionuclides in terrestrial ecosystems

    A bibliographical database has been developed to provide quick access to research and background literature in the field of radioecology. This is a development of an earlier database described by Nelson (Bocock 1981). ITE's particular fields of interest have led to a subject bias in the bibliography towards studies in Cumbria, especially those concerned with radionuclides originating from the reprocessing plant at Sellafield, and towards ecological research studies that are complementary to radionuclide studies. Other subjects covered, include the chemistry of radionuclides, budgets and transfers within ecosystems and techniques for the analysis of environmental samples. ITE's research objectives have led to the establishment of a specialized database which is intended to complement rather than compete with the large international databases made available by suppliers such as IRS-DIALTECH or DIALOG. Currently the database holds about 1900 references which are stored on a 2 1/2 megabyte hard disk on a Digital PDP11/34 computer operating under a time shared system. The references follow a standard format. (author)

  19. Optimization of Samarium-153 labeled Hydroxyapatite Particles as Therapeutic Agent for Radiation Synovectomy

    Hydroxyapatite (HA) was studied as a particular carrier for beta-emitting radionuclides in radiation synovectomy. Particles were labeled with 153Sm (T1/2 = 46.7 hrs., β-energy = 810 (20%), 710(50%), 640(30%) keV, γ-energy = 103.2 (29.8%) KeV, range in tissue = 2.5 mm). Labeling efficiency was greater than 95%, pH 4-6, sterile and pyrogen free, stability is 6 days and in vivo studies by intra-articular injection into knee of normal rats showed the total cumulative leakage of 153Sm over 6 days was around 2% ID, The ease of preparation of 153Sm-HA, efficiency of labeling and low leakage from the joint make 153Sm-HA attractive for radiation synovectomy

  20. Understanding Radionuclide Interactions with Layered Materials

    Wang, Y.

    2015-12-01

    Layered materials play an important role in nuclear waste management and environmental cleanup. Better understanding of radionuclide interactions with those materials is critical for engineering high-performance materials for various applications. This presentation will provide an overview on radionuclide interactions with two general categories of layered materials - cationic clays and anionic clays - from a perspective of nanopore confinement. Nanopores are widely present in layered materials, either as the interlayers or as inter-particle space. Nanopore confinement can significantly modify chemical reactions in those materials. This effect may cause the preferential enrichment of radionuclides in nanopores and therefore directly impact the mobility of the radionuclides. This effect also implies that conventional sorption measurements using disaggregated samples may not represent chemical conditions in actual systems. The control of material structures on ion exchange, surface complexation, and diffusion in layered materials will be systematically examined, and the related modeling approaches will be discussed. This work was performed at Sandia National Laboratories, which is a multiprogram laboratory operated by Sandia Corporation, a Lockheed-Martin Company, for the DOE under contract DE-AC04-94AL8500.

  1. Transport and accumulation of radionuclides in soil

    The movement of radioactive isotopes through the water phase of soils is by far the most important. Most of the water-transported radioactive isotopes (radionuclides) occur via their dissolved salts, while the rest is carried by small soil particles to which the radionuclides are adsorbed. In the case of many chemicals, it is possible to calculate the movement or migration through soil from adsorption measurements made in the laboratory and from knowledge of the flow pattern of soil water. With increasing complexity of the chemical-soil-water system predictions become more uncertain. In the case of radionuclides the amounts expressed in units of weight are extremely small. This renders terms such as 'soluble' or 'insoluble' inapplicable. In these cases transport of 'radiocolloids' and adsorbed particles as 'insoluble' compounds may be more significant. For fallout strontium and cesium reliable predictive models have been developed. For fallout plutonium such models are under development. For calculations or predictions of the migration of radioactive material from deep soil layers to the soil surface fewer mathematical models are available. Many laboratory studies cannot yet be made due to lack of suitable soil samples from the sites under study. Nevertheless safety studies already carried out in a preliminary way are reliable, since factos such as adsorption of radionuclides on soils are neglected; consequently most safety studies overestimate possible risks. Further studies are required to ascertain how 'pessimistic' are the present safety criteriy. (orig./MG)

  2. RTP: Radionuclides inventories calculation using ORIGEN Code

    ORIGEN is a widely used computer code for calculating the buildup, decay, and processing of radioactive materials. The ORIGEN code was created by famous and reputable nuclear institution in United States, Oak Ridge National Laboratory (ORNL). For a nuclear reactor, either it is a nuclear power reactor or nuclear research reactor, the radionuclide inventories data is important. This data is acquired by performing source term modelling. A fresh nuclear fuel could not cause any harm to human. However, used nuclear fuel could pose danger threat to human. The fission products particularly long-lived radionuclides for example H-3, Co-60, Cs-137 that are generated inside the fuel yield a significance amount of radioactivity. Therefore, there is no doubt that for a facility having a nuclear reactor, it is vital to anticipate the amount of fission products inside the fuel together with the radioactivity that it may emit. Sufficient information on the radionuclide inventories allows the facility to provide adequate shielding protection and ensure safe transportation of nuclear fuel, when it is needed. This paper briefly describes application of ORIGEN code to calculate the radionuclides inventories of TRIGA-PUSPATI REACTOR (RTP) fuel. (author)

  3. Mechanisms controlling radionuclide mobility in forest soils

    Soil processes strongly influence the radionuclide mobility in soils. The mobility of radionuclides in forest soils is governed by several processes involving both abiotic and biotic factors. The sorption-desorption process chiefly governs the activity of radionuclides in the soil solution, hence thereby their mobility and biological availability. Radiocaesium exhibits a very low mobility in mineral soils. Both mobility and bioavailability however increase as the thickness of organic layers and their content in organic matter increases. Clay minerals of micaceous origin strongly act as slinks for radiocaesium in forest soils. The magnitude of cesium mineral fixation in topsoils is expected to be the highest in mineral soils of Eutric cambisol type, and, to a lesser extent, of type of Distric cambisol and Podzoluvisol. A low mobility of radiocaesium in the surface horizons of forest soils may also be partially explained by a biological mobilization: fungi absorb radiocaesium and transport it to upper layers, thereby contributing to constantly recycle the radioelement in the organic horizons. This mechanism is probably important in soils with thick organic layers (Podsol, Histosol, and, to a lesser extent, Distric cambisol and Podzoluvisol). Radionuclides can be associated with soluble organic anions in the soil solution of forest acid soils. Such associations are highly mobile: they are stable in conditions of poor biological activity (low temperatures, acid soil infertility, water excess, etc.). Their magnitude is expected to be the highest in thick acid organic layers (soils of type Podzol and Histosol)

  4. Improving cancer treatment with cyclotron produced radionuclides

    This new DOE proposal appropriately builds on past developments. The development and application of radionuclides for diagnosis, treatment and research has been a continuing concern for more than the past three decades. A brief description of this development and previous achievements was considered important in order to provide a frame of reference for the evolving program here. Earlier, the use of certain radionuclides, radon progeny and I-131 in particular, and also x-rays, had been developed by the work of such pioneers as Failla, Quimby and Marinelli. In 1952, at the instigation of Dr. C.P. Rhoads, Director of both Memorial Hospital and Sloan-Kettering Institute, the restoration of the Department of Physics and Biophysics was undertaken in response to a perceived need to promote the utilization of radionuclides and of high energy radiations for therapeutic, diagnostic and research purposes. This resulted in several research and developmental projects with close clinical collaboration in areas of radiation treatment; medical studies with radionuclides and labeled compounds; the diagnostic uses of x-rays; and some projects in surgery and other clinical areas. Aspects of some of these projects that have had some relevance for the evolving AEC-DOE projects are outlined briefly. 34 refs

  5. The relevance of speciation to the environmental behaviour of radionuclides

    Full text: Radionuclides exist in different chemical forms in the environment ranging from low molecular mass species such as ions, molecules and complexes to high molecular mass species such as colloids, particles and fragments. Furthermore, the physical characteristics of released radionuclides can vary considerably in morphology and structure, size, shape, density, valence and charge. For instance, a proportion of the radionuclides released from a nuclear weapons tests, routine discharges and reactor accidents are present as radioactive particles of varying size. Initially, radionuclide speciation is dependent on the source and release conditions. Once deposited, they can be transformed with time through interaction with various ecosystem components. Many studies have shown that differences in chemical and physical form can lead to varying environmental mobility and hence affect radiation doses. Low molecular mass species are reported to be more bioavailable and environmentally mobile than colloids and particles. Thus, to reliably predict the environmental impact of radioactive contamination of different ecosystems, we need to link information on radionuclide composition and speciation to an understanding of the influence this might have on environmental mobility. To do this, various techniques have been developed to estimate bioavailability of radionuclides in soils and sediments, which often act as the major sink for radionuclides, and in plants. Here, I summarize current knowledge linking radionuclide speciation to bioavailability and then consider whether such information has been adequately integrated into currently available predictive models of radionuclide behaviour in the environment. The transfer of radioactivity to the milk and meat of farm animals is likely be a major exposure pathway of human populations, following an environmental release of radioactivity. As a more detailed example, the importance of source dependent bioavailability in determining

  6. EBS Radionuclide Transport Abstraction

    J.D. Schreiber

    2005-08-25

    The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in ''Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration'' (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment for the license application (TSPA-LA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA-LA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport

  7. Radionuclide transport coupled with bentonite extrusion in a saturated fracture system

    Borrelli, Robert Angelo

    The study in this dissertation focuses on the characterization of radionuclide migration in a water saturated fracture. The near field of a high level radioactive waste repository contains the engineered barrier system, which provides manufactured components designed to limit radionuclide releases to the environment. A major component in this system involves the utilization of bentonite as a buffer to protect the degraded waste package and limit release of radionuclides into intersecting fractures that pose possible pathways for transport to the environment. A model is derived for radionuclide migration through this fracture. The model incorporates the features of bentonite: extrusion into the fracture, sorption, and the effect of bentonite swelling on groundwater flow. The resulting derivation of this model is a coupled system of differential equations. The differential equation describing the mass conservation of radionuclides is coupled to the equation system for bentonite extrusion. The models are coupled through the parameters in the radionuclide transport model, which are dependent on the spatial distribution of solid material in the domain. Numerical evaluations of the solution to this radionuclide transport model were conducted for neptunium, a weakly sorbing radionuclide and americium, a strongly sorbing radionuclide. Results were presented in terms normalized spatial distribution of radionuclide concentration in the fluid phase and normalized radionuclide release rate in the fluid phase. Major findings of the study conducted for this dissertation are provided. (1) Bentonite extrusion affects fluid phase advection resulting in groundwater flow countercurrent to the direction of extrusion to the direction of radionuclide migration. (2) The sorption distribution coefficient is the most important parameter affecting radionuclide behavior in this system for this model. (3) Simulations of the model for americium, a highly sorbing radionuclide, indicate that

  8. Absorption of selected radionuclides

    In October 1978, the Institut fuer Energie- und Umweltforschung Heidelberg e.V. published a contribution to part 26 of the model study of radio-ecology at Biblis under the title 'Estimation of the absorption of radionuclides from the gastrointestinal tract in the blood'. Using the example of this contribution, a critical analysis is made to show how a selection of the information contained in various scientific publications and other items of literature can give uncritical readers the impression that all statements made are scientifically well founded. (orig./HP)

  9. Sherlock Holmes for radionuclides

    At the end of 2001 ARC Seibersdorf research has taken the management of the first worldwide certified laboratory to control the realization of the international Comprehensive Nuclear Test Ban Treaty (CTBT). Altogether there will be 16 CTBT certified laboratories worldwide; therefore a global network of radionuclides measurements stations and test laboratories as well as seismic, radiation and hydroacustic measurements stations is necessary . In the future air samples will be taken from these stations and analyzed in one of these certified laboratories, when appears the suspicion that an atomic test was carried out. (nevyjel)

  10. Modifying radionuclide effects

    This project involves a study of the relationship of physiological and environmental factors to the metabolism and effects of radionuclides. We have studied placental transfer and suckling as pathways of americium entry into the newborn or juvenile rat. Rats were injected intravenously with 5 μCi of 241Am while nulliparous (30 days prior to mating), pregnant (day 19 of gestation), or lactating (1 day after parturition), and subsequent litters were killed to determine 241Am retention. A deficit in reproductive performance was observed in the group injected before mating, as evidenced by reduced number and weight of offspring