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Sample records for 153sm important radionuclides

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

    CERN Document Server

    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.

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

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    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.

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

    Science.gov (United States)

    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

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  8. Experimental studies on apoptosis imaging of 153Sm-Annexin V%153Sm-Annexin V凋亡显像的实验研究

    Institute of Scientific and Technical Information of China (English)

    刘江; 赵颖如; 王健; 孙雷娜; 牛瑞芳; 徐文贵

    2013-01-01

      Objective: This work aimed to investigate the feasibility of apoptosis imaging of Annexin V labeled with the radionu-clide 153Sm. Methods: 153Sm-Annexin V was prepared by using the cyclic diethylene triamine pentaacetic acid (DTPA) method, after which physical, chemical, and biological assays of the protein were conducted. Apoptosis imaging experiment both for in vitro cell cul-ture and for tumor-bearing mice was performed using 153Sm-Annexin V. Results: The features of 153Sm-Annexin V prepared via the cy-clic DTPA method are as follows: colorless and transparent, pH 7.4, radioactivity of 100 μg/10 mCi/2 mL, radiochemical purity of over 90%, and 88.6% radiolabeling rate. Annexin V is sterile, pyrogen-free, and presents an LD50 of 333 μg/kg body weight and plasma half-life of 13 min. Positive apoptosis images were obtained from both cultured cells and tumor-bearing mice. Conclusion: 153Sm-An-nexin V, as a radionuclide-labeled apoptosis imaging agent, exhibits a high labeling rate and relatively long half-life. The agent can effi-ciently facilitate continuous tracking and capturing of apoptotic peak activity, thus establishing an optimal apoptosis imaging window period. These advantages indicate that the proposed imaging method has great potential in many clinical applications.%  目的:探讨放射性核素153Sm 标记 Annexin V 凋亡显像的可行性。方法:采用环二乙三胺五醋酸(DTPA)法进行153Sm-Annexin V制备,并进行物理、化学及生物学检测。应用153Sm-Annexin V进行体外细胞培养及荷瘤小鼠动物凋亡显像实验。结果:经环DTPA法制备的153Sm-Annexin V无色透明,pH为7.4,比活度100μg/10 mCi/2 mL;放化纯RCP>90%,标记率为88.6%;无菌,无热原,LD50>333μg/kg体质量,血浆半衰期13 min;体外细胞培养及荷瘤小鼠动物凋亡显像实验均阳性。结论:153Sm-Annex⁃in V作为放射性核素凋亡显像剂,标记率高,半衰期相对较长,利于

  9. 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

    Institute of Scientific and Technical Information of China (English)

    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.

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

    Directory of Open Access Journals (Sweden)

    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.

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

    Science.gov (United States)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  13. Application of a wrist dosimeter prototype for radiation monitoring ({sup 153}Sm) during a therapeutic procedure simulation

    Energy Technology Data Exchange (ETDEWEB)

    Cecatti, S G P [Fundacentro, Ministerio do Trabalho e Emprego, Rua Capote Valente, 710, 05409-002, Sao Paulo (Brazil); Guimaraes, M I C C [Centro de Medicina Nuclear, Universidade de Sao Paulo, Travessa da Rua Dr. Ovidio Pires de Campos s/n, 05403-010, Sao Paulo (Brazil); Caldas, L V E [Instituto de Pesquisas Energeticas e Nucleares, IPEN-Comissao Nacional de Energia Nuclear, Avenida Professor Lineu Prestes, 2242, 05508-000, Sao Paulo (Brazil)], E-mail: scecatti@fundacentro.gov.br, E-mail: ines@hcnet.usp.br, E-mail: lcaldas@ipen.br

    2009-12-01

    Gamma and beta radiation emitting radiopharmaceuticals are handled in nuclear medicine services, and in many cases there is only individual monitoring of gamma radiation. In this paper, the results obtained using a wrist dosimeter prototype (CaSO{sub 4}:Dy+Teflon pellets) show that the doses for workers occupationally exposed to beta radiation from {sup 153}Sm are not negligible. It is important that this dose is evaluated, and it has to be taken into consideration in the individual monitoring system.

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

    Institute of Scientific and Technical Information of China (English)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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)

  18. 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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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. Polyphosphoric acid capping radioactive/upconverting NaLuF4:Yb,Tm,153Sm nanoparticles for blood pool imaging in vivo.

    Science.gov (United States)

    Peng, Juanjuan; Sun, Yun; Zhao, Lingzhi; Wu, Yongquan; Feng, Wei; Gao, Yanhong; Li, Fuyou

    2013-12-01

    Nanoparticles that circulate in the bloodstream for a prolonged period of time have important biomedicine applications. However, no example of lanthanide-based nanoparticles having a long-term circulation bloodstream has been reported to date. Herein, we report on difunctional radioactive and upconversion nanoparticles (UCNP) coated with polyphosphoric acid ligand, that is ethylenediamine tetramethylenephosphonic acid (EDTMP), for an application in single-photon emission computed tomography (SPECT) blood pool imaging. The structure, size and zeta-potential of the EDTMP-coated nanoparticles (EDTMP-UCNP) are verified using transmission electron microscopy and dynamic light scattering. Injection of radioisotope samarium-153-labeled EDTMP-UCNP (EDTMP-UCNP:(153)Sm) into mice reveal superior circulation time compared to control nanoparticles coated with citric acid (cit-UCNP:(153)Sm) and (153)Sm complex of EDTMP (EDTMP-(153)Sm). The mechanism for the extended circulation time may be attributed to the adhesion of EDTMP-UCNP on the membrane of red blood cells (RBCs). In vivo toxicity results show no toxicity of EDTMP-UCNP at the dose of 100 mg/kg, validating its safety as an agent for blood pool imaging. Our results provide a new strategy of nanoprobe for a long-term circulation bloodstream by introducing polyphosphoric acid as surface ligand.

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

  3. Evaluation of the dinical curative effect of using 153Sm-EDTMP in painful bone metastasis of malignant tumor%153Sm-乙二胺四甲基撑膦酸治疗恶性肿瘤骨转移疼痛

    Institute of Scientific and Technical Information of China (English)

    张晓娟; 晋建华; 刘建中; 李思进; 李险峰; 张承刚; 郭睿; 宁艳丽

    2008-01-01

    目的 评价153Sm-乙二胺四甲基撑膦酸(153Sm-EDTMP)在恶性肿瘤骨转移疼痛治疗中的临床应用价值.方法 对80例骨转移癌患者进行153Sm-EDTMP治疗,按22.2~37 MBq/kg体重一次性静脉注射给药.按照视觉模拟评分法和Kamofsky评分标准,分别评价治疗前后患者疼痛缓解及生活质量改善情况.结果 153Sm-EDTMP治疗的80例骨转移癌患者中,疼痛缓解总有效率为68.75%.其中前列腺癌骨转移癌痛缓解率最高,达81.82%,其次为乳腺癌和肺癌,分别为80.00%、75.00%.分析治疗前后Karnofsky评分变化情况,发现疼痛级别越高生活质量改善越明显.结论 153Sm-EDTMP对恶性肿瘤骨转移所致的疼痛具有较好的缓解作用,对中、重度骨痛患者的生活质量有明显的改善,该法是使用放疗、镇痛药物等方法治疗骨转移癌痛的有益补充.%Objective To evaluate the clinical curative effect of using 153Sm-EDTMP in painful bone metastasis of malignant tumor. Methods Eighty patients with bone metastasis of malignant rumor underwent radionuclide bone palliation therapy were analysed.The treatment efficacy was evaluated by visual analogue scale (VAS) and Kamofsky performance scale.Results 68.75% of patients had a positive response.A better analgesic effect was found in cases of lung,prostate and breast carcinoma metastasm compared to metastasis from other malignant lesions.Improvement of performance in Karnofsky scale was found in cases of midrange and heavy range patients.Conclusion The analgesic effects of 153Sm-EDTMP is obvious in painful bone metastasis of malignant tumor.Improvement of life quality is significant in cases of midrange and heavy range patients.The therapeusis is a beneficial supplement of radiotherapy and odynolysis therapy.

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

    International Nuclear Information System (INIS)

    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

  5. Standardization of {sup 153}Sm using anti-coincidence method; Padronizacao do {sup 153}Sm pelo metodo de anti-coincidencia

    Energy Technology Data Exchange (ETDEWEB)

    Laranjeira, Adilson da Silva; Silva, Carlos J. da; Delgado, Jose Ubiratan; Cruz, Paulo A.L. da; Poledna, Roberto; Silva, Ronaldo L. da; Oliveira, Antonio E. de; Gomes, Regio S.; Veras, Eduardo V. de; Araujo, Miriam Taina Ferreira de, E-mail: adilson@ird.gov.br [Instituto de Radioprotecao e Dosimetria, (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2014-07-01

    {sup 153}Sm was standardized at the Brazilian National Laboratory of Metrology of Ionizing Radiation to provide traceability for measurements in nuclear medicine services and manufacturers of radiopharmaceuticals in Brazil. {sup 153}Sm decays by emission β-γ to {sup 153}Eu, the gamma rays of higher-intensity are 69.7 keV (4.7%) and 103.2 keV (29.2%). The standardization was made by anticoincidence and CIEMAT/NIST methods with uncertainties combined (0.4% and 0.3%) and (0.5% and 0.4%), respectively. The difference between the standardized activities was 0.15%. The uncertainties are consistent with other publications. (author)

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

    International Nuclear Information System (INIS)

    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

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

    CERN Document Server

    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.

  8. Labelling of MoAb with 153SmH1ETA: Preliminary results

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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.

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

    International Nuclear Information System (INIS)

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.)

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

    International Nuclear Information System (INIS)

    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)

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

    Institute of Scientific and Technical Information of China (English)

    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.

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

    International Nuclear Information System (INIS)

    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

  16. Calculation of the Dose of Samarium-153-Ethylene Diamine Tetramethylene Phosphonate (153Sm-EDTMP as a Radiopharmaceutical for Pain Relief of bone Metastasis

    Directory of Open Access Journals (Sweden)

    Fatemeh Razghandi

    2016-04-01

    Full Text Available Introduction One of the important applications of nuclear physics in medicine is the use of radioactive elements as radiopharmaceuticals. Metastatic bone disease is the most common form of malignant bone tumors. Samarium-153-ethylene diamine tetramethylene phosphonate (153Sm-EDTMP as a radiopharmaceutical is used for pain palliation. This radiopharmaceutical usually emits beta particles, which have a high uptake in bone tissues. The purpose of this study was to calculate the radiation dose distribution of 153Sm-EDTMP in bone and other tissues, using MCNPX Monte Carlo code in the particle transport model. Materials and Methods Dose delivery to the bone was simulated by seeking radiopharmaceuticals on the bone surface. The phantom model had a simple cylindrical geometry and included bone, bone marrow, and soft tissue. Results The simulation results showed that a significant amount of radiation dose was delivered to the bone by the use of this radiopharmaceutical. Conclusion Thebone acted as a fine protective shield against rays for the bone marrow. Therefore, the trivial absorbed dose by the bone marrow caused less damage to bone-making cells. Also, the high absorbed dose of the bone could destroy cancer cells and relieve the pain in the bone.

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

    International Nuclear Information System (INIS)

    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)

  18. 153 SM-EDTMP (Samario como tratamiento del dolor óseo de origen metastático 153 SM-EDTMP (SAMARIO For the treatment of metastatic bone pain

    Directory of Open Access Journals (Sweden)

    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

  19. 153Sm -DOTA-phosphine-ruthenium and gold bimetallic complexes as new radio-theranostics

    International Nuclear Information System (INIS)

    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)

  20. 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

    Energy Technology Data Exchange (ETDEWEB)

    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)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

  4. Environmentally important radionuclides in nonproliferative fuel cycles

    International Nuclear Information System (INIS)

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

    OpenAIRE

    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...

  6. 153Sm-EDTMP治療肺癌多發性骨轉移的臨床應用78例%Clinical applications of 153 Sm-EDTMP in treatment of multiple bone metastases in 78 patients with lung cancer

    Institute of Scientific and Technical Information of China (English)

    肖國有; 李黨生; 梁藝華; 姚新娟

    2001-01-01

    Objective To evaluate the effect of 153Sm-EDTMP in treating patients with lung cancer and multiple bone metastases. Methods A dose of 18.5~25.9MBq/Kg ~Sm-EDTMP was administered once a month to each patient through vein injection according to disease severity and body weight. 3 injections made up one therapy cycle. Results Pain relieves were obtained in 65 patients, with an effective rate of 83.3%. Pain relief of grade Ⅰ was observed in 19 patients (24.3%), grade Ⅱ in 46 patients (59%) and grade Ⅲ in 13 patients (16.7%0),respectively. Lesions of bone metastases disappeared or shrunk in 9 patients, with a positive rate of 11.5 %. which included 3 cases of grade I and 6 cases of grade Ⅱ , respectively. Better effects were obtained in adenocarcinoma and squamous carcinoma than in small cell lung cancer. Conclusion 153Sm-EDTMP is safe and effective in treating patients with lung cancer and multiple bone metastases.

  7. 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

    Energy Technology Data Exchange (ETDEWEB)

    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)

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

    Science.gov (United States)

    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

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

    International Nuclear Information System (INIS)

    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)

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

    Science.gov (United States)

    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).

  11. 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

    Institute of Scientific and Technical Information of China (English)

    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.

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

    International Nuclear Information System (INIS)

    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)

  13. 99TC-MDP@153Sm-EDTMP治疗骨转移癌64例报告

    Institute of Scientific and Technical Information of China (English)

    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.

  14. Production and first use of {sup 153}SmCl{sub 3}-ion exchange resin capsule formulation for assessing gastrointestinal motility

    Energy Technology Data Exchange (ETDEWEB)

    Yeong, Chai-Hong; Abdullah, Basri Johan Jeet; Ng, Kwan-Hoong [University of Malaya Research Imaging Centre, University of Malaya, 50603 Kuala Lumpur (Malaysia); Department of Biomedical Imaging, Faculty of Medicine, University of Malaya, 50603 Kuala Lumpur (Malaysia); Chung, Lip-Yong [Department of Pharmacy, Faculty of Medicine, University of Malaya, 50603 Kuala Lumpur (Malaysia); Goh, Khean-Lee [Department of Medicine, Faculty of Medicine, University of Malaya, 50603 Kuala Lumpur (Malaysia); Sarji, Sazilah Ahmad [University of Malaya Research Imaging Centre, University of Malaya, 50603 Kuala Lumpur (Malaysia); Department of Biomedical Imaging, Faculty of Medicine, University of Malaya, 50603 Kuala Lumpur (Malaysia); Perkins, Alan Christopher, E-mail: alan.perkins@nottingham.ac.uk [Radiological and Imaging Sciences and Nottingham Digestive Diseases Biomedical Research Unit, University of Nottingham, Nottingham NG7 2UH (United Kingdom)

    2012-03-15

    We produced an enteric-coated gelatine capsule containing neutron-activated {sup 153}Sm-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 {sup 153}Sm. All the capsules remained intact in stomach. This proved to be a safe and practical oral capsule formulation for whole gut transit scintigraphy. - Highlights: Black-Right-Pointing-Pointer Enteric-coated gelatin capsule containing {sup 153}Sm-labelled resin was manufactured. Black-Right-Pointing-Pointer In vitro disintegration test ensured targeted release properties of the formulation. Black-Right-Pointing-Pointer In vivo volunteers study confirmed safeness and practical use of the formulation. Black-Right-Pointing-Pointer {sup 153}Sm can be used as an alternative nuclide to {sup 111}In in GI transit scintigraphy.

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

    International Nuclear Information System (INIS)

    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)

  16. Environmentally important radionuclides in nonproliferative fuel cycles

    International Nuclear Information System (INIS)

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.)

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

    International Nuclear Information System (INIS)

    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)

  20. Treatment efficacy of 153Sm-EDTMP for painful bone metastasis

    Directory of Open Access Journals (Sweden)

    Narjess Ayati

    2013-04-01

    Full Text Available Introduction: Involvement of the skeleton can cause an excruciating pain in two-thirds of terminal patients with a history of malignancy. Due to several limitations of other therapies, such as analgesics, bisphosphonates, chemotherapy, hormonal therapy and external beam radiotherapy; bone-seeking radiopharmaceuticals have an important role in palliation of pain from bone metastases. Although these kinds of therapies have many advantages including the ability to treat multiple sites of tumoral involvement simultaneously, no significant confliction with other treatments, ease of administration and the potential to be used repetitively; in Iran using of this modality is not widely practiced. In this study we evaluated the clinical usefulness of Sm-153 lexidronamfor pain management of bone metastases. Methods: 28 patients (14 males and 14 females aged 38-77 years with a history of painful bone metastases caused by different cancers, not responding to conventional treatments were included in the study. All patients had a recent whole body bone scan indicating multiple bone metastases. 1 mCi/Kg Sm-153 lexidronam was injected intravenously to the patients. Whole body scintigraphy was done 3 or 18 hours post injection. Pain relief and quality of life have been evaluated by analog pain scale and Karnofsky index every week, respectively. Also, all patients were evaluated for hematological toxicity every two weeks. Active follow ups were performed. Results: 43% of patients showed the presence of the flare phenomenon during the first three days after Sm injection with a mean duration of 2.2 days. The pain relief began between 2 and 16 days post injection and the duration of pain palliation was in the range of 4 to 32 weeks (mean±SD=15.22±7.8. 64.3% of patients showed complete relief of pain and 21.4% achieved partial response to therapy. (Over all response to therapy was 85.7%. The lowest amount of peripheral blood cells was detected in the fourth week

  1. Treatment efficacy of 153Sm-EDTMP for painful bone metastasis

    Directory of Open Access Journals (Sweden)

    Narjess Ayati

    2013-04-01

    Full Text Available Introduction: Involvement of the skeleton can cause an excruciating pain in two-thirds of terminal patients with a history of malignancy. Due to several limitations of other therapies, such as analgesics, bisphosphonates, chemotherapy, hormonal therapy and external beam radiotherapy; bone-seeking radiopharmaceuticals have an important role in palliation of pain from bone metastases. Although these kinds of therapies have many advantages including the ability to treat multiple sites of tumoral involvement simultaneously, no significant confliction with other treatments, ease of administration and the potential to be used repetitively; in Iran using of this modality is not widely practiced. In this study we evaluated the clinical usefulness of Sm-153 lexidronamfor pain management of bone metastases. Methods: 28 patients (14 males and 14 females aged 38-77 years with a history of painful bone metastases caused by different cancers, not responding to conventional treatments were included in the study. All patients had a recent whole body bone scan indicating multiple bone metastases. 1 mCi/Kg Sm-153 lexidronam was injected intravenously to the patients. Whole body scintigraphy was done 3 or 18 hours post injection. Pain relief and quality of life have been evaluated by analog pain scale and Karnofsky index every week, respectively. Also, all patients were evaluated for hematological toxicity every two weeks. Active follow ups were performed. Results: 43% of patients showed the presence of the flare phenomenon during the first three days after Sm injection with a mean duration of 2.2 days. The pain relief began between 2 and 16 days post injection and the duration of pain palliation was in the range of 4 to 32 weeks (mean±SD=15.22±7.8. 64.3% of patients showed complete relief of pain and 21.4% achieved partial response to therapy. (Over all response to therapy was 85.7%. The lowest amount of peripheral blood cells was detected in the fourth week

  2. 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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  3. Environmentally important radionuclides in non-proliferative fuel cycles

    International Nuclear Information System (INIS)

    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)

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

    Energy Technology Data Exchange (ETDEWEB)

    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.)

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

    International Nuclear Information System (INIS)

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    International Nuclear Information System (INIS)

    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.

  8. 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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  9. 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

    International Nuclear Information System (INIS)

    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

  10. 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

    Energy Technology Data Exchange (ETDEWEB)

    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

  11. 153 Sm-EDTMP骨摄取率测定及其与疗效的关系%Samarium-153-EDTMP bone uptake rate and its relation to therapeutic effect

    Institute of Scientific and Technical Information of China (English)

    李林; 梁正路; 邓候富; 匡安仁; 谭天秩; 罗顺忠

    2002-01-01

    Objective To evaluate the measurement of Samarium-153 ethylenediaminetetramethylene phosphonic acid (153Sm-EDTMP) bone uptake rate using whole-body scintigraphy and analyze the relationship between bone uptake rate and therapeutic effect. Methods Sixty-six patients with painful bony metastases from prostate (n=15), lung (n=20), breast (n=18), nasopharyngeal carcinoma (NPC) (n=5), colon (n=2), kidney (n=2) and unknown cause (n=4) carcinoma were examined with whole-body scintigraphy 10 min and 5 h post administration of 153 Sm-EDTMP. Bone uptake rate was then calculated. (1) Complete response (CR): disappearance of >2 metastases, Karnofsky Performance Score (KPS) increase >20, moderate or complete remission of bone pain 7 d post injection of 153 Sm-EDTMP. (2) Partial response (PR): disappearance of 1-2 metastases, KPS increase 10-20, moderate remission of bone pain in 3 wk. (3) Non-response (NR): no disappearance or shrinkage of metastases, KPS increase <10, no or slight remission of bone pain.Results The range of bone uptake rate in 66 patients was 31.9%-86.6% (mean=56.0%). The bone uptake rate in the CR group (17 cases, 25.7%), PR group (24 cases, 36.4%), and NR group (25 cases, 37.9%) was 52.4%-86.6% (mean=68.7%), 43.7%-70.4% (mean=58.3%), and 31.9%-51.5% (mean=41.0%) respectively. Statistical analysis showed that there was a significant difference between the CR and PR groups (t=4.258, P=0.001) as well as between PR and NR groups (t=8.48, P=0.001). Conclusions Using a simple and reliable whole-body scintigraphic technique to calculate prospectively the bone uptake rate, we have, for the first time in China, reported the relationship between bone uptake rate and therapeutic effect. This allows nuclear medicine physicians to calculate a safe and effective dose of 153 Sm-EDTMP in individual patients to palliate bone cancer pain without myelotoxicity.%目的在国内首次采用全身显像法测定153Sm-EDTMP(乙二胺四甲撑膦酸)骨摄取率并探讨骨摄取

  12. Concentrations of natural radionuclides in imported zirconium minerals

    Directory of Open Access Journals (Sweden)

    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%.

  13. 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

    International Nuclear Information System (INIS)

    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

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

    Science.gov (United States)

    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.

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

    International Nuclear Information System (INIS)

    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)

  16. 153 Sm-EDTMP显像测定骨摄取率在个体化治疗剂量计算中的应用%Dosimetry of 153 Sm-EDTMP therapy by preparative whole-body scintigraphy

    Institute of Scientific and Technical Information of China (English)

    李林; 梁正路; 邓候富; 李云春

    2001-01-01

    目的探讨153Sm-乙二胺四甲撑膦酸(EDTMP)全身显像法在个体化给药剂量计算中的价值。方法对20例骨转移癌患者进行153Sm-EDTMP显像,计算骨摄取率,并与尿液收集法进行比较。结果显像法与尿液收集法所测得的骨摄取率之间具有很好的相关性(r=0.93)。根据显像法计算的骨摄取率,给药剂量为1.40~2.27 GBq(平均1.90 GBq),骨髓吸收剂量为1.37~1.43 Gy(平均1.40 Gy)。按标准体重计算,则应给予的剂量为1.75~2.41 GBq(平均2.18 GBq),骨髓吸收剂量为1.37~2.27 Gy(平均1.63 Gy)。两种方法给药剂量之间差异有显著性(t=4.075, P=0.001),骨髓吸收剂量差异也有显著性(t=4.030, P=0.001)。结论骨转移癌患者治疗剂量按153Sm-EDTMP显像法测定的骨摄取率进行个体化给药,在达到治疗目的的同时,还可避免发生骨髓毒性反应,具有重要的临床价值。

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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)

  1. Table of radionuclides (Vol. 5 - A = 22 to 244)

    Energy Technology Data Exchange (ETDEWEB)

    Be, M.M.; Chiste, V.; Dulieu, C.; Mougeot, X.; Browne, E.; Chechev, V.; Kuzmenko, N.; Kondev, F.; Luca, A.; Galan, M.; Arinc, A.; Huang, X.

    2010-07-01

    This monograph is one of several published in a series by the Bureau International des Poids et Mesures (BIPM) on behalf of the Comite Consultatif des Rayonnements Ionisants (CCRI), previously known as the Comite Consultatif pour les Etalons de Mesure des Rayonnements Ionisants (CCEMRI). The aim of this series of publications is to review topics that are of importance for the measurement of ionizing radiation and especially of radioactivity, in particular those techniques normally used by participants in international comparisons. It is hoped that these publications will prove to be useful reference volumes both for those who are already engaged in this field and for those who are approaching such measurements for the first time. The purpose of this monograph is to present the recommended values of nuclear and decay data for a wide range of radionuclides. Activity measurements for more than forty of these radionuclides have already been the subject of comparisons under the auspices of Section II of the CCRI. The material for this monograph is now covered in four volumes. The first two volumes contain the primary recommended data relating to half-lives, decay modes, x-rays, gamma-rays, electron emissions; alpha- and beta-particle transitions and emissions, and their uncertainties for a set of sixty-eight radionuclides: Volume 1 for those radionuclides with mass number up to and including 150, and Volume 2 for those radionuclides with mass number over 150. Volume 3 contains the equivalent data for twenty-six additional radionuclides and re-evaluations for {sup 125}Sb and {sup 153}Sm; Volume 4 contains the data for a further thirty-one radionuclides with re-evaluation for {sup 226}Ra while the present Volume 5 includes 17 new radionuclide evaluations and 8 re-evaluations of previous data as identified in the contents page. The data have been collated and evaluated by an international working group (Decay Data Evaluation Project) led by the LNE-LNHB. The evaluators

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  3. Dose evaluation of therapeutic radiolabeled bleomycin complexes based on biodistribution data in wild-type rats:Effect of radionuclides in absorbed dose of different organs

    Institute of Scientific and Technical Information of China (English)

    Hassan Yousefnia; Samaneh Zolghadri; Amir Reza Jalilian; Mohammad Ghannadi-Maragheh

    2015-01-01

    Bleomycins (BLMs), as tumor-seeking antibiotics, have been used for over 20 years in treatment of several types of cancers. Several radioisotopes are used in radiolabeling of BLMs for therapeutic and diagnostic purpos-es. An important points in developing new radiopharmaceuticals, especially therapeutic agents, is the absorbed dose delivered in critical organs. In this work, absorbed dose to organs after injection of 153Sm-, 177Lu-and 166Ho-labeled BLM was investigated by radiation dose assessment resource (RADAR) method based on biodis-tribution data in wild-type rats. The absorbed dose effect of the radionuclides was evaluated. The maximum absorbed dose for the complexes was observed in the kidneys, liver and lungs. For all the radiolabeled BLMs, bone and red marrow received considerable absorbed dose. Due to the high energy beta particles emitted by 166Ho, higher absorbed dose is observed for 166Ho-BLM in the most organs. The reported data can be useful for the determination of the maximum permissible injected activity of the radiolabeled BLMs in the treatment planning programs.

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

    Energy Technology Data Exchange (ETDEWEB)

    Roussel-Debet, S. [CEA Cadarache (DEI/SECRE/LRE), Laboratory of Radioecology and Ecotoxicology, Institute for Radioprotection and Nuclear Safety, 13 - Saint-Paul-lez-Durance (France); Deneux-Mustin, S. [Nancy-1 Univ. Henri Poincare, LIMOS Laboratoire des Interactions Microorganismes-Mineraux-Matiere Organique dans les sols, UMR7137 CNRS, 54 - Vandoeuvre-les-Nancy (France)

    2004-07-01

    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)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

  10. New Measurements of the Astrophysically Important ^44Ti Radionuclide Through the ^40Ca(α,γ)^44Ti Reaction

    Science.gov (United States)

    Robertson, Daniel; Becker, Hans-Werner; Collon, Philippe; Goerres, Joachim; Wiescher, Michael

    2010-11-01

    The relatively short-lived radionuclide ^44Ti (t1/2=58.9 ± 0.3 yrs), is of considerable importance in the study of nucleosynthesis in explosive stellar environments. It's production predominantly through the ^40Ca(α,γ)^44Ti reaction, takes place during α-rich freeze-out, in the inner most layers of a core-collapse supernova. A number of experimental studies have been previously performed to determine the stellar reaction rate. These studies included prompt γ-ray measurements from in-beam experiments, atom counting techniques utilizing accelerator mass spectrometry (AMS) and multi energy step measurements at the DRAGON recoil mass separator. The resulting calculated reaction rates show drastic disagreement. New results from experiments at the DTL, Bochum and NSL, Notre Dame, used both gamma spectroscopy and AMS techniques to measure the reaction, and investigate the discrepancies in both the experimental and predicted results. Final results of the experiments and their impact on the reaction rate will be discussed.

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

    International Nuclear Information System (INIS)

    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

  12. Progress on Standardization of Radioanalytical Methods for determination of important radionu-clides for environmental assessment and waste management in Nordic nuclear industry

    DEFF Research Database (Denmark)

    Hou, Xiaolin; Olsson, Mattias; Vaaramaa, Kaisa;

    The NKS-B STANDMETHOD project was launched in January 2014, aiming to standardize the radioanalytical method for the determination of important radionuclides difficult to measure in Nordic industry. The present status of radioanalysis in Nordic laboratories is reviewed and presented in this report...... participated in the intercomparison and reported their analytical results of 63Ni. Different analytical methods used by the labs, and the results are discussed in this report. The intercomparison results for 63Ni agree relatively well for the spiked water, but a big variation of the results was observed...

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

    Science.gov (United States)

    Lanconelli, N.; Pacilio, M.; Lo Meo, S.; Botta, F.; Di Dia, A.; Torres Aroche, L. A.; Coca Pérez, M. A.; Cremonesi, M.

    2012-01-01

    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.medphys.it.

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

    Science.gov (United States)

    Lanconelli, N; Pacilio, M; Lo Meo, S; Botta, F; Di Dia, A; Aroche, A Torres; Pérez, M A Coca; Cremonesi, M

    2012-01-21

    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.medphys.it.

  15. Cosmogenic radionuclides

    CERN Document Server

    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

  16. Radionuclide cisternography

    International Nuclear Information System (INIS)

    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.)

  17. Radionuclide carriers

    International Nuclear Information System (INIS)

    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)

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

    Science.gov (United States)

    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

  19. Conditions and processes affecting radionuclide transport

    Science.gov (United States)

    Simmons, Ardyth M.; Neymark, Leonid A.

    2012-01-01

    Characteristics of host rocks, secondary minerals, and fluids would affect the transport of radionuclides from a previously proposed repository at Yucca Mountain, Nevada. Minerals in the Yucca Mountain tuffs that are important for retarding radionuclides include clinoptilolite and mordenite (zeolites), clay minerals, and iron and manganese oxides and hydroxides. Water compositions along flow paths beneath Yucca Mountain are controlled by dissolution reactions, silica and calcite precipitation, and ion-exchange reactions. Radionuclide concentrations along flow paths from a repository could be limited by (1) low waste-form dissolution rates, (2) low radionuclide solubility, and (3) radionuclide sorption onto geological media.

  20. Radionuclide migration in water reservoirs

    International Nuclear Information System (INIS)

    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

  1. EBS Radionuclide Transport Abstraction

    Energy Technology Data Exchange (ETDEWEB)

    R. Schreiner

    2001-06-27

    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&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

  2. Anthropogenic radionuclides in the environment

    Energy Technology Data Exchange (ETDEWEB)

    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

    CERN Document Server

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

    OpenAIRE

    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 ...

  5. Radionuclides in terrestrial ecosystems

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

    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

  7. Radionuclide Therapy. Chapter 19

    International Nuclear Information System (INIS)

    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

  8. Speciation of radionuclides in the environment

    International Nuclear Information System (INIS)

    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)

  9. Quantitative radionuclide angiocardiography

    Energy Technology Data Exchange (ETDEWEB)

    Scholz, P.M.; Rerych, S.K.; Moran, J.F.; Newman, G.E.; Douglas, J.M.; Sabiston, D.C. Jr.; Jones, R.H.

    1980-01-01

    This study introduces a new method for calculating actual left ventricular volumes and cardiac output from data recorded during a single transit of a radionuclide bolus through the heart, and describes in detail current radionuclide angiocardiography methodology. A group of 64 healthy adults with a wide age range were studied to define the normal range of hemodynamic parameters determined by the technique. Radionuclide angiocardiograms were performed in patients undergoing cardiac catherization to validate the measurements. In 33 patients studied by both techniques on the same day, a close correlation was documented for measurement of ejection fraction and end-diastolic volume. To validate the method of volumetric cardiac output calcuation, 33 simultaneous radionuclide and indocyanine green dye determinations of cardiac output were performed in 18 normal young adults. These independent comparisons of radionuclide measurements with two separate methods document that initial transit radionuclide angiocardiography accurately assesses left ventricular function.

  10. Status report on radionuclide transfer

    International Nuclear Information System (INIS)

    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)

  11. Radionuclide retention in geologic media

    International Nuclear Information System (INIS)

    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)

  12. Significant Radionuclides Determination

    International Nuclear Information System (INIS)

    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''

  13. Natural radionuclides in mineral fertilizers and farmland

    OpenAIRE

    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...

  14. Livermore Accelerator Source for Radionuclide Science (LASRS)

    Energy Technology Data Exchange (ETDEWEB)

    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.

  15. Process for encapsulating radionuclides

    International Nuclear Information System (INIS)

    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

  16. Radionuclide imaging of musculoskeletal infection

    Energy Technology Data Exchange (ETDEWEB)

    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)

  17. Radionuclide synovectomy - essentials for rheumatologists.

    Science.gov (United States)

    Chojnowski, Marek M; Felis-Giemza, Anna; Kobylecka, Małgorzata

    2016-01-01

    Radionuclide synovectomy is a minimally invasive method of treating persistent joint inflammation. It involves intra-articular injection of radioactive colloids which induce necrosis and fibrosis of hypertrophic synovial membrane. The most common indication for radiosynovectomy is rheumatoid arthritis, although patients with seronegative spondyloarthropathies, unclassified arthritis, haemophilic arthropathy and other less common arthropathies can also benefit from this method. Radiosynovectomy is safe, well tolerated and efficacious. About 70-80% of patients respond well to the therapy. However, the therapeutic effects are considerably worse in patients with co-existent osteoarthritis and advanced joint degeneration. Despite its advantages, radionuclide synovectomy is not performed as often as it could be, so greater knowledge and understanding of this method are needed. The authors present the most important facts about radiosynovectomy that may help rheumatologists in their daily clinical practice.

  18. Radionuclides in US coals

    Energy Technology Data Exchange (ETDEWEB)

    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.

  19. Radionuclide fixation mechanisms in rocks

    International Nuclear Information System (INIS)

    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. Radionuclide therapy revisited

    Energy Technology Data Exchange (ETDEWEB)

    Hoefnagel, C.A. (Nederlands Kanker Inst., Amsterdam (Netherlands). Dept. of Nuclear Medicine)

    1991-06-01

    Apart from its use in endocrinology and rheumatology, therapeutic nuclear medicine is developing rapidly as an additional treatment modality in oncology. Many different specific tumour-seeking radiopharmaceuticals are being applied both for diagnostic scintigraphy and treatment, using multiple routes and mechanisms to target radionuclides at tumours. After a brief introduction of some basic principles of radionuclide targeting, the therapeutic radiopharmaceuticals available are reviewed according to the accumulation site in relation to the cell nucleus; the results of their current clinical use for therapy are also reviewed. The response observed to a number of these applications, the non-invasiveness of the procedure and the relative lack of toxicity and late effects in comparison with chemotherapy and external beam radiotherapy make radionuclide therapy an attractive and realistic alternative in the management of malignant disease, as well as in the treatment of a few benign disorders. (orig.).

  1. Radionuclides in house dust

    CERN Document Server

    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

    International Nuclear Information System (INIS)

    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. Targeted Radionuclide Therapy

    Directory of Open Access Journals (Sweden)

    David Cheng

    2011-10-01

    Full Text Available Targeted radiotherapy is an evolving and promising modality of cancer treatment. The killing of cancer cells is achieved with the use of biological vectors and appropriate radionuclides. Among the many advantages of this approach are its selectiveness in delivering the radiation to the target, relatively less severe and infrequent side effects, and the possibility of assessing the uptake by the tumor prior to the therapy. Several different radiopharmaceuticals are currently being used by various administration routes and targeting mechanisms. This article aims to briefly review the current status of targeted radiotherapy as well as to outline the advantages and disadvantages of radionuclides used for this purpose.

  4. Orbital radionuclide examinations

    International Nuclear Information System (INIS)

    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.)

  5. Natural Radionuclide Activity Concentrations In Spas Of Argentina

    Science.gov (United States)

    Gnoni, G.; Czerniczyniec, M.; Canoba, A.; Palacios, M.

    2008-08-01

    Geothermal waters have been used on a large scale for bathing, drinking and medical purposes. These waters can contain natural radionuclides that may increase the exposure to people. In this work the most important natural radionuclide activity concentrations in different thermal spas of Argentina were measured to characterize waters and to evaluate the exposure of workers and members of the public.

  6. 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

    Energy Technology Data Exchange (ETDEWEB)

    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

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

    International Nuclear Information System (INIS)

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  9. Radionuclide transfer from contaminated field to crops

    International Nuclear Information System (INIS)

    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

    International Nuclear Information System (INIS)

    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

    Energy Technology Data Exchange (ETDEWEB)

    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. EBS Radionuclide Transport Abstraction

    International Nuclear Information System (INIS)

    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

  13. EBS Radionuclide Transport Abstraction

    Energy Technology Data Exchange (ETDEWEB)

    J. Prouty

    2006-07-14

    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. Radionuclides in food

    International Nuclear Information System (INIS)

    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

  15. Radionuclide diagnosis of nephrolithiasis

    International Nuclear Information System (INIS)

    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

  16. Radionuclide fate and effects

    International Nuclear Information System (INIS)

    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

  17. Radionuclides in terrestrial ecosystems

    International Nuclear Information System (INIS)

    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)

  18. Radionuclide diagnosis of allograft rejection

    Energy Technology Data Exchange (ETDEWEB)

    George, E.A.

    1982-10-01

    Interaction with one or more anatomical and physiopathological characteristics of the rejecting renal allograft is suggested by those radioagents utilized specifically for the diagnosis of allograft rejection. Rejection, the most common cause of declining allograft function, is frequently mimicked clinically or masked by other immediate or long term post transplant complications. Understanding of the anatomical pathological features and kinetics of rejection and their modification by immunosuppressive maintenance and therapy are important for the proper clinical utilization of these radioagents. Furthermore, in selecting these radionuclides, one has to consider the comparative availability, preparatory and procedural simplicity, acquisition and display techniques and the possibility of timely report. The clinical utilities of radiofibrinogen, /sup 99m/Tc sulfur colloid and /sup 67/Ga in the diagnosis of allograft rejection have been evaluated to a variable extent in the past. The potential usefulness of the recently developed preparations of /sup 111/In labeled autologous leukocytes and platelets are presently under investigation.

  19. EBS Radionuclide Transport Abstraction

    Energy Technology Data Exchange (ETDEWEB)

    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

  20. Sherlock Holmes for radionuclides

    International Nuclear Information System (INIS)

    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)

  1. Osteopetrosis: radiological & radionuclide imaging.

    Science.gov (United States)

    Sit, Cherry; Agrawal, Kanhaiyalal; Fogelman, Ignac; Gnanasegaran, Gopinath

    2015-01-01

    Osteopetrosis is a rare inherited bone disease where bones harden and become abnormally dense. While the diagnosis is clinical, it also greatly relies on appearance of the skeleton radiographically. X-ray, radionuclide bone scintigraphy and magnetic resonance imaging have been reported to identify characteristics of osteopetrosis. We present an interesting case of a 59-year-old man with a history of bilateral hip fractures. He underwent (99m)Tc-methylene diphosphonate whole body scan supplemented with single-photon emission computed tomography/computed tomography of spine, which showed increased uptake in the humeri, tibiae and femora, which were in keeping with osteopetrosis.

  2. Critical comparison of radiometric and mass spectrometric methods for the determination of radionuclides in environmental, biological and nuclear waste samples

    DEFF Research Database (Denmark)

    Hou, Xiaolin; Roos, Per

    2008-01-01

    spectrometry, and glow discharge mass spectrometry are reviewed for the determination of radionuclides. These methods are critically compared for the determination of long-lived radionuclides important for radiation protection, decommissioning of nuclear facilities, repository of nuclear waste, tracer...

  3. Understanding Radionuclide Interactions with Layered Materials

    Science.gov (United States)

    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.

  4. Transport and accumulation of radionuclides in soil

    International Nuclear Information System (INIS)

    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)

  5. Mechanisms controlling radionuclide mobility in forest soils

    International Nuclear Information System (INIS)

    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)

  6. Improving cancer treatment with cyclotron produced radionuclides

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

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

    Science.gov (United States)

    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

  9. Radionuclides in nephrology

    Energy Technology Data Exchange (ETDEWEB)

    Lausanne, A.B.D.

    1987-01-01

    In 47 expert contributions, this volume provides a summary of the latest research on radionuclides in nephro-urology together with current and new clinical applications especially in renovascular hypertension, kidney transplantation, and metabolic and urological diseases. In addition, attention is given to aspects of basic renal physiology and function and possible applications of nuclear magnetic resonance and spectroscopy in nephro-urology. New testing procedures which promise to improve diagnosis, and new radiopharmaceuticals are described. The reports are divided into eight sections, the first of which features studies on the renin-angiotensin system, cisplatin, atrial natriuretic factor and determining plasma oxalate. Four papers describe a number of new radiopharmaceuticals which have the potential to replace hippuran. In the third section, radionuclide methods for the measurement of renal function parameters are discussed. The book then focuses on the potential role of captopril in the improved diagnosis of renovascular hypertension. Applications of nuclear magnetic resonance and spectroscopy are demonstrated in the diagnosis of acute pyelonephritis, kidney assessment after lithotripsy, kidney evaluation prior to transplantation, and in monitoring renal ischemia during hypotension.

  10. Scientific Analysis Cover Sheet for Radionuclide Screening

    Energy Technology Data Exchange (ETDEWEB)

    G. Ragan

    2002-08-09

    The waste forms under consideration for disposal in the proposed repository at Yucca Mountain contain scores of radionuclides (Attachments V and VI). It would be impractical and highly inefficient to model all of these radionuclides in a total system performance assessment (TSPA). Thus, the purpose of this radionuclide screening analysis is to remove from further consideration (screen out) radionuclides that are unlikely to significantly contribute to radiation dose to the public from the proposed nuclear waste repository at Yucca Mountain. The remaining nuclides (those screened in) are recommended for consideration in TSPA modeling for license application. This analysis also covers radionuclides that are not screened in based on dose, but need to be included in TSPA modeling for other reasons. For example, U.S. Environmental Protection Agency (EPA) and U.S. Nuclear Regulatory Commission (NRC) regulations require consideration of the combined activity of Ra-226 and Ra-228 in groundwater (40 CFR 197.30, 10 CFR 63.331). Also, Cm-245, Pu-241, and U-235 decay indirectly to potentially important radionuclides, and are not identified by the screening analysis as important. The radionuclide screening analysis separately considers two different postclosure time periods: the 10,000-y regulatory period for the proposed repository at Yucca Mountain and the period after 10,000 y up to 1 million y after emplacement. The incremental effect of extending the screening for the regulatory period to 20,000 y is also addressed. Four release scenarios are considered: (1) the nominal scenario, which entails long-term degradation of disposal containers and waste forms, (2) a human-intrusion scenario, (3) an intrusive igneous event, and (4) an eruptive igneous event. Because the first three scenarios require groundwater transport, they are called groundwater scenarios below. The screening analysis considers the following waste forms: spent boiling water reactor (BWR) fuel, spent

  11. Illicit Trafficking of Natural Radionuclides

    Science.gov (United States)

    Friedrich, Steinhäusler; Lyudmila, Zaitseva

    2008-08-01

    Natural radionuclides have been subject to trafficking worldwide, involving natural uranium ore (U 238), processed uranium (yellow cake), low enriched uranium (20% U 235), radium (Ra 226), polonium (Po 210), and natural thorium ore (Th 232). An important prerequisite to successful illicit trafficking activities is access to a suitable logistical infrastructure enabling an undercover shipment of radioactive materials and, in case of trafficking natural uranium or thorium ore, capable of transporting large volumes of material. Covert en route diversion of an authorised uranium transport, together with covert diversion of uranium concentrate from an operating or closed uranium mines or mills, are subject of case studies. Such cases, involving Israel, Iran, Pakistan and Libya, have been analyzed in terms of international actors involved and methods deployed. Using international incident data contained in the Database on Nuclear Smuggling, Theft and Orphan Radiation Sources (DSTO) and international experience gained from the fight against drug trafficking, a generic Trafficking Pathway Model (TPM) is developed for trafficking of natural radionuclides. The TPM covers the complete trafficking cycle, ranging from material diversion, covert material transport, material concealment, and all associated operational procedures. The model subdivides the trafficking cycle into five phases: (1) Material diversion by insider(s) or initiation by outsider(s); (2) Covert transport; (3) Material brokerage; (4) Material sale; (5) Material delivery. An Action Plan is recommended, addressing the strengthening of the national infrastructure for material protection and accounting, development of higher standards of good governance, and needs for improving the control system deployed by customs, border guards and security forces.

  12. Illicit Trafficking of Natural Radionuclides

    International Nuclear Information System (INIS)

    Natural radionuclides have been subject to trafficking worldwide, involving natural uranium ore (U 238), processed uranium (yellow cake), low enriched uranium (20% U 235), radium (Ra 226), polonium (Po 210), and natural thorium ore (Th 232). An important prerequisite to successful illicit trafficking activities is access to a suitable logistical infrastructure enabling an undercover shipment of radioactive materials and, in case of trafficking natural uranium or thorium ore, capable of transporting large volumes of material. Covert en route diversion of an authorised uranium transport, together with covert diversion of uranium concentrate from an operating or closed uranium mines or mills, are subject of case studies. Such cases, involving Israel, Iran, Pakistan and Libya, have been analyzed in terms of international actors involved and methods deployed. Using international incident data contained in the Database on Nuclear Smuggling, Theft and Orphan Radiation Sources (DSTO) and international experience gained from the fight against drug trafficking, a generic Trafficking Pathway Model (TPM) is developed for trafficking of natural radionuclides. The TPM covers the complete trafficking cycle, ranging from material diversion, covert material transport, material concealment, and all associated operational procedures. The model subdivides the trafficking cycle into five phases: (1) Material diversion by insider(s) or initiation by outsider(s); (2) Covert transport; (3) Material brokerage; (4) Material sale; (5) Material delivery. An Action Plan is recommended, addressing the strengthening of the national infrastructure for material protection and accounting, development of higher standards of good governance, and needs for improving the control system deployed by customs, border guards and security forces

  13. Radionuclide - Soil Organic Matter Interactions

    DEFF Research Database (Denmark)

    Carlsen, Lars

    1985-01-01

    Interactions between soil organic matter, i.e. humic and fulvic acids, and radionuclides of primary interest to shallow land burial of low activity solid waste have been reviewed and to some extent studied experimentally. The radionuclides considered in the present study comprise cesium, strontium...

  14. Radionuclide trap studies using porous carbon

    International Nuclear Information System (INIS)

    Towards import substitute, an attempt has been made to synthesise porous carbon by acidic sucrose solution route for use as trap material for cesium isotopes. The radionuclide trap experiments have been carried out to study the uptake of fission product cesium (137Cs) using reticulated vitreous carbon (RVC) and home made porous carbon (HMPC) in static sodium system. The trapping efficiency and distribution coefficient have been measured and compared. (author)

  15. Radioactivity, radionuclides, radiation

    CERN Document Server

    Magill, Joseph

    2005-01-01

    RADIOACTIVITY – RADIONUCLIDES – RADIATION is suitable for a general audience interested in topical environmental and human health radiological issues such as radiation exposure in aircraft, food sterilisation, nuclear medicine, radon gas, radiation dispersion devices ("dirty bombs")… It leads the interested reader through the three Rs of nuclear science, to the forefront of research and developments in the field. The book is also suitable for students and professionals in the related disciplines of nuclear and radiochemistry, health physics, environmental sciences, nuclear and astrophysics. Recent developments in the areas of exotic decay modes (bound beta decay of ‘bare’ or fully ionized nuclei), laser transmutation, nuclear forensics, radiation hormesis and the LNT hypothesis are covered. Atomic mass data for over 3000 nuclides from the most recent (2003) evaluation are included.

  16. Transfer of radionuclides to animal products following ingestion or inhalation

    International Nuclear Information System (INIS)

    Contamination of animal products forms an important pathway in the transfer of radionuclides from source to man. Simulation of radionuclide transfer via animal products requires an understanding of the processes and mechanisms involved in absorption, distribution, turnover and excretion of radionuclides and related elements in animals as well as knowledge of animal grazing habits and husbandry. This paper provides a summary of the metabolism of important radionuclides in typical domestic animals and of the mathematical approaches that have been used to simulate transfer from diet to animal product. The equilibrium transfer factor approach has been used widely but suffers a number of disadvantages when releases or intakes are variable with time or when intakes are short relative to the lifetime of the animal of interest. Dynamic models, especially those of the compartmental type, have been developed and used widely. Both approaches have benefited from experiences obtained after the Chernobyl accident but a number of uncertainties still exist. Whereas there is now extensive knowledge on the behaviour of radiocaesium in both domestic and wild animals, knowledge of the behaviour of other potentially important radionuclides remains limited. Further experimental and metabolic studies will be required to reduce uncertainties associated with the transfer of radionuclides other than radiocaesium and thereby produce a sound basis for radiological assessments. (author)

  17. Tracing Noble Gas Radionuclides in the Environment

    CERN Document Server

    Collon, P; Lu, Z T

    2004-01-01

    Trace analysis of radionuclides is an essential and versatile tool in modern science and technology. Due to their ideal geophysical and geochemical properties, long-lived noble gas radionuclides, in particular, 39Ar (t1/2 = 269 yr), 81Kr (t1/2 = 2.3x10^5 yr) and 85Kr (t1/2 = 10.8 yr), have long been recognized to have a wide range of important applications in Earth sciences. In recent years, significant progress has been made in the development of practical analytical methods, and has led to applications of these isotopes in the hydrosphere (tracing the flow of groundwater and ocean water). In this article, we introduce the applications of these isotopes and review three leading analytical methods: Low-Level Counting (LLC), Accelerator Mass Spectrometry (AMS) and Atom Trap Trace Analysis (ATTA).

  18. Radionuclide synovectomy – essentials for rheumatologists

    Science.gov (United States)

    Felis-Giemza, Anna; Kobylecka, Małgorzata

    2016-01-01

    Radionuclide synovectomy is a minimally invasive method of treating persistent joint inflammation. It involves intra-articular injection of radioactive colloids which induce necrosis and fibrosis of hypertrophic synovial membrane. The most common indication for radiosynovectomy is rheumatoid arthritis, although patients with seronegative spondyloarthropathies, unclassified arthritis, haemophilic arthropathy and other less common arthropathies can also benefit from this method. Radiosynovectomy is safe, well tolerated and efficacious. About 70–80% of patients respond well to the therapy. However, the therapeutic effects are considerably worse in patients with co-existent osteoarthritis and advanced joint degeneration. Despite its advantages, radionuclide synovectomy is not performed as often as it could be, so greater knowledge and understanding of this method are needed. The authors present the most important facts about radiosynovectomy that may help rheumatologists in their daily clinical practice. PMID:27504020

  19. Geotrap: radionuclide migration in geologic, heterogeneous media

    International Nuclear Information System (INIS)

    Most countries producing nuclear energy are considering, or actively pursuing, a deep geologic repository for radioactive waste. As part of the assessment of the performance or safety of such a repository, radionuclide transport through the heterogeneous, geologic environment must be modelled. In most cases, an important migration mechanism is transport in groundwater and developing an understanding and modelling capability for how radionuclides might migrate away from the repository through the surrounding geosphere is an integral part of making the safety case for a repository. This understanding has been significantly improved through the NEA GEOTRAP Project, the results of which have been documented in a final synthesis report summarizing the outcomes of the five GEOTRAP workshops held between 1996 and 2001

  20. Gas: A Neglected Phase in Remediation of Metals and Radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Denham, Miles E.; Looney, Brian B

    2005-09-28

    The gas phase is generally ignored in remediation of metals and radionuclides because it is assumed that there is no efficient way to exploit it. In the literal sense, all remediations involve the gas phase because this phase is linked to the liquid and solid phases by vapor pressure and thermodynamic relationships. Remediation methods that specifically use the gas phase as a central feature have primarily targeted volatile organic contaminants, not metals and radionuclides. Unlike many organic contaminants, the vapor pressure and Henry's Law constants of metals and radionuclides are not generally conducive to direct air stripping of dissolved contaminants. Nevertheless, the gas phase can play an important role in remediation of inorganic contaminants and provide opportunities for efficient, cost effective remediation. The objective here is to explore ways in which manipulation of the gas phase can be used to facilitate remediation of metals and radionuclides.

  1. Tumor therapy with radionuclides; assessment of progress and problems

    International Nuclear Information System (INIS)

    Radionuclide therapy is a promising modality for treatment of tumors of hematopoietic origin while the success for treatment of solid tumors so far has been limited. The authors consider radionuclide therapy mainly as a method to eradicate disseminated tumor cells and small metastases while bulky tumors and large metastases have to be treated surgically or by external radiation therapy. The promising therapeutic results for hematological tumors give hope that radionuclide therapy will have a breakthrough also for treatment of disseminated cells from solid tumors. New knowledge is continuously emerging related to this since new molecular target structures are being characterized and the knowledge on pharmacokinetics and cellular processing of different types of targeting agents increases. There is also improved understanding of the factors of importance for the choice of appropriate radionuclides with respect to their decay properties and the therapeutic applications. Furthermore, new methods to modify the uptake of radionuclides in tumor cells and normal tissues are emerging. However, we still need improvements regarding dosimetry and treatment planning as well as an increased knowledge about the tolerance doses for normal tissues and the radiobiological effects on tumor cells. This is especially important in targeted radionuclide therapy where the dose rates often are low

  2. Radionuclide Retention in Concrete Wasteforms

    Energy Technology Data Exchange (ETDEWEB)

    Bovaird, Chase C.; Jansik, Danielle P.; Wellman, Dawn M.; Wood, Marcus I.

    2011-09-30

    Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how wasteform performance is affected by the full range of environmental conditions within the disposal facility; the process of wasteform aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of wasteform aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the wasteforms come in contact with groundwater. The information present in the report provides data that (1) measures the effect of concrete wasteform properties likely to influence radionuclide migration; and (2) quantifies the rate of carbonation of concrete materials in a simulated vadose zone repository.

  3. Radionuclide diffusion in soils. I

    International Nuclear Information System (INIS)

    The factors are discussed affecting the rate of migration of radionuclides in the soil (properties of the radionuclide - the sign and magnitude of ion charge, soil properties - moisture, density, presence of salts and organic substances, composition of sorption complex and soil solution, climatic conditions -temperature). Fick's 2nd law cannot be used for the mathematical description of vertical migration of radionuclides in the soil and equations are therefore suggested for describing the movement of substances through an absorbing porous medium and for the calculation of the diffusion coefficient. In order to specify the mathematical description of migration it is necessary to obtain a great numbert of experimental data and to use multiparameter regression analysis for identifying the effect of the different properties of the soil on the diffusion of radionuclides. (J.C.)

  4. Drift-Scale Radionuclide Transport

    Energy Technology Data Exchange (ETDEWEB)

    J. Houseworth

    2004-09-22

    The purpose of this model report is to document the drift scale radionuclide transport model, taking into account the effects of emplacement drifts on flow and transport in the vicinity of the drift, which are not captured in the mountain-scale unsaturated zone (UZ) flow and transport models ''UZ Flow Models and Submodels'' (BSC 2004 [DIRS 169861]), ''Radionuclide Transport Models Under Ambient Conditions'' (BSC 2004 [DIRS 164500]), and ''Particle Tracking Model and Abstraction of Transport Process'' (BSC 2004 [DIRS 170041]). The drift scale radionuclide transport model is intended to be used as an alternative model for comparison with the engineered barrier system (EBS) radionuclide transport model ''EBS Radionuclide Transport Abstraction'' (BSC 2004 [DIRS 169868]). For that purpose, two alternative models have been developed for drift-scale radionuclide transport. One of the alternative models is a dual continuum flow and transport model called the drift shadow model. The effects of variations in the flow field and fracture-matrix interaction in the vicinity of a waste emplacement drift are investigated through sensitivity studies using the drift shadow model (Houseworth et al. 2003 [DIRS 164394]). In this model, the flow is significantly perturbed (reduced) beneath the waste emplacement drifts. However, comparisons of transport in this perturbed flow field with transport in an unperturbed flow field show similar results if the transport is initiated in the rock matrix. This has led to a second alternative model, called the fracture-matrix partitioning model, that focuses on the partitioning of radionuclide transport between the fractures and matrix upon exiting the waste emplacement drift. The fracture-matrix partitioning model computes the partitioning, between fractures and matrix, of diffusive radionuclide transport from the invert (for drifts without seepage) into the rock water

  5. Statistical analysis of fallout radionuclides transfer to paddy-field rice

    International Nuclear Information System (INIS)

    Radionuclides released from nuclear facilities to atmosphere are transported through various pathways in biosphere and cause human exposure. Among these radionuclides transfer pathways, an ingestion of crops containing radionuclides is one of the dominant pathway for human exposure. For the safety assessment of nuclear facilities, it is important to understand the behavior of radionuclides in agricultural environment and to describe them in a mathematical model. In this paper, a statistical model is proposed for estimating the concentration of fallout radionuclides in paddy-field rice, the staple food for Japanese people. For describing behavior of fallout radionuclides in a paddy-field, a dynamic model and a statistical model have been proposed respectively. The model used in this study has been developed assuming that the amount of radionuclides transfer to brown rice (hulled rice) or polished rice through direct deposition of airborne radionuclides (the direct deposition pathway) and root uptake from a paddy soil (the root uptake pathway) are proportional to the deposition flux of radionuclides and concentration of radionuclides in paddy soil respectively. That is, the model has two independent variables; the deposition flux of radionuclides and the concentration of radionuclides in the paddy soil, and has single dependent variable; the concentration of radionuclides in brown rice or polished rice. The regression analysis is applied by using environmental monitoring data. Then the distribution of radionuclides between rice-bran (skin part of rice crop) and polished rice (core part) through both the direct deposition pathway and the root uptake pathway are evaluated by the model. (author)

  6. Radionuclide salivary gland imaging

    Energy Technology Data Exchange (ETDEWEB)

    Mishkin, F.S.

    1981-10-01

    Salivary gland imaging with 99mTc as pertechnetate provides functional information concerning trapping and excretion of the parotid and submandibular glands. Anatomic information gained often adds little to clinical evaluation. On the other hand, functional information may detect subclinical involvement, which correlates well with biopsy of the minor labial salivary glands. Salivary gland abnormalities in systemic disease such as sarcoidosis, rheumatoid arthritis, lupus erythematosus, and other collagenvascular disorders may be detected before they result in the clinical manifestaions of Sjoegren's syndrome. Such glands, after initially demonstrating increased trapping in the acute phase, tend to have decreased trapping and failure to discharge pertechnetate in response to an appropriate physiologic stimulus. Increased uptake of gallium-67 citrate often accompanies these findings. Inflammatory parotitis can be suspected when increased perfusion is evident on radionuclide angiography with any agent. The ability of the salivary gland image to detect and categorize mass lesions, which result in focal areas of diminished activity such as tumors, cysts, and most other masses, is disappointing, while its ability to detect and categorize Warthin's tumor, which concentrates pertechnetate, is much more valuable, although not specific.

  7. Radionuclide brain scanning

    International Nuclear Information System (INIS)

    At one stage of medical imaging development, radionuclide brain scanning was the only technique available for imaging of the brain. Advent of CT and MRI pushed it to the background. It regained some of the grounds lost to ''allied advances'' with the introduction of brain perfusion radiopharmaceuticals. Positron emission tomography is a promising functional imaging modality that at present will remain as a research tool in special centres in developed countries. However, clinically useful developments will gradually percolate from PET to SPECT. The non-nuclear imaging methods are totally instrument dependent; they are somewhat like escalators, which can go that far and no further. Nuclear imaging has an unlimited scope for advance because of the new developments in radiopharmaceuticals. As the introduction of a radiopharmaceutical is less costly than buying new instruments, the recent advances in nuclear imaging are gradually perfusing through the developing countries also. Therefore, it is essential to follow very closely PET developments because what is research today might become routine tomorrow

  8. Radionuclide generators for biomedical applications

    International Nuclear Information System (INIS)

    This document reviews the chemical literature of those radionuclide generators that have gained or appear to possess utility in medical imaging. The text represents a conscientious effort to peruse the scientific literature through 1980. The intent of this work is to provide a reference point for the investigator who is interested in the development of a particular generator system and the refinements which have been reported. Moreover, the incorporation of the particular daughter radionuclide into a suitable radiodiagnostic agent is presented

  9. Radionuclide imaging of musculoskeletal infection

    Directory of Open Access Journals (Sweden)

    Christopher J. Palestro

    2007-09-01

    Full Text Available 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.Estudos através de imagens com o uso de radionuclídeos são rotineiramente usadas para avaliar pacientes suspeitos de terem infecção músculo-esquelética. A imagem óssea em tridimensional é facilmente avaliável, relativamente de baixo custo, e muito precisa na localização de alterações ósseas. Imagem com leucócito marcado poderia ser usada nos casos de "osteomielite com complicações" tais como infecção prostética articular. Esse teste também é útil na não suspeita clinica de osteomielite associada ao pé diabético tanto quanto nas junções neuropáticas. É sempre necessário, por outro lado, realizar imagem complementar da medula óssea para aumentar a precisão da imagem com leucócito marcado. Em contraste com outras regiões no esqueleto, imagem com leucócito marcado não é útil para diagnosticar osteomielite da coluna vertebral. Até agora, o gálio é o radionuclídeo preferido para

  10. Solubility limits on radionuclide dissolution

    Energy Technology Data Exchange (ETDEWEB)

    Kerrisk, J.F.

    1984-12-31

    This paper examines the effects of solubility in limiting dissolution rates of a number of important radionuclides from spent fuel and high-level waste. Two simple dissolution models were used for calculations that would be characteristics of a Yucca Mountain repository. A saturation-limited dissolution model, in which the water flowing through the repository is assumed to be saturated with each waste element, is very conservative in that it overestimates dissolution rates. A diffusion-limited dissolution model, in which element-dissolution rates are limited by diffusion of waste elements into water flowing past the waste, is more realistic, but it is subject to some uncertainty at this time. Dissolution rates of some elements (Pu, Am, Sn, Th, Zr, Sm) are always limited by solubility. Dissolution rates of other elements (Cs, Tc, Np, Sr, C, I) are never solubility limited; their release would be limited by dissolution of the bulk waste form. Still other elements (U, Cm, Ni, Ra) show solubility-limited dissolution under some conditions. 9 references, 3 tables.

  11. Radionuclide evaluation of lung trauma.

    Science.gov (United States)

    Lull, R J; Tatum, J L; Sugerman, H J; Hartshorne, M F; Boll, D A; Kaplan, K A

    1983-07-01

    Nuclear medicine imaging procedures can play a significant role in evaluating the pulmonary complications that are seen in trauma patients. A quantitative method for measuring increased pulmonary capillary permeability that uses Tc-99m HSA allows early diagnosis of acute respiratory distress syndrome (ARDS) and accurately differentiates this condition from pneumonia or cardiogenic pulmonary edema. This technique may be of great value in following the response to therapy. The use of 133Xe to diagnose inhalation injury remains an important diagnostic tool, particularly at hospitals with specialized burn units. Regional decreases in ventilation-perfusion images reliably localize aspirated foreign bodies. Radionuclide techniques that are used to demonstrate gastropulmonary aspiration remain controversial and require further clinical evaluation. Pulmonary perfusion imaging, although nonspecific, may provide the earliest clue for correct diagnosis of fat embolism, air embolism, contusion, or laceration. Furthermore, the possibility of perfusion abnormality due to these uncommon conditions must be remembered whenever trauma patients are evaluated for pulmonary thromboembolism with scintigraphy. Occasionally, liver or spleen scintigraphy may be the most appropriate procedure when penetrating chest trauma also involves these subdiaphragmatic organs. PMID:6226097

  12. Radionuclide evaluation of lung trauma

    Energy Technology Data Exchange (ETDEWEB)

    Lull, R.J.; Tatum, J.L.; Sugerman, H.J.; Hartshorne, M.F.; Boll, D.A.; Kaplan, K.A.

    1983-07-01

    Nuclear medicine imaging procedures can play a significant role in evaluating the pulmonary complications that are seen in trauma patients. A quantitative method for measuring increased pulmonary capillary permeability that uses Tc-99m HSA allows early diagnosis of acute respiratory distress syndrome (ARDS) and accurately differentiates this condition from pneumonia or cardiogenic pulmonary edema. This technique may be of great value in following the response to therapy. The use of 133Xe to diagnose inhalation injury remains an important diagnostic tool, particularly at hospitals with specialized burn units. Regional decreases in ventilation-perfusion images reliably localize aspirated foreign bodies. Radionuclide techniques that are used to demonstrate gastropulmonary aspiration remain controversial and require further clinical evaluation. Pulmonary perfusion imaging, although nonspecific, may provide the earliest clue for correct diagnosis of fat embolism, air embolism, contusion, or laceration. Furthermore, the possibility of perfusion abnormality due to these uncommon conditions must be remembered whenever trauma patients are evaluated for pulmonary thromboembolism with scintigraphy. Occasionally, liver or spleen scintigraphy may be the most appropriate procedure when penetrating chest trauma also involves these subdiaphragmatic organs.

  13. Radionuclide evaluation of lung trauma

    International Nuclear Information System (INIS)

    Nuclear medicine imaging procedures can play a significant role in evaluating the pulmonary complications that are seen in trauma patients. A quantitative method for measuring increased pulmonary capillary permeability that uses Tc-99m HSA allows early diagnosis of acute respiratory distress syndrome (ARDS) and accurately differentiates this condition from pneumonia or cardiogenic pulmonary edema. This technique may be of great value in following the response to therapy. The use of 133Xe to diagnose inhalation injury remains an important diagnostic tool, particularly at hospitals with specialized burn units. Regional decreases in ventilation-perfusion images reliably localize aspirated foreign bodies. Radionuclide techniques that are used to demonstrate gastropulmonary aspiration remain controversial and require further clinical evaluation. Pulmonary perfusion imaging, although nonspecific, may provide the earliest clue for correct diagnosis of fat embolism, air embolism, contusion, or laceration. Furthermore, the possibility of perfusion abnormality due to these uncommon conditions must be remembered whenever trauma patients are evaluated for pulmonary thromboembolism with scintigraphy. Occasionally, liver or spleen scintigraphy may be the most appropriate procedure when penetrating chest trauma also involves these subdiaphragmatic organs

  14. The development and use of radionuclide generators in nuclear medicine -- recent advances and future perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Knapp, F.F. Jr.

    1998-03-01

    Although the trend in radionuclide generator research has declined, radionuclide generator systems continue to play an important role in nuclear medicine. Technetium-99m obtained from the molybdenum-99/technetium-99m generator system is used in over 80% of all diagnostic clinical studies and there is increasing interest and use of therapeutic radioisotopes obtained from generator systems. This paper focuses on a discussion of the major current areas of radionuclide generator research, and the expected areas of future research and applications.

  15. Diffusion of sorbing and non-sorbing radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Triay, I.R.; Birdsell, K.H.; Mitchell, A.J.; Ott, M.A.

    1993-02-01

    Diffusion is considered one of the most important retardation mechanisms in fractured media. The diffusion experiments conducted involved solid tuff and groundwater from Yucca Mountain. The uptake of radionuclides by the tuff was studied utilizing containers made of tuff in the form of beakers. The solution containing the radionuclides of interest was placed in the tuff beaker cavity and the uptake of the radionuclides by the tuff was measured as a function of time. Our results indicate that the diffusion coefficient for nonsorbing radionuclides into saturated Yucca Mountain tuff is on the order of 10{sup {minus}6} cm{sup 2}/s. Large anions, such as pertechnetate are excluded from tuff pores and their diffusion coefficients are on the order of 10{sup {minus}7}cm{sup 2}/s. Comparison of the predictions for the uptake of sorbing radionuclides by the tuff with the actual data obtained indicates that conservative transport calculations will result from predicting diffusion using the batch sorption coefficient for the sorbing radionuclide and the diffusion coefficient obtained for tritiated water.

  16. Dosimetry in radionuclide therapy

    International Nuclear Information System (INIS)

    While it is known that therapeutic effects of radionuclides are due to absorbed radiation dose and to radiosensitivity, individual dosimetry in 'Gy' is practiced rarely in clinical Nuclear Medicine but 'doses' are described in 'mCi' or 'MBq', which is only indirectly related to 'Gy' in the target. To estimate 'Gy', the volume of the target, maximum concentration of the radiopharmaceutical in it and residence time should be assessed individually. These parameters can be obtained usually only with difficulty, involving possibly also quantitative SPET or PET, modern imaging techniques (sonography, CT, MRT), substitution of y- or positron emitting radiotracers for β-emitting radiopharmaceuticals as well as whole-body distribution studies. Residence time can be estimated by obtaining data on biological half-life of a comparable tracer and transfer of these data in the physical characteristics of the therapeutic agent. With all these possibilities for gross dosimetry the establishment of a dose-response-relation should be possible. As distribution of the radiopharmaceutical in lesions is frequently inhomogenous and microdosimetric conditions are difficult to assess in vivo as yet, it could be observed since decades that empirically set, sometimes 'fixed' doses (mCi or MBq) can also be successful in many diseases. Detailed dosimetric studies, however, are work- and cost-intensive. Nevertheless, one should be aware at a time when more sophisticated therapeutic possibilities in Nuclear Medicine arise, that we should try to estimate radiation dose (Gy) in our new methods even as differences in individual radiosensitivity cannot be assessed yet and studies to define individual radiosensitivity in lesions should be encouraged. (author)

  17. Fungi contaminated by radionuclides. Critical review of approaches to modeling

    International Nuclear Information System (INIS)

    Global fallout from nuclear weapon tests in the 1960s revealed the potential of fungi as enhanced accumulators of radioactivity. More recently, data derived from Chernobyl fallout conferred fungi as major accumulators of radionuclides and in addition an important food-chain contributor to the human radiation dose. According to both individual expert judgment elicitation and group discussions conducted during a recent workshop on forest radioecology (Linkov and Schell, 1999), fungi determine to a large extent the fate and transport processes of radionuclides in forests. Forest microflora, particularly fungal mycelia, can retain a significant fraction of the deposited radionuclides in the organic layer. Recent model-model-data intercomparisons organized by the International Atomic Energy Agency (BIOMASS 1999) led to the conclusion that the radionuclide accumulation in fungi is the most difficult to predict. This talk will critically review existing modeling techniques and will proposes an approach for understanding and describing radionuclide fate and transport in forest soils as a part of multimedia modeling aiming at human health and risk assessment. Fungal mycelia determine to a large extent the radionuclide retention in the organic layers. However, the detailed mechanisms involved in radionuclide and heavy metal fixation by fungi are not yet well understood. The results of our analysis show that in spite of this limited knowledge, simple models can be developed to reproduce the measured and predict the future radionuclide concentration in the organic layer compartments and fungal fruit bodies. Our review shows that transfer parameters (transfer factors of concentration ratios) from forest soil to fungal fruit bodies aggregated over a standardized soil depth or the total radionuclide deposition per unit area are highly uncertain. For modeling purposes the relevant kinetic processes are best described by uptake rates or effective half-times. These dynamic

  18. NATURAL AND ARTIFICIAL RADIOACTIVITY IN IMPORTED FISHERY PRODUCTS

    Directory of Open Access Journals (Sweden)

    R. Cavallina

    2013-02-01

    Full Text Available Considering the growing public concern over marine environmental quality, a program of monitoring radionuclids in imported fishery products has been established. The analyses have been performed by gamma spectrometry allowing the rapid detection of many artificial radionuclides such as 137Cs, 134Cs and 40K. The data obtained show Cs radionuclides levels within expected limits. The detection of natural radionuclide K showed different levels in the same fishery product as they came from different sea areas.

  19. NATURAL AND ARTIFICIAL RADIOACTIVITY IN IMPORTED FISHERY PRODUCTS

    OpenAIRE

    M.C. Campagna; A. Nardoni; R. Cavallina

    2010-01-01

    Considering the growing public concern over marine environmental quality, a program of monitoring radionuclids in imported fishery products has been established. The analyses have been performed by gamma spectrometry allowing the rapid detection of many artificial radionuclides such as 137Cs, 134Cs and 40K. The data obtained show Cs radionuclides levels within expected limits. The detection of natural radionuclide K showed different levels in the same fishery product as they came from differe...

  20. Radionuclide Retention in Concrete Wasteforms

    Energy Technology Data Exchange (ETDEWEB)

    Wellman, Dawn M.; Jansik, Danielle P.; Golovich, Elizabeth C.; Cordova, Elsa A.

    2012-09-24

    Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how wasteform performance is affected by the full range of environmental conditions within the disposal facility; the process of wasteform aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of wasteform aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the wasteforms come in contact with groundwater. Data collected throughout the course of this work will be used to quantify the efficacy of concrete wasteforms, similar to those used in the disposal of LLW and MLLW, for the immobilization of key radionuclides (i.e., uranium, technetium, and iodine). Data collected will also be used to quantify the physical and chemical properties of the concrete affecting radionuclide retention.

  1. Comparisons of activity measurements in nuclear medicine with radionuclide calibrators in the Czech Republic

    International Nuclear Information System (INIS)

    Radionuclide calibrators consisting of a well type ionization chamber and an electrometer are used in nuclear medicine for the determination of the activity of radioactive pharmaceuticals administered to patients. In order to maximize the safety of patients, it is important to ensure the long term accuracy of radionuclide calibrators.The paper presents data obtained in annual calibrator accuracy checks carried out in the Czech Republic by the Czech Metrological Institute during the past decade. Changes in radionuclide calibrator models, the range of radionuclides used and the development of measurement accuracies are also described. In addition, the results of a regional international comparison are given. (author)

  2. Retardation characteristics of radionuclides in geologic media through batch and packed column experiments

    International Nuclear Information System (INIS)

    Batch and packed column experiments are performed to investigate the retardation characteristics of radionuclide,i.e, Cs-137 in geologic media. In batch experiment, the effects of important parameters on the sorption of radionuclide in geologic media, such as nuclide concentration, pH, and particle size are examined. The Kd value obtained from breakthrough curve was compared with that from the batch sorption experiment to investigate the applicability of the Kd value from batch experiment to prediction of radionuclide migration in dynamic flow through porous media. The proposed model of radionuclide migration in porous media is also verified using the experimental results. (Author)

  3. Optimization of hydroxyapatite particles labeling with samarium-153 as a therapeutic agent for radiation synovectomy

    Energy Technology Data Exchange (ETDEWEB)

    Aungurarat, Angkanan [Isotope Production Division, Office of Atomic Energy for Peace, Vibhawadi Rangsit, Chatuchak, Bangkok (Thailand)

    2000-10-01

    Hydroxyapatite (HA) was studied as a particulate carrier for beta-emitting radionuclides in radiation synovectomy. Particles were labeled with {sup 153}Sm (T{sub 1/2}=1.95 days, {beta}-energy=810 (20%), 710 (50%), 640 (30%) keV, {gamma}-energy=103.2 (29.8%) keV, range of beta particles in tissue is 2.5 mm). Labeling efficiency was greater than 95% at pH 4-6. The compounds is sterile and pyrogen free with its stability of 6 days. In vivo studies by intra-articular injection into the knee joints of normal rats showed the total cumulative leakage of {sup 153} Sm over 6 days was around 2 percentage injected dose (ID). The ease of preparation of {sup 153}Sm-HA, the high efficiency of labeling and low leakage from the joint make {sup 153}Sm-HA attractive for radiation synovectomy. (author)

  4. Recent progress in radioisotope production in Vietnam

    Energy Technology Data Exchange (ETDEWEB)

    Le Van So [Radioisotope Dept., Nuclear Research Institute, Dalat (Viet Nam)

    1998-10-01

    This is a report on the recent progress in radioisotope production in Vietnam. Using a nuclear research reactor of 500 KW with continuous operation cycles of 100 hours a month, the production of some important radioisotopes used in nuclear medicine and research was routinely carried out. More than 80 per cent of irradiation capacity of reactor for radioisotope production were exploited. The radioactivity of more than 150 Ci of {sup 131}I, {sup 99}Mo-{sup 99m}Tc, {sup 32}P, {sup 51}Cr, {sup 153}Sm, {sup 46}Sc, {sup 192}Ir was produced annually. Radiopharmaceuticals such as {sup 131}I-Hippuran and in-vivo Kits for {sup 99m}Tc labelling were also prepared routinely and regularly. More than 10 in-vivo Kits including modern radiopharmaceuticals such as HmPAO kit were supplied to hospitals in Vietnam. The research on the improvement of dry distillation technology for production of {sup 131}I was carried out. As a result obtained a new distillation apparatus made from glass was successfully put to routine use in place of expensive quartz distillation furnace. We have also continued the research programme on the development of {sup 99m}Tc generators using low power research reactors. Gel technology using Zr- and Ti- molybdate gel columns for {sup 99m}Tc generator production was developed and improved continually. Portable {sup 99m}Tc generator using Zr-({sup 99}Mo) molybdate gel column and ZISORB adsorbent column for {sup 99m}Tc concentration were developed. The ZISORB adsorbent of high adsorption capacity for {sup 99}Mo and other parent radionuclides was also studied for the development purpose of alternative technology of {sup 99m}Tc and other different radionuclide generator systems. The studies on the preparation of therapeutic radiopharmaceuticals labelling with {sup 153}Sm and {sup 131}I such as {sup 153}Sm-EDTMP, {sup 131}I-MIBG were carried out. (author)

  5. SU-C-201-06: Utility of Quantitative 3D SPECT/CT Imaging in Patient Specific Internal Dosimetry of 153-Samarium with GATE Monte Carlo Package

    Energy Technology Data Exchange (ETDEWEB)

    Fallahpoor, M; Abbasi, M [Tehran University of Medical Sciences, Vali-Asr Hospital, Tehran, Tehran (Iran, Islamic Republic of); Sen, A [University of Houston, Houston, TX (United States); Parach, A [Shahid Sadoughi University of Medical Sciences, Yazd, Yazd (Iran, Islamic Republic of); Kalantari, F [UT Southwestern Medical Center, Dallas, TX (United States)

    2015-06-15

    Purpose: Patient-specific 3-dimensional (3D) internal dosimetry in targeted radionuclide therapy is essential for efficient treatment. Two major steps to achieve reliable results are: 1) generating quantitative 3D images of radionuclide distribution and attenuation coefficients and 2) using a reliable method for dose calculation based on activity and attenuation map. In this research, internal dosimetry for 153-Samarium (153-Sm) was done by SPECT-CT images coupled GATE Monte Carlo package for internal dosimetry. Methods: A 50 years old woman with bone metastases from breast cancer was prescribed 153-Sm treatment (Gamma: 103keV and beta: 0.81MeV). A SPECT/CT scan was performed with the Siemens Simbia-T scanner. SPECT and CT images were registered using default registration software. SPECT quantification was achieved by compensating for all image degrading factors including body attenuation, Compton scattering and collimator-detector response (CDR). Triple energy window method was used to estimate and eliminate the scattered photons. Iterative ordered-subsets expectation maximization (OSEM) with correction for attenuation and distance-dependent CDR was used for image reconstruction. Bilinear energy mapping is used to convert Hounsfield units in CT image to attenuation map. Organ borders were defined by the itk-SNAP toolkit segmentation on CT image. GATE was then used for internal dose calculation. The Specific Absorbed Fractions (SAFs) and S-values were reported as MIRD schema. Results: The results showed that the largest SAFs and S-values are in osseous organs as expected. S-value for lung is the highest after spine that can be important in 153-Sm therapy. Conclusion: We presented the utility of SPECT-CT images and Monte Carlo for patient-specific dosimetry as a reliable and accurate method. It has several advantages over template-based methods or simplified dose estimation methods. With advent of high speed computers, Monte Carlo can be used for treatment planning

  6. Tumor Immunotargeting Using Innovative Radionuclides

    Directory of Open Access Journals (Sweden)

    Françoise Kraeber-Bodéré

    2015-02-01

    Full Text Available This paper reviews some aspects and recent developments in the use of antibodies to target radionuclides for tumor imaging and therapy. While radiolabeled antibodies have been considered for many years in this context, only a few have reached the level of routine clinical use. However, alternative radionuclides, with more appropriate physical properties, such as lutetium-177 or copper-67, as well as alpha-emitting radionuclides, including astatine-211, bismuth-213, actinium-225, and others are currently reviving hopes in cancer treatments, both in hematological diseases and solid tumors. At the same time, PET imaging, with short-lived radionuclides, such as gallium-68, fluorine-18 or copper-64, or long half-life ones, particularly iodine-124 and zirconium-89 now offers new perspectives in immuno-specific phenotype tumor imaging. New antibody analogues and pretargeting strategies have also considerably improved the performances of tumor immunotargeting and completely renewed the interest in these approaches for imaging and therapy by providing theranostics, companion diagnostics and news tools to make personalized medicine a reality.

  7. Tumor immunotargeting using innovative radionuclides.

    Science.gov (United States)

    Kraeber-Bodéré, Françoise; Rousseau, Caroline; Bodet-Milin, Caroline; Mathieu, Cédric; Guérard, François; Frampas, Eric; Carlier, Thomas; Chouin, Nicolas; Haddad, Ferid; Chatal, Jean-François; Faivre-Chauvet, Alain; Chérel, Michel; Barbet, Jacques

    2015-01-01

    This paper reviews some aspects and recent developments in the use of antibodies to target radionuclides for tumor imaging and therapy. While radiolabeled antibodies have been considered for many years in this context, only a few have reached the level of routine clinical use. However, alternative radionuclides, with more appropriate physical properties, such as lutetium-177 or copper-67, as well as alpha-emitting radionuclides, including astatine-211, bismuth-213, actinium-225, and others are currently reviving hopes in cancer treatments, both in hematological diseases and solid tumors. At the same time, PET imaging, with short-lived radionuclides, such as gallium-68, fluorine-18 or copper-64, or long half-life ones, particularly iodine-124 and zirconium-89 now offers new perspectives in immuno-specific phenotype tumor imaging. New antibody analogues and pretargeting strategies have also considerably improved the performances of tumor immunotargeting and completely renewed the interest in these approaches for imaging and therapy by providing theranostics, companion diagnostics and news tools to make personalized medicine a reality. PMID:25679452

  8. Transfer of radionuclides to plants

    International Nuclear Information System (INIS)

    Sampling of Water Horsetail and Bracken Fern including upper soil layer (0-10 cm) and water was carried out in Torahult, Sweden, in Almindingen on Bornholm, in Asserbo and Arresoe on Zealand and in Sdr. Hostrup and Nydam mose in Jutland. Furthermore, sampling was carried out in 2004 for seawater, seaweed and shrimps at locations in Danish waters at Bornholm (Svenskehavn), at Zealand (Klint), at Lolland/Falster (Guldborgsund) and on the west coast of Jutland (Hirtshals, Agger, Hvide Sande and Roemoe). Concentrations of gamma-emitting radionuclides and uranium were determined in Bracken Fern, Water Horsetail and soil samples. The concentration ratios (CR) are highest for 40K in both plant species and show the lowest variability across locations. The CR's for 40K range from 1 to 2, while the CR's for the other radionuclides range one to three orders of magnitude lower. The CR's for 137Cs show particularly high variability across locations. The CR's were analysed in a two-way ANOVA on the log-transformed values to test differences between plant species and radionuclides. The difference between radionuclides was highly significant, p137Cs and 99Tc in marine samples. Concentration ratios calculated from the analysed samples are presented. The concentration ratios for 99Tc agree with those reported elsewhere in the Indofern Project. The concentration ratios for 137Cs in Fucus show a correlation to salinity with higher values in low salinity water at Bornholm than in high salinity water on the west coast of Jutland. (LN)

  9. [Role of Radionuclide Technologies in Medicine].

    Science.gov (United States)

    Chernyaev, A P; Belousov, A V; Varzar, S M; Borchegovskaya, P Y; Nikolaeva, A A; Krusanov, G A

    2016-01-01

    The paper describes the role of radionuclide technologies among the nuclear-physical methods used in medicine. The condition and prospects of the development of nuclear technology with use of radionuclides in medicine, and in particular, the method of brachytherapy are analyzed. The analysis of the current state of applying radionuclide facilities in medicine is provided.

  10. Radionuclides and ionizing radiation in water management

    International Nuclear Information System (INIS)

    The proceedings of the conference contain 22 texts of contributions presented, out of which 21 have been inputted in INIS. The topics treated include mainly contamination of surface waters by radionuclides, e.g from the operation of nuclear power plants, accumulation of radionuclides by the biosphere, and analytical problems of determination of radionuclides in the hydrosphere. (P.A.)

  11. The use of radionuclide skeleton visualization method in hygienic studies

    International Nuclear Information System (INIS)

    Inhalation, intragastric and combined effect of two cadmium compounds on rats is studied. Investigations are performed by biochemical methods and the method of radionuclide visualization of the skeleton which was performed delta hours after RPP introduction in gamma-chamber with computer tape recording for the following mathematical treatment of the image. Using the method of radionuclide skeleton visualization pronounced quantitative characteristics of changes in the bone tissue are obtained, it is found that dose dependence of these changes is especially important when estimating the complex effect. Biochemical methods, are used to find alterations, however they have not been assessed quantitatively

  12. Clay as a barrier to radionuclide migration: a review

    International Nuclear Information System (INIS)

    Because of their low permeability, high sorption capacity and plasticity, clay bodies are potentially suitable repositories for radioactive waste. The 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 summarised and compared. (author)

  13. Naturally Occurring Radionuclides in Pottery, Ceramic and Glasswares Produced in Bangladesh

    International Nuclear Information System (INIS)

    The concentrations of naturally occurring radionuclides were measured using gamma spectrometry in the finished products of pottery, glass, ceramic and tiles. Ceramic and pottery utensils, tiles, basin and glassware contained naturally occurring radionuclides. Pottery is produced from local clay materials, but ceramic, tiles, basin and glassware's are made from both local and imported raw materials. Radium and thorium radionuclides are concentrated during the making of pottery from the clay materials due to calcination. Radionuclides concentrated more in the highly calcined pottery products than the low calcined products. Glassware products contained very low quantities of radionuclides comparing with the ceramic and pottery products. Study on radioactivity in the pottery, ceramic and glassware products is important in the assessment of possible radiological hazards to human health. The knowledge is essential for the development of standards and guidelines for the use and management of these materials. (author)

  14. Models for transport and fate of carbon, nutrients and radionuclides in the aquatic ecosystem at Oeregrundsgrepen

    International Nuclear Information System (INIS)

    The aim of the work was to provide supplementary input to the risk assessment of a planned final nuclear waste repository at Forsmark. The main deliverable was a computed water exchange between basins in the Forsmark marine area for the period 6500 BC to 9000 AD - based on the hydrodynamic modelling - to be used as input to the landscape dose model. In addition and what is described in this report, a second deliverable was development and application of high-resolution models for the marine ecosystem and radionuclide processes. The purpose of this deliverable was to illustrate the spatial and temporal variation in important processes and parameters, while constituting a complement to previous modelling approaches and providing supporting information to discussions of the marine ecosystem, parameters and variation (see Chapter 4 and 6).To this end, a hydrodynamic model of high temporal and spatial resolution was constructed and calibrated for the Forsmark area. An ecosystem model was then developed and coupled to the hydrodynamic model. In turn, a detailed radionuclide model was coupled to the ecosystem model to provide detailed predictions of radionuclide transport and accumulation in the coastal ecosystem. The ecosystem and radionuclide models were developed in the equation solver MIKE ECOLab that links seamless to the MIKE3 FM hydrodynamic model. The 'standard' ECOLab ecosystem model was extended with six biological state variables, perennial macroalgae, benthic herbivors, detritus feeders, planktivorus fish and, benthic predators representing the relict isopod Saduria and cod. In contrast to the ecosystem model, the radionuclide model was developed from scratch but building on the structure of the ecosystem model and using the output (process rates linking state variables) from the ecosystem model as input to the radionuclide model. Both the ecosystem model and the radionuclide model were run for several years (5-8 years) to bring state variables into quasi

  15. Models for transport and fate of carbon, nutrients and radionuclides in the aquatic ecosystem at Oeregrundsgrepen

    Energy Technology Data Exchange (ETDEWEB)

    Erichsen, Anders Christian; Moehlenberg, Flemming; Closter, Rikke Margrethe; Sandberg, Johannes (DHI, Hoersholm (Denmark))

    2010-06-15

    The aim of the work was to provide supplementary input to the risk assessment of a planned final nuclear waste repository at Forsmark. The main deliverable was a computed water exchange between basins in the Forsmark marine area for the period 6500 BC to 9000 AD - based on the hydrodynamic modelling - to be used as input to the landscape dose model. In addition and what is described in this report, a second deliverable was development and application of high-resolution models for the marine ecosystem and radionuclide processes. The purpose of this deliverable was to illustrate the spatial and temporal variation in important processes and parameters, while constituting a complement to previous modelling approaches and providing supporting information to discussions of the marine ecosystem, parameters and variation (see Chapter 4 and 6).To this end, a hydrodynamic model of high temporal and spatial resolution was constructed and calibrated for the Forsmark area. An ecosystem model was then developed and coupled to the hydrodynamic model. In turn, a detailed radionuclide model was coupled to the ecosystem model to provide detailed predictions of radionuclide transport and accumulation in the coastal ecosystem. The ecosystem and radionuclide models were developed in the equation solver MIKE ECOLab that links seamless to the MIKE3 FM hydrodynamic model. The 'standard' ECOLab ecosystem model was extended with six biological state variables, perennial macroalgae, benthic herbivors, detritus feeders, planktivorus fish and, benthic predators representing the relict isopod Saduria and cod. In contrast to the ecosystem model, the radionuclide model was developed from scratch but building on the structure of the ecosystem model and using the output (process rates linking state variables) from the ecosystem model as input to the radionuclide model. Both the ecosystem model and the radionuclide model were run for several years (5-8 years) to bring state variables into

  16. Radionuclides and ionizing radiation in water management

    International Nuclear Information System (INIS)

    The proceedings contain 31 papers dealing with the impact of nuclear power plants on the hydrosphere (radionuclide composition of waste waters and their assessment, the effect of liquid radioactive wastes on surface water organisms, the occurrence of radionuclides in bottom sediments, the cost-effectiveness of risk reduction of liquid radioactive wastes, etc.); the methods of concentrating and separating radionuclides from high-volume liquid samples; the methods of radionuclide contamination measurement (semiconductor spectrometry, the use of silicon detectors, the measurement of gross alpha and beta activities, etc.); and radionuclide migration in ground waters. (E.S.). 25 figs., 30 tabs., 86 refs

  17. Baltic Sea: Radionuclides

    DEFF Research Database (Denmark)

    Nielsen, Sven Poul; Lüning, Maria; Ilus, Erkki;

    2011-01-01

    The most significant source of anthropogenic radioactivity in the Baltic Sea is fallout from the accident at the Chernobyl nuclear power plant in 1986. The second most important source is global fallout from atmospheric nuclear weapons tests carried out during the late 1950s and early 1960s....... Radioactivity inputs into the Baltic Sea from nuclear reprocessing plants in Western Europe have become of minor importance due to significant reduction of discharges in recent years. In terms of input of 137Cs into the Baltic Sea, Chernobyl fallout has contributed about 82% and nuclear weapons test fallout...... about 14%. For 90Sr in the Baltic Sea, input from atmospheric fallout from nuclear weapons tests has contributed about 81%, while the contribution from Chernobyl fallout was about 13%. Cesium-137 is the main indicator of Baltic seawater with respect to anthropogenic radioactivity. The highest...

  18. Baltic Sea: Radionuclides

    DEFF Research Database (Denmark)

    Nielsen, Sven Poul; Lüning, Maria; Ilus, Erkki;

    2010-01-01

    The most significant source of anthropogenic radioactivity in the Baltic Sea is fallout from the accident at the Chernobyl nuclear power plant in 1986. The second most important source is global fallout from atmospheric nuclear weapons tests carried out during the late 1950s and early 1960s....... Radioactivity inputs into the Baltic Sea from nuclear reprocessing plants in Western Europe have become of minor importance due to significant reduction of discharges in recent years. In terms of input of 137Cs into the Baltic Sea, Chernobyl fallout has contributed about 82% and nuclear weapons test fallout...... about 14%. For 90Sr in the Baltic Sea, input from atmospheric fallout from nuclear weapons tests has contributed about 81%, while the contribution from Chernobyl fallout was about 13%. Cesium-137 is the main indicator of Baltic seawater with respect to anthropogenic radioactivity. The highest...

  19. Radionuclides in the Great Lakes basin.

    Science.gov (United States)

    Ahier, B A; Tracy, B L

    1995-12-01

    The Great Lakes basin is of radiologic interest due to the large population within its boundaries that may be exposed to various sources of ionizing radiation. Specific radionuclides of interest in the basin arising from natural and artificial sources include 3H, 14C, 90Sr, 129I, 131I, 137Cs, 222Rn, 226Ra, 235U, 238U, 239Pu, and 241Am. The greatest contribution to total radiation exposure is the natural background radiation that provides an average dose of about 2.6 mSv/year to all basin residents. Global fallout from atmospheric nuclear weapons tests conducted before 1963 has resulted in the largest input of anthropogenic radioactivity into the lakes. Of increasing importance is the radionuclide input from the various components of the nuclear fuel cycle. Although the dose from these activities is currently very low, it is expected to increase if there is continued growth of the nuclear industry. In spite of strict regulations on design and operation of nuclear power facilities, the potential exists for a serious accident as a result of the large inventories of radionuclides contained in the reactor cores; however, these risks are several orders of magnitude less than the risks from other natural and man-made hazards. An area of major priority over the next few decades will be the management of the substantial amounts of radioactive waste generated by nuclear fuel cycle activities. Based on derived risk coefficients, the theoretical incidence of fatal and weighted nonfatal cancers and hereditary defects in the basin's population, attributable to 50 years of exposure to natural background radiation, is conservatively estimated to be of the order of 3.4 x 10(5) cases. The total number of attributable health effects to the year 2050 from fallout radionuclides in the Great Lakes basin is of the order of 5.0 x 10(3). In contrast, estimates of attributable health effects from 50 years of exposure to current nuclear fuel cycle effluent in the basin are of the order of 2

  20. Radionuclide behavior at underground environment

    International Nuclear Information System (INIS)

    This study of radionuclide behavior at underground environment has been carried out as a part of the study of high-level waste disposal technology development. Therefore, the main objectives of this project are constructing a data-base and producing data for the safety assessment of a high-level radioactive waste, and verification of the objectivity of the assessment through characterization of the geochemical processes and experimental validation of the radionuclide migration. The various results from the this project can be applicable to the preliminary safety and performance assessments of the established disposal concept for a future high-level radioactive waste repository. Providing required data and technical basis for assessment methodologies could be a direct application of the results. In a long-term view, the results can also be utilized as a technical background for the establishment of government policy for high-level radioactive waste disposal

  1. Radionuclide behavior at underground environment

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, Phil Soo; Park, Chung Kyun; Keum, Dong Kwon; Cho, Young Hwan; Kang, Moon Ja; Baik, Min Hoon; Hahn, Kyung Won; Chun, Kwan Sik; Park, Hyun Soo

    2000-03-01

    This study of radionuclide behavior at underground environment has been carried out as a part of the study of high-level waste disposal technology development. Therefore, the main objectives of this project are constructing a data-base and producing data for the safety assessment of a high-level radioactive waste, and verification of the objectivity of the assessment through characterization of the geochemical processes and experimental validation of the radionuclide migration. The various results from the this project can be applicable to the preliminary safety and performance assessments of the established disposal concept for a future high-level radioactive waste repository. Providing required data and technical basis for assessment methodologies could be a direct application of the results. In a long-term view, the results can also be utilized as a technical background for the establishment of government policy for high-level radioactive waste disposal.

  2. Physical and chemical characteristics of radionuclide carriers the environment

    International Nuclear Information System (INIS)

    In spite of the nuclear energy advantages related to the smallest environmental impact due to protection of resources and reduction of greenhouse gas emissions, the environment has been affected by nuclear activities. In order to evaluate trends, to study transport processes and to predict consequences of radionuclide releases/leakage from a source and atmospheric fallout, information on the present levels of radioactive contamination, releases and source terms is essential. At present it is generally recognized that a realistic estimation of the long-term consequences of radioactive contamination is possible through the better understanding of physical and chemical processes of radionuclide migration in the environment. To assess the transfer and fate of radioactive contaminants in the atmosphere, terrestrial and marine environment the information on physical and chemical parameters of radionuclide carriers is required. The release of radionuclides associated with particles of different sizes and mineralogical composition into the environment can considerably affect their transport and bioavailability. Thus, after nuclear explosions different spreading velocities and downward movement of 137Cs, 95Zr+95Nb, 22Na aerosols and gaseous 14C(14CO2) were observed. In addition, low chemical reactivity is characteristic of highly insoluble, refractory oxides of uranium and plutonium formed in nuclear explosions, and they are very kinetically stable and remain in a form in which they are injected into environment for a long time. They were distinguished for their behaviour in the environment from radionuclides released into environment processing plants and laboratory research The emission of radiocesium from combustion of contaminated firewood can also contribute to the radiational situation in Lithuania. The analysis of activity concentrations, meteorological situation, types of particle are important for understanding the sources and possible impact on given location. Our

  3. Radionuclides and maternal lactation

    International Nuclear Information System (INIS)

    The increase in the number of nuclear medicine centers, both official and private in the country, as well as the increase in the number of patients, due to the effectiveness of their diagnostic and therapeutic procedures, brings out new situations that must be studied from the point of view of radioprotection. This work makes a revision in the medical literature about procedures with radioisotopes during the maternal nursing period. In general, it is recommended to stop nursing for 24 hours for 99mtc test, and to resume it after the draining of the milky content. This can be done in spite of the sensitivity of the target organ of the baby, because the dosage will be below permissible limits accepted by international agencies with respect to diagnostic test and I-131 treatment, and if continuing nursing is desired, it is recommended to use other diagnostic or therapeutic procedures before discontinuing the most important nutritional resource at this age

  4. Radionuclide 252Cf neutron source

    International Nuclear Information System (INIS)

    Characteristics of radionuclide neutron sourses of 252Cf base with the activity from 106 to 109 n/s have been investigated. Energetic distributions of neutrons and gamma-radiation have been presented. The results obtained have been compared with other data available. The hardness parameter of the neutron spectrum for the energy range from 3 to 15 MeV is 1.4 +- 0.02 MeV

  5. Radionuclide behavior in the environment

    International Nuclear Information System (INIS)

    The purpose of this report is to document the results of the following task: Review for quality and consistency the available data on measurements of initial ground contamination of Chernobyl radionuclides in various parts of Norway and subsequent concentrations of these radionuclides in various environmental media as functions of time. Utilize the data obtained to verify the existing models, or to improve them, for describing radionuclide behavior in the environment. Some of the processes standard were: migration into soil; weathering; resuspension; food-chain contamination; and loss or reconcentration by run-off. The task performed within this contract has been to use post-Chernobyl data from Norway to verify or find areas for possible improvement in the chronic exposure pathway models utilized in MACCS. Work has consisted mainly of collecting and evaluating post-Chernobyl information from Norway or other countries when relevant; but has also included experimental work performed specifically for the current task. In most connections the data available show the models and data in MACCS to be appropriate. A few areas where the data indicate that the MACCS approach is faulty or inadequate are, however, pointed out in the report. These should be examined carefully, and appropriate modifications should eventually be made. 14 refs., 12 figs., 22 tabs

  6. Study on natural radionuclide activities in meat samples consumed in Sao Paulo City, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Rosa, Mychelle M.L.; Taddei, Maria HelenaT. [Comissao Nacional de Energia Nuclear (LAPOC/CNEN), Pocos de Caldas, MG (Brazil). Laboratorio de Pocos de Caldas; Avegliano, Roseane P.; Maihara, Vera A., E-mail: mychelle@cnen.gov.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    Consumption of food is usually the most important route by which natural and artificial radionuclides can enter the human body. An assessment of radionuclide levels in different foods and diets is therefore important to estimate the intake of these radionuclides by man. The contamination by radionuclides can occur via the food chain (soil, root, plant and animal), with emphasis to the long half-life radionuclides, which can also have their transfer through the animal meat. The inclusion of meat in human nutrition is important because it is an excellent source of high quality protein, nutrient related to construction and cell regeneration. This work aims the determination of natural radionuclides ({sup 234}U, {sup 235}U, {sup 238}U, {sup 228}Th, {sup 230}Th, {sup 232}Th, {sup 226}Ra, {sup 228}Ra, and {sup 210}Pb) in meat samples. Five groups of samples were analyzed, such as cattle meat (beef), fish, pork, poultry, and processed meat, after radiochemical separation followed by alpha or alpha beta spectrophotometry, and total count quantification. The determination of these radionuclides is very important because they are products of the natural decay series of {sup 238}U and {sup 232}Th, being easily found in meat samples. (author)

  7. Biokinetics and dose assessment of radionuclides in juveniles

    International Nuclear Information System (INIS)

    In the aftermath of the Chernobyl accident, it becomes evident that dose coefficients for members of the public are necessary. International Commission on Radiological Protection (ICRP) established a task group of Committee 2 charged with the assessment of dose coefficients as a function of an individual's age. However, little data is available on the biokinetics of radionuclides in juvenile and there is a need to develop age-dependent biokinetic models, such as for the gastrointestinal tract. The present paper reviewed an outline on characteristics of biokinetics of radionuclides in juvenile animals focusing on the previous experimental data. The following radionuclides are discussed: 54Mn, 60Co, 65Zn, 75Se, 106Ru, 110mAg, 115mCd, 125Sb, 137Cs, 141Ce, 203Hg and 3H. Generally, intestinal absorption and whole-body retention of radionuclides in juveniles were higher than that of adult. In the case of sucklings, it is very important to study how radionuclides are transferred through the placenta and milk. The transfer rate of radionuclides through the placenta and milk is dependent on the period of gestation at the time of dosing. The IDES(Internal Dose Estimation System) which is based on the ICRP model was used for dose calculation. We modified the IDES using the biokinetic data which was gained animal experiment. The IDES is flexible because the absorbed dose can be calculated by substituting arbitrary physical and physiological parameters and also substituting ingested dose coefficients not only for the ICRP Reference Man, but also for Japanese of 1 year old, 5 years old, 10 years old, 15 years old and the adult, respectively. (author)

  8. Reliability of Current Biokinetic and Dosimetric Models for Radionuclides: A Pilot Study

    Energy Technology Data Exchange (ETDEWEB)

    Leggett, Richard Wayne [ORNL; Eckerman, Keith F [ORNL; Meck, Robert A. [U.S. Nuclear Regulatory Commission

    2008-10-01

    studied radionuclides. (4) The biokinetics of a radionuclide in the human body typically represents the greatest source of uncertainty or variability in dose per unit intake. (5) Characterization of uncertainty in dose per unit exposure is generally a more straightforward problem for external exposure than for intake of a radionuclide. (6) For many radionuclides the most important outcome of a large-scale critical evaluation of databases and biokinetic models for radionuclides is expected to be the improvement of current models. Many of the current models do not fully or accurately reflect available radiobiological or physiological information, either because the models are outdated or because they were based on selective or uncritical use of data or inadequate model structures. In such cases the models should be replaced with physiologically realistic models that incorporate a wider spectrum of information.

  9. Natural radionuclide analysis in chattarpur area of southeastern coastal area of Odisha, India

    Science.gov (United States)

    Rautela, Bhagwat; Gusain, Gurupad; Yadav, Manjulata; Sahoo, Sarat; Tokonami, Shinji; Ramola, Rakesh

    2013-08-01

    The energy released in a spontaneous decay process of natural radionuclides is the main source of the total radiation dose to human beings. Natural radionuclides are widely distributed in soil, rocks, air, and groundwater. In present investigation, the analysis of terrestrial radionuclides such as 226Ra, 232Th, and 40K in soil and sand of Chattarpur area of southeastern coast of Odisha has been carried out using NaI(Tl) gamma ray detector. The higher activity concentrations of naturally occurring radionuclides have been reported from the study area. The gamma radiationdose originating from the terrestrial radionuclides was found to vary from 95 to 1813 nGy/h with an average of 700 nGy/h. This study is important to generate a baseline data of radiation exposure in the area. Health hazard effects due to natural radiation exposure are discussed in details.

  10. Production parameters of the therapeutic 105Rh radionuclide using medium energy cyclotron

    Indian Academy of Sciences (India)

    Mayeen Uddin Khandaker; Kwangsoo Kim; Guinyun Kim

    2012-08-01

    Production cross-sections of the therapeutic 105Rh radionuclide from proton-induced reactions on natural palladium target were measured using stacked-foil activation technique combined with high resolution -ray spectrometry at the MC50 cyclotron of the Korea Institute of Radiological and Medical Sciences. Note that cyclotron production of the 105Rh radionuclide from natural palladium target was measured here for the first time. Results are compared with the theoretical values obtained using the model codes TALYS and ALICE-IPPE. Thick target integral yields for the investigated 105Rh radionuclide were deduced from the threshold energy to 40 MeV. Measured data of the 105Rh radionuclide are important because of its potential applications in nuclear medicine and/or therapeutic purposes. Optimal production circumstances for the therapeutic 105Rh radionuclide using a cyclotron are discussed elaborately.

  11. The transfer of radionuclides into domestic animals and their products

    International Nuclear Information System (INIS)

    The contamination of animal products, especially milk, with radionuclides, are regarded as the important problem in the food chain, and has been one of the remarkable public concerns in Japan since the nuclear tests in 1954. The transfer of several radionuclides into domestic animals and their products is described. 131I, 90Sr and 137Cs are very important as the radionuclides that transfer into domestic animals and their products. The data of the transfer of several orally administered radionuclides into milk from the references are summarized as follows: (1) 131I transfered into milk was 5 -- 30% of dose (cow), 10 -- 40% (goat). (2) 90Sr(89Sr) transfered into milk was 0.6 -- 1.9% (cow), 0.5 -- 0.6% (goat). (3) 137Cs(134Cs) transfered into milk was 10 -- 13% (cow), 7.0% (goat). (4) 140Ba-140La transfered into milk was 0.6% (cow), 0.1 -- 0.2% (goat). (5) 181W transfered into milk was 0.06% (goat). (author)

  12. Radiation protection aspects of the trafficking radionuclides contaminated metal scrap

    International Nuclear Information System (INIS)

    This paper covers the legal base of the release in the environment of radionuclides containing materials and the radiation protection aspects of trafficking in radionuclides contaminated materials. Materials, substance and objects containing radionuclides or contaminated by them may be released into the environment, if they do not exceed values authorized by SONS (State Office of Nuclear Safety). Legislative measures should be taken against illicit trafficking of the nuclear material in all the areas. The creation of a sophisticated system for the control and regulation of all important radionuclides released into the environment should be based on the radiation protection limits, constraints, reference and exemption levels which are introduced in the legislative documents; the strong supervision of producers and users of the sealed sources by SONS side, in addition to the requirements of the licensing process of their sources; a complete data-base and information exchange system related to illicit trafficking in contaminated material; in this system all the authorities with jurisdiction should be involved. The responsibilities of the persons involved in metal scrap trafficking should include arrangement of appropriate monitoring, rules for transport of the metal scrap, an adequate measuring system to monitor metal scrap including monitoring to prevent processing or smelting of the radioactive material, control measures, etc. All of the above items of legislation are an important challenge for the Czech Republic. (author)

  13. Transfer of radionuclides to the higher plants through direct deposition and root uptake pathways

    International Nuclear Information System (INIS)

    Radionuclides have been released to the environment from several sources, e.g., nuclear weapons testing and discharges from nuclear facilities. Mathematical models have been used for assessment of potential exposures to humans from released radionuclides. In the models, intake of foods is one of the important pathways, and thus, the mechanisms of radionuclide transfer to crops from environmental media (air, water, soil) are of interest. The mechanisms can be also applicable to all types of higher plants (wood and herbaceous plants) thus the topic is extended to plants. There are two main transport pathways to plant, i.e. direct deposition to plant surface and root uptake from soil. When plants absorb radionuclides, Cs could be translocated to other parts of plants, while Sr, Zn, Pu and Am were less mobile and remained at the absorbed area of the plant. After the releases of radionuclides to the air are ceased, the main radionuclide transfer pathway is root uptake. The uptake is controlled by a combination of several environmental and plant physiological factors; if the soil fixes a radionuclide then the uptake by root is not high, and if the radionuclide is a non-essential element, then the amount of root uptake is limited. Once Cs is absorbed by woody plants, Cs is partially removed when leaves are off from the trees, but a part of Cs remained in the wood body which can cause Cs contamination in newly emerged parts in the following growing season. (author)

  14. Uncertainties in geologic disposal of high-level wastes - groundwater transport of radionuclides and radiological consequences

    International Nuclear Information System (INIS)

    The analysis for radionuclide transport in groundwater considers models and methods for characterizing (1) the present geologic environment and its future evolution due to natural geologic processes and to repository development and waste emplacement, (2) groundwater hydrology, (3) radionuclide geochemistry, and (4) the interactions among these phenomena. The discussion of groundwater transport focuses on the nature of the sources of uncertainty rather than on quantitative estimates of their magnitude, because of the lack of evidence that current models can provide realistic quantitative predictions of radionuclide transport in groundwater for expected repository environments. The analysis for the long-term health risk to man following releases of long-lived radionuclides to the biosphere is more quantitative and involves estimates of uncertainties in (1) radionuclide concentrations in man's exposure environment, (2) radionuclide intake by exposed individuals per unit concentration in the environment, (3) the dose per unit intake, (4) the number of exposed individuals, and (5) the health risk per unit dose. For the important long-lived radionuclides in high-level waste, uncertainties in most of the different components of a calculation of individual and collective dose per unit release appear to be no more than two or three orders of magnitude; these uncertainties are certainly much less than uncertainties in predicting groundwater transport of radionuclides between a repository and the biosphere. Several limitations in current models for predicting the health risk to man per unit release to the biosphere are discussed

  15. Multi-phase analytical model of radionuclide migration in lake water and bottom sediment system

    Energy Technology Data Exchange (ETDEWEB)

    Maceika, Evaldas; Filistovic, Vitold; Luksiene, Bena; Tarasiuk, Nikolay; Buivydas, Sarunas; Konstantinova, Marina; Puzas, Andrius [State research institute Center for Physical Sciences and Technology, Savanoriu ave. 231, LT-2300 Vilnius (Lithuania)

    2014-07-01

    Migration of long-lived radionuclides in lake eco-system is governed by several processes: advection, dilution, seasonal exchange, sedimentation; bioaccumulation. Interaction of dissolved radionuclide in water with the bottom sediments is of particular importance. Radionuclide can be adsorbed and desorbed by the bottom sediments. In turn, radionuclide is rapidly absorbed by organic and nonorganic origin particles in the lake water sphere. At the end, the particles will sink to the lake bottom and will form sediment layers of elevated contamination. Therefore explicit evaluation and balance of multi-phase radionuclide activity fluxes at the interface of lake water and bottom sediments surface is modelled in details. Created mathematical model, analytically describing dynamic of radionuclide migration, encompass both spheres of lake eco-system: water and bottom sediments. Solid and liquid radionuclide activity fractions are considered in every sphere. Sediment contamination is described by 1-D depth dependent advection-diffusion and adsorption/desorption reaction equation. Processes, taking place in the solid phase at the lake water sphere, are described by the adsorption/desorption dynamic equation as well as by activity fluxes balance at the interface with bottom sediments. Mathematical equations are rapidly solved by using Laplace transform and numerical inversion methods. Created model better described experimental measurement data of {sup 137}Cs radionuclide activity distribution profiles in studied lake bottom sediment vertical layers. This research was funded by a grant (No. MIP-041/2012) from the Research Council of Lithuania. (authors)

  16. Multi-phase analytical model of radionuclide migration in lake water and bottom sediment system

    International Nuclear Information System (INIS)

    Migration of long-lived radionuclides in lake eco-system is governed by several processes: advection, dilution, seasonal exchange, sedimentation; bioaccumulation. Interaction of dissolved radionuclide in water with the bottom sediments is of particular importance. Radionuclide can be adsorbed and desorbed by the bottom sediments. In turn, radionuclide is rapidly absorbed by organic and nonorganic origin particles in the lake water sphere. At the end, the particles will sink to the lake bottom and will form sediment layers of elevated contamination. Therefore explicit evaluation and balance of multi-phase radionuclide activity fluxes at the interface of lake water and bottom sediments surface is modelled in details. Created mathematical model, analytically describing dynamic of radionuclide migration, encompass both spheres of lake eco-system: water and bottom sediments. Solid and liquid radionuclide activity fractions are considered in every sphere. Sediment contamination is described by 1-D depth dependent advection-diffusion and adsorption/desorption reaction equation. Processes, taking place in the solid phase at the lake water sphere, are described by the adsorption/desorption dynamic equation as well as by activity fluxes balance at the interface with bottom sediments. Mathematical equations are rapidly solved by using Laplace transform and numerical inversion methods. Created model better described experimental measurement data of 137Cs radionuclide activity distribution profiles in studied lake bottom sediment vertical layers. This research was funded by a grant (No. MIP-041/2012) from the Research Council of Lithuania. (authors)

  17. The behaviour of radionuclides in the Ribble Estuary, NW England

    International Nuclear Information System (INIS)

    The main aim of this project was to consider the geochemical behaviour of a suite of radionuclides (137Cs, 241Am, isotopes of Pu, Th and U and 234mPa) in the Ribble estuarine environment. Controls on the vertical distribution of radionuclides in sediment deposits were considered and the fluxes of sediment and radionuclides at sites close to the river channel were investigated. Vertical activity distributions were studied by taking cores from various intertidal sediment deposits. Sediment/activity fluxes were studied by installing sediment traps. All samples were analysed by gamma spectrometry. Selected samples were analysed for total organic carbon, mineralogy (XRD), major and trace-metals (XRF), grain-size distribution (laser granulometry) and alpha-emitting radionuclides (alpha spectrometry). The geochemical phase associations of radionuclides were investigated using sequential extraction experiments. Sellafield-derived radionuclides exhibited distinct subsurface maxima (up to 4 785 ± 42 Bq kg-1137Cs, 618 ± 14 Bq kg-1239,240Pu and 868 ± Bq kg-1241Am) in mature saltmarsh sediment deposits. Thorium-230 exhibited more complex depth profiles (maximum = 2383 ± 36 Bq kg-1). Variations in grain-size were low and therefore not important in controlling the specific activity variation with depth at these sites. The effects of early diagenesis on the specific activity profiles of 137Cs, 241Am, 239,240Pu and 230Th were small. The vertical distribution of Sellafield-derived radionuclides reflected the cumulative discharge pattern from Sellafield implicating a sediment transport mechanism that has involved the integration of contamination from previous discharge events. The vertical distribution of 230Th reflected the annual discharge pattern from BNFL Springfields implicating a transport pathway that involves little mixing of sediment. Levels of Springfields-derived 234mPa and 234Th were highly variable in time and space (-1 recorded at Penwortham over the course of the

  18. Determination of Long-lived Radionuclides in the Environment using ICP-MS and AMS

    DEFF Research Database (Denmark)

    Hou, Xiaolin

    2011-01-01

    ICP-MS and AMS have been widely used for the measurement of radionuclides, especially long-lived radionculides. The new progress, major advantages of these two techniques and their major applications for measurement of important radionculides are summarized.......ICP-MS and AMS have been widely used for the measurement of radionuclides, especially long-lived radionculides. The new progress, major advantages of these two techniques and their major applications for measurement of important radionculides are summarized....

  19. Targeted Radionuclide Therapy of Human Tumors

    Directory of Open Access Journals (Sweden)

    Sergey V. Gudkov

    2015-12-01

    Full Text Available Targeted radionuclide therapy is one of the most intensively developing directions of nuclear medicine. Unlike conventional external beam therapy, the targeted radionuclide therapy causes less collateral damage to normal tissues and allows targeted drug delivery to a clinically diagnosed neoplastic malformations, as well as metastasized cells and cellular clusters, thus providing systemic therapy of cancer. The methods of targeted radionuclide therapy are based on the use of molecular carriers of radionuclides with high affinity to antigens on the surface of tumor cells. The potential of targeted radionuclide therapy has markedly grown nowadays due to the expanded knowledge base in cancer biology, bioengineering, and radiochemistry. In this review, progress in the radionuclide therapy of hematological malignancies and approaches for treatment of solid tumors is addressed.

  20. Microbial Transformations of Actinides and Other Radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Francis,A.J.; Dodge, C. J.

    2009-01-07

    Microorganisms can affect the stability and mobility of the actinides and other radionuclides released from nuclear fuel cycle and from nuclear fuel reprocessing plants. Under appropriate conditions, microorganisms can alter the chemical speciation, solubility and sorption properties and thus could increase or decrease the concentrations of radionuclides in solution in the environment and the bioavailability. Dissolution or immobilization of radionuclides is brought about by direct enzymatic action or indirect non-enzymatic action of microorganisms. Although the physical, chemical, and geochemical processes affecting dissolution, precipitation, and mobilization of radionuclides have been extensively investigated, we have only limited information on the effects of microbial processes and biochemical mechanisms which affect the stability and mobility of radionuclides. The mechanisms of microbial transformations of the major and minor actinides U, Pu, Cm, Am, Np, the fission products and other radionuclides such as Ra, Tc, I, Cs, Sr, under aerobic and anaerobic conditions in the presence of electron donors and acceptors are reviewed.

  1. Liquid scintillation counting of novel radionuclides

    International Nuclear Information System (INIS)

    The theoretical background of counting radionuclides in liquid scintillators is presented. The effects of quenching and finite scintillator size are briefly described and the theory is justified by an experimental comparison between 55Fe and 3H in which all facets of the theory are important. Counting efficiencies for other nuclides decaying by 100% electron capture are calculated and compared with efficiencies for the β emitters 3H, 14C and 36Cl. Also included are comments on the special problems associated with counting plutonium in biological materials. The essential conclusion is that in order to improve the technique and avoid unnecessary pitfalls it is necessary to have a sound understanding of the underlying theory of liquid scintillation counting

  2. Development of Cyclotron Radionuclides for Medical Applications

    OpenAIRE

    Qaim, S. M.

    2015-01-01

    Soon after the discovery of radioactivity it was shown that radionuclides can be used both for diagnostic and therapeutic studies, depending on the characteristic radiations emitted by them. By 1960’s the radionuclide production technology using nuclear reactors was well established. In early 1970’s a renaissance of the cyclotrons occurred because many of the neutron deficient radionuclides could only be produced using irradiations with charged particles, like protons, deuterons, α-particles,...

  3. Preparation of porous materials for radionuclides capture

    International Nuclear Information System (INIS)

    Porous materials showing promise for radionuclide capture from water at contaminated sites were prepared. Nanoporous materials (size of pores 1-100 nm) and some polymers are well suited to this purpose owing their affinity for selected radionuclides. Nanoporous metal oxides and silica gel with styrene-divinylbenzene-TODGA-modified surface were prepared, characterized and tested for radionuclide (227Ac, 227Th, 223Ra) capture efficiency. (orig.)

  4. Radionuclide imaging of non osseous infection

    Energy Technology Data Exchange (ETDEWEB)

    Palestro, C.J. (Long Island Jewish Medical Center, New York, NY, (United States). Dept. Nuclear Medicine New York, Yeshiva Univ., NY (United States). Albert Einstein College of Medicine); Torres, M.A. (Long Island Jewish Medical Center, New York, NY, (United States). Dept. Nuclear Medicine)

    1999-03-01

    Nuclear medicine is an important tool in the diagnostic evaluation of patients with a variety of non osseous infections. In the immunocompetent population labeled leukocyte imaging is the radionuclide procedure of choice, with Gallium imaging reserved for those situations in which the leukocyte study is non diagnostic or cannot be performed. Fever of unknown origin is caused by infection in less than one-third of cases, and therefore the number of positive leukocyte studies will be relatively low. The negative leukocyte study is also useful as it has been demonstrated that a negative study excludes, with a high degree of certainty, focal infection as the cause of an FUO. In the cardiovascular system, labeled leukocyte scintigraphy is very useful for diagnosing mycotic aneurysms and infected prosthetic vascular grafts. The specificity of the study is somewhat more variable. In the central nervous system, labeled leukocyte imaging can provide important information about the etiology of contrast enhancing brain lesions identified on computed tomography. In the immunocompromised population, typified by the AIDS patient, Gallium scintigraphy is the radionuclide procedure of choice for diagnosing opportunistic diseases. In the thorax, a normal Gallium scan, in the setting of a negative chest X-ray, virtually excludes pulmonary disease. In the abdomen, Gallium is also useful for detecting nodal disease, but is not reliable for detecting large bowel disease. Labeled leukocyte imaging should be performed when colitis is a concern. Both [sup 18]FDG PET and [sup 201]T1 SPECT imaging of the brain are useful for distinguishing between central nervous system lymphoma and toxoplasmosis in the HIV (+) patient. On both studies, lymphoma manifests as a focus of increased tracer uptake, whereas toxoplasmosis shows little or no uptake of either tracer.

  5. Therapy for incorporated radionuclides: scope and need

    International Nuclear Information System (INIS)

    In the United States the recent termination of funding for research on therapy for incorporated radionuclides has virtually halted progress on improved or new agents and procedures for removing radioactivity from the body. Research was eliminated, but is still needed on new removal agents, improved delivery system, in vitro test systems, and the toxicology of treatments. For many radionuclides, no adequate therapy exists. The relationship between radionuclide removal and reduction in cancer risk is still unanswered. Without proper research support, needed improvements in the treatment for incorporated radionuclides in the US are uncertain

  6. Radionuclides and ionizing radiation in water management

    International Nuclear Information System (INIS)

    The conference proceedings contain 22 papers, all have been incorporated in INIS. They relate to the escape of radianuclides from nuclear power plant operation and nuclear power plant accidents into the hydrosphere, the measurement of radioactivity of and concentration of radionuclides in surface, ground and drinking waters, the study of the impact of radionuclides on aquatic organisms and the investigation of the deposition of radionuclides in these organisms and in water sediments, to modeling of the kinetics of radionuclide transport in the hydrosphere, and the problems of radon in the ambient air of water treatment plants and dwelling areas. (M.D.). 3 figs., 28 tabs., 124 refs

  7. Dosimetry of incorporated transuranic radionuclides

    International Nuclear Information System (INIS)

    Modern in vivo and in vitro techniques for detecting transuranic radionuclides within the human body are described with special emphasis on multiparameter measuring methods developed at the National Board of Nuclear Safety and Radiation Protection. Furthermore, problems related to calibration and interpretation of measuring data are discussed and new methods presented for the calculation of committed dose equivalents on the basis of data from ICRP Publication 30. Also included is an introductory chapter on radiobiological fundamentals of intake, translocation and metabolism of these nuclides. (author)

  8. Manual of food quality control 16. radionuclides in food

    International Nuclear Information System (INIS)

    The world's attitude toward radionuclide contamination of foods suddenly changed on April 26, 1986. On that date the accident and fire at the nuclear reactor at the Chernobyl power station released a considerable amount of radioactive substances into the atmosphere. Radioactive particles were transported over Europe and Asia by air currents and eventually settled to earth to begin a new life as environmental contaminants. Widespread monitoring of radionuclide contamination of foods had been commonplace in the 1950's and 60's. However, since the cessation of above-ground testing of nuclear weapons in the 1960's there had been little public concern and consequently reduced monitoring of radionuclides in foods. As a result of the widespread fallout of radionuclides from Chernobyl, nations began intensive sampling and analysis efforts to determine the level and extent of the contamination. Food sampling and regular monitoring of radioactivity levels were activated by all the countries affected by the fallout and by countries importing food from affected areas

  9. Modeling of radionuclide migration through porous material with meshless method

    International Nuclear Information System (INIS)

    To assess the long term safety of a radioactive waste disposal system, mathematical models are used to describe groundwater flow, chemistry and potential radionuclide migration through geological formations. A number of processes need to be considered when predicting the movement of radionuclides through the geosphere. The most important input data are obtained from field measurements, which are not completely available for all regions of interest. For example, the hydraulic conductivity as an input parameter varies from place to place. In such cases geostatistical science offers a variety of spatial estimation procedures. Methods for solving the solute transport equation can also be classified as Eulerian, Lagrangian and mixed. The numerical solution of partial differential equations (PDE) is usually obtained by finite difference methods (FDM), finite element methods (FEM), or finite volume methods (FVM). Kansa introduced the concept of solving partial differential equations using radial basis functions (RBF) for hyperbolic, parabolic and elliptic PDEs. Our goal was to present a relatively new approach to the modelling of radionuclide migration through the geosphere using radial basis function methods in Eulerian and Lagrangian coordinates. Radionuclide concentrations will also be calculated in heterogeneous and partly heterogeneous 2D porous media. We compared the meshless method with the traditional finite difference scheme. (author)

  10. Ecological processes in the cycling of radionuclides within arctic ecosystems

    International Nuclear Information System (INIS)

    Worldwide fallout radionuclides in arctic ecosystems was investigated ecologically by circumpolar nations during 1959-80. Several of the radionuclides are isotopes of elements which currently contribute to arctic haze; they thus serve as effective tracers of biogeochemical processes. Investigations demonstrated the effective concentration of several radionuclides, particularly strontium-90 (an alkaline earth metal) and cesium-137 (a light alkali metal) which are chemical analogs of calcium and potassium, two very important stable elements in biotic systems. Transfer of 137Cs through the lichen-cariboureindeer-man food chain characteristic of circumpolar nations, resulted in body burdens in Inuit that were 20 to 200 times greater than those in human populations of temperature latitudes. Radiation exposures from 90Sr, 137Cs and other natural and worldwide fallout radionuclides, were two to three times greater than for most other world populations. These results demonstrate the concentration capabilities of arctic ecosystems for several groups of chemical elements that have counterparts in arctic haze. These elements, therefore, provide the basis for considering the ecological implications of current situations

  11. A study on the radionuclide transport by bacteria in geologic media

    International Nuclear Information System (INIS)

    The purpose of this paper is to provide a methodology to develop a predictive model based on a conceptual three phase system and to investigate the influence of bacteria and their generation on the transport of radionuclide in porous and fractured media. The mass balance for bacteria, substrate and radionuclide were formulated. To illustrate the model simply, an equilibrium condition was assumed to partition the substrate, bacteria and radionuclide concentrations between the solid soil matrix, aqueous phase, rock matrix and bacterial surface. From the numerical calculation of the radionuclide transport in the presence of bacteria, it was found that the growth of bacteria and supplied primary substrate as limiting or stimulating growth factor of bacteria are the most important factors of the radionuclide transport. We also found that, depend on the transport of bacteria the temporal and spatial distribution of radionuclide concentration was significantly altered. The model proposed in this study will improve the evaluation of the role of the bacteria in the transport of radionuclide in groundwater systems. Furthermore, this model would be usefully utilized in analyzing the important role of colloidal particulate on the overall performance of radioactive waste safety

  12. Radionuclides and the birds at Ravenglass.

    Science.gov (United States)

    Lowe, V P

    1991-01-01

    Since 1983, concern has been expressed about the apparent decline in numbers of birds in the Ravenglass estuary in west Cumbria, particularly of the black-headed gull colony on the Drigg dunes, and suggestions have been made that this decline might be due to excessive radiation in the birds' food and their general environment. Twelve species of marine invertebrates from Ravenglass, most of them known to be important foods for birds, were analysed, and further samples were taken from sites along the west Cumbrian coast. None of these samples showed excessive contamination with any of the radionuclides analysed. Analysis of a sample of bird carcasses from the areas showed oystercatchers (Haematopus ostralegus) and shelduck (Tadorna tadorna) to have some of the highest concentrations of (137)Cs in their tissues; yet their breeding success and populations were not affected. Black-headed gulls, on the other hand, were found to be feeding mainly inland, and were the least contaminated with radionuclides of all the birds at Ravenglass, yet this species and its breeding success were in decline. Calculations of the total dose equivalent rate to the whole body of the most contaminated black-headed gull amounted to 9.8 x 10(-4) mSvh(-1) (approximately equal to 8.4 x 10(-4) mGy h(-1), whole body absorbed dose rate), and the background exposure dose was of the order of 8.3 x 10(-4) mGy h(-1). As a minimum chronic dose of 1000 mGy day(-1) has been found necessary to retard growth of nestling birds, and 9600 mGy over 20 days of incubation to cause the death of 50% of embryos in black-headed gulls' eggs, the concentrations of radionuclides in the foods, body tissues and general environment were at least three orders of magnitude too low to have had any effect. The more likely cause of the desertion of the gullery was the combination of an uncontrolled fox population, the severest outbreak of myxomatosis amongst the rabbits since 1954 and the driest May-July period on record, all

  13. Radionuclide behavior at underground environment

    International Nuclear Information System (INIS)

    This study of radionuclide behavior at underground environment has been carried out as a part of the study of high-level waste disposal technology development. Therefore, the main objectives of this project are constructing a data-base and producing data for the safety assessment of a high-level radioactive waste, and verification of the objectivity of the assessment through characterization of the geochemical processes and experimental validation of the radionuclide migration. This project is composed of 6 subjects such as data production required for safety assessments, sorption properties and mechanisms, nuclide migration in the fractured rock, colloid formation and migration, nuclide speciation in deep geological environments, and total evaluation of geochemical behaviors considering multi-factors. The various results from the this project can be applicable to the preliminary safety and performance assessments of the established disposal concept for a future high-level radioactive waste repository. Providing required data and technical basis for assessment methodologies could be a direct application of the results. In a long-term view, the results can also be utilized as a technical background for the establishment of government policy for high-level radioactive waste disposal

  14. Infusion of radionuclides throughout pregnancy

    International Nuclear Information System (INIS)

    This work is part of a long-term study to examine the cancer incidence in the offspring of mice exposed to 239Pu or 147Pm throughout pregnancy. The need to model the human intake scenario and the possibility of a critical period during uterine development necessitates constant availability of radionuclides throughout pregnancy. Various methods (multiple daily injections, infusion by external cannula and infusion by indwelling osmotic pump) have been examined and osmotic infusion pumps chosen. These pumps result in a near-constant blood concentration for up to 21 days. Part of the study is the estimation of dose to the critical haemopoietic tissues of the pup from a knowledge of the radionuclide distribution and kinetics. At present the distribution has been followed from birth to 180 days. Activity in the suckling pups at 7 days old is around 1 percent of the infused activity, though most of this is accounted for by the contents of the stomach and gastrointestinal tract. The liver and femur account for around 0.025 percent and 0.012 percent respectively per pup. Activity increases in both liver and femur during lactation after which both concentration and activity fall with time. Long-term studies with the pups of dams exposed to a range of 239Pu concentrations between 0-70 kBq/kg are underway. Correlation of average organ dose with tumour incidence will be determined at completion of the life-span study. (Author) 39 refs., 5 tabs., 6 figs

  15. Challenge in determination of long-lived radionuclides by ICP-MS

    International Nuclear Information System (INIS)

    The ultra-trace and isotope analysis of long-lived radionuclides in environmental materials (in biological or geological samples and waters) is relevant of increasing importance [1-5].E.g., the determination of long-lived radionuclides is for the detection of radionuclide contamination in environmental materials in which several radioactive nuclides (e.g.99Tc, 129I , 237Np, 239Pu, 240Pu, 241Am) are present from fallout due to nuclear weapons testing, nuclear power plants or nuclear accidents. Especially, isotope ratios of uranium and plutonium [6] can indicate the origin of contamination in the environmental samples

  16. Radionuclide Geomicrobiology of the Deep Biosphere

    DEFF Research Database (Denmark)

    Anderson, Craig; Johnsson, Anna; Moll, Henry;

    2011-01-01

    This review summarizes research into interactions between microorganisms and radionuclides under conditions typical of a repository for high-level radioactive waste in deep hard rock environments at a depth of approximately 500 m. The cell-radionuclide interactions of strains of two bacterial spe...

  17. Technological radionuclides as landscape contamination source

    International Nuclear Information System (INIS)

    Morphology of radioactive spots on territory of the Valozhyn Region of Belarus has been considered. The reasons of tessellated distribution of such contamination were discussed. Tendencies and main mechanisms of secondary redistribution of radionuclides were shown. Features of radionuclides migration in various landscapes were described. Were proposed recommendations to reduce consequences of radioactive contamination for population and national economy. 9 refs

  18. Separation of radionuclides from electrochemical decontamination waste

    International Nuclear Information System (INIS)

    This study demonstrated the efficiency and applicability of a combined process for the separation of radionuclides from organic complexonates containing waste. A combination of photo-catalytic degradation of organic complexonates followed by the sorption of the radionuclides onto a strongly acidic ion exchanger offers a promising route for the treatment of the spent electrochemical decontamination solution. (authors)

  19. Critical comparison of radiometric and mass spectrometric methods for the determination of radionuclides in environmental, biological and nuclear waste samples

    OpenAIRE

    Hou, Xiaolin; Roos, Per

    2008-01-01

    The radiometric methods, alpha (alpha)-, beta (beta)-, gamma (gamma)-spectrometry, and mass spectrometric methods, inductively coupled plasma mass spectrometry, accelerator mass spectrometry, thermal ionization mass spectrometry resonance ionization mass spectrometry, secondary ion mass spectrometry, and glow discharge mass spectrometry are reviewed for the determination of radionuclides. These methods are critically compared for the determination of long-lived radionuclides important for rad...

  20. Hydrogeological interpretation of natural radionuclide contents in Austrian groundwaters

    Science.gov (United States)

    Schubert, Gerhard; Berka, Rudolf; Hörhan, Thomas; Katzlberger, Christian; Landstetter, Claudia; Philippitsch, Rudolf

    2010-05-01

    The Austrian Agency for Health and Food Safety (AGES) stores comprehensive data sets of radionuclide contents in Austrian groundwater. There are several analyses concerning Rn-222, Ra-226, gross alpha and gross beta as well as selected analyses of Ra-228, Pb-210, Po-210, Uranium and U-234/U-238. In a current project financed by the Austrian Federal Ministry of Agriculture, Forestry, Environment and Water Management, AGES and the Geological Survey of Austria (GBA) are evaluating these data sets with regard to the geological backgrounds. Several similar studies based on groundwater monitoring have been made in the USA (for instance by Focazio, M.J., Szabo, Z., Kraemer, T.F., Mullin, A.H., Barringer, T.H., De Paul, V.T. (2001): Occurrence of selected radionuclides in groundwater used for drinking water in the United States: a reconnaissance survey, 1998. U.S. Geological Survey Water-Resources Investigations Report 00-4273). The geological background for the radionuclide contents of groundwater will be derived from geological maps in combination with existing Thorium and Uranium analyses of the country rocks and stream-sediments and from airborne radiometric maps. Airborne radiometric data could contribute to identify potential radionuclide hot spot areas as only airborne radiometric mapping could provide countrywide Thorium and Uranium data coverage in high resolution. The project will also focus on the habit of the sampled wells and springs and the hydrological situation during the sampling as these factors can have an important influence on the Radon content of the sampled groundwater (Schubert, G., Alletsgruber, I., Finger, F., Gasser, V., Hobiger, G. and Lettner, H. (2010): Radon im Grundwasser des Mühlviertels (Oberösterreich) Grundwasser. - Springer (in print). Based on the project results an overview map (1:500,000) concerning the radionuclide potential should be produced. The first version should be available in February 2011.

  1. Radionuclide Transport in Fracture-Granite Interface Zones

    Energy Technology Data Exchange (ETDEWEB)

    Hu, Q; Mori, A

    2007-09-12

    In situ radionuclide migration experiments, followed by excavation and sample characterization, were conducted in a water-conducting shear zone at the Grimsel Test Site (GTS) in Switzerland to study diffusion paths of radionuclides in fractured granite. In this work, we employed a micro-scale mapping technique that interfaces laser ablation sampling with inductively coupled plasma-mass spectrometry (LA/ICP-MS) to measure the fine-scale (micron-range) distribution of actinides ({sup 234}U, {sup 235}U, and {sup 237}Np) in the fracture-granite interface zones. Long-lived {sup 234}U, {sup 235}U, and {sup 237}Np were detected in flow channels, as well as in the adjacent rock matrix, using the sensitive, feature-based mapping of the LA/ICP-MS technique. The injected sorbing actinides are mainly located within the advective flowing fractures and the immediately adjacent regions. The water-conducting fracture studied in this work is bounded on one side by mylonite and the other by granitic matrix regions. These actinides did not penetrate into the mylonite side as much as the relatively higher-porosity granite matrix, most likely due to the low porosity, hydraulic conductivity, and diffusivity of the fracture wall (a thickness of about 0.4 mm separates the mylonite region from the fracture) and the mylonite region itself. Overall, the maximum penetration depth detected with this technique for the more diffusive {sup 237}Np over the field experimental time scale of about 60 days was about 10 mm in the granitic matrix, illustrating the importance of matrix diffusion in retarding radionuclide transport from the advective fractures. Laboratory tests and numerical modeling of radionuclide diffusion into granitic matrix was conducted to complement and help interpret the field results. Measured apparent diffusivity of multiple tracers in granite provided consistent predictions for radionuclide transport in the fractured granitic rock.

  2. Influence of variety variations of eastern galega on radionuclides accumulation

    International Nuclear Information System (INIS)

    The general characteristic of development of agricultural branch in conditions of radioactive pollution of territory of Belarus is analyzed. The urgency of problem of reception of corresponding to norm pure from radionuclides production of plant growing and animal industries is marked. The scientific substantiation of the factors influencing on behaviour of radionuclides in soil, their transition from soil into plants and an organism of the person through foodder and food biological circuits is given. Biological features of eastern galega, its value in feed production, plant growing, efficiency of cultivation in the polluted territories. Factors of transition of 137-caesium and 90-strontium are presented to plants at variety samples of eastern galega of the first and second years of life, in a crop of green weight from the first and second hay crops are presented. Distinctions in accumulation by green weight of eastern galega and trifolium pratense are shown. In comparison with trifolium pratense eastern galega in 2 times accumulates 90-strontium less than 2 times. Varieties distinctions influenced on accumulation of radionuclides from soil in plants by eastern galega. Authentically less than others variety sample BSAA-1 accumulates radionuclides in plants at which the factor of transition had the lowest parameter and has made on 137-caesium 0,109, on 90-strontium 2,29, or accordingly on 0,027 and 0,25 below, than at standard variety Nesterka. Studying of variety samples of eastern galega on a degree of accumulation of radionuclides at cultivation on a provocative background with radioactive soil pollution is the important factor of increase in efficiency of selection radiophobia varieties

  3. Mobility and Bioavailability of Radionuclides in Soils

    International Nuclear Information System (INIS)

    It is crucial to understand the behavior of radionuclides in the environment, their potential mobility and bioavailability related to long-term persistence, radiological hazards, and impact on human health. Such key information is used to develop strategies that support policy decisions. The environmental behavior of radionuclides depends on ecosystem characteristics. A given soil’s capacity to immobilize radionuclides has been proved to be the main factor responsible for their resulting activity concentrations in plants. The mobility and bioavailability of radionuclides in soils is complex, depending on clay-sized soil fraction, clay mineralogy, organic matter, cation exchange capacity, pH and quantities of competing cations. Moreover, plant species have different behaviors regarding radionuclide absorption depending on soil and plan characteristics

  4. Modelling seasonal variations of natural radionuclides in agricultural soils

    OpenAIRE

    Guagliardi I.; Buttafuoco G; Ricca N.; Cipriani M. G.; Civitelli D.; Froio R.; Gabriele A. L.; De, Rosa R.

    2013-01-01

    Estimating activity of natural radionuclides in agricultural soil is very important for the protection of public health because the released radioactivity can enter the food chain. Radioactivity measurements were carried out in two different dates (winter and summer) in agricultural soil using a GRM-260 gamma-ray spectrometer. The study area (100 m x 100 m) was an olive orchard in southern Italy. Measurements were carried out at 361 locations in January and July 2011. At the same locations, s...

  5. Radionuclide imaging of spinal infections

    Energy Technology Data Exchange (ETDEWEB)

    Gemmel, Filip [Ghent Maria-Middelares, General Hospital, Division of Nuclear Medicine, Ghent (Belgium); Medical Center Leeuwarden (MCL), Division of Nuclear Medicine, Henri Dunantweg 2, Postbus 888, Leeuwarden (Netherlands); Dumarey, Nicolas [Universite Libre de Bruxelles, Hopital Erasme, Division of Nuclear Medicine, Brussels (Belgium); Palestro, Christopher J. [Long Island Jewish Medical Center, Division of Nuclear Medicine, Long Island, NY (United States)

    2006-10-15

    The diagnosis of spinal infection, with or without implants, has been a challenge for physicians for many years. Spinal infections are now being recognised more frequently, owing to aging of the population and the increasing use of spinal-fusion surgery. The diagnosis in many cases is delayed, and this may result in permanent neurological damage or even death. Laboratory evidence of infection is variable. Conventional radiography and radionuclide bone imaging lack both sensitivity and specificity. Neither in vitro labelled leucocyte scintigraphy nor {sup 99m}Tc-anti-granulocyte antibody scintigraphy is especially useful, because of the frequency with which spinal infection presents as a non-specific photopenic area on these tests. Sequential bone/gallium imaging and {sup 67}Ga-SPECT are currently the radionuclide procedures of choice for spinal osteomyelitis, but these tests lack specificity, suffer from poor spatial resolution and require several days to complete. [{sup 18}F]Fluoro-2-deoxy-D-glucose (FDG) PET is a promising technique for diagnosing spinal infection, and has several potential advantages over conventional radionuclide tests. The study is sensitive and is completed in a single session, and image quality is superior to that obtained with single-photon emitting tracers. The specificity of FDG-PET may also be superior to that of conventional tracers because degenerative bone disease and fractures usually do not produce intense FDG uptake; moreover, spinal implants do not affect FDG imaging. However, FDG-PET images have to be read with caution in patients with instrumented spinal-fusion surgery since non-specific accumulation of FDG around the fusion material is not uncommon. In the future, PET-CT will likely provide more precise localisation of abnormalities. FDG-PET may prove to be useful for monitoring response to treatment in patients with spinal osteomyelitis. Other tracers for diagnosing spinal osteomyelitis are also under investigation, including

  6. Radionuclide interactions with marine sediments

    International Nuclear Information System (INIS)

    A critical review of the literature on the subject of the interactions of radionuclides with marine sediments has been carried out. On the basis of the information available, an attempt has been made to give ranges and 'best estimates' for the distribution ratios between seawater and sediments. These estimates have been based on an understanding of the sediment seawater system and the porewater chemistry and mineralogy. Field measurements, laboratory measurements and estimates based on stable-element geochemical data are all taken into account. Laboratory measurements include distribution-ratio and diffusion-coefficient determinations. The elements reviewed are carbon, chlorine, calcium, nickel, selenium, strontium, zirconium, niobium, technetium, tin, iodine, caesium, lead, radium, actinium, thorium, protactinium, uranium, neptunium, plutonium, americium and curium. (author)

  7. Radionuclides in surface and groundwater

    Science.gov (United States)

    Campbell, Kate M.

    2009-01-01

    Unique among all the contaminants that adversely affect surface and water quality, radioactive compounds pose a double threat from both toxicity and damaging radiation. The extreme energy potential of many of these materials makes them both useful and toxic. The unique properties of radioactive materials make them invaluable for medical, weapons, and energy applications. However, mining, production, use, and disposal of these compounds provide potential pathways for their release into the environment, posing a risk to both humans and wildlife. This chapter discusses the sources, uses, and regulation of radioactive compounds in the United States, biogeochemical processes that control mobility in the environment, examples of radionuclide contamination, and current work related to contaminated site remediation.

  8. Radionuclide Transport in Tuff and Carbonate Fractures from Yucca Flat, Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    Zavarin, M; Johnson, M R; Roberts, S K; Pletcher, R; Rose, T P; Kersting, A B; Eaton, G; Hu, Q; Ramon, E; Walensky, J; Zhao, P

    2006-02-01

    In the Yucca Flat basin of the Nevada Test Site (NTS), 747 shaft and tunnel nuclear detonations were conducted primarily within the tuff confining unit (TCU) or the overlying alluvium. The TCU in the Yucca Flat basin is hypothesized to reduce radionuclide migration to the regional carbonate aquifer (lower carbonate aquifer) due to its wide-spread aerial extent and chemical reactivity. However, shortcuts through the TCU by way of fractures may provide a migration path for radionuclides to the lower carbonate aquifer (LCA). It is, therefore, imperative to understand how radionuclides migrate or are retarded in TCU fractures. Furthermore, understanding the migration behavior of radionuclides once they reach the fractured LCA is important for predicting contaminant transport within the regional aquifer. The work presented in this report includes: (1) information on the radionuclide reactive transport through Yucca Flat TCU fractures (likely to be the primary conduit to the LCA), (2) information on the reactive transport of radionuclides through LCA fractures and (3) data needed to calibrate the fracture flow conceptualization of predictive models. The predictive models are used to define the extent of contamination for the Underground Test Area (UGTA) project. Because of the complex nature of reactive transport in fractures, a stepwise approach to identifying mechanisms controlling radionuclide transport was used. In the first set of TCU experiments, radionuclide transport through simple synthetic parallel-plate fractured tuff cores was examined. In the second, naturally fractured TCU cores were used. For the fractured LCA experiments, both parallel-plate and rough-walled fracture transport experiments were conducted to evaluate how fracture topography affects radionuclide transport. Tuff cores were prepared from archived UE-7az and UE-7ba core obtained from the USGS core library, Mercury, Nevada. Carbonate cores were prepared from archived ER-6-1 core, also obtained

  9. The influence of the unsaturated zone on the upward transport of radionuclides in soils

    International Nuclear Information System (INIS)

    The transport of radionuclides from the deep soil to the surface soil is an important part of biosphere modelling. In this study the effect of transient hydrological conditions on the upward transport of radionuclides through soils has been studied. The effect of varying soil properties, climate conditions have been considered as well as the effect of a fluctuating groundwater level. It was shown that the soil characteristics influences the radionuclide concentration; an increased hydraulic conductivity leads to increase in the concentration in the root zone. The climate conditions were shown to be of major importance. A dispersion dependent on both velocity and saturation leads to a more effective upward transport of radionuclides to the root zone than if dispersion is assumed to be dependent only on the saturation. The boundary condition used in the case with varying groundwater level may be more realistic than the boundary condition applied for the case with a constant groundwater level. All calculations with varying groundwater level gave lower radionuclide concentration in the root zone. Sorption is redox sensitive for many radionuclides and the redox potential in the soil will be affected by the degree of water saturation. The performed calculations did, however, not result in any significant change in the radionuclide concentration in the root zone due to variation in sorption. A comparison between the results of the two models show that the compartment model in all studied cases predicts a higher annual average radionuclide concentration in the root zone than the numerical model. Annual variation in soil water flow were not included in the compartment model. During the summer the concentration in the root zone may be several times higher than the annual average. This may be important for plant uptake, since this increased concentrations coincides with the plant growing season. The calculations made with the simple compartment model also show that these

  10. Human dose pathways of radionuclides in forests

    International Nuclear Information System (INIS)

    Forest soil, understorey vegetation and trees are all sources of radionuclides and human radiation doses after contaminating atmospheric deposition. People are exposed to radiation externally from sources outside the body and internally via ingestion and inhalation of radionuclides. Understorey vegetation contributes to ingestion doses through berries, herbs, wild honey, mushrooms and game meat; also trees provide feed to terrestrial birds and big game. During stay in forests people are subject to external radiation from forest floor and overstorey, and they may inhale airborne radioactive aerosol or gaseous radionuclides in ground level air. In the early phase of contamination also resuspended radionuclides may add to the internal dose of people via inhalation. People in Nordic countries are most exposed to radiation via ingestion of radionuclides in wild foods. The distribution of radionuclides in forests is changed by environmental processes, and thereby also the significance of various dose pathways to humans will change with time. External exposure is received in living environment from contaminated stemwood used as building timber and for manufacturing of furniture and other wood products. The aim of this paper is to outline the significance of various human dose pathways of radionuclides in forests considering the public and workers in forestry and production of bioenergy. Examples on effective doses are given based on two historical events, atmospheric nuclear weapon tests (mostly in 1950's and in 1960's) and the Chernobyl nuclear power plant accident in 1986. (au)

  11. Measured radionuclide production from copper, gold and lead spallation targets

    International Nuclear Information System (INIS)

    Spallation target materials are chosen so as to produce large numbers of neutrons while at the same time avoiding the creation of long-lived radioactive wastes. While there has been considerable research to determine the number of neutrons produced per incident particle for various target materials, there has been less effort to precisely quantify the types and amounts of radionuclides produced. Accurate knowledge of the radioactive species produced by spallation reactions is important for specifying waste disposal criteria for targets. In order to verify the production rates calculated by LAHET, a study has been conducted using the Texas A ampersand M University (TAMU) Cyclotron to measure radionuclide yields from copper, gold, and lead targets

  12. Predicting exposure of wildlife in radionuclide contaminated wetland ecosystems.

    Science.gov (United States)

    Stark, K; Andersson, P; Beresford, N A; Yankovich, T L; Wood, M D; Johansen, M P; Vives i Batlle, J; Twining, J; Keum, D-K; Bollhöfer, A; Doering, C; Ryan, B; Grzechnik, M; Vandenhove, H

    2015-01-01

    Many wetlands support high biodiversity and are protected sites, but some are contaminated with radionuclides from routine or accidental releases from nuclear facilities. This radiation exposure needs to be assessed to demonstrate radiological protection of the environment. Existing biota dose models cover generic terrestrial, freshwater, and marine ecosystems, not wetlands specifically. This paper, which was produced under IAEA's Environmental Modelling for Radiation Safety (EMRAS) II programme, describes an evaluation of how models can be applied to radionuclide contaminated wetlands. Participants used combinations of aquatic and terrestrial model parameters to assess exposure. Results show the importance of occupancy factor and food source (aquatic or terrestrial) included. The influence of soil saturation conditions on external dose rates is also apparent. In general, terrestrial parameters provided acceptable predictions for wetland organisms. However, occasionally predictions varied by three orders of magnitude between assessors. Possible further developments for biota dose models and research needs are identified. PMID:25463715

  13. Modelling seasonal variations of natural radionuclides in agricultural soils

    Directory of Open Access Journals (Sweden)

    Guagliardi I.

    2013-04-01

    Full Text Available Estimating activity of natural radionuclides in agricultural soil is very important for the protection of public health because the released radioactivity can enter the food chain. Radioactivity measurements were carried out in two different dates (winter and summer in agricultural soil using a GRM-260 gamma-ray spectrometer. The study area (100 m x 100 m was an olive orchard in southern Italy. Measurements were carried out at 361 locations in January and July 2011. At the same locations, soil water content was measured to take into account the effect of soil moisture on radioactivity. A multi-Gaussian approach was used to explore and map the activity of naturally occurring radionuclides and soil water content for both seasons of measurements. The minimum radioactivity values were recorded in winter and the maximum values in summer, probably as a consequence of changes in weather and soil conditions (rainfall, soil moisture, temperature.

  14. Factors that affect the association of radionuclides with soil phases

    International Nuclear Information System (INIS)

    The use of field experiments to investigate the chemical or physical associations of some radionuclides with soil phases is limited by low levels of activity and complicated by the number of phases involved. Sequential extraction procedures provide one means of evaluating the relative importance of various phases in disposition. Although the separation steps may not be absolutely selective, these schemes can be used in a comparative manner to rationalise changes in association and disposition that can occur as soil conditions alter. In this way they can give a direction for specific laboratory studies and be of value in the prediction of the consequences of land contamination - an important aspect of radiological protection. In this paper the authors draw upon field and laboratory studies of the disposition of artificial radionuclides to illustrate the effects of changes in, for example, iron or organic content. The variety of soil types that are amenable to field studies is restricted. Complementary laboratory experiments are therefore essential. Results show that the generalisations often applied to radionuclide availability are not always approximate and that although predictions of disposition can sometimes be made on the basis of gross soil characteristics, this capability is limited and a more rigorous approach is desirable in extreme cases. The specificity of the extraction procedure is discussed and evidence is presented to support the participation of the residual phase which was previously observed in field studies of plutonium and americium

  15. TRANSPORT OF RADIONUCLIDES ALONG MARINE FOODCHAIN

    Institute of Scientific and Technical Information of China (English)

    吴国斌; 余君岳; 等

    1995-01-01

    A compartment model is employed to calculate the radionuclide concentrations in the ocean currents for a nuclear accient scenario where the long-lived 137 Cs is totally discharged into the sea.The radionuclide concentrations in both the waters of Daya Bay and the adjacent south China Sea are considered.Using the concentration factors for the marine organisms:fish,crustacea and mollusca,their radionuclide concentrations are also estimated.In this way,the whole body radiation doses received by an individual due to ingestion of marine organisms from the Daya Bay and the South China Sea are calculated.

  16. DNA damage induced by radionuclide internal irradiation

    International Nuclear Information System (INIS)

    Objective: To study the DNA damage of peripheral blood mononuclear cell (PBMC) in rats exposed to radionuclide internal irradiation. Methods: The radionuclides were injected into the rats and single cell get electrophoresis (SCGE) was performed to detect the length of DNA migration in the rat PBMC. Results: DNA migration in the rat PBMC increased with accumulative dose or dose-rate. It showed good relationship of dose vs. response and of dose-rate vs. response, both relationship could be described as linear models. Conclusion: Radionuclide internal irradiation could cause DNA damage in rat PBMC. (authors)

  17. 2010 LANL radionuclide air emissions report /

    Energy Technology Data Exchange (ETDEWEB)

    Fuehne, David P.

    2011-06-01

    The emissions of radionuclides from Department of Energy Facilities such as Los Alamos National Laboratory (LANL) are regulated by the Amendments to the Clean Air Act of 1990, National Emissions Standards for Hazardous Air Pollutants (40 CFR 61 Subpart H). These regulations established an annual dose limit of 10 mrem to the maximally exposed member of the public attributable to emissions of radionuclides. This document describes the emissions of radionuclides from LANL and the dose calculations resulting from these emissions for calendar year 2010. This report meets the reporting requirements established in the regulations.

  18. 2008 LANL radionuclide air emissions report

    Energy Technology Data Exchange (ETDEWEB)

    Fuehne, David P.

    2009-06-01

    The emissions of radionuclides from Department of Energy Facilities such as Los Alamos National Laboratory (LANL) are regulated by the Amendments to the Clean Air Act of 1990, National Emissions Standards for Hazardous Air Pollutants (40 CFR 61 Subpart H). These regulations established an annual dose limit of 10 mrem to the maximally exposed member of the public attributable to emissions of radionuclides. This document describes the emissions of radionuclides from LANL and the dose calculations resulting from these emissions for calendar year 2008. This report meets the reporting requirements established in the regulations.

  19. 2009 LANL radionuclide air emissions report

    Energy Technology Data Exchange (ETDEWEB)

    Fuehne, David P.

    2010-06-01

    The emissions of radionuclides from Department of Energy Facilities such as Los Alamos National Laboratory (LANL) are regulated by the Amendments to the Clean Air Act of 1990, National Emissions Standards for Hazardous Air Pollutants (40 CFR 61 Subpart H). These regulations established an annual dose limit of 10 mrem to the maximally exposed member of the public attributable to emissions of radionuclides. This document describes the emissions of radionuclides from LANL and the dose calculations resulting from these emissions for calendar year 2009. This report meets the reporting requirements established in the regulations.

  20. Radionuclides accumulation in the lake Drukshiai hydrophytes

    International Nuclear Information System (INIS)

    Investigations carried out in 1988-1993 in lake Drukshiai and by the model experiments allow to maintain that peculiarities of biological radionuclides migration in the lake ecosystem could be conditioned by following factors: the Ignalina NPP sewerage waste waters, containing chemical compounds increasing accumulation of radionuclides, of ionic form or inclined to hydrolysis (especially of corrosive origin), in the hydrophytes. Processes of eutrophication due to thermal and chemical contamination, because increasing volume of organic matter decrease the accumulation of inclined to hydrolysis radionuclides, especially of corrosive origin, in the hydrophytes. (author). 8 refs., 8 tabs

  1. Release of Radionuclides from spent fuel under repository conditions: mathematical modelling and preliminary results

    International Nuclear Information System (INIS)

    In the framework of the Enresa 2000 PA exercise and as a continuation of the developments made during SR 97, we have developed a conceptual and numerical model to calculate the release of radionuclides from spent fuel under repository conditions. The model includes both thermodynamic and kinetic considerations. Hence, although certain radionuclides are solubility controlled, for other radionuclides their release is governed by kinetic processes such as radiolytically promoted oxidative dissolution of the matrix and the associated water turnover in the gap. The fluxes of selected radionuclides are calculated as an indication of the relative importance of the various processes considered to define source term concentrations in the performance assessment of the spent fuel repository. Copyright (2001) Material Research Society

  2. Natural colloids in groundwater from granite and their potential impact on radionuclide transport

    International Nuclear Information System (INIS)

    AECL Research is assessing the concept of nuclear fuel waste disposal in an engineered vault at a depth of 500 to 1000 m in plutonic rock of the Canadian Shield and submitted an Environmental Impact Statement to the Canadian Environmental Agency for review. Radionuclide transport in groundwater is the only likely path for radionuclide migration to the biosphere through the mass of rock surrounding a disposal vault. To evaluate the potential impact of natural particles on radionuclide migration it is necessary to determine the range of particle concentrations in ground water, which is a measure of their sorption capacity for radionuclides. An understanding of particle formation, stability and size distribution is important for predicting migration properties. This paper discusses the sampling and characterization of groundwater particles from the Whiteshell Research Area (WRA) and provides information on particle size, concentration, and composition. The significance of radiocolloid formation with colloids in groundwater from granite is also discussed

  3. Radionuclides in fruit systems: Model-model intercomparison study

    International Nuclear Information System (INIS)

    Modeling is widely used to predict radionuclide distribution following accidental radionuclide releases. Modeling is crucial in emergency response planning and risk communication, and understanding model uncertainty is important not only in conducting analysis consistent with current regulatory guidance, but also in gaining stakeholder and decision-maker trust in the process and confidence in the results. However, while methods for dealing with parameter uncertainty are fairly well developed, an adequate representation of uncertainties associated with models remains rare. This paper addresses uncertainty about a model's structure (i.e., the relevance of simplifying assumptions and mathematical equations) that is seldom addressed in practical applications of environmental modeling. The use of several alternative models to derive a range of model outputs or risks is probably the only available technique to assess consistency in model prediction. Since each independent model requires significant resources for development and calibration, multiple models are not generally applied to the same problem. This study uses results from one such model intercomparison conducted by the Fruits Working Group, which was created under the International Atomic Energy Agency (IAEA) BIOMASS (BIOsphere Modelling and ASSessment) Program. Model-model intercomparisons presented in this study were conducted by the working group for two different scenarios (acute or continuous deposition), one radionuclide (137Cs), and three fruit-bearing crops (strawberries, apples, and blackcurrants). The differences between models were as great as five orders of magnitude for short-term predictions following acute radionuclide deposition. For long-term predictions and for the continuous deposition scenario, the differences between models were about two orders of magnitude. The difference between strawberry, apple, and blackcurrant contamination predicted by one model is far less than the difference in

  4. Isolation of Cu radionuclides with dithizone impregnated XAD-8

    Energy Technology Data Exchange (ETDEWEB)

    Dolley, S.G. [Cape Peninsula Univ. of Technology, Bellville (South Africa). Dept. of Chemistry; Walt, T.N. van der [Cape Peninsula Univ. of Technology, Bellville (South Africa). Dept. of Chemistry; National Research Foundation, Somerset West (South Africa). iThemba LABS

    2014-04-01

    A novel separation method for Cu radionuclides from proton bombardment of {sup nat}Zn is presented. A solid phase extraction procedure using a modified dithizone (diphenylthiocarbazone) XAD-8 chelating resin was used for the purification of the Cu radionuclides from up to 5 g of {sup nat}Zn and other radionuclides. More than 95% of the Cu radionuclides was recovered. (orig.)

  5. Transfer of radionuclides into human milk

    International Nuclear Information System (INIS)

    Up until now the potential radiation exposure to breast-fed babies due to contaminated human milk has not been taken into account, when deriving international limit values and reference levels for radionuclides in foodstuffs, in air at monitored work places or for exposures in the medical field. It was the aim of the research project 'Transfer of radionuclides into human milk' to quantify the transfer of incorporated radionuclides into mother's milk, and develop simple models to estimate the radiation exposure of babies through the ingestion of human milk. The study focused on considerations of the radiation exposure due to the ingestion of contaminated foodstuffs by the mother, the inhalation of radionuclides at monitored work places, and the administration of radiopharmaceuticals to breast-feeding mothers. The blocking of infant thyroid glands by stable iodine in the case of accidental releases of radioiodine was considered as well. (orig.)

  6. Radiation safety requirements for radionuclide laboratories

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The guide lays down the requirements for laboratories and storage rooms in which radioactive substances are used or stored as unsealed sources. In addition, some general instructions concerning work in radionuclide laboratories are set out.

  7. Long lived gamma emitting radionuclides in incense.

    Science.gov (United States)

    Alrefae, Tareq

    2013-10-01

    A study of long-lived gamma emitters in incense was performed. The incense samples originated from seven different countries, and the investigated radionuclides were Ra, Ra, and K. Gamma spectroscopy revealed the presence of all three investigated radionuclides in all samples. Interestingly, the activity concentrations revealed a clear bimodal distribution that distinguished samples that were natural incense from others that were processed incense. The activity concentrations in the latter group were found to be one order of magnitude greater than in the former group. Consequently, the estimated annual effective dose from the latter group was one order of magnitude higher than that of the former group. Nonetheless, the doses from both groups were found to be some three orders of magnitude less than the average worldwide exposure to inhaled natural radionuclides. This finding suggests the radiological safety of incense for the investigated radionuclides.

  8. Application of radionuclides in nuclear technology

    International Nuclear Information System (INIS)

    Four main applications of radionuclides in nuclear technology are presented which are level-, density- and thickness gauging and moisture determination. Each method is surveyed for its general principle, various designs, accuracy, errors and practical designs. (Author)

  9. Gut-related radionuclide studies

    International Nuclear Information System (INIS)

    This project is concerned with the behavior of radioactive materials that may be ingested as a consequence of a reactor accident, unavoidable occupational exposure, or after release to the environment and incorporation into the food chain. Current emphasis is directed toward evaluating hazards from ingested actinides as a function of animal age, species, nutrition, and diet, or chemicophysical state of the actinide. Recent observations indicate that the influence of chemical form on plutonium absorption observed at high mass levels does not occur at low mass concentrations. For example, at doses of 0.6 μg/kg there was no difference between absorption of the carbonate, citrate or nitrate forms of plutonium. However, at 1.5 mg/kg, the citrate was absorbed in quantities 30 times higher than the nitrate. The opposite effect occurred for neptunium GI absorption. Furthermore, it was demonstrated that materials such as citrus fruit juices and calcium, as well as drugs that affect GI function (such as aspirin and DTPA), markedly influence GI absorption of plutonium. Such studies provide evidence that diet and nutritional state should be considered in establishing safe limits for radionuclides that may be ingested

  10. The uptake of radionuclides by plants

    International Nuclear Information System (INIS)

    A review of the literature, since 1970, on the research into the uptake of radionuclides by plants, with references to earlier soil and plant studies on the fate of nuclear weapons fallout. Experimental data on the uptake of plutonium isotopes, americium 241, cesium 137, radium 226, curium 244 and neptunium 237 and details of the chemical form of the radionuclide, soil type and plant growth period are tabulated. (U.K.)

  11. Valuation of radionuclides using radioecological models

    International Nuclear Information System (INIS)

    The evaluation of the radiation exposure of the public following an accidental release of radionuclides into the atmosphere by means of radioecological models is shown. The radiation exposure after the Chernobyl-accident is used as an example to demonstrate the identification of the relevant radionuclides and exposure pathways. The natural radiation exposure is given as a means for the valuation of the calculated radiation exposures. (orig.)

  12. Alchemy with short-lived radionuclides

    International Nuclear Information System (INIS)

    A variety of short-lived radionuclides are produced and subsequently incorporated into radiopharmaceutical compounds in the radionuclide production program currently being conducted at the Cyclotron Facility of Mount Sinai Medical Center. The recovery of high specific activity oxygen-15 labelled water prepared by means of an inexpensive system operating in conjunction with an on-line radiogas target routinely utilized for oxygen-15 labelled carbon dioxide studies is currently receiving particular attention

  13. Model of the long-term transfer of radionuclides in forests

    Energy Technology Data Exchange (ETDEWEB)

    Avila, Rodolfo [Facilia AB, Bromma (Sweden)

    2006-05-15

    This report describes a model of the long-term behaviour in temperate and boreal forests of radionuclides entering the ecosystem with subsurface water. The model can be applied for most radionuclides that are of relevance in safety assessment of repositories for high-level radioactive waste. The model can be used for estimating radionuclide concentrations in soil, trees, understorey plants, mushrooms and forest mammals. A recommended (nominal) value and an interval of variation are provided for each model parameter and a classification of parameters by the degree of confidence in the values is given. Model testing against existing empirical data showing satisfactory results is also presented. Forests can play an important role in the spatial and temporal distribution of radionuclides in the environment. Despite of this, forest ecosystems have not been addressed in previous safety assessments. This can be explained by the fact that a suitable model of the long-term transfer of a wide range of radionuclides in forests has not been readily available. The objective of this work was to develop a forest model applicable for a wide range of radionuclides of relevance for high level radioactive waste management (Am-241, Cl-36, Cs-135, I-129, Ni-59, Np-237, Pu-239, Ra-226, Sr-90, Tc-99, Th-232, U-238) that can potentially enter the ecosystem with contaminated groundwater. The model assumes that biomass growth, precipitation and evapo-transpiration drive the radionuclide cycling in the system by influencing the uptake of radionuclides by vegetation and their export from the system via runoff. The mathematical model of radionuclide transfer consists of a system of ordinary differential describing the mass balance in different forest compartments, taking into account the fluxes in and out from the compartment and the radionuclides decay. The fluxes between compartments are calculated by multiplying a transfer coefficient (TC) by the radionuclide inventory in the compartment

  14. Inventories of selected radionuclides in the oceans

    International Nuclear Information System (INIS)

    In March 1984 an ad hoc Review Committee composed of senior experts in the marine radioactivity field made recommendations that ''the Monaco Laboratory should be engaged in compiling and evaluating the input of radionuclides into the marine environment''. The Committee recommended that work should commence on selected radionuclides, viz., 14C, caesium isotopes, plutonium isotopes, 210Po and 210Pb followed by 226Ra. Depending on the radionuclides involved the assistance of competent experts from outside as well as inside the IAEA was sought. The present document is a product of the work carried out within the framework of the above-mentioned task and contains reports on 14C, 90Sr, 137Cs, 238Pu, 239+240Pu, 210Pb, 210Po and 226Ra. Although the estimation of the inventory in the marine environment and related input and output fluxes, is the same for all radionuclides concerned, different approaches were followed to achieve this objective. These approaches depended on the geochemical characteristics of the radionuclides and the availability of data for different times and locations. For regions where data were lacking, extrapolation on the basis of specific assumptions has often been necessary. As the work was initiated during the pre-Chernobyl period, the radionuclides derived from the Chernobyl incident were not, in general, considered. Since the work for preparing the forthcoming report of the UNSCEAR is scheduled to be completed by 1991, it is hoped that the information contained in this volume will be beneficial. Refs, figs and tabs

  15. Vertical distribution of natural radionuclides in soils

    Directory of Open Access Journals (Sweden)

    Lozano J. C.

    2012-04-01

    Full Text Available Low-level alpha spectrometry techniques using semiconductor detectors (PIPS and liquid scintillation counters (LKB Quantulus 1220™ were used in order to determine the activity concentration of 238U, 232Th, 234U, 230Th, 226Ra, and 210Pb in soil samples. The soils were collected from an old disused uranium mine located in southwest Spain. The soils were selected with different levels of influence from the installation, in such a way that they had different levels of radioactive contamination. The vertical profiles in the soils (down to 40 cm depth were studied in order to evaluate the vertical distribution of the natural radionuclides. The possible contamination of subsurface waters depends strongly on vertical migration, and the transfer to plants (herbs, shrubs, and trees also will depend on the distribution of the radionuclides in the root zone. The study of the activity ratios between radionuclides belonging to the same series allowed us to assess the differing behaviour of the radionuclides involved. The vertical profiles for these radionuclides were different at each sampling point, showing the local impact of the installation. However, the profiles per point were similar for the long-lived radionuclides of the 238TJ series (238U, 234U, 230Th, and 226Ra. Also, a major disequilibrium was observed between 210Pb and 226Ra in the surface layer, due to 222Rn emanation and subsequent surface deposition of 210Pb.

  16. Radionuclide sorption from the safety evaluation perspective

    International Nuclear Information System (INIS)

    Research and development directed towards the assessment of the long-term performance of radioactive waste disposal systems has been recognised as a priority area with a strong need for international co-operation and co-ordination. The ultimate aims is to promote the quality and credibility of safety assessment techniques for radioactive waste disposal. Sorption in the geosphere is one of the key processes for retarding the transport of radionuclide from the underground disposal facility to the biosphere. In many cases, sorption in the near field and in the biosphere is also important. A workshop, organised to favor discussion around a small number of invited papers, was held in October 1991: - to evaluate critically the way sorption processes are incorporated in performance assessment models; - to identify open issues of high priority, and; - to propose future activities to resolve these issues. These proceedings reproduce the invited papers and the conclusions and recommendations adopted by the workshop. Eight papers are in the INIS SCOPE. The main subjects studied are: sorption database comparison, sorption database development and three case studies, experimental techniques, adsorption models

  17. Improving cancer treatment with cyclotron produced radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Larson, S.M.; Finn, R.D.

    1992-08-04

    Our goal is to improve the scientific basis for tumor diagnosis, treatment and treatment follow-up based on the use of cyclotron produced radiotracers in oncology. The grant includes 3 interactive components: Radiochemistry/Cyclotron; Pharmacology; and Immunology. The radiochemistry group seeks to develop innovative cyclotron targetry, radiopharmaceuticals, and radiolabeled antibodies, which are then used to assess important unanswered questions in tumor pharmacology and immunology. Examples include selected positron emitting radionuclides, such as Iodine-124, and Ga-66; I-124, I-123, I-131 labeled iododeoxyuridine, C-11 colchicine, and antimetabolites, like C-11 methotrexate; and radiolabeled antibodies, 3F8, M195, A33, and MRK16 for application in the pharmacology and immunology projects. The pharmacology program studies tumor resistance to chemotherapy, particularly the phenomenon of multidrug resistance and the relationship between tumor uptake and retention and the tumor response for anti-metabolite drugs. The immunology program studies the physiology of antibody localization at the tissue level as the basis for novel approaches to improving tumor localization such as through the use of an artificial lymphatic system which mechanically reduces intratumoral pressures in tumors in vivo. Quantitative imaging approaches based on PET and SPECT in radioimmunotherapy are studied to give greater insight into the physiology of tumor localization and dosimetry.

  18. Critical comparison of radiometric and mass spectrometric methods for the determination of radionuclides in environmental, biological and nuclear waste samples.

    Science.gov (United States)

    Hou, Xiaolin; Roos, Per

    2008-02-11

    The radiometric methods, alpha (alpha)-, beta (beta)-, gamma (gamma)-spectrometry, and mass spectrometric methods, inductively coupled plasma mass spectrometry, accelerator mass spectrometry, thermal ionization mass spectrometry, resonance ionization mass spectrometry, secondary ion mass spectrometry, and glow discharge mass spectrometry are reviewed for the determination of radionuclides. These methods are critically compared for the determination of long-lived radionuclides important for radiation protection, decommissioning of nuclear facilities, repository of nuclear waste, tracer application in the environmental and biological researches, these radionuclides include (3)H, (14)C, (36)Cl, (41)Ca, (59,63)Ni, (89,90)Sr, (99)Tc, (129)I, (135,137)Cs, (210)Pb, (226,228)Ra, (237)Np, (241)Am, and isotopes of thorium, uranium and plutonium. The application of on-line methods (flow injection/sequential injection) for separation of radionuclides and automated determination of radionuclides is also discussed.

  19. Critical comparison of radiometric and mass spectrometric methods for the determination of radionuclides in environmental, biological and nuclear waste samples.

    Science.gov (United States)

    Hou, Xiaolin; Roos, Per

    2008-02-11

    The radiometric methods, alpha (alpha)-, beta (beta)-, gamma (gamma)-spectrometry, and mass spectrometric methods, inductively coupled plasma mass spectrometry, accelerator mass spectrometry, thermal ionization mass spectrometry, resonance ionization mass spectrometry, secondary ion mass spectrometry, and glow discharge mass spectrometry are reviewed for the determination of radionuclides. These methods are critically compared for the determination of long-lived radionuclides important for radiation protection, decommissioning of nuclear facilities, repository of nuclear waste, tracer application in the environmental and biological researches, these radionuclides include (3)H, (14)C, (36)Cl, (41)Ca, (59,63)Ni, (89,90)Sr, (99)Tc, (129)I, (135,137)Cs, (210)Pb, (226,228)Ra, (237)Np, (241)Am, and isotopes of thorium, uranium and plutonium. The application of on-line methods (flow injection/sequential injection) for separation of radionuclides and automated determination of radionuclides is also discussed. PMID:18215644

  20. Separation Techniques for Quantification of Radionuclides in Environmental Samples

    Directory of Open Access Journals (Sweden)

    Dusan Galanda

    2009-01-01

    Full Text Available The reliable and quantitative measurement of radionuclides is important in order to determine environmental quality and radiation safety, and to monitor regulatory compliance. We examined soil samples from Podunajske Biskupice, near the city of Bratislava in the Slovak Republic, for the presence of several natural (238U, 232Th, 40K and anthropogenic (137Cs, 90Sr, 239Pu, 240Pu, 241Am radionuclides. The area is adjacent to a refinery and hazardous waste processing center, as well as the municipal incinerator plant, and so might possess an unusually high level of ecotoxic metals. We found that the levels of both naturally occurring and anthropogenic radionuclides fell within the expected ranges, indicating that these facilities pose no radiological threat to the local environment. During the course of our analysis, we modified existing techniques in order to allow us to handle the unusually large and complex samples that were needed to determine the levels of 239Pu, 240Pu, and 241Am activity. We also rated three commercial techniques for the separation of 90Sr from aqueous solutions and found that two of them, AnaLig Sr-01 and Empore Extraction Disks, were suitable for the quantitative and reliable separation of 90Sr, while the third, Sr-Spec Resin, was less so. The main criterion in evaluating these methods was the chemical recovery of 90Sr, which was less than we had expected. We also considered speed of separation and additional steps needed to prepare the sample for separation.

  1. Radionuclide angiocardiography in the diagnosis of congenital heart disorders

    Energy Technology Data Exchange (ETDEWEB)

    Jones, R.H.; Austin, E.H.; Peter, C.A.; Sabiston, D.C. Jr.

    1981-06-01

    Radionuclide angiocardiography provides a noninvasive assessment of cardiac function and blood flow through the heart and lungs. During the past three years, this procedure has been used at the Duke University Medical Center for evaluation of 343 patients with congenital heart disorders. A review of this experience shows tat the resulting data were frequently useful in the surgical management of these patients. In patients with abnormal blood flow patterns, noninvasive imaging of blood flow was useful before and after operative correction. Radionuclide measurements of left-to-right intracardiac shunts were sufficiently accurate for use in the initial evaluation of patients with murmurs and to document the absence of shunt after operative closure of intracardiac septal defects. Moreover, measurements of right-to-left cardiac shunts were of benefit in the management of children with cyanotic heart disease. Measurements of left ventricular function obtained during rest and exercise were most useful in patients with origin of the left coronary artery from the pulmonary artery and in patients with congenital valvular insufficiency. This experience demonstrates that radionuclide angiocardiography provides important measurements of central hemodynamics and cardiac function which are useful in the management of patients with congenital heart disorders.

  2. A statistical study on scaling factors for radionuclide assay

    International Nuclear Information System (INIS)

    To comply with the classification requirements listed in 10 CFR 61, operators of nuclear power plants are recommended to identify and quantify the concentration of several nuclids in low-level radioactive wastes(LLWs). Much of the specified radionuclides can not be easily measured in routine plant analyses. Many indirect methods has been suggested to determine the radionuclide concentrations upon which the waste classification is based. Such indirect methods include the use of scaling factors which infer the concentration of one radionuclide from another which can be measured easily. In this study, correlation analysis is performed to find out the important variables. Regression equations are attempted to provide a means of indirectly determining the concentration of the difficult-to-measure nuclides based on the result of the correlation analysis. Then residual analysis and the corresponding stepwise procedure are followed to check the regression model and select the best regression equation. The regression equation whose log mean dispersion is smaller than 10 is suggested as the appropriate correlation formula. Most of the quadratic regression equations are turned out to be able to use as a correlation formula. But, TRUs show log mean dispersions which are much larger than 10. It is concluded that the mechanisms of their formation and disappearance are much more complex. And it is also difficult to select the key nuclide. In the case of TRUs, further study is required to find out the relevant correlation formula

  3. Modelling interaction of deep groundwaters with bentonite and radionuclide speciation

    International Nuclear Information System (INIS)

    In the safety analysis recently reported for a potential Swiss high-level waste repository, radionuclide speciation and solubility limits are calculated for expected granitic groundwater conditions. With the objective of deriving a more realistic description of radionuclide release from the near-field, an investigation has been initiated to quantitatively specify the chemistry of the near-field. In the Swiss case, the main components of the near-field are the glass waste-matrix, a thick steel canister horizontally emplaced in a drift, and a backfill of highly compacted sodium bentonite. This report describes a thermodynamic model which is used to estimate the chemical composition of the pore water in compacted sodium bentonite. Solubility limits and speciation of important actinides and the fission product technetium in the bentonite pore water are then calculated. The model is based on available experimental data on the interaction of sodium bentonite and groundwater and represents means of extrapolation from laboratory data to repository conditions. The modelled composition of the pore water of compacted sodium bentonite, as well as the various compositions resulting from the long-term extrapolation, are used to estimate radionuclide solubilities in the near-field of a deep repository. From the chemical point of view, calcium bentonite seems to be more stable than sodium bentonite in the presence of Swiss Reference Groundwater. Since the effect of calcium bentonite on the groundwater chemical composition will be considerably less marked than that of sodium bentonite, especially with respect to key parameters for the nuclide speciation like carbonate concentration and pH, the use of calcium bentonite instead of sodium bentonite will improve the reliability in the prediction of source terms for radionuclide transport in the geosphere. (author)

  4. Determination of natural radionuclides in lichen samples of Carnoparmelia Texana

    International Nuclear Information System (INIS)

    Lichen plays an important role in studies of environmental pollution. It can be used for the evaluation of air contaminants, including heavy metals and radionuclides. The main objective of this study is to verify the possibility of using the lichen species Canoparmelia Texana for the assessment of natural radionuclides of the U and Th decay series in air in the vicinity of Instituto de Pesquisas Energeticas e Nucleares (IPEN) installations. IPEN has as major activity to perform research in the field of the nuclear fuel cycle, and therefore deals with natural radionuclides of the U and Th series. The content of 238U, 234U, 230Th, 210Po and 232Th in lichen samples were determined by alpha spectrometry after a radiochemical separation. Ra isotopes and 210Pb were determined by gross alpha and beta counting after a radiochemical separation and measurement on a low background gas flow proportional detector. The results obtained for 238U varied from 2.4 ± 0.4 Bq kg-1 to 6.6 ± 0.1 Bq kg-1 and from 4.4 ± 0.3 Bq kg-1 to 12.1 ± 2.6 Bq kg-1, for 232Th. For 226Ra varied from 13 ± 1 Bq kg-1 to 38 ± 2 Bq kg-1 and from 200 ± 13 Bq kg-1 to 351 ± 12 Bqkg-1 for 228Ra. The results obtained were compared with data obtained for the same radionuclides in lichen samples in an area affected by TENORM industry and can be considered as background for this lichen species. It can be concluded that the control of atmospheric discharges of IPEN facilities has been effective along the years, giving no evidence of radiological environmental impact. (author)

  5. Radionuclides release possibility analysis of MSR at various accident conditions

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Choong Wie; Kim, Hee Reyoung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    There are some accidents which go beyond our expectation such as Fukushima Daiichi nuclear disaster and amounts of radionuclides release to environment, so more effort and research are conducted to prevent it. MSR (Molten Salt Reactor) is one of GEN-IV reactor types, and its coolant and fuel are mixtures of molten salt. MSR has a schematic like figure 1 and it has different features with the solid fuel reactor, but most important and interesting feature of MSR is its many safety systems. For example, MSR has a large negative void coefficient. Even though power increases, the reactor slows down soon. Radionuclides release possibility of MSR was analyzed at various accident conditions including Chernobyl and Fukushima ones. The MSR was understood to prevent the severe accident by the negative reactivity coefficient and the absence of explosive material such as water at the Chernobyl disaster condition. It was expected to contain fuel salts in the reactor building and not to release radionuclides into environment even if the primary system could be ruptured or broken and fuel salts would be leaked at the Fukushima Daiichi nuclear disaster condition of earthquake and tsunami. The MSR, which would not lead to the severe accident and therefore prevents the fuel release to the environment at many expected scenarios, was thought to have priority in the aspect of accidents. A quantitative analysis and a further research are needed to evaluate the possibility of radionuclide release to the environment at the various accident conditions based on the simple comparison of the safety feature between MSR and solid fuel reactor.

  6. Phytoremediation and land management of radionuclide contaminated areas

    Energy Technology Data Exchange (ETDEWEB)

    Vanek, T.; Valenova, S.; Soudek, P. [Czech Academy of Science, Dept. of Plant Tissue Cultures, Inst. of Organic Chemistry and Biochemistry (Czech Republic)

    2006-07-01

    A study was conducted to examine the feasibility of using radiophytoremediation for wastewater treatment, where the conditions of contaminants can be similar to hydroponic arrangement. Due to the fact that large doses of radiation can cause cellular damage, the remediation of radionuclides from the environment is important for human health. These high risk pollutants are introduced into the environment at uranium ore processing factories, nuclear power plants, and nuclear bomb testing sites. Following the Chernobyl accident in 1986, various studies were conducted to analyze the dynamic of {sup 137}Cs radionuclide in natural and semi-natural environments. The use of plants to clean up soils, sediments, surface and ground waters contaminated by radionuclides or toxic elements has been extensively tested. This study in particular, examined the uptake, translocation and distribution of {sup 137}Cs, {sup 90}Sr and {sup 125}I uptake from a radioactive hydroponic solution. It also examined the activity distribution within different plant tissues. The influence of K{sup +}, Ca{sup 2+} and NH{sub 4}{sup +} on {sup 137}Cs and {sup 90}Sr uptake and accumulation by sunflowers was also studied in order to evaluate the effects of these ions that are normally present in the soil. The study examined which plant species could grow in contaminated areas and accumulate large amounts of radionuclides which would be suitable for radiophytoremediation purposes. Approximately 44 plant species were tested in greenhouse experiments, field studies and constructed wetlands. It was concluded that for soil-cleaning purposes, the solubility of the contaminant and its mobility in soil is the main limiting factor along with the extent of root-zone of certain plant species.

  7. Phytoremediation and land management of radionuclide-contaminated areas

    Energy Technology Data Exchange (ETDEWEB)

    Vanek, T.; Valenova, S.; Soudek, P. [Czech Academy of Science, Inst. of Organic Chemistry and Biochemistry, (Czech Republic). Dept. of Plant Tissue Cultures

    2006-07-01

    A study was conducted to examine the feasibility of using radiophytoremediation for wastewater treatment, where the conditions of contaminants can be similar to hydroponic arrangement. Due to the fact that large doses of radiation can cause cellular damage, the remediation of radionuclides from the environment is important for human health. These high risk pollutants are introduced into the environment at uranium ore processing factories, nuclear power plants, and nuclear bomb testing sites. Following the Chernobyl accident in 1986, various studies were conducted to analyze the dynamic of {sup 137}Cs radionuclide in natural and semi-natural environments. The use of plants to clean up soils, sediments, surface and ground waters contaminated by radionuclides or toxic elements has been extensively tested. This study in particular, examined the uptake, translocation and distribution of {sup 137}Cs, {sup 90}Sr and {sup 125}I uptake from a radioactive hydroponic solution. It also examined the activity distribution within different plant tissues. The influence of K{sup +}, Ca{sup 2+} and NH{sub 4}{sup +} on {sup 137}Cs and {sup 90}Sr uptake and accumulation by sunflowers was also studied in order to evaluate the effects of these ions that are normally present in the soil. The study examined which plant species could grow in contaminated areas and accumulate large amounts of radionuclides which would be suitable for radiophytoremediation purposes. Approximately 44 plant species were tested in greenhouse experiments, field studies and constructed wetlands. It was concluded that for soil-cleaning purposes, the solubility of the contaminant and its mobility in soil is the main limiting factor along with the extent of root-zone of certain plant species. 38 refs., 5 tabs., 7 figs.

  8. Sequential extraction as a tool for mobility studies of radionuclides and metals in soils and sediments

    Energy Technology Data Exchange (ETDEWEB)

    Skipperud, Lindis; Salbu, Brit [Norwegian Univ. of Life Sciences, Aas (Norway). Dept. of Environmental Sciences (IMV)

    2015-06-01

    To assess the long term environmental impact of radioactive contamination of ecosystems, information on source terms including radionuclide speciation, mobility and biological uptake is of high importance. The speciation of radionuclides deposited or occurring naturally depends on source term and release scenario characteristics, transport and dispersion mechanisms and ecosystem properties. If mobile species are present, ecosystem transfer is relatively fast, whereas the ecosystem transfer is delayed if radionuclides are present as particles or incorporated in mineral lattices. This paper discusses cases showing important factors influencing the mobility of different radionuclides and metals. As examples can be given: - the difference between {sup 137}Cs and {sup 90}Sr from Chernobyl fallout and stable Cs and Sr in the soil showing that the fallout has not reached a steady state and therefore shows different mobility properties, thus the time since contamination is important. - the presence of organic matter affect the mobility of plutonium in soils and sediments even though the source term is the same. - physical properties (i.e. pH, OM, clay content, grain sice etc.) is important to interpret mobility data between similar sites. - the influence of industrial activity on radionuclides and metals shows that any man-made activity might change the mobility.

  9. Effects of bedrock fractures on radionuclide transport near a vertical deposition hole for spent nuclear fuel

    International Nuclear Information System (INIS)

    Effects of bedrock fractures on radionuclide transport near a vertical deposition hole for spent nuclear fuel are studied computationally. The studied fractures are both natural and excavation damage fractures. The emphasis is on the detailed modelling of geometry in 3D in contrast to the traditional radionuclide transport studies that often concentrate on chain decays, sorption, and precipitation at the expense of the geometry. The built computer model is used to assess the significance of components near a deposition hole for radionuclide transport and to estimate the quality of previously used modelling techniques. The results show nearly exponential decrease of radionuclide mass in the bentonite buffer when the release route is a thin natural fracture. The results also imply that size is the most important property of the tunnel section for radionuclide transport. In addition, the results demonstrate that the boundary layer theory can be used to approximate the release of radionuclides with certain accuracy and that a thin fracture in rock can be modelled, at least to a certain limit, by using a fracture with wider aperture but with same flow rate as the thin fracture. (orig.)

  10. Regulatory Technology Development Plan - Sodium Fast Reactor. Mechanistic Source Term - Metal Fuel Radionuclide Release

    Energy Technology Data Exchange (ETDEWEB)

    Grabaskas, David [Argonne National Lab. (ANL), Argonne, IL (United States); Bucknor, Matthew [Argonne National Lab. (ANL), Argonne, IL (United States); Jerden, James [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-02-01

    The development of an accurate and defensible mechanistic source term will be vital for the future licensing efforts of metal fuel, pool-type sodium fast reactors. To assist in the creation of a comprehensive mechanistic source term, the current effort sought to estimate the release fraction of radionuclides from metal fuel pins to the primary sodium coolant during fuel pin failures at a variety of temperature conditions. These release estimates were based on the findings of an extensive literature search, which reviewed past experimentation and reactor fuel damage accidents. Data sources for each radionuclide of interest were reviewed to establish release fractions, along with possible release dependencies, and the corresponding uncertainty levels. Although the current knowledge base is substantial, and radionuclide release fractions were established for the elements deemed important for the determination of offsite consequences following a reactor accident, gaps were found pertaining to several radionuclides. First, there is uncertainty regarding the transport behavior of several radionuclides (iodine, barium, strontium, tellurium, and europium) during metal fuel irradiation to high burnup levels. The migration of these radionuclides within the fuel matrix and bond sodium region can greatly affect their release during pin failure incidents. Post-irradiation examination of existing high burnup metal fuel can likely resolve this knowledge gap. Second, data regarding the radionuclide release from molten high burnup metal fuel in sodium is sparse, which makes the assessment of radionuclide release from fuel melting accidents at high fuel burnup levels difficult. This gap could be addressed through fuel melting experimentation with samples from the existing high burnup metal fuel inventory.

  11. Development of radionuclide inventory estimation method using scaling factor for the Korean NPPs: scope and status

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Ki Ha; Lee, Sang Chul; Kang, Sang Hee; Lee, Kun Jai [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Jeong, Chan Woo; Ahn, Sang Myeon [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Kim, Tae Wook; Kim, Kyoung Doek; Herr, Y. H. [Byckear Environment Technology Institute, Taejon (Korea, Republic of)

    2003-07-01

    Regulations and guidelines for radionuclide waste disposal require detailed information about the characteristics of radioactive waste drums prior to the transport to the disposal sites. Therefore, it is important to know the accurate radionuclide inventory of radioactive waste. However, estimation of radionuclide concentrations on drummed radioactive waste is difficult and unreliable. In order to overcome these difficulties, scaling factors have been used to assess the activities of radionuclides which could not be directly analyzed. A radionuclides assay system has been operated at Korean nuclear power plant (KORI site) since 1996 and consolidated scaling factor concept has played a dominant role in determination of radionuclides concentrations. For corrosion product radionuclides, generic scaling factors were used due to the similar trend and better-characterized properties of Korean analyzed data compared to the worldwide database. It is not easy to use the generic scaling factors for fission product and TRU radionuclides. Thus simple model reflecting the history of the operation of power plant and nuclear fuel condition is applied. However, some problems are still remained. For examples, disparity between the actual and ideal correlation pairs, inaccuracy of analyzed sample values, uncertainty in representative of derived scaling factor values and so on. As a result, the correlation ratios are somewhat dispersive. So it is planned to establish an assay system using more improved scaling factors. In this study, the scope of research is expanded and planned such as following. 1) Considering more assay target nuclides, 2) Considering more target NPPs, 3) More reliable sampling and measurement techniques, 4) Improvement of accuracy and representativeness of derived scaling factor values and 5) Conformation of correlation pairs based on Korean analyzed data. As this study progresses, it is possible to get more accurate and reliable prediction for the information of

  12. Radiolabelled somatostatin analogues for radionuclide therapy of tumours

    International Nuclear Information System (INIS)

    Molecular imaging and therapy are rapidly developing and will become important topics in medicine in the 21st century. Radiolabelled peptides that bind to receptors form an important class of radiopharmaceuticals for tumour diagnosis and therapy. The specific receptor binding property of the peptide can be exploited by labelling with radionuclide and using the radiolabelled peptide as a vehicle to guide the radioactivity to tumours expressing a particular receptor. The high affinity of the peptide for the peptide-receptor complex facilitates high uptake of the radiolabel in receptor expressing tumours, while its relatively small size facilitates rapid clearance from blood, resulting in low background radioactivity. The use of radiolabelled peptides is growing rapidly due to these favourable characteristics, their low antigenicity and ease of production. Receptor binding peptides labelled with gamma radiation emitters or positron emitters enable non-evasive, whole body visualization. This process is referred to as peptide receptor scintigraphy and is being used to detect, stage and plan the therapy of receptor expressing tumours and also to follow tumours after therapy. In addition, labelled with a therapeutic beta emitter these peptide molecules have the potential to destroy receptor expressing tumours, an approach referred to as peptide receptor radionuclide therapy (PRRT). To date, five somatostatin receptor subtypes (sst1-sst5) have been identified and cloned. The diagnostic accuracy of 111In labelled octreotide to visualize tumour lesions after intravenous injection has been determined in a large series of patients with sst2 positive, mostly neuroendocrine tumours. Most interesting is the successful application of somatostatin analogues in PET, after labelling with positron emitters. The next logical step was to try to label these with therapeutic radionuclides and to treat receptor positive tumors with peptide receptor radionuclides. So far, 90Y and 177Lu are

  13. Geochemical factors affecting radionuclide transport through near and far fields at a Low-Level Waste Disposal Site

    Energy Technology Data Exchange (ETDEWEB)

    Kaplan, D.I.; Seme, R.J. [Pacific Northwest Lab., Richland, WA (United States); Piepkho, M.G. [Westinghouse Hanford Co., Richland, WA (United States)

    1995-03-01

    The concentration of low-level waste (LLW) contaminants in groundwater is determined by the amount of contaminant present in the solid waste, rate of release from the waste and surrounding barriers, and a number of geochemical processes including adsorption, desorption, diffusion, precipitation, and dissolution. To accurately predict radionuclide transport through the subsurface, it is essential that the important geochemical processes affecting radionuclide transport be identified and, perhaps more importantly, accurately quantified and described in a mathematically defensible manner.

  14. Geochemical factors affecting radionuclide transport through near and far fields at a Low-Level Waste Disposal Site

    International Nuclear Information System (INIS)

    The concentration of low-level waste (LLW) contaminants in groundwater is determined by the amount of contaminant present in the solid waste, rate of release from the waste and surrounding barriers, and a number of geochemical processes including adsorption, desorption, diffusion, precipitation, and dissolution. To accurately predict radionuclide transport through the subsurface, it is essential that the important geochemical processes affecting radionuclide transport be identified and, perhaps more importantly, accurately quantified and described in a mathematically defensible manner

  15. Radionuclide Release from High Burnup Fuel

    International Nuclear Information System (INIS)

    In this paper we investigate the production, evolution and release of radioactive fission products in a light water reactor. The production of the nuclides is determined by the neutronics, their evolution in the fuel by local temperature and by the fuel microstructure and the rate of release is governed by the scenario and the properties of the microstructure where the nuclides reside. The problem combines fields of reactor physics, fuel behaviour analysis and accident analysis. Radionuclide evolution during fuel reactor life is also important for determination of instant release fraction of final repository analysis. The source term problem is investigated by literature study and simulations with reactor physics code Serpent as well as fuel performance code ENIGMA. The capabilities of severe accident management codes MELCOR and ASTEC for describing high burnup structure effects are reviewed. As the problem is multidisciplinary in nature the transfer of information between the codes is studied. While the combining of the different fields as they currently are is challenging, there are some possibilities to synergy. Using reactor physics tools capable of spatial discretization is necessary for determining the HBS inventory. Fuel performance studies can provide insight how the HBS should be modelled in severe accident codes, however the end effect is probably very small considering the energetic nature of the postulated accidents in these scenarios. Nuclide release in severe accidents is affected by fuel oxidation, which is not taken into account by ANSI/ANS-5.4 but could be important in some cases, and as such, following the example of severe accident models would benefit the development of fuel performance code models. (author)

  16. Preparation of Radiopharmaceuticals Labeled with Metal Radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Welch, M.J.

    2012-02-16

    The overall goal of this project was to develop methods for the production of metal-based radionuclides, to develop metal-based radiopharmaceuticals and in a limited number of cases, to translate these agents to the clinical situation. Initial work concentrated on the application of the radionuclides of Cu, Cu-60, Cu-61 and Cu-64, as well as application of Ga-68 radiopharmaceuticals. Initially Cu-64 was produced at the Missouri University Research Reactor and experiments carried out at Washington University. A limited number of studies were carried out utilizing Cu-62, a generator produced radionuclide produced by Mallinckrodt Inc. (now Covidien). In these studies, copper-62-labeled pyruvaldehyde Bis(N{sup 4}-methylthiosemicarbazonato)-copper(II) was studied as an agent for cerebral myocardial perfusion. A remote system for the production of this radiopharmaceutical was developed and a limited number of patient studies carried out with this agent. Various other copper radiopharmaceuticals were investigated, these included copper labeled blood imaging agents as well as Cu-64 labeled antibodies. Cu-64 labeled antibodies targeting colon cancer were translated to the human situation. Cu-64 was also used to label peptides (Cu-64 octriatide) and this is one of the first applications of a peptide radiolabeled with a positron emitting metal radionuclide. Investigations were then pursued on the preparation of the copper radionuclides on a small biomedical cyclotron. A system for the production of high specific activity Cu-64 was developed and initially the Cu-64 was utilized to study the hypoxic imaging agent Cu-64 ATSM. Utilizing the same target system, other positron emitting metal radionuclides were produced, these were Y-86 and Ga-66. Radiopharmaceuticals were labeled utilizing both of these radionuclides. Many studies were carried out in animal models on the uptake of Cu-ATSM in hypoxic tissue. The hypothesis is that Cu-ATSM retention in vivo is dependent upon the

  17. Idaho radionuclide exposure study: Literature review

    International Nuclear Information System (INIS)

    Phosphate ores contain elevated levels of natural radioactivity, some of which is released to the environment during processing or use of solid byproducts. The effect of radionuclides from Idaho phosphate processing operations on the local communities has been the subject of much research and study. The literature is reviewed in this report. Two primary radionuclide pathways to the environment have been studied in detail: (1) airborne release of volatile radionuclides, primarily 210Po, from calciner stacks at the two elemental phosphorus plants; and (2) use of byproduct slag as an aggregate for construction in Soda Springs and Pocatello. Despite the research, there is still no clear understanding of the population dose from radionuclide emissions, effluents, and solid wastes from phosphate processing plants. Two other potential radionuclide pathways to the environment have been identified: radon exhalation from phosphogypsum and ore piles and contamination of surface and ground waters. Recommendations on further study needed to develop a data base for a complete risk assssment are given in the report

  18. Evaluation of radionuclides migration in environment

    International Nuclear Information System (INIS)

    Radioactive waste management is one of the most pressing problems facing the world today because of its long half-life and the transport of radionuclides to the environment. The migration of radionuclides in environment is affected by its sorption in backfill materials, water pore velocity, water flowing direction, dispersion of radionuclides, components of backfill materials, species of radionuclides, microorganism effect and complexation ability of organic substances etc. In this study, the distribution coefficient of Eu(III) derived from batch experiments is used to evaluate the migration behavior of Eu(III) in compacted bentonite after long time. The effect of the dispersion coefficient and the pore water velocity on the migration of Eu(III)is also calculated. It is found that the variation of the distribution coefficient and water velocity has an obviously effect on the migration of Eu(III) in backfill materials and 30 m of the backfill materials is sufficient to prevent the migration of Eu(III) in environment. The dispersion coefficient has little effect on the migration of Eu(III). The evaluated results are applicable to estimate the escape of radionuclides from buried radioactive waste to the environment. (authors)

  19. Radionuclide Retention in Concrete Wasteforms - FY13

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Michelle MV; Golovich, Elizabeth C.; Wellman, Dawn M.; Crum, Jarrod V.; Lapierre, Robert; Dage, Denomy C.; Parker, Kent E.; Cordova, Elsa A.

    2013-10-15

    Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how wasteform performance is affected by the full range of environmental conditions within the disposal facility; the process of wasteform aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of wasteform aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the wasteforms come in contact with groundwater. Data collected throughout the course of this work will be used to quantify the efficacy of concrete wasteforms, similar to those used in the disposal of low-level waste and mixed low-level waste, for the immobilization of key radionuclides (i.e., uranium, technetium, and iodine). Data collected will also be used to quantify the physical and chemical properties of the concrete affecting radionuclide retention.

  20. Radionuclide Mobility at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    Hu, Q; Smith, D; Rose, T; Glascoe, L; Steefel, C; Zavarin, M

    2003-11-13

    Underground nuclear tests conducted at the Nevada Test Site (NTS) are characterized by abundant fission product and actinide source terms. Included are {sup 99}Tc and other soluble radionuclides ({sup 3}H, {sup 14}C, {sup 36}Cl, {sup 85}Kr, and {sup 129}I), which are presumably mobile in groundwater and potentially toxic to down-gradient receptors. NTS provides the Office of Civilian Radioactive Waste Management (OCRWM) with an analog of the release of these radionuclides from a nuclear waste repository in the absence of engineered barriers. The investigation described in this report synthesizes a substantial body of data collected on the identity and distribution of soluble radionuclides at field scales over distances of hundreds of meters, for durations up to 40 years, and under hydrogeologic conditions very similar to the proposed geological repository at Yucca Mountain. This body of data is complemented by laboratory transport studies and a synthesis of recent modeling investigations from the NTS, with an emphasis on the ongoing Yucca Mountain Program (YMP) efforts. Overall, understanding the controls of radionuclide mobility associated with these nuclear tests will provide insight into the repository's future performance as well as bounds and calibrations for the numerical predictions of long-term radionuclide releases and migration.

  1. Models for transport and fate of carbon, nutrients and radionuclides in the aquatic ecosystem at Oeregrundsgrepen

    Energy Technology Data Exchange (ETDEWEB)

    Erichsen, Anders Christian; Moehlenberg, Flemming; Closter, Rikke Margrethe; Sandberg, Johannes (DHI, Hoersholm (Denmark))

    2010-06-15

    The aim of the work was to provide supplementary input to the risk assessment of a planned final nuclear waste repository at Forsmark. The main deliverable was a computed water exchange between basins in the Forsmark marine area for the period 6500 BC to 9000 AD - based on the hydrodynamic modelling - to be used as input to the landscape dose model. In addition and what is described in this report, a second deliverable was development and application of high-resolution models for the marine ecosystem and radionuclide processes. The purpose of this deliverable was to illustrate the spatial and temporal variation in important processes and parameters, while constituting a complement to previous modelling approaches and providing supporting information to discussions of the marine ecosystem, parameters and variation (see Chapter 4 and 6).To this end, a hydrodynamic model of high temporal and spatial resolution was constructed and calibrated for the Forsmark area. An ecosystem model was then developed and coupled to the hydrodynamic model. In turn, a detailed radionuclide model was coupled to the ecosystem model to provide detailed predictions of radionuclide transport and accumulation in the coastal ecosystem. The ecosystem and radionuclide models were developed in the equation solver MIKE ECOLab that links seamless to the MIKE3 FM hydrodynamic model. The 'standard' ECOLab ecosystem model was extended with six biological state variables, perennial macroalgae, benthic herbivors, detritus feeders, planktivorus fish and, benthic predators representing the relict isopod Saduria and cod. In contrast to the ecosystem model, the radionuclide model was developed from scratch but building on the structure of the ecosystem model and using the output (process rates linking state variables) from the ecosystem model as input to the radionuclide model. Both the ecosystem model and the radionuclide model were run for several years (5-8 years) to bring state variables into

  2. Evaluation of data on the transfer of radionuclides in the food chain post-Chernobyl action

    International Nuclear Information System (INIS)

    During the accident at Chernobyl large amounts of radioactive materials were released into the atmosphere and distributed all over Europe. Depending on the trajectories of the radioactive clouds and the large variation of rainfall during its passage through, large local and regional differences in deposition were observed, leading to an enhanced contamination of soil and plants. Consequently, the radionuclides entered the foodchain by several pathways. The radiological consequences of radionuclides discharged from nuclear installations usually are evaluated using doses assessment models. In these models the passage from one compartment into another, e.g. the transfer from soil into plants, from plants into milk or meat is defined by transfer factors, which are influenced by various parameters. From the long term point of view only the long-lived nuclides like 134/137Cs are important for long term radiation risk assessment after the Chernobyl accident. In this accident the release of radioactive materials took place over a longer time period and varied in rate and radionuclide composition. Some regions of Europe were contaminated several times. To improve radiation dose prediction the CEC has initiated the Post-Chernobyl radiation protection programme 'Evaluation of Data on the Transfer of Radionuclides in the Foodchain' including five main items to be studied by different laboratories: 1. Impact of chemical speciation on the radionuclide transfer in terrestrial ecosystems after a core disruptive accident, especially in soils and plants. 2. Transfer paths of radionuclides in seminatural and natural ecosystems and their role in contaminating the foodchain. 3. Validation of soil-to-plant parameters. 4. Transfer of radionuclides to animals and animal products. 5. Transfer paths in aquatic systems and their importance for the contamination of the foodchain

  3. Pain palliative Radiopharmaceuticals

    International Nuclear Information System (INIS)

    A pain relieving agents based on β emitters mainly and in some cases a complex preparation are being given for bone metastasis in relation with breast,prostate and lung carcinoma with good performance in clinical practice.Several radionuclides and radiopharmaceuticals are mentioned giving strength to those newly proposed, 153Sm and 186Re.Bibliography

  4. Metal-ion Speciation in Blood Plasma as a Tool in Predicting the "in vivo" Behaviour of Potential Bone-Seeking Radiopharmaceuticals

    NARCIS (Netherlands)

    Zeevaart, J.R.

    2001-01-01

    In a quest for more effective radiopharmaceuticals for palliation of pain experienced by metastatic bone cancer patients, results obtained with the therapeutic radionuclides 153 SM, 166 Ho and 117mSn complexed to bone-seeking phopsphate ligands are related. As phosphonates are known to enhance the r

  5. Estimation of the radionuclide distribution in sediment in coast area

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    The study of radionuclide distribution in sediment is a very important aspect in environmental impact of the low level radioactive liquid waste (LLW) from coastal nuclear facilities or nuclear power plant. Even now we do not know much about it. In this paper, a simple and useful method is put forward and it is used to estimate the nuclide distribution in sediment. The result showed that the LLW from nuclear facility or nuclear power plant will do little harm to the sediment nearby. But the harm is not veryserious. Much works have to be done before full understanding of the situation.

  6. Peptide receptor radionuclide therapy of neuroendocrine tumours.

    Science.gov (United States)

    Brabander, Tessa; Teunissen, Jaap J M; Van Eijck, Casper H J; Franssen, Gaston J H; Feelders, Richard A; de Herder, Wouter W; Kwekkeboom, Dik J

    2016-01-01

    In the past decades, the number of neuroendocrine tumours that are detected is increasing. A relative new and promising therapy for patients with metastasised or inoperable disease is peptide receptor radionuclide therapy (PRRT). This therapy involves an infusion of somatostatin analogues linked to radionuclides like Yttrium-90 or Lutetium-177. Objective response rates are reported in 15-35%. Response rates may vary between type of tumour and radionuclide. Besides the objective response rate, overall survival and progression free survival increase significantly. Also, the quality of life improves as well. Serious side-affects are rare. PRRT is usually well tolerated, also in patients with extensive metastasised disease. Recent studies combined PRRT with other types of therapies. Unfortunately no randomised trials comparing these strategies are available. In the future, more research is needed to evaluate the best therapy combinations or sequence of therapies. PMID:26971847

  7. EPA perspective on radionuclide aerosol sampling

    International Nuclear Information System (INIS)

    The Environmental Protection Agency (EPA) is concerned with radionuclide aerosol sampling primarily at Department of Energy (DOE) facilities in order to insure compliance with national air emission standards, known as NESHAPs. Sampling procedures are specified in open-quotes National Emission Standards for Emissions of Radionuclides other than Radon from Department of Energy Sitesclose quotes (Subpart H). Subpart H also allows alternate procedures to be used if they meet certain requirements. This paper discusses some of the mission differences between EPA and Doe and how these differences are reflected in decisions that are made. It then describes how the EPA develops standards, considers alternate sampling procedures, and lists suggestions to speed up the review and acceptance process for alternate procedures. The paper concludes with a discussion of the process for delegation of Radionuclide NESHAPs responsibilities to the States, and responsibilities that could be retained by EPA

  8. Transport of radionuclides in the biosphere

    International Nuclear Information System (INIS)

    The dispersion of radionuclides in the biosphere and their uptake by man via various nutritional pathways is studied using a compartment model. The sample environment is the area of the lower Limmat and Aare valleys. General considerations of the compartmental description of the biosphere are made. The problem of the description of surface features, in particular soil, sediment and water, is studied in detail using the code BIOPATH. This study is intended to be an example of how a model of the biosphere could be constructed. It is shown that this is a reasonable model to calculate the spreading of radionuclides in the biosphere and that it indicates the relative significance of individual compartments, pathways and radionuclides. Calculated values of dose committment, however, should not be used as reference data for safety analyses. (Auth.)

  9. 2014 LANL Radionuclide Air Emissions Report

    Energy Technology Data Exchange (ETDEWEB)

    Fuehne, David Patrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-07-21

    This report describes the emissions of airborne radionuclides from operations at Los Alamos National Laboratory (LANL) for calendar year 2014, and the resulting off-site dose from these emissions. This document fulfills the requirements established by the National Emissions Standards for Hazardous Air Pollutants in 40 CFR 61, Subpart H – Emissions of Radionuclides other than Radon from Department of Energy Facilities, commonly referred to as the Radionuclide NESHAP or Rad-NESHAP. Compliance with this regulation and preparation of this document is the responsibility of LANL’s RadNESHAP compliance program, which is part of the Environmental Protection Division. The information in this report is required under the Clean Air Act and is being submitted to the U.S. Environmental Protection Agency (EPA) Region 6.

  10. Radionuclides in ground-level air

    International Nuclear Information System (INIS)

    In the air surveillance programme the concentrations of artificial radionuclides are monitored in the air close to the ground to obtain the necessary basic data for estimating the exposure of the Finnish population to fall-out radionuclides and also to detect atmospheric traces of radioactive materials caused by their use or production. Airborne dust is collected on filters with high-volume air samplers and the concentrations of gamma-emitting radionuclides in the air are evaluated. In the first quarter of 1986 only long-lived cesium, caused by earlier atmospheric nuclear explosions was detected. The concentrations of cesium were very low. In January and March a small amount of short-lived, fresh fission and activation products were also observed

  11. A biokinetics of radionuclides in juvenile animals

    International Nuclear Information System (INIS)

    Calculation of dose coefficient in the general population, especially infants, poses a problem in that physical function and biokinetics in infants are different from those in adults. This paper gives an outline on characteristics of biokinetics of radionuclides in jevenile animals, focusing on the previous experimental data. The following radionuclides are discussed: cesium, strontium, cobalt, manganese, lead, ruthenium, cerium, silver and antimony. The retention rate of any kind of radionuclide in the body after the oral administration has been shown to be age-dependent in rats. Dose coefficient in adults has been shown to be unsuitable for that in infants, even if limited to the rate of digestive absorption. Although fetuses are also included in the general population, there is a paucity of such information. Actually, exposure assessment remains, as yet, an issue unsettled. (N.K.)

  12. Radionuclide sorption on well construction materials

    International Nuclear Information System (INIS)

    Laboratory experiments were conducted to measure the extent to which trace concentrations of radioactive materials would sorb on well construction materials and to assess the rapidity with which sorption would occur. The radionuclides employed in these studies were tritium, Cs-137, and Co-57. Solutions with trace concentrations of these radionuclides were contacted with casings of PVC, fiber-glass-epoxy, stainless steel, carbon steel, and steel rods coated with epoxy. The PVC showed no interaction with the tritium or Cs-137 during contact times of two hours to three weeks; however, it did sorb Co-57. The fiber-glass-epoxy also interacted only with the cobalt. The stainless steel sorbed cesium and cobalt. The epoxy-coated steel rods did not interact measurably with any of the radionuclides so long as the coating was intact. The sorption reactions generally were apparent after a few days of contact; in the case of carbon steel, they were detectable in a few hours

  13. Radionuclide detection of lower gastrointestinal bleeding sites

    International Nuclear Information System (INIS)

    A retrospective review of two years' experience with radionuclide screening to detect lower gastrointestinal bleeding sites was conducted at New York's Montefiore Medical Center. Of 82 studies performed in 63 patients, 13 identified active bleeding sites. Only three of eight angiograms obtained in these 13 patients were positive. Thirteen contrast angiograms were performed in the group of 50 patients with negative radionuclide studies of which ten were negative and one was equivocal. The results of this study suggest that the Tc-99m sulfur colloid study for active lower gastrointestinal (GI) bleeding is an effective screening procedure. Positive studies help determine which vessel to catheterize selectively if an angiogram is to be performed. If vascular ectasis is still suspected following a negative radionuclide study, contrast angiography can be more efficaciously performed on a nonemergent basis

  14. Therapeutic radionuclides: Making the right choice

    Energy Technology Data Exchange (ETDEWEB)

    Srivastava, S.C.

    1996-08-01

    Recently, there has been a resurgence of interest in nuclear medicine therapeutic procedures. Using unsealed sources for therapy is not a new concept; it has been around since the beginnings of nuclear medicine. Treatment of thyroid disorders with radioiodine is a classic example. The availability of radionuclides with suitable therapeutic properties for specific applications, as well as methods for their selective targeting to diseased tissue have, however, remained the main obstacles for therapy to assume a more widespread role in nuclear medicine. Nonetheless, a number of new techniques that have recently emerged, (e.g., tumor therapy with radiolabeled monoclonal antibodies, treatment of metastatic bone pain, etc.) appear to have provided a substantial impetus to research on production of new therapeutic radionuclides. Although there are a number of new therapeutic approaches requiring specific radionuclides, only selected broad areas will be used as examples in this article.

  15. Metrology of Radionuclides. Proceedings of a Symposium

    International Nuclear Information System (INIS)

    ''Metrology of Radionuclides'' is the science of precise measurements of the absolute value of the activity of radioactive sources. A rapid expansion has taken place over the past few years in the applications of radionuclides in various fields of scientific research, particularly in the production of commodities which lead to improved living standards. This has occurred not only in the countries most advanced in nuclear science, but in many others. In order to allow those actively engaged in this field to exchange research results and discuss their problems, the International Atomic Energy Agency sponsored a symposium which was held in Vienna from 14-16 October, 1959. Thirty-seven papers were presented from 14 countries. These covered a general survey on the routine methods of standardization of radionuclides and new developments of absolute measuring methods for their standardization.

  16. SALTSTONE AND RADIONUCLIDE INTERACTIONS: RADIONUCLIDE SORPTION AND DESORPTION, AND SALTSTONE REDUCTION CAPACITY

    Energy Technology Data Exchange (ETDEWEB)

    Kaplan, D; Kimberly Roberts, K; Steven Serkiz, S; Matthew Siegfried, M

    2008-10-30

    The overall objective of this study was to measure a number of key input parameters quantifying geochemical processes in the subsurface environment of the Savannah River Site's (SRS's) Saltstone Facility. For the first time, sorption (K{sub d}) values of numerous radionuclides were measured with Saltstone and Vault 2 concrete. Particular attention was directed at understanding how Tc adsorbs and desorbs from these cementitious materials with the intent to demonstrate that desorption occurs at a much slower rate than adsorption, thus permitting the use of kinetic terms instead of (or along with) the steady state K{sub d} term. Another very important parameter measured was the reduction capacity of these materials. This parameter is used to estimate the duration that the Saltstone facility remains in a reduced chemical state, a condition that maintains several otherwise mobile radionuclides in an immobile form. Key findings of this study follow. K{sub d} values for Am, Cd, Ce, Co, Cs, Hg, I, Np, Pa, Pu, Se, Sn, Tc, U, and Y for Saltstone and Vault 2 concrete were measured under oxidized and reduced conditions. Precipitation of several of the higher valence state radionuclides was observed. There was little evidence that the Vault 2 and Saltstone K{sub d} values differed from previous SRS K{sub d} values measured with reducing grout (Kaplan and Coates 2007). These values also supported a previous finding that K{sub d} values of slag-containing cementitious materials, tend to be greater for cations and about the same for anions, than regular cementitious materials without slag. Based on these new findings, it was suggested that all previous reducing concrete K{sub d} values be used in future PAs, except Np(V) and Pu(IV) K{sub d} values, which should be increased, and I values, which should be slightly decreased in all three stages of concrete aging. The reduction capacity of Saltstone, consisting of 23 wt-% blast furnace slag, was 821.8 microequivalents per

  17. Data Authentication Demonstration for Radionuclide Stations

    Energy Technology Data Exchange (ETDEWEB)

    Harris, Mark; Herrington, Pres; Miley, Harry; Ellis, J. Edward; McKinnon, David; St. Pierre, Devon

    1999-08-03

    Data authentication is required for certification of sensor stations in the International Monitoring System (IMS). Authentication capability has been previously demonstrated for continuous waveform stations (seismic and infrasound). This paper addresses data surety for the radionuclide stations in the IMS, in particular the Radionuclide Aerosol Sampler/Analyzer (RASA) system developed by Pacific Northwest National Laboratory (PNNL). Radionuclide stations communicate data by electronic mail using formats defined in IMS 1.0, Formats and Protocols for Messages. An open message authentication standard exists, called S/MIME (Secure/Multipurpose Internet Mail Extensions), which has been proposed for use with all IMS radionuclide station message communications. This standard specifies adding a digital signature and public key certificate as a MIME attachment to the e-mail message. It is advantageous because it allows authentication to be added to all IMS 1.0 messages in a standard format and is commercially supported in e-mail software. For command and control, the RASA system uses a networked Graphical User Interface (GUI) based upon Common Object Request Broker Architecture (CORBA) communications, which requires special authentication procedures. The authors have modified the RASA system to meet CTBTO authentication guidelines, using a FORTEZZA card for authentication functions. They demonstrated signing radionuclide data messages at the RASA, then sending, receiving, and verifying the messages at a data center. They demonstrated authenticating command messages and responses from the data center GUI to the RASA. Also, the particular authentication system command to change the private/public key pair and retrieve the new public key was demonstrated. This work shows that data surety meeting IMS guidelines may be immediately applied to IMS radionuclide systems.

  18. TURVA-2012: Formulation of radionuclide release scenarios

    International Nuclear Information System (INIS)

    TURVA-2012 is Posiva's safety case in support of the Preliminary Safety Analysis Report (PSAR) and application for a construction licence for a repository for disposal of spent nuclear fuel at the Olkiluoto site in south-western Finland. This paper gives a summary of the scenarios and the methodology followed in formulating them as described in TURVA-2012: Formulation of Radionuclide Release Scenarios (Posiva, 2013). The scenarios are further analysed in TURVA-2012: Assessment of Radionuclide Release Scenarios for the Repository System and TURVA-2012: Biosphere Assessment (Posiva, 2012a, 2012b). The formulation of scenarios takes into account the safety functions of the main barriers of the repository system and the uncertainties in the features, events, and processes (FEP) that may affect the entire disposal system (i.e. repository system plus the surface environment) from the emplacement of the first canister until the far future. In the report TURVA-2012: Performance Assessment (2012d), the performance of the engineered and natural barriers has been assessed against the loads expected during the evolution of the repository system and the site. Uncertainties have been identified and these are taken into account in the formulation of radionuclide release scenarios. The uncertainties in the FEP and evolution of the surface environment are taken into account in formulating the surface environment scenarios used ultimately in estimating radiation exposure. Formulating radionuclide release scenarios for the repository system links the reports Performance Assessment and Assessment of Radionuclide Release Scenarios for the Repository System. The formulation of radionuclide release scenarios for the surface environment brings together biosphere description and the surface environment FEP and is the link to the assessment of the surface environment scenarios summarised in TURVA-2012: Biosphere Assessment. (authors)

  19. What is the role of the bystander response in radionuclide therapies?

    Directory of Open Access Journals (Sweden)

    Darren eBrady

    2013-08-01

    Full Text Available Radionuclide therapy for cancer is undergoing a renaissance, with a wide range of radionuclide and clinical delivery systems currently under investigation. Dosimetry at the cellular and subcellular level is complex with inhomogeneity and incomplete targeting of all cells such that some tumour cells will receive little or no direct radiation energy. There is now sufficient preclinical evidence of a bystander response which can modulate the biology of these unirradiated cells with current research demonstrating both protective and inhibitory responses. Dependence upon fraction of irradiated cells has also been found has and the presence of functional gap junctions appears to be import for several bystander responses. The selection of either high or low LET radionuclides may be critical. While low LET radionuclides appear to have a bystander response proportional to dose, the dose-response from high LET radionuclides are more complex. In media transfer experiments a U shaped response curve has been demonstrated for high LET treatments. However this U shaped response has not been seen with co-culture experiments and its relevance remains uncertain. For high LET treatments there is a suggestion that dose rate effects may also be important with inhibitory effects noted with 125I labelling study and a stimulatory seen with 123I labelling in one study.

  20. Effects of radionuclide decay on waste glass behavior: A critical review

    Energy Technology Data Exchange (ETDEWEB)

    Wronkiewicz, D.J.

    1993-12-01

    This paper is an extension of a chapter in an earlier report [1] that provides an updated review on the status of radiation damage problems in nuclear waste glasses. This report will focus on radiation effects on vitrified borosilicate nuclear waste glasses under conditions expected in the proposed Yucca mountain repository. Radiation effects on high-level waste glasses and their surrounding repository environment are important considerations for radionuclide immobilization because of the potential to alter the glass stability and thereby influence the radionuclide retentive properties of this waste form. The influence of radionuclide decay on vitrified nuclear waste may be manifested by several changes, including volume, stored energy, structure, microstructure, mechanical properties, and phase separation. Radiation may also affect the composition of aqueous fluids and atmospheric gases in relatively close proximity to the waste form. What is important to the radionuclide retentive properties of the repository is how these radiation effects collectively or individually influence the durability and radionuclide release from the glass in the event of liquid water contact.

  1. Effects of radionuclide decay on waste glass behavior: A critical review

    International Nuclear Information System (INIS)

    This paper is an extension of a chapter in an earlier report [1] that provides an updated review on the status of radiation damage problems in nuclear waste glasses. This report will focus on radiation effects on vitrified borosilicate nuclear waste glasses under conditions expected in the proposed Yucca mountain repository. Radiation effects on high-level waste glasses and their surrounding repository environment are important considerations for radionuclide immobilization because of the potential to alter the glass stability and thereby influence the radionuclide retentive properties of this waste form. The influence of radionuclide decay on vitrified nuclear waste may be manifested by several changes, including volume, stored energy, structure, microstructure, mechanical properties, and phase separation. Radiation may also affect the composition of aqueous fluids and atmospheric gases in relatively close proximity to the waste form. What is important to the radionuclide retentive properties of the repository is how these radiation effects collectively or individually influence the durability and radionuclide release from the glass in the event of liquid water contact

  2. [Radionuclide therapy for cancer--what's new?].

    Science.gov (United States)

    Hanna, Mäenpää; Mikko, Tenhunen

    2012-01-01

    Radionuclide therapy is radiation therapy, the effect of which is based on radiation damage in cancer cells. The most common radionuclide therapy for cancer is radioiodine therapy for thyroid cancer. Two new forms of treatment have recently been initiated in Finland: 177lutetium octreotate therapy for neuroendocrine tumors, pheochromocytoma and paraganglioma as well as radioembolization (selective internal radiation therapy, SIRT) with 90yttrium-coated resin beads against liver metastases. Still in experimental use, 223radium chloride is a drug prolonging survival in prostate cancer that has metastasized to bone. The treatments require special knowledge and collaboration between several units. PMID:23210283

  3. Assessment of waste management of volatile radionuclides

    International Nuclear Information System (INIS)

    This document presents a review of the Technologies for Waste Management of the Volatile Radionuclides of iodine-129, krypton-85, tritium, and carbon-14. The report presents an estimate of the quantities of these volatile radionuclides as are produced in the nuclear power industry. The various technologies as may be used, or which are under investigation, to immobilize these nuclides and to contain them during storage and in disposal are discussed. Also, the alternative disposal options as may be applied to isolate these radioactive wastes from the human environment are presented. The report contains information which was available through approximately January 1978

  4. RAPRAN, Radionuclide Migration from Waste Glass Release

    International Nuclear Information System (INIS)

    1 - Description of program or function: The code treats one-dimensional advection-diffusion combined with linear sorption to calculate radionuclide migration behavior in multi-porous media with time-dependent diffusion/retardation parameters. It uses both leaching rate and solubility simultaneously to model nuclide release from a waste glass as the inner boundary condition. The program is applied to, for example, the analysis of radionuclide diffusion through the engineered barrier system or radioactive wastes disposal. 2 - Method of solution: Finite-difference method in porous media. 3 - Restrictions on the complexity of the problem: None. Size-adjustable

  5. Entrapment of Radionuclides in Nanoparticle Compositions

    DEFF Research Database (Denmark)

    2012-01-01

    such as radionuclides,for example 61Cu and 64Cu copper isotopes. The invention further relates to a novel method for loading delivery systems, such as liposome compositions, with metal entities such as radionuclides, and the use of liposomes for targeted diagnosis and treatment of a target site, such as cancerous......The present invention is directed to the technical field of imaging compositions useful for diagnosing cancer and other diseases in a subject. In particular, the invention relates to a class of diagnostic compounds comprising a novel liposome composition with encapsulated metal entities...

  6. Radionuclide transfer from feed to camel milk

    International Nuclear Information System (INIS)

    The transfer of 137Cs, 85Sr, 131I, 210Po, 210Pb and 238U from feed to camel's milk was investigated in a pilot experiment with three lactating camels. For a period of 60 days, the animals were fed on spiked feed containing the studied radionuclides. They were subsequently returned to a contamination-free diet and monitored for another 90 days. The activity concentrations of 137Cs, 85Sr and 131I in milk decreased with time and reached background levels after 20 days. Equilibrium transfer coefficients and biological half-lives were estimated and transfer coefficients were calculated as (8.1 ± 3.6) × 10−4, (4.4 ± 1.6) × 10−2, (7.8 ± 3.9) × 10−4, (2.7 ± 3.5) × 10−4, (1.8 ± 1.5) × 10−4 and (7.0 ± 3.6) × 10−3 d L−1 for 85Sr, 131I, 137Cs, 210Po, 210Pb and 238U, respectively. The biological half-lives were estimated to be 6.4, 4.2, 8.9, and 53.3 days for 85Sr, 131I, 137Cs, and 238U, respectively. Estimates of the half-lives were based on a one component model: it was found that the half-life values measured for artificial radionuclides were slightly shorter than those for natural radionuclides. The data obtained in the study are the first published experimental data on radionuclide transfer to camel milk. - Highlights: • Estimated Fm values for Sr, Cs, Pb, Po tend to be lower compared to other milk producing domestic animals. • The Fm values would help to predict ingestion dose to the general public due to intake of radionuclides through camel. • Estimated half-lives for artificial radionuclides were shorter than those for natural radionuclides. • The data obtained in the study can be considered as the first published data on radionuclide transfer to camel milk

  7. Modelling accumulation of radionuclides in terrestrial ecosystems originating from a long-term groundwater contamination

    Energy Technology Data Exchange (ETDEWEB)

    Gaerdenaes, Annemieke I. [Dept. of Soil and Environment, Swedish University of Agricultural Sciences (SLU), P.O. Box 7001, 750 07 Uppsala (Sweden); Eckersten, Henrik [Dept. of Ecology and Crop Production, SLU, P.O. Box 7042, 750 07 Uppsala (Sweden); Reinlert, Andre [Dept. of Physical Geography and Ecosystems Analysis, Lund University, 223 62 Lund (Sweden); MMT, Sven Kaellfelts Gata 11 SE 426 71 Vaestra Froelunda (Sweden); Gustafsson, David; Jansson, Per-Erik [Dept. Land and Water Resources, KTH, SE 100 44, Stockholm (Sweden); Ekstroem, Per-Anders [Facilia AB, Gustavlundsvaegen 151A, 167 51 Bromma (Sweden); Greger, Maria [Dept. of Ecology, Environment and Plant Sciences, Stockholm University, 106 91 Stockholm (Sweden)

    2014-07-01

    This study was conducted as part of the risk assessment of final deposits of nuclear fuel waste. The overall objective is to assess the possible accumulation of radionuclides in terrestrial ecosystems after an eventual long-term groundwater contamination. The specific objectives are to assess: i) What proportion of the contamination will accumulate in the soil-plant-system? ii) Where in the soil-plant- system will it accumulate? iii) Which ecosystem characteristics and radionuclides properties are important for the accumulation? and iv) Under which circumstances do losses from the ecosystems occur? We developed the dynamic model Tracey (Gaerdenaes et al. 2009) describing cycling of radionuclides in terrestrial ecosystems with high temporal resolution (1 day). The model is a multi-compartmental model in which fluxes and storage of radionuclides are described for different plant parts and soil pools in each of the 10 soil layers. The radionuclide fluxes are driven either by water or carbon fluxes. The water and the carbon fluxes are simulated with the dynamic, bio-geophysical Coup Model (Jansson and Karlberg, 2004). Tracey includes two root uptake approaches of radionuclides; (i) passive uptake driven by root water uptake and (ii) active uptake driven by plant growth. A linear approach describes the adsorption of radionuclides to soil particles and organic matter. Tracey was applied on two ecosystems with contrasting hydrology, the mixed Pinus-Picea forests found in the dry, elevated areas and the Alnus forests found in the wet, low-land areas of Uppland in central east Sweden. Different varieties of the two forest types were created by varying the root depth and radiation use efficiency. The climate was cold-temperate and based on 30-year daily weather data from Uppsala. The assumed groundwater contamination was close to 1 mg of an unspecified radionuclide per m2 and year. This load corresponds to 1 Bq per m{sup 2} and year of {sup 238}U, a common long

  8. Modelling accumulation of radionuclides in terrestrial ecosystems originating from a long-term groundwater contamination

    International Nuclear Information System (INIS)

    This study was conducted as part of the risk assessment of final deposits of nuclear fuel waste. The overall objective is to assess the possible accumulation of radionuclides in terrestrial ecosystems after an eventual long-term groundwater contamination. The specific objectives are to assess: i) What proportion of the contamination will accumulate in the soil-plant-system? ii) Where in the soil-plant- system will it accumulate? iii) Which ecosystem characteristics and radionuclides properties are important for the accumulation? and iv) Under which circumstances do losses from the ecosystems occur? We developed the dynamic model Tracey (Gaerdenaes et al. 2009) describing cycling of radionuclides in terrestrial ecosystems with high temporal resolution (1 day). The model is a multi-compartmental model in which fluxes and storage of radionuclides are described for different plant parts and soil pools in each of the 10 soil layers. The radionuclide fluxes are driven either by water or carbon fluxes. The water and the carbon fluxes are simulated with the dynamic, bio-geophysical Coup Model (Jansson and Karlberg, 2004). Tracey includes two root uptake approaches of radionuclides; (i) passive uptake driven by root water uptake and (ii) active uptake driven by plant growth. A linear approach describes the adsorption of radionuclides to soil particles and organic matter. Tracey was applied on two ecosystems with contrasting hydrology, the mixed Pinus-Picea forests found in the dry, elevated areas and the Alnus forests found in the wet, low-land areas of Uppland in central east Sweden. Different varieties of the two forest types were created by varying the root depth and radiation use efficiency. The climate was cold-temperate and based on 30-year daily weather data from Uppsala. The assumed groundwater contamination was close to 1 mg of an unspecified radionuclide per m2 and year. This load corresponds to 1 Bq per m2 and year of 238U, a common long-living radionuclide in

  9. Tracing Fukushima Radionuclides in the Northern Hemisphere -An Overview

    Science.gov (United States)

    Thakur, Punam; Ballard, Sally; Nelson, Roger

    2013-04-01

    hemisphere. Although the releases from the Fukushima NPP were pronounced, due to significant dilution of the radioactivity in the atmosphere as it was transported across the globe, the concentrations of radionuclides measured outside Japan were extremely low. The activities of I-131, Cs-134, and Cs-137 in air were estimated to have diluted by a factor of 105 to 108 during trans-Pacific transport. This paper will present a compilation of the radionuclide concentrations measured across the northern hemisphere by various national and international monitoring networks. It will focus on the most prevalent cesium and iodine isotopes, but other secondary isotopes will be discussed. Spatial and Temporal patterns and differences will be contrasted. The effects from this global radionuclide dispersal are reported and discussed. The activity ratios of ^131I/^137Cs and ^134Cs/^137Cs measured at several locations are evaluated to gain an insight into the fuel burn-up, the inventory of radionuclides in the reactor and thus on the isotopic signature of the accident. It is important to note that all of the radiation levels detected across the northern hemisphere have been very low and are well below any level of public and environmental concern.

  10. 21 CFR 892.1390 - Radionuclide rebreathing system.

    Science.gov (United States)

    2010-04-01

    ... gaseous or volatile radionuclide or a radionuclide-labeled aerosol and permit it to be respired by the patient during nuclear medicine ventilatory tests (testing process of exchange between the lungs and...

  11. Long-range radionuclide transfer in air and water systems

    International Nuclear Information System (INIS)

    Long-range radionuclide air transfer of radionuclide after the first nuclear explosions and after accidents at nuclear installations is observed. Data on transport of radionuclides by the Yenisej river, Pripyat' river, Sozh river, Iput' river, Besed' river are given. The time of radionuclide transfer from Irish sea to Baltic and Barents sea has been defined using change of a relationship of isotopes Cs 134/Cs 137. (authors)

  12. Radiopharmaceuticals and other compounds labelled with short-lived radionuclides

    CERN Document Server

    Welch, Michael J

    2013-01-01

    Radiopharmaceuticals and Other Compounds Labelled with Short-Lived Radionuclides covers through both review and contributed articles the potential applications and developments in labeling with short-lived radionuclides whose use is restricted to institutions with accelerators. The book discusses the current and potential use of generator-produced radionuclides as well as other short-lived radionuclides, and the problems of quality control of such labeled compounds. The book is useful to nuclear medicine physicians.

  13. Oral intake of radionuclides in the population

    International Nuclear Information System (INIS)

    Dose factors of some radionuclides have been reviewed with respect to a chronic oral intake by means of the public. The radionuclides taken into account are Pu-239, Np-237, Ra-226, Th-230, Pa-231, Tc-99 and I-129, all of which might be of potential hazard at a long term storage disposal. The parameter that have the major influence on the dose factor, for most of the radionuclides studied, is the uptake from the gut. In order to assess the dose factor it is therefore essential to make a good estimate of the gastrointestinal uptake of the radionuclides under the actual conditions. The 'annual limit of intake' (ALI) given in ICRP 30, is intended to be applicable on a population of workers, and for a single intake. Since the gut uptake in the ICRP-publication are based mainly on uptake values recieved in experimental animals, given single relatively large oral doses of the isotope studied. From a review of current literature, gut absorbtion factors and dose factors, to be used for members of the public at a chronic oral intake, are suggested. Compared with those for workers in ICRP 30, the dose factors increase for plutonium and protactinium, and decrease for neptunium. An attempt to predict possible future changes of the ALI for members of the general public is also made. (Author)

  14. Bioaccumulation factors for radionuclides in freshwater biota

    International Nuclear Information System (INIS)

    This report analyzes over 200 carefully selected papers to provide concise data sets and methodology for estimation of bioaccumulation factors for tritium and isotopes of strontium, cesium, iodine, manganese, and cobalt in major biotic components of freshwater environments. Bioaccumulation factors of different tissues are distinguished where significant differences occur. Since conditions in the laboratory are often unnatural in terms of chemical and ecological relationships, this review was restricted as far as possible to bioaccumulation factors determined for natural systems. Because bioaccumulation factors were not available for some shorter-lived radionuclides, a methodology for converting bioaccumulation factors of stable isotopes to those of shorter-lived radionuclides was derived and utilized. The bioaccumulation factor for a radionuclide in a given organism or tissue may exhibit wide variations among bodies of water that are related to differences in ambient concentrations of stable-element and carrier-element analogues. To account for these variations, simple models are presented that relate bioaccumulation factors to stable-element and carrier-element concentrations in water. The effects of physicochemical form and other factors in causing deviations from these models are discussed. Bioaccumulation factor data are examined in the context of these models, and bioaccumulation factor relations for the selected radionuclides are presented

  15. Radionuclide transport in a single fissure

    International Nuclear Information System (INIS)

    The study of radionuclide migration through rock is currently of great interest due to its relevance to the possible escape paths into the biosphere of radionuclides released from high level radioactive wastes burried in deep geological repositories. While water will provide the vehicle for transportation, interaction with geological material may greatly influence the radionuclide movement relative that of water. A flow system for laboratory studies of radionuclide transport in natural fissures in granitic rock under reducing conditions is described. The system based on the use of synthetic ground water equilibrated with granitic rock in a well sealed system, allow experiments to be carried out at -240 mV reduction potential. In flow experiments with technetium the retardation was found to be dependent on the method used for reducing TcO4-. The preparation of the tracer solutions is crucial, as some of the redox-reactions may be very slow. The dynamics of the Tc(VII) reduction and also speciation need to be carried out in separate experiments. (4 illustrations, 5 tables)

  16. Oral intake of radionuclides in the population

    International Nuclear Information System (INIS)

    Dose factors of some radionuclides have been reviewed with respect to a chronic oral intake by members of the public. The radionuclides taken into account are Pu-239, Np-237, Ra-226, Th-230, Pa-231, Tc-99 and I-129, all of which might be of potential hazard at a long term storage disposal. The parameter which has the major influence on the dose factor, for most of the radionuclides studied, is the uptake from the gut. In order to assess the dose factor it is therefore essential to make a good estimate of the gastrointestinal uptake of the radionuclides under the actual conditions. The annual limit of intake (ALI) given in ICRP 30, is intended to be applicable on a population of workers, and for a single intake. Since the gut uptake figures in the ICRP-publication are based mainly on uptake values recieved in experiment animals, given single relatively large oral doses of the isotope studied. From a review of current literature, gut absorbation factors and dose factors, to be used for members of the public at a chronic oral intake, are suggested. Compared with those for workers in ICRP 30, the dose factors increases for plutonium and protactinium, and decreases for neptunium. (Author)

  17. RANCH, Radionuclide Migration in Geological Media

    International Nuclear Information System (INIS)

    1 - Description of problem or function: One-dimensional transport of radionuclide chains through layered geological media, taking into account longitudinal dispersion, convection and retention. 2 - Method of solution: Semi-analytical solution by Laplace transform. Convolution integrals. 3 - Restrictions on the complexity of the problem: Maximum 4 nuclides and 10 layers. Peclet number large compared to 1

  18. A basic toxicity classification of radionuclides

    International Nuclear Information System (INIS)

    In the course of its work in the field of health and safety the International Atomic Energy Agency has often met the practical requirement for grading radionuclides in order of their relative radiotoxicities. This need was particularly evident when the Agency's Basic Safety Standards for the protection of health against ionizing radiation were in preparation, when it was necessary to exempt quantities of radionuclides from inclusion in the norms. A basic toxicity grading might be of help to laboratories in meeting some of their requirements in problems related to waste management as well as for the design of experimental facilities. It should also serve as a basis for the development of safety criteria for laboratory equipment and procedures for handling and transporting various quantities and kinds of radionuclides. The purpose of the present Report is to make a toxicity grading of the radionuclides according to the risk of biological injury which they may cause when they have become incorporated in the human body. 4 refs, 4 tabs

  19. RADIONUCLIDE TRANSPORT MODELS UNDER AMBIENT CONDITIONS

    International Nuclear Information System (INIS)

    The purpose of this model report is to document the unsaturated zone (UZ) radionuclide transport model, which evaluates, by means of three-dimensional numerical models, the transport of radioactive solutes and colloids in the UZ, under ambient conditions, from the repository horizon to the water table at Yucca Mountain, Nevada

  20. Removal of radionuclides at a waterworks

    DEFF Research Database (Denmark)

    Gäfvert, T.; Ellmark, C.; Holm, E.

    2002-01-01

    filtration and from the municipal distribution network. The samples were analysed with respect to their content of uranium, thorium, polonium, radium, plutonium and caesium. The results show a high removal capacity for uranium (about 85%), thorium (>90%), plutonium (>95%) and polonium (>90...... concentrations for the naturally occurring radionuclides and plutonium....

  1. RADIONUCLIDE TRANSPORT MODELS UNDER AMBIENT CONDITIONS

    Energy Technology Data Exchange (ETDEWEB)

    S. Magnuson

    2004-11-01

    The purpose of this model report is to document the unsaturated zone (UZ) radionuclide transport model, which evaluates, by means of three-dimensional numerical models, the transport of radioactive solutes and colloids in the UZ, under ambient conditions, from the repository horizon to the water table at Yucca Mountain, Nevada.

  2. Biogeochemical cycles of Chernobyl-born radionuclides in the contaminated forest ecosystems: long-term dynamics of the migration processes

    Science.gov (United States)

    Shcheglov, Alexey; Tsvetnova, Ol'ga; Klyashtorin, Alexey

    2013-04-01

    Biogeochemical migration is a dominant factor of the radionuclide transport through the biosphere. In the early XX century, V.I. Vernadskii, a Russian scientist known, noted about a special role living things play in transport and accumulation of natural radionuclide in various environments. The role of biogeochemical processes in migration and redistribution of technogenic radionuclides is not less important. In Russia, V. M. Klechkovskii and N.V. Timofeev-Ressovskii showed some important biogeochemical aspects of radionuclide migration by the example of global fallout and Kyshtym accident. Their followers, R.M. Alexakhin, M.A. Naryshkin, N.V. Kulikov, F.A. Tikhomirov, E.B. Tyuryukanova, and others also contributed a lot to biogeochemistry of radionuclides. In the post-Chernobyl period, this area of knowledge received a lot of data that allowed building the radioactive element balance and flux estimation in various biogeochemical cycles [Shcheglov et al., 1999]. Regrettably, many of recent radioecological studies are only focused on specific radionuclide fluxes or pursue some applied tasks, missing the holistic approach. Most of the studies consider biogeochemical fluxes of radioactive isotopes in terms of either dose estimation or radionuclide migration rates in various food chains. However, to get a comprehensive picture and develop a reliable forecast of environmental, ecological, and social consequences of radioactive pollution in a vast contaminated area, it is necessary to investigate all the radionuclide fluxes associated with the biogeochemical cycles in affected ecosystems. We believe such an integrated approach would be useful to study long-term environmental consequences of the Fukushima accident as well. In our long-term research, we tried to characterize the flux dynamics of the Chernobyl-born radionuclides in the contaminated forest ecosystems and landscapes as a part of the integrated biogeochemical process. Our field studies were started in June of

  3. Assessment of the radiation exposure of man due to radionuclides in the ground water

    International Nuclear Information System (INIS)

    The radioecological simulation model ECOSYS-87-B has been developed in order to assess the potential radiation exposure of infants and adults due to radionuclides in the ground water released from a radioactive waste repository and used as drinking water for humans and animals as well as for irrigation of food and feed crops emphasizing on a realistic simulation of the radionuclide transfer in the food chain. From the calculations with ECOSYS-87-B, assuming a normalized activity concentration of 1 Bq/l in the ground water, for each radionuclide considered the following conclusions can be drawn: - The most important contamination processes for plants is due to direct deposition of radionuclides on the foliage and due to the uptake from the soil. - For element with transfer factors soil-plant below 0.001 the contamination of plants due to resuspension of contaminated soil exceeds the uptake via the roots. - The involuntary intake of contaminated soil by grazing animals dominates the root uptake for elements with transfer factors soil-grass below 0.005. - Although the activity intakes of adults are higher than for infants, the doses for infants are exceeding the potential doses for adults for all radionuclides considered, except Cs-135 and Pa-231. - For infants and adults, the intake of drinking water is by far the most important pathway for nearly all of the radionuclides considered. - Among the foodstuffs, cereals, milk and leafy vegetables are most important for the potential radiation exposure. - A sensitivity analysis shows that an enhanced consumption of plants food products leads to higher potential radiation exposures whereas and increased fraction of meat in the food basket results in lower doses. (30 refs.) (au)

  4. Sediment and radionuclide transport in rivers: radionuclide transport modeling for Cattaraugus and Buttermilk Creeks, New York

    Energy Technology Data Exchange (ETDEWEB)

    Onishi, Y.; Yabusaki, S.B.; Kincaid, C.T.; Skaggs, R.L.; Walters, W.H.

    1982-12-01

    SERATRA, a transient, two-dimensional (laterally-averaged) computer model of sediment-contaminant transport in rivers, satisfactorily resolved the distribution of sediment and radionuclide concentrations in the Cattaraugus Creek stream system in New York. By modeling the physical processes of advection, diffusion, erosion, deposition, and bed armoring, SERATRA routed three sediment size fractions, including cohesive soils, to simulate three dynamic flow events. In conjunction with the sediment transport, SERATRA computed radionuclide levels in dissolved, suspended sediment, and bed sediment forms for four radionuclides (/sup 137/Cs, /sup 90/Sr, /sup 239/ /sup 240/Pu, and /sup 3/H). By accounting for time-dependent sediment-radionuclide interaction in the water column and bed, SERATA is a physically explicit model of radionuclide fate and migration. Sediment and radionuclide concentrations calculated by SERATA in the Cattaraugus Creek stream system are in reasonable agreement with measured values. SERATRA is in the field performance phase of an extensive testing program designed to establish the utility of the model as a site assessment tool. The model handles not only radionuclides but other contaminants such as pesticides, heavy metals and other toxic chemicals. Now that the model has been applied to four field sites, including the latest study of the Cattaraugus Creek stream system, it is recommended that a final model be validated through comparison of predicted results with field data from a carefully controlled tracer test at a field site. It is also recommended that a detailed laboratory flume be tested to study cohesive sediment transport, deposition, and erosion characteristics. The lack of current understanding of these characteristics is one of the weakest areas hindering the accurate assessment of the migration of radionuclides sorbed by fine sediments of silt and clay.

  5. Diffusion of radionuclides in concrete/bentonite systems

    International Nuclear Information System (INIS)

    In a repository for nuclear waste, different construction materials will be used. Two important materials among these are concrete and bentonite clay. These will act as mechanical barriers, preventing convective water flow and also retard transport due to diffusion of dissolved radionuclides by a combination of mechanical constraints and chemical interactions with the solid. An important issue is the possible change of the initial sodium bentonite into the calcium form due to ion exchange with calcium from the cement. The initial leaching of the concrete has been studied using radioactive spiked concrete in contact with compacted bentonite. The diffusion of Cs, Am and Pu into 5 different types of concrete in contact with porewater have been measured. The measured diffusivity for Cs agrees reasonable well with data found in literature. For Am and Pu no movement could be measured (less than 0.2 mm) even though the contact times were extremely long (2.5 y and 5 y, respectively). This report gives also a summary of the previously published results about sorption and diffusion of radionuclides in cement performed in Prav/KBS/SKB projects 1980-1990. 25 refs

  6. NSARP reference document: radionuclide transport through the geosphere, January 1992

    International Nuclear Information System (INIS)

    UK Nirex Ltd is planning the development of a deep geological repository at Sellafield in Cumbria for the disposal of solid low-level and intermediate-level radioactive wastes. The post-closure performance assessments for this repository are being undertaken by the Nirex Disposal Safety Assessment Team (DSAT), which was set up specifically to carry out such assessments. The broad objectives of this programme are: to understand the important physical, chemical and biological processes that govern the transport of radionuclides away from the repository; to construct models that provide a good representation of these processes, allowing the description of what is currently observed and the prediction of future evolution; to provide data, by laboratory and field investigations, for the important parameters and radionuclides; to provide advice to Nirex on matters such as repository materials and to liaise with the DSAT, so that the research is focused on key processes and parameters. This report is one of four reference documents that record information from the Nirex Safety Assessment Research Programme (NSARP) being used in repository performance assessments. (author)

  7. Calculated distribution of radionuclides in soils and sediments

    International Nuclear Information System (INIS)

    The description of the accumulation of radionuclides in some biospheric compartments is in general based on a sorption distribution coefficient Kd. This value is very decisive for the concentration of long-lived radionuclides in reservoirs that are important from the dose point of view. Sorption is due to several processes such as ion-exchange and a variety of physical and chemical interactions which are difficult to interpret with the current Kd-methodology. In addition, many of the Kd values are obtained from laboratory or geospheric conditions not comparable to conditions prevailing in the biosphere. The main objective with this work is to deepen the knowledge about the theoretical background of Kd-values. To achieve this purpose, available theoretical models for ion-exchange and surface complexation have been adapted for simulation under biospheric conditions. The elements treated are cesium, radium, neptunium, uranium and plutonium The results show that a triple layer surface complexation model may be used in estimating Kd-values for actinides as a function of important chemical parameters such as pH and EH. It is concluded that by estimating some equilibrium constants and making some careful approximations, surface complexation models can be used for performance assessment of radioactive waste repositories. 72 refs, 7 figs

  8. Radionuclides concentration in foods in Peninsular Malaysia

    International Nuclear Information System (INIS)

    The concentrations of natural radionuclides (U-238, Th-232, Ra-226, Ra-228 and K-40) and artificial radionuclides (Cs-137) in fresh, dried and cooked foodstuffs from 30 major towns in Peninsular Malaysia were determined by gamma spectrometry system and Instrumental Neutron Activation Analysis (INAA) technique. A total of 232 samples representing a typical Malaysian community diet were analysed. The results showed that most of the samples contained only natural radionuclides. The percentage of radionuclides detected in the samples were found about 2% for U-238, 9% for Th-232, 49% for Ra-226, 77% for Ra-228, 99% for K-40 and 15% for Cs-137. The radionuclide concentrations were in the ranges of <6.1 - 29.3, <2.0 - 55.8, <0.1 - 34.4, <0.1 - 41, <0.1- 2552.3 and < 0.1 - 6.6 Bq/Kg dry weight for U-238, Th-232, Ra-226, Ra-228 and K-40 and Cs-137 respectively. The study revealed that most of the foodstuffs did not contain U-238. Lentils were found to contain significant concentration of Th-232 (4 - 49 Bq/kg) and can be considered as thorium accumulators. The concentrations of Ra-226 and Ra-228 in leafy vegetables were higher than the fruit and root vegetables. These data can be used as a reference for future food radioactivity monitoring. As edible mushroom and fern had high concentrations of Cs-137, indicating their high ability to accumulate Cs-137, they could be used as indicator plants in the event of radioactive fall outs

  9. Radionuclide distributions and sorption behavior in the Susquehanna--Chesapeake Bay System

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, C.R.; Larsen, I.L.; Lowry, P.D.; McLean, R.I.; Domotor, S.L.

    1989-01-01

    Radionuclides released into the Susquehanna--Chesapeake System from the Three Mile Island, Peach Bottom, and Calvert Cliffs nuclear power plants are partitioned among dissolved, particulate, and biological phases and may thus exist in a number of physical and chemical forms. In this project, we have measured the dissolved and particulate distributions of fallout /sup 137/Cs; reactor-released /sup 137/Cs, /sup 134/Cs, /sup 65/Zn, /sup 60/Co, and /sup 58/Co; and naturally occurring /sup 7/Be and /sup 210/Pb in the lower Susquehanna River and Upper Chesapeake Bay. In addition, we chemically leached suspended particles and bottom sediments in the laboratory to determine radionuclide partitioning among different particulate-sorbing phases to complement the site-specific field data. This information has been used to document the important geochemical processes that affect the transport, sorption, distribution, and fate of reactor-released radionuclides (and by analogy, other trace contaminants) in this river-estuarine system. Knowledge of the mechanisms, kinetic factors, and processes that affect radionuclide distributions is crucial for predicting their biological availability, toxicity, chemical behavior, physical transport, and accumulation in aquatic systems. The results from this project provide the information necessary for developing accurate radionuclide-transport and biological-uptake models. 76 refs., 12 figs.

  10. Activity concentrations of radionuclides in energy production from peat, wood chips and straw

    International Nuclear Information System (INIS)

    In this thesis quantitative analyses of radionuclide concentrations in bioenergy fuels such as peat, wood chips and straw are presented. For comparison a brief description is included of radionuclide concentrations and radiation doses from other sources of power and also from some industrial applications. Radioactive potassium is found in most materials and is the most easily detected radionuclide in fuels. It's activity concentration in Bq/kg normally dominates over the concentration of other natural radionuclides. The radiation dose from K in emission from combustion is nevertheless negligible. The most important radionuclides in the dose to man are the U- and Th-isotopes and 210Pb and 210Po. 137Cs is the most common nuclide among the fission products in fallout from the Chernobyl accident. Compared to natural nuclides, the contribution from emission of 137Cs is less than a few percent of the total dose to the population. A total dose of approx. only a few μSv from inhalation can be calculated from the emission of a district heating plant in Sweden. This dose can be compared with the annual dose limit to the public from nuclear industry, which is 0.1 mSv and the global collective effective dose of 5 manSv/year. 143 refs

  11. Accumulation of artificial radionuclides in agricultural plants in the area used for surface nuclear tests

    International Nuclear Information System (INIS)

    The paper reports on the study of artificial radionuclide accumulation in agricultural crops grown at the territory with high concentration of radionuclides, and first of all – with high concentration of transuranium elements. As a result of this work, peculiarities of accumulation and distribution of artificial radionuclides in the vegetative and generative organs of the studied plants have been revealed. Basic accumulation factors have been found for 137Cs, 90Sr, 239+240Pu, and 241Am in agricultural products. Accumulation factor dependence on type of planting was found for the investigated types of plants. It has been found that the vegetative organs accumulate radionuclides most of all. - Highlights: • The experiment with plants was performed under natural conditions in the area of ground nuclear explosions at “Experimental field” site of the Semipalatinsk test site. • Nature of radionuclides distribution in different plant organs has been revealed. • Main accumulation factors for 137Cs, 90Sr, 239+240Pu and 241Am have been obtained for the crop products. • Obtained results are of particular importance in the issues related to assessments of radiological environmental contamination and its consequences

  12. Quantification of radionuclide uptake levels for primary bone tumors

    Directory of Open Access Journals (Sweden)

    Hasford Francis

    2015-04-01

    Full Text Available The purpose of the study is to quantify the level of uptake of administered radionuclide in primary bone tumors for patients undergoing bone scintigraphy. Retrospective study on 48 patient's scintigrams to quantify the uptake levels of administered radiopharmaceuticals was performed in a nuclear medicine unit in Ghana. Patients were administered with activity ranging between 0.555 and 1.110 MBq (15–30 mCi, and scanned on Siemens e.cam SPECT system. Analyses on scintigrams were performed with Image J software by drawing regions of interest (ROIs over identified hot spots (pathologic sites. Nine skeletal parts namely cranium, neck, shoulder, sacrum, sternum, vertebra, femur, ribcage, and knee were considered in the study, which involved 96 identified primary tumors. Radionuclide uptakes were quantified in terms of the estimated counts of activity per patient for identified tumor sites. Average normalized counts of activity (nGMC per patient ranged from 5.2759 ± 0.6590 cts/mm2/MBq in the case of cranium tumors to 72.7569 ± 17.8786 cts/mm2/MBq in the case of ribcage tumors. The differences in uptake levels could be attributed to different mechanisms of Tc-99m MDP uptake in different types of bones, which is directly related to blood flow and degree of osteoblastic activity. The overall normalized count of activity for the 96 identified tumors was estimated to be 23.0350 ± 19.5424 cts/mm2/MBq. The study revealed highest uptake of activity in ribcage and least uptake in cranium. Quantification of radionuclide uptakes in tumors is important and recommended in assessing patient's response to therapy, doses to critical organs and in diagnosing tumors.

  13. Methodology for implementation of a national metrology net of radionuclides used in nuclear medicine

    International Nuclear Information System (INIS)

    The National Laboratory for Ionizing Radiation Metrology, of the Institute of Radiation Protection and Dosimetry, of the National Commission on Nuclear Energy (IRD/CNEN), comes leading a comparison program for activity measurements of radiopharmaceuticals administered to patients in the Nuclear Medicine Services (NMS) with the purpose to promote the quality control. This work presents a quality assurance program for the performance of such measurements, evaluated in the comparison runs between hospitals and LNMRI, under the statistic point of view and the compliment of regulatory authority norms. The performance of the radionuclides 67Ga, 123I, 131I,99mTc and 210Tl were evaluated and 201TI have been standardized by absolute methods. Besides, it was established the traceability of the radioactivity standards used in nuclear medicine and a methodology for implementation of a national metrology net of radionuclides. The comparison results prove that the implementation of a radionuclide metrology net is viable, important and feasible. (author)

  14. Proposed development of a radionuclide washoff model for the German Reactor Safety Study

    International Nuclear Information System (INIS)

    This report presents a brief overview of the possible development of a model for the attenuation of radionuclide concentrations in urban environments due to rainfall/runoff relationships. The following sequence of actions is suggested: (1) preliminary review, (2) exploratory modeling, (3) detailed literature review, (4) development of mathematical model, (5) development of computer model, and (6) model review including verification and sensitivity analysis. To facilitate the initiation of the indicated efforts, an introduction to the relevant literature is provided. Further, the following topics are also briefly discussed: (1) radionuclide transport and removal in the terrestrial environment, (2) need for a description of the chemical and physical forms of the radionuclides released in a reactor accident, and (3) potential importance of surface-water contamination. (orig./HP)

  15. Determination of radionuclides present in the relation of waste plant storage of El Cabril

    International Nuclear Information System (INIS)

    Different waste streams of low and medium level radioactive are generated from the operation of Nuclear Power Plants with light water reactors. The most important waste streams are: spent ion exchange resin, used to purify the water of the reactor coolant and the evaporator concentrates produced in the evaporation of some liquid radioactive waste. In this paper are show the improvement and development of the analytical methods of all these radionuclides, performed in the CIEMAT project about Characterization of Radioactive Wastes and Materials. The alpha, beta and low energy gamma-emitting radionuclides are analyzed after the separation procedure by alpha-spectrometry, liquid scintillation counting and low-energy gamma spectrometry. The high energy gamma-emitting radionuclides (>50 keV) are analyzed by gamma spectrometry without separation. This work has been developed within the framework of the CIEMAT-ENRESA Association Agreement. (Author) 12 refs

  16. Aspects of uranium/thorium series disequilibrium applications to radionuclide migration studies

    International Nuclear Information System (INIS)

    The aim of this paper is to consider the contribution which the uranium/thorium series disequilibrium concept can make to understanding the retardation and transport of radionuclides in the far-field of a radioactive waste repository. In principle, naturally occurring isotopes of uranium, thorium and radium can be regarded as geochemical analogues of the divalent radionuclides and multivalent actinides expected to be present in the radioactive waste inventory. The study of their retardation and/or transport in real rock/water systems which have taken place over geological timescales, can make an important contribution to establishing a rational basis for long-term predictive modelling of radionuclide transport required for safety assessments. (author)

  17. Review of speciation and solubility of radionuclides in the near and far field. Pt. 2

    International Nuclear Information System (INIS)

    This report represents Part 2 in a series of three reports which review the speciation and solubility of radionuclides in the near and far field. Part 2 is a general bibliography from 1978 to 1991. This report contains the bibliography for the review of speciation and solubility radionuclides in the near and far field from 1978 to 1991. The importance of the solubility and speciation of radionuclides in relation to the safety assessment of the repository is discussed. Solubility is defined, both theoretically and pragmatically, and the factors which influence solubility and speciation are discussed. The literature search was performed using the INIS database. The UKAEA RECAP database, the NIREX report bibliography and a list of DOE reports provided by the DOE were also used. The bibliography is divided into five sections, solubility and speciation experimental data, basic thermodynamic data, solubility limiting solid phases, experimental design and review and overview articles. Some references appear in more than one section. (Author)

  18. Publications of AFR-members on the subject of Applied radionuclide technology

    International Nuclear Information System (INIS)

    This compilation prepared for the first time in this form and containing publications announced by the AFR office on the subject of 'Applied radionuclide technology' does neither claim completeness nor is it clearly visible that all contributions relate to the year 1980. None the less, this compilation of reports of results, together with the 'General Program on the Advancement of the Radionuclide Technology' (AFR report No. 001) and the AFR subject list, constitute an important reference to the documentation of results achieved within the preceding period of time. It is thus possible to compare, at least in partial areas of the application spectrum of radionuclide technology, scientific problems with solutions realized. (orig./HP)

  19. Effective dose per unit intake of radionuclides by adults and young people

    International Nuclear Information System (INIS)

    This paper describes the NRPB's computerised database of effective dose and organ doses per unit intake by adults, children (10 years) and infants (1 year) of over 300 radionuclides. It describes and discusses the changes that have recently been made to the database and lists effective dose equivalents for intakes by inhalation and ingestion of 48 of the more important nuclides. (author)

  20. Chemical Speciation of Long-lived Radionuclide Technetium-99 and its Environmental Behaviour

    DEFF Research Database (Denmark)

    Shi, Keliang

    Because of the high fission yield, high mobility and long half-life, technetium-99 is considered to be one of the most important radionuclides in environmental trace application as well as nuclear waste management. The study on the determination of technetium and its speciation is therefore a key...

  1. Geochemical ways of artificial radionuclide migration in biosphere

    International Nuclear Information System (INIS)

    This collection presents abstracts of papers on the following subjects: organization and methodology of research and developments on creation of combined medium- and largescale landscape-geochemical and radioecological maps for territories contaminated by radionuclides; typological and space features of distribution of artificial radionuclides and regularities of their migration, the radionuclides being entered the biosphere during accidents at NPPs; forms of artificial radionuclides in biosphere after the NPP accidents; simulation of primary entering and secondary migration of radionuclides in biosphere; methodology of organization and conducting radiogeochemical monitoring of biosphere; new methods and means for radiation monitoring of the environment

  2. Interlaboratory comparison: Radionuclides in Irish sea water. IAEA-443

    International Nuclear Information System (INIS)

    Our society is giving increasing importance to the study and assessment of the state and health of the environment. Organizations involved in such activities rely on the quality of the information provided and, ultimately, on the precision and accuracy of the data on which the information is based. Many laboratories are involved in the production of environmental data, in many cases leading to wider assessments. These laboratories may develop and validate new analytical methods, study the environmental impact of human activities, provide services to other organizations, etc. In particular, laboratories are providing data on levels of radioactivity in a variety of marine matrixes such as water, suspended matter, sediments and biota. Because of the need to base scientific conclusions on valid and internationally comparable data, the need to provide policy makers with correct information and the need for society to be informed of the state of the environment, it is indispensable to ensure the quality of the data produced by each laboratory. Principles of good laboratory practice require both internal and external procedures to verify the quality of the data produced. Internal quality is verified in a number of ways, such as the use of laboratory information systems, keeping full records of equipment performance and standardization of analytical procedures. External quality can also be ascertained in a number of ways, notably accreditation by an external body under a defined quality scheme but also, amongst others, the use of internationally accepted calibration standards that are traceable to the SI international system of units, the participation in interlaboratory comparisons or the regular use of Reference Materials to test laboratory performance. The Radiometrics Laboratory of the International Atomic Energy Agency's Marine Environment Laboratories has been providing quality products for the last 40 years, which include the organization of interlaboratory

  3. Alligator Rivers Analogue project. Radionuclide transport. Final Report - Volume 14

    Energy Technology Data Exchange (ETDEWEB)

    Golian, C. [Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia); Lever, D.A.; Baker, A.J.; Connell, L.D. [AEA Decommissioning and Radwaste, Harwell (United Kingdom); Bennett, D.G.; Read, D. [WS Atkins Science and Technology Epsom Surrey (United Kingdom); Lindgreen, M.; Pers, K.; Skagius, K. [Kemakta Consultants co., Stockholm (Sweden); Murakami, T.; Ohnuki, T. [Japan Atomic Energy Research Institute, Tokai-mura, IBARAKI (Japan)

    1992-12-31

    The Koongarra orebody and its associated dispersion fan are examined as a geological analogue for the transport of radionuclides from waste repositories. The aim is to build a consistent picture of the transport that has been taking place in the orebody and the important processes controlling the retardation of uranium series isotopes and to test models of radionuclide transport. A particularly distinctive feature of the Koongarra system is the strong seasonal dependence of the groundwater flow. However, the Koongarra system is similar to a radioactive waste disposal system in that mobilization of uranium is taking place as a result of the infiltration of groundwaters that are in gross chemical disequilibrium with the mineralogy of the primary ore body. There are considerable differences between the Koongarra uranium orebody and a radioactive waste repository, particularly a deep waste repository. The Koongarra system is shallow, affected by seasonal hydrogeological changes as well as climatic variations on a longer timescale and transport is taking place in a zone of active weathering. Some of these features make the Koongarra system harder to characterise than a deep repository. However, there are nevertheless many analogies between the processes occurring at Koongarra and those occurring around a deep or shallow waste repository. The difficulties encountered because of the heterogeneity of the Koongarra weathered zone mirror those to be addressed in assessing radionuclide transport in repository systems. The {sup 234}U/{sup 238}U activity ratios in rock samples from the dispersion fan decrease in the direction of groundwater transport, whereas in many other systems it has been reported that {sup 234}U is preferentially mobile relative to {sup 238}U (Osmond and Cowart, 1982; Osmond et al., 1983). As most uranium resides in the rock rather than in the groundwater, the net recoil flux of uranium daughter radionuclides is usually from the rock to the groundwater

  4. Review of Russian-language studies on radionuclide behaviour in agricultural animals: part 4. Transfer to poultry

    Energy Technology Data Exchange (ETDEWEB)

    Fesenko, S. [International Atomic Energy Agency, 1400 Vienna (Austria)], E-mail: s.fesenko@iaea.org; Howard, B.J. [Centre for Ecology and Hydrology, Lancaster Environment Centre, Library Avenue, Bailrigg, Lancaster LAI 4AP (United Kingdom); Isamov, N. [Russian Institute of Agricultural Radiology and Radioecology, 249020 Obninsk (Russian Federation); Beresford, N.A.; Barnett, C.L. [Centre for Ecology and Hydrology, Lancaster Environment Centre, Library Avenue, Bailrigg, Lancaster LAI 4AP (United Kingdom); Sanzharova, N. [Russian Institute of Agricultural Radiology and Radioecology, 249020 Obninsk (Russian Federation); Voigt, G. [International Atomic Energy Agency, 1400 Vienna (Austria)

    2009-10-15

    Data on radionuclide transfer to domestic chickens and ducks obtained from research performed in the former Soviet Union were reviewed to provide transfer coefficient values (Ff) to poultry and edible egg contents. The majority of the data are from experiments with {sup 90}Sr and {sup 137}Cs, reflecting the importance of these radionuclides after global fallout and major radiation accidents. Data for {sup 3}H, {sup 54}Mn, {sup 59}Fe, {sup 60}Co, {sup 22}Na {sup 65}Zn, {sup 131}I and U are also given. The values derived have been compared with those in the current IAEA Handbook of parameter values for the prediction of radionuclide transfer in temperate environments (TRS 364) and the recent revision which incorporates the values from this paper. The Russian-language data give improved estimates for many radionuclides and the revised handbook is now based on the better quality data given for chronic administration.

  5. Uptake by plants of radionuclides from FUSRAP waste materials

    Energy Technology Data Exchange (ETDEWEB)

    Knight, M.J.

    1983-04-01

    Radionuclides from FUSRAP wastes potentially may be taken up by plants during remedial action activities and permanent near-surface burial of contaminated materials. In order to better understand the propensity of radionuclides to accumulate in plant tissue, soil and plant factors influencing the uptake and accumulation of radionuclides by plants are reviewed. In addition, data describing the uptake of the principal radionuclides present in FUSRAP wastes (uranium-238, thorium-230, radium-226, lead-210, and polonium-210) are summarized. All five radionuclides can accumulate in plant root tissue to some extent, and there is potential for the translocation and accumulation of these radionuclides in plant shoot tissue. Of these five radionuclides, radium-226 appears to have the greatest potential for translocation and accumulation in plant shoot tissue. 28 references, 1 figure, 3 tables.

  6. Uptake by plants of radionuclides from FUSRAP waste materials

    International Nuclear Information System (INIS)

    Radionuclides from FUSRAP wastes potentially may be taken up by plants during remedial action activities and permanent near-surface burial of contaminated materials. In order to better understand the propensity of radionuclides to accumulate in plant tissue, soil and plant factors influencing the uptake and accumulation of radionuclides by plants are reviewed. In addition, data describing the uptake of the principal radionuclides present in FUSRAP wastes (uranium-238, thorium-230, radium-226, lead-210, and polonium-210) are summarized. All five radionuclides can accumulate in plant root tissue to some extent, and there is potential for the translocation and accumulation of these radionuclides in plant shoot tissue. Of these five radionuclides, radium-226 appears to have the greatest potential for translocation and accumulation in plant shoot tissue. 28 references, 1 figure, 3 tables

  7. Effects of the variation of samples geometry on radionuclide calibrator response for radiopharmaceuticals used in nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Albuquerque, Antonio Morais de Sa; Fragoso, Maria Conceicao de Farias; Oliveira, Mercia L. [Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife, PE (Brazil)

    2011-07-01

    In the nuclear medicine practice, the accurate knowledge of the activity of radiopharmaceuticals which will be administered to the subjects is an important factor to ensure the success of diagnosis or therapy. The instrument used for this purpose is the radionuclide calibrator. The radiopharmaceuticals are usually contained on glass vials or syringes. However, the radionuclide calibrators response is sensitive to the measurement geometry. In addition, the calibration factors supplied by manufactures are valid only for single sample geometry. To minimize the uncertainty associated with the activity measurements, it is important to use the appropriate corrections factors for the each radionuclide in the specific geometry in which the measurement is to be made. The aims of this work were to evaluate the behavior of radionuclide calibrators varying the geometry of radioactive sources and to determine experimentally the correction factors for different volumes and containers types commonly used in nuclear medicine practice. The measurements were made in two ionization chambers of different manufacturers (Capintec and Biodex), using four radionuclides with different photon energies: {sup 18}F, {sup 99m}Tc, {sup 131}I and {sup 201}Tl. The results confirm the significant dependence of radionuclide calibrators reading on the sample geometry, showing the need of use correction factors in order to minimize the errors which affect the activity measurements. (author)

  8. Role of soil micro-organisms in the sorption of radionuclides in organic systems

    International Nuclear Information System (INIS)

    Although the fraction of radionuclides linked to soil organic matter and soil microorganisms may be relatively small when compared to the amount bound to the mineral constituents, (mostly irreversibly bound), this fraction is of great importance as it remains readily exchangeable and is thus available for plant uptake. Many studies have measured the uptake of radionuclides by organic soils but the role of soil micro-organisms may have been masked by the presence of even small amounts of clay minerals occurring in these soils. We have carried out a series of experiments using a biologically active, 'mineral-free' organic soil produced under laboratory conditions, to determine the potential of soil micro-organisms to accumulate radionuclides Cs-134 and Sr-85. Biological uptake and release was differentiated from abiotic processes by comparing experimental results with inoculated and non-inoculated sterile organic material. We have investigated the role of different clay minerals, competing potassium and calcium ions, and changes in temperature on the sorption of Cs and Sr isotopes. The results from studies so far show conclusively that living components of soil systems are of primary importance in the uptake of radionuclides in organic material, microorganisms also influence the importance of chemical factors (e.g. adsorption to clay minerals) which may play a secondary role in these highly organic systems. In further experiments we hope to define the precise role of specific soil micro-organisms in these organic systems. (author)

  9. Coprecipitation of radionuclides: basic concepts, literature review and first applications

    Energy Technology Data Exchange (ETDEWEB)

    Curti, E. [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1997-11-01

    Coprecipitation of radionuclides with solid products is currently not analysed quantitatively in safety assessments for nuclear waste repositories, although this process is thought to be an important mechanism for limiting nuclide concentrations in solution. This is due to the fact that neither the solid phases controlling coprecipitation nor the parameter values necessary to describe this process are known sufficiently. This introductory report provides basic knowledge on this subject and a review of experimental data from the literature. Emphasis is placed on experiments of trace metal coprecipitation with calcite, because this mineral is a dominating alteration product of cement in the Swiss L/ILW repository. This resulted in a database of partition coefficients, which allow to describe empirically the distribution of trace elements between calcite and solution and thus to quantify coprecipitation processes. Since laboratory data on coprecipitation with calcite are lacking for many safety-relevant radioelements, their partition coefficients were inferred with the help of estimation techniques. Such techniques rely on empirical correlations, which relate the uptake of trace metals in calcite (measured in laboratory tests) with selected chemical properties of the coprecipitated metals (e.g. ionic radius, sorption properties, solubility products of the pure trace metal carbonates). The combination of these correlations with independent geochemical evidence allows the extrapolation of radioelement-specific partition coefficients, which are then used for the quantitative modelling. In a first step the potential role of radionuclide coprecipitation during cement degradation in the L/ILW repository planned at Wellenberg is assessed. (author) figs., tabs., refs.

  10. Improving cancer treatment with cyclotron produced radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Larson, S.M. Finn, R.D.

    1992-08-04

    This report describes the author's continuing long term goal of promoting nuclear medicine applications by improving the scientific basis for tumor diagnosis treatment and treatment follow-up based on the use of cyclotron produced radiotracers in oncology. The program has 3 interactive components: Radiochemistry /Cyclotron; Pharmacology; and Immunology. An essential strategy is as follows: novel radionuclides and radiotracers developed in the Radiochemistry/Cyclotron section under the DOE grant during the 1989--1992 grant period, will be employed in the Pharmacology and Immunology sections of the DOE grant during the 1992--1995 grant period. The development of novel radionuclides and tracers is of course useful in and of itself, but their utility is greatly enhanced by the interaction with the immunology and pharmacology components of the program.

  11. Sorption of radionuclides on a soil

    International Nuclear Information System (INIS)

    Disposal of radioactive wastes into the ground has been discussed, and this paper emphasized significance of the investigation for underground water flow and for the prediction of radionuclides through a stratified aquifer using column experiments to evaluate the internal radiation dose. Distributions and redistributions of radionuclides in a sandy layer were observed to identify the sorption model which predicts the behavior, and the underground water flow in the Plio-Pleistocene Osaka Group was investigated as an example, by mean of the measurement of 222Rn concentration, the pumping technique and the tracer technique using the activation analysis. Then, the estimation of radioactive concentration in the underground water was worked out for the boundary condition of steady state inflow of liquid wastes and of which the 90Sr are leached from the solidified body, moreover, the equation which easily evaluates the suitability of the disposal site was proposed. These approach may be useful for the actual site selection of radioactive wastes disposal. (author)

  12. Intakes of radionuclides by young people

    International Nuclear Information System (INIS)

    A general conclusion is drawn from this study is that if, for members of the public, both the dietary composition and the metabolic parameters of radionuclides are independent of age, the committed dose equivalents for young persons are broadly similar to those for adults and are never more than three times greater when all age groups are exposed to the same concentrations of radionuclides in air and foodstuffs. The differences in committed effective dose equivalents (which are weighted averages of committed dose equivalents) will be even smaller. It seems possible, therefore, that the critical groups' within the population will be principally determined by differences in dietary composition and in metabolic or retention parameters. (author)

  13. Radionuclide transport in the Yenisei River

    CERN Document Server

    Vakulovsky, S M; Kabanov, A I

    2012-01-01

    Data characterizing the pollution of the Yenisei River (water and bottom sediment) by radionuclide resulting from the use of the river water for cooling industrial reactors in the Mining-Chemical Complex are presented. Studies have been made of the contamination of the river during the period when reactors with direct flow cooling were used and after these were shut down. Distinctive features of the migration of radionuclide in the Yenisei are noted, in particular, their distribution between the solid and liquid phases. The amounts of 137Cs, 65Zn, 60Co, 54Mn, and 152Eu in the channel are determined from the effluent discharge site to Dudinka port. The rate of continuous self removal of 137Cs is estimated to be 0.19 1/year, corresponding to a half purification time of 3.6 years for a 600 km long segment of the river bed.

  14. Behaviors of radionuclides in wet underground soil

    International Nuclear Information System (INIS)

    Experimental studies were made of the variations of the distribution coefficient of 65Zn, 60Co, and /sup 110 m/Ag with Ca ion contents in sand--water and resin--water systems. It is concluded that: (1) The distribution coefficient of a radionuclide is not constant but varies greatly especially with calcium ion concentration in underground water. (2) The Saturation Index I=pH-pHs can be used as a parameter to indicate such variations. (3) Some radionuclides, existing as radiocolloids like (sup 110m/Ag and 59Fe, are inactive toward ion exchange reactions as with hydroxide. In such cases, the nuclides migrate underground as fast as underground water

  15. Radionuclides accumulation in milk and its products

    Energy Technology Data Exchange (ETDEWEB)

    Marmuleva, N.I.; Barinov, E.Y.; Petukhov, V.L. [Novosibirsk State Agrarian University (Russian Federation)

    2003-05-01

    The problem of radioactive pollution is extremely urgent in Russia in connection with presence of territories polluted by radionuclides on places of nuclear tests, in zones around the enterprises on production, processing and storage of radioactive materials, and also in areas of emergency pollution (Barakhtin, 2001). The aim of our investigation was a determination of the levels of the main radioactive elements - {sup 137}Cs and {sup 90}Sr in diary products. 363 samples of milk, dry milk, butter, cheese and yogurt from Novosibirsk region were examined. {sup 137}Cs level was 3.7 to 9.2 times higher than {sup 90}Sr one in milk, cheese and yogurt. At the same time the level of these radio-nuclides in butter was identical (8.03 Bk/kg). (authors)

  16. Radionuclide evaluation of renal artery dilatation

    Energy Technology Data Exchange (ETDEWEB)

    Born, M.L.; Gerlock, A.J. Jr.; Goncharenko, V.; Hollifield, J.W.; MacDonell, R.C. Jr.

    1981-01-01

    Radionuclide studies were used in three patients to evaluate renal perfusion and function within 24 hours following transluminal dilatation. In one patient, technetium-99 m pertechnetate showed good renal perfusion one and 12 hours after a post-dilatation arteriogram had shown a renal artery intimal defect. Improved clearance of iodine-131 ortho-iodohippurate from the blood demonstrated an increase in renal function 18 hours following dilatation of a stenosis at a renal allograft anastomosis in the second patient, while technetium-99 m-labeled DTPA showed an improved total glomerular filtration rate 24 hours after dilatation of a saphenous vein bypass graft in the third patient. It was concluded that renal radionuclide studies are of benefit in evaluating patients in the immediate post-dilatation period.

  17. Decline of radionuclides in Columbia River biota

    International Nuclear Information System (INIS)

    In January 1971, the last of nine plutonium production reactors using direct discharge of once-through cooling waters into the Columbia River was closed. Sampling was initiated at three stations on the Columbia River to document the decline of the radionuclide body burdens in the biota of the Columbia River ecosystem. The data show that in a river-reservoir complex, the measurable body burden of fission-produced radionuclides decreased to essentially undetectable levels within 18 to 24 mo after cessation of discharge of once-through cooling water into the river. On the basis of data from the free-flowing station, we believe that this decrease would be even more rapid in an unimpounded river

  18. Radionuclide-labelled antigens in serological epidemiology

    International Nuclear Information System (INIS)

    The feasibility of tests using radionuclide-labelled antigens in serological surveys was studied, with particular attention to the likely availability of facilities and personnel in the tropics and arctics, where measurements may be disturbed by climatic influences. The methodology required was to be simple, rapid and suitable for examining large numbers of sera, as for epidemological surveys. In the introduction, limitations of labelled antigen tests are discussed, the choice of radionuclide and measurement methods, test procedures and evaluation of results. Collection, preservation and shipment of speciments (serum, faeces, cerebrospinal fluid, sputum, etc.) are described. Experiments with bacteria and bacterial toxins (Enterobacteriaceae, vibrios, staphylococci, meningococci, etc.), with protozoa and metazoa (Entamoeba hystolytica, Schistosoma mansoni, Trypanosoma cruzi, Plasmodia and other parasites), with viruses (vaccinia, adeno-, polio-, and influenza viruses, etc.), and with fungi are discussed

  19. Radionuclide bone scintigraphy in pediatric orthopedics

    International Nuclear Information System (INIS)

    Radionuclide bone scintigraphy is highly sensitive and specific for diagnosing the musculoskeletal disorders of childhood. Conditions such as neonatal osteomyelitis, septic arthritis, diskitis of childhood, Legg-Calve-Perthes disease, the osteochondroses, the toddler's fracture, sports injuries, spondylolysis, myositis ossificians, and reflex sympathetic dystrophy are readily defined. High-quality state-of-the-art scintigraphy is essential in infants and young children. 64 references

  20. Radionuclide release calculations for SAR-08

    Energy Technology Data Exchange (ETDEWEB)

    Thomson, Gavin; Miller, Alex; Smith, Graham; Jackson, Duncan (Enviros Consulting Ltd, Wolverhampton (United Kingdom))

    2008-04-15

    Following a review by the Swedish regulatory authorities of the post-closure safety assessment of the SFR 1 disposal facility for low and intermediate waste (L/ILW), SAFE, the SKB has prepared an updated assessment called SAR-08. This report describes the radionuclide release calculations that have been undertaken as part of SAR-08. The information, assumptions and data used in the calculations are reported and the results are presented. The calculations address issues raised in the regulatory review, but also take account of new information including revised inventory data. The scenarios considered include the main case of expected behaviour of the system, with variants; low probability releases, and so-called residual scenarios. Apart from these scenario uncertainties, data uncertainties have been examined using a probabilistic approach. Calculations have been made using the AMBER software. This allows all the component features of the assessment model to be included in one place. AMBER has been previously used to reproduce results the corresponding calculations in the SAFE assessment. It is also used in demonstration of the IAEA's near surface disposal assessment methodology ISAM and has been subject to very substantial verification tests and has been used in verifying other assessment codes. Results are presented as a function of time for the release of radionuclides from the near field, and then from the far field into the biosphere. Radiological impacts of the releases are reported elsewhere. Consideration is given to each radionuclide and to each component part of the repository. The releases from the entire repository are also presented. The peak releases rates are, for most scenarios, due to organic C-14. Other radionuclides which contribute to peak release rates include inorganic C-14, Ni-59 and Ni-63. (author)

  1. Loading technique for preparing radionuclide containing nanoparticles

    DEFF Research Database (Denmark)

    2011-01-01

    Source: US2012213698A The present invention relates to a novel composition and method for loading delivery systems such as liposome compositions with radionuclides useful in targeted diagnostic and/or therapy of target site, such as cancerous tissue and, in general, pathological conditions associ...... of positron emission tomography (PET) imaging technique. One specific aspect of the invention is directed to a method of producing nanoparticles with desired targeting properties for diagnostic and/or radio-therapeutic applications....

  2. Radionuclide Air Emission Report for 2008

    Energy Technology Data Exchange (ETDEWEB)

    Wahl, Linnea

    2009-05-21

    Berkeley Lab operates facilities where radionuclides are handled and stored. These facilities are subject to the U.S. Environmental Protection Agency (EPA) radioactive air emission regulations in Code of Federal Regulations (CFR) Title 40, Part 61, Subpart H (EPA 1989). Radionuclides may be emitted from stacks or vents on buildings where radionuclide production or use is authorized or they may be emitted as diffuse sources. In 2008, all Berkeley Lab sources were minor sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]). These minor sources include more than 100 stack sources and one source of diffuse emissions. There were no unplanned emissions from the Berkeley Lab site. Emissions from minor sources (stacks and diffuse emissions) either were measured by sampling or monitoring or were calculated based on quantities used, received for use, or produced during the year. Using measured and calculated emissions, and building-specific and common parameters, Laboratory personnel applied the EPA-approved computer code, CAP88-PC, to calculate the effective dose equivalent to the maximally exposed individual (MEI). The effective dose equivalent from all sources at Berkeley Lab in 2008 is 5.2 x 10{sup -3} mrem/yr (5.2 x 10{sup -5} mSv/yr) to the MEI, well below the 10 mrem/yr (0.1 mSv/yr) dose standard. The location of the MEI is at the University of California (UC) Lawrence Hall of Science, a public science museum about 1500 ft (460 m) east of Berkeley Lab's Building 56. The estimated collective effective dose equivalent to persons living within 50 mi (80 km) of Berkeley Lab is 1.1 x 10{sup -1} person-rem (1.1 x 10{sup -3} person-Sv) attributable to the Lab's airborne emissions in 2008.

  3. Radionuclide Air Emission Report for 2009

    Energy Technology Data Exchange (ETDEWEB)

    Wahl, Linnea

    2010-06-01

    Berkeley Lab operates facilities where radionuclides are handled and stored. These facilities are subject to the EPA radioactive air emission regulations in 40CFR61, Subpart H (EPA 1989). Radionuclides may be emitted from stacks or vents on buildings where radionuclide production or use is authorized or they may be emitted as diffuse sources. In 2009, all Berkeley Lab sources were minor sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]). These minor sources included more than 100 stack sources and one source of diffuse emissions. There were no unplanned emissions from the Berkeley Lab site. Emissions from minor sources (stacks and diffuse emissions) either were measured by sampling or monitoring or were calculated based on quantities used, received for use, or produced during the year. Using measured and calculated emissions, and building-specific and common parameters, Laboratory personnel applied the EPA-approved computer code, CAP88-PC, to calculate the effective dose equivalent to the maximally exposed individual (MEI). The effective dose equivalent from all sources at Berkeley Lab in 2009 is 7.0 x 10{sup -3} mrem/yr (7.0 x 10{sup -5} mSv/yr) to the MEI, well below the 10 mrem/yr (0.1 mSv/yr) dose standard. The location of the MEI is at the University of California (UC) Lawrence Hall of Science, a public science museum about 1500 ft (460 m) east of Berkeley Lab's Building 56. The estimated collective effective dose equivalent to persons living within 50 mi (80 km) of Berkeley Lab is 1.5 x 10{sup -1} person-rem (1.5 x 10{sup -3} person-Sv) attributable to the Lab's airborne emissions in 2009.

  4. Radionuclide release calculations for SAR-08

    International Nuclear Information System (INIS)

    Following a review by the Swedish regulatory authorities of the post-closure safety assessment of the SFR 1 disposal facility for low and intermediate waste (L/ILW), SAFE, the SKB has prepared an updated assessment called SAR-08. This report describes the radionuclide release calculations that have been undertaken as part of SAR-08. The information, assumptions and data used in the calculations are reported and the results are presented. The calculations address issues raised in the regulatory review, but also take account of new information including revised inventory data. The scenarios considered include the main case of expected behaviour of the system, with variants; low probability releases, and so-called residual scenarios. Apart from these scenario uncertainties, data uncertainties have been examined using a probabilistic approach. Calculations have been made using the AMBER software. This allows all the component features of the assessment model to be included in one place. AMBER has been previously used to reproduce results the corresponding calculations in the SAFE assessment. It is also used in demonstration of the IAEA's near surface disposal assessment methodology ISAM and has been subject to very substantial verification tests and has been used in verifying other assessment codes. Results are presented as a function of time for the release of radionuclides from the near field, and then from the far field into the biosphere. Radiological impacts of the releases are reported elsewhere. Consideration is given to each radionuclide and to each component part of the repository. The releases from the entire repository are also presented. The peak releases rates are, for most scenarios, due to organic C-14. Other radionuclides which contribute to peak release rates include inorganic C-14, Ni-59 and Ni-63. (author)

  5. Radionuclide bone scintigraphy in pediatric orthopedics

    Energy Technology Data Exchange (ETDEWEB)

    Conway, J.J.

    1986-12-01

    Radionuclide bone scintigraphy is highly sensitive and specific for diagnosing the musculoskeletal disorders of childhood. Conditions such as neonatal osteomyelitis, septic arthritis, diskitis of childhood, Legg-Calve-Perthes disease, the osteochondroses, the toddler's fracture, sports injuries, spondylolysis, myositis ossificians, and reflex sympathetic dystrophy are readily defined. High-quality state-of-the-art scintigraphy is essential in infants and young children. 64 references.

  6. UPTAKE OF RADIONUCLIDE METALS BY SPME FIBERS

    Energy Technology Data Exchange (ETDEWEB)

    Duff, M; S Crump, S; Robert02 Ray, R; Keisha Martin, K; Donna Beals, D

    2006-08-28

    The Federal Bureau of Investigation (FBI) Laboratory currently does not have on site facilities for handling radioactive evidentiary materials and there are no established FBI methods or procedures for decontaminating high explosive (HE) and fire debris (FD) evidence while maintaining evidentiary value. One experimental method for the isolation of HE and FD residue involves using solid phase microextraction or SPME fibers to remove residue of interest. Due to their high affinity for organics, SPME fibers should have little affinity for most metals. However, no studies have measured the affinity of radionuclides for SPME fibers. The focus of this research was to examine the affinity of dissolved radionuclide ({sup 239/240}Pu, {sup 238}U, {sup 237}Np, {sup 85}Sr, {sup 133}Ba, {sup 137}Cs, {sup 60}Co and {sup 226}Ra) and stable radionuclide surrogate metals (Sr, Co, Ir, Re, Ni, Ba, Cs, Nb, Zr, Ru, and Nd) for SPME fibers at the exposure conditions that favor the uptake of HE and FD residues. Our results from radiochemical and mass spectrometric analyses indicate these metals have little measurable affinity for these SPME fibers during conditions that are conducive to HE and FD residue uptake with subsequent analysis by liquid or gas phase chromatography with mass spectrometric detection.

  7. [Biosorption of Radionuclide Uranium by Deinococcus radiodurans].

    Science.gov (United States)

    Yang, Jie; Dong, Fa-qin; Dai, Qun-wei; Liu, Ming-xue; Nie, Xiao-qin; Zhang, Dong; Ma, Jia-lin; Zhou, Xian

    2015-04-01

    As a biological adsorbent, Living Deinococcus radiodurans was used for removing radionuclide uranium in the aqueous solution. The effect factors on biosorption of radionuclide uranium were researched in the present paper, including solution pH values and initial uranium concentration. Meanwhile, the biosorption mechanism was researched by the method of FTIR and SEM/EDS. The results show that the optimum conditions for biosorption are as follows: pH = 5, co = 100 mg · L(-1) and the maximum biosorption capacity is up to 240 mgU · g(-1). According to the SEM results and EDXS analysis, it is indicated that the cell surface is attached by lots of sheet uranium crystals, and the main biosorpiton way of uranium is the ion exchange or surface complexation. Comparing FTIR spectra and FTIR fitting spectra before and after biosorption, we can find that the whole spectra has a certain change, particularly active groups (such as amide groups of the protein, hydroxy, carboxyl and phosphate group) are involved in the biosorption process. Then, there is a new peak at 906 cm(-1) and it is a stretching vibration peak of UO2(2+). Obviously, it is possible that as an anti radiation microorganism, Deinococcus radiodurans could be used for removing radionuclide uranium in radiation environment.

  8. Interaction between water, sediments and radionuclides

    International Nuclear Information System (INIS)

    A model-based measurements program was carried out to evaluate the primary mechanisms controlling transport of uranium 238 and thorium 232 decay chain radionuclides in Quirke Lake, a water body draining much of the uranium mining and milling district near Elliot Lake, Ontario. This program included studies of radionuclide accumulation in sediments, particle settling and lake mass-balance studies. Also, sediment studies were undertaken to evaluate chemical fractionation, mineralogical associations, and sediment-water adsorption and release. A limnocorral experiment was conducted in an isolated portion of a lake to measure radium 226 removal from the water column and diffusion from the sediments back to the water. Modelling studies were made to assess the data. Substantial agreement was obtained using the model originally developed for the AECB between model predictions and observations for Quirke Lake and for the limnocorrals. Further work is required to complete the studies undertaken in this project to assess the significance of the efflux of radionuclides from the sediments. These studies include a laboratory program to measure kinetics of adsorption, sediment-water modelling studies of the results and a field measurement program to develop a mass-balance analysis for thorium. (numerous refs)

  9. Distribution of natural radionuclide along Main Central Thrust in Garhwal Himalaya

    Directory of Open Access Journals (Sweden)

    R.C. Ramola

    2014-10-01

    Full Text Available Study of natural radionuclide is important to assess the radiation level in a particular area. Radionuclide present in earth's crust is different for different geological areas because of the variety of soil and rocks present in a particular area. In present study, the estimation of natural radionuclides have been carried out along the Main Central Thrust (MCT in Uttarkashi, Budhakedar, Ukhimath and Healang regions of Garhwal Himalaya, India. The large variations in the radionuclide distribution have been estimated along the Main Central Thrust. The 226Ra, 232Th and 40K contents in MCT area varies from 8 ± 1 Bq.kg−1 to 285 ± 28 Bq.kg−1 with an average of 64 Bq.kg−1, 7 ± 1 Bq.kg−1 to 136 ± 15 Bq.kg−1 with an average 69 Bq.kg−1 and 115 ± 18 Bq.kg−1 to 1588 ± 162 Bq.kg−1 with an average 792 Bq.kg−1, respectively. The radon exhalation rate and radon concentration in the soil of study area varies from 2.20 × 10−5 Bq.kg−1h−1 to 3.2 × 10−5 Bq.kg−1h−1 and 287 Bq/m3 to 417 Bq/m3, respectively. It was observed that the distribution of natural radionuclide in the soil of study area is not uniform and concentrated along geological active region. These values of radionuclide and radon mass exhalation rate may be used as baseline data for further study in the area.

  10. Distribution and speciation of radionuclides in the environment: their implication in radioecology

    International Nuclear Information System (INIS)

    Following the discovery of X-ray and radioactivity, radioecological researches were initiated all over the world. But only after the 2nd World War the knowledge of the effects of ionizing radiations on the organisms and the processes of the diffusion of radionuclides in the environment achieved an outstanding level. On account of the great sensitivity of the radioactivity measurements, negligible amounts of radionuclides could be easily identified and measured in different environmental compartments without any slight interference with the metabolisms of living organisms. Many processes and phenomena could then be detected and studied. Ecology took advantage from such studies and its growth in a few years was probably greater than in the whole of the previous century. As a result a great interest in the determination of concentration factors in any organism spread widely in many laboratories, a large number of values were available in a few years time. Further it appeared that the transfer of the radionuclides from the environment to man could be better evaluated and monitored through the definition of some 'critical' quantity: a critical group, a critical radionuclide, a critical pathway, etc. The fallout dispersed by the experimental detonation of nuclear weapons and, more recently, the contamination due to the Chernobyl accident, were the most important sources of radionuclides in most of the environmental compartments. Undoubtedly in the post Chernobyl situation radioecology is in a better position because the description of the environment is presently much closer to reality and its conclusions much more reliable. But, as it is usual in science development, new problems appeared and new questions were asked. Speciation of radionuclides and other pollutants is considered and some of the effects on the diffusion and consequences are discussed. Finally, the application of the great amount of knowledge obtained by the radioecological research to a better

  11. Radionuclide characterization and associated dose from long-lived radionuclides in close-in fallout delivered to the marine environment at Bikini and Enewetak Atoll

    Energy Technology Data Exchange (ETDEWEB)

    Noshkin, V. E.; Robison, W. L.

    1998-09-01

    Between June 1946 and October 1958, Enewetak and Bikini Atolls were used by the United States as testing grounds for 66 nuclear devices. The combined explosive yield from these tests was 107 Mt (Mt TNT equivalents). This testing produced close-in fallout debris that was contaminated with quantities of radioactive fission and particle activated products, and unspent radioactive nuclear fuel that entered the aquatic environment of the atolls. Today, the sediments in the lagoons are reservoirs for 10's of TBq of the transuranics and some long-lived fission and activation products. The larger amounts of contamination are associated with fine and coarse sediment material adjacent to the locations of the high yield explosions. Radionuclides are also distributed vertically in the sediment column to various depths in all regions of the lagoons. Concentrations greater than fallout background levels are found in filtered water sampled over several decades from all locations and depths in the lagoons. This is a direct indication that the radionuclides are continuously mobilized to solution from the solid phases. Of particular importance is the fact that the long-lived radionuclides are accumulated to different levels by indigenous aquatic plants and organisms that are used as food by resident people. One might anticipate finding continuous high contamination levels in many of the edible marine organisms from the lagoons, since the radionuclides associated with the sediments are not contained and are available to the different organisms in a relatively shallow water environment. This is not the case. We estimate that the radiological dose from consumption of the edible parts of marine foods at Enewetak and Bikini is presently about 0.05% of the total 50-year integral effective dose from all other exposure pathways that include ingestion of terrestrial foods and drinking water, external exposure and inhalation. The total radiological dose from the marine pathway is

  12. Anthropogenic radionuclides in Ottawa River sediment near Chalk River Laboratories

    International Nuclear Information System (INIS)

    The Ottawa River has received nuclear reactor effluent from Chalk River Laboratories (CRL) for more than 60 years, including releases from a NRX accident in 1952. Recent interest in the potential impact of these historical releases and the possible need for remediation of a small region immediately downstream from the release point has led to comprehensive studies to assess risk to people and wildlife. In this paper, the results of an extensive survey of gamma-emitting anthropogenic radionuclides in Ottawa River sediment in the vicinity of CRL are presented. Anthropogenic radionuclides detected in Ottawa River sediment include 60Co, 94Nb, 137Cs, 152Eu, 154Eu, 155Eu and 241Am. Concentrations of all anthropogenic radionuclides decline rapidly with distance downstream of the process outfall, reaching stable concentrations about 2 km downstream. All of these radionuclides are found at some sites within 2 km upstream of the process outfall suggesting limited upstream transport and sedimentation. Comparison of anthropogenic radionuclides with several representative primordial radionuclides shows that with the exception of sites at the process outfall and within 2 km downstream of the process outfall, primordial radionuclide concentrations greatly exceed CRL derived anthropogenic radionuclide concentrations. Thus, over 60 years of radionuclide releases from operations at CRL have had little impact on radionuclide concentrations in Ottawa River sediment, except at a few sites immediately adjacent to the process outfall. (author)

  13. Artificial radionuclides in the atmosphere over Lithuania

    International Nuclear Information System (INIS)

    Systematic observations of radionuclide composition and concentration in the atmosphere have been carried out at the Institute of Physics in Vilnius since 1963. An increase in activity concentration of radionuclides in the atmosphere was observed after nuclear weapon tests and the Chernobyl NPP accident. At present the radiation situation in Lithuania is determined by two main sources of radionuclides, forest fire and resuspension products transferred from highly polluted region of the Ukraine and Belarus. During forest fires the increase in activity concentration of 137Cs in the atmosphere was registered in many countries and in Lithuania as well. This work summarizes the experimental data on transport of cesium, plutonium, americium from the highly contaminated territories after the Chernobyl accident. The activity concentrations of 137Cs were measured in two - three days samples while plutonium and americium in monthly samples. In addition, the analyses of the events of the increase activity concentration, meteorological situation, speciation of radionuclides and mechanisms of formation and transformation of aerosol carriers of radionuclides are presented. Aerosols were sampled on perchlorvinyl filters and the large volume air samplers with a flow rate from 2400 m3/h to about 6000 m3/h were used. The radiochemical analyses of monthly samples of aerosol ashes (about 30 g) were performed. For separation of Pu isotopes the TOPO/cyclohexane extraction and radiochemical purification using UTEVA resin were performed, Am was separated after TOPO/cyclohexane extraction using TRU and TEVA resins (100-150 μm). 242Pu and 243Am were used as tracers in the separation procedure. The alpha spectrometry measurements of Pu and Am isotopes deposited on a stainless steel disc were carried out with the Alphaquattro (Silena) spectrometer. 137Cs was determined by gamma-ray spectrometry using the high purity HPGe detector (resolution - 1.9 keV/1.33 Mev, efficiency - 42%). Accuracy

  14. Radiolabelled somatostatin analogs for radionuclide therapy of tumours

    International Nuclear Information System (INIS)

    Full text: Introduction Molecular imaging and therapy are rapidly developing fields and will become important topics in medicine in the 21st century. Nuclear medicine has applied molecular imaging and therapy since the 1940s by imaging and treating thyroid disorders with radioactive iodine transported into the target cells via the sodium iodide pump. We transferred the idea of radionuclides for molecular imaging and cancer treatment to peptides because peptide receptors are known to be over expressed on certain cancers and started using radiolabelled somatostatin derivatives to image and treat tumours. Targeting peptide receptors Radiolabelled peptides that bind to receptors form an important class of radiopharmaceuticals for tumour diagnosis and therapy. The specific receptor binding property of the peptide can be exploited by labelling with a radionuclide and using the radiolabelled peptide as a vehicle to guide the radioactivity to tumours expressing a particular receptor. The high affinity of the peptide for the receptor plus the internalization of the receptor-peptide complex facilitates high uptake of the radiolabel in receptor-expressing tumours, while its relatively small size facilitates rapid clearance from the blood, resulting in low background radioactivity. The use of radiolabelled peptides is growing rapidly due to these favourable characteristics, their low antigenicity and ease of production. Receptor-binding peptides labelled with gamma radiation emitters or positron emitters enable non-invasive, whole-body visualization. This process is referred to as peptide-receptor scintigraphy (PRS) and is being used to detect, stage and plan the therapy of receptor-expressing tumours, and also to follow tumours after therapy. In addition, labelled with therapeutic beta-emitter these peptide molecules have potential to destroy receptor-expressing tumours: an approach referred to as peptide receptor radionuclide therapy (PRRT). Somatostatin Receptor Imaging The

  15. Gamma spectrometric validation of measurements test of radionuclides in food matrices

    International Nuclear Information System (INIS)

    In a testing laboratory the quality system encompasses a set of activities planned and systematic, which ensure the traceability process of an analysis, which is based on the standards NBR ISO/TEC 17025. With the need for analysis of radionuclides in food products to meet the requirements of import and export, accreditation of testing on this standard becomes increasingly necessary. The Gamma Spectrometry is a technique used for direct determination of radionuclides in different matrices, among them the food, being possible the simultaneous determination of different radionuclides in the same sample without the need for a chemical separation. In the process of Accreditation the methodology validation is an important step that includes testing accuracy, traceability, linearity and recovery. This paper describes the procedures used to validate the assay for determining radionuclides using gamma spectrometry in food. These procedures were performed through analysis of a certificated reference material by the International Atomic Energy Agency (IAEA Soil 327), analysis of samples of milk powder prepared from the doping with certified liquid standards also by the results obtained in the participation of tests of proficiency in analysis of environmental samples. (author)

  16. Experimental Studies to Evaluate the Role of Colloids on the Radionuclide Migration in a Crystalline Medium

    Energy Technology Data Exchange (ETDEWEB)

    Albarran, Nairoby; Missana, Tiziana; Alonso, Ursula; Garcia-Gutierrez, Miguel; Mingarro, Manuel; Lopez, Trinidad [CIEMAT, Departamento de Medioambiente, Avenida Complutense, 22 28040 Madrid (Spain)

    2008-07-01

    In a deep geological repository (DGR) of high level radioactive waste, all the possible phenomena affecting radionuclide migration have to be studied to assess its security over time. Colloids can play an important role for contaminant transport if the following conditions are fulfilled: colloids exist in a non negligible concentration, they are mobile and stable in the environment of interest, and they are able to adsorb radionuclides irreversibly. In this study, different transport experiments where performed to improve the knowledge on the main mechanisms affecting the radionuclide migration in the presence of colloids in a crystalline medium. Firstly, colloid stability was analysed and then transport experiments in an artificial granite longitudinal fracture were carried out. Synthetic colloids of different size and bentonite clay colloids were used to evaluate the effects of colloid size, charge, and water flow rate on their mobility. Results showed that both major importance of the water flow rate on the mobility of colloids and their recovery and a higher interaction of smaller particles with the surface. Finally, the migration behaviour of Sr, and Sr adsorbed onto bentonite colloids was compared. The elution curves of Sr adsorbed onto colloid were significantly different from the ones of Sr alone, pointing out that sorption/desorption mechanisms must be taken into account to understand the radionuclide migration in the fracture in the presence of colloids. (authors)

  17. The vertical distribution of radionuclides in a Ribble Estuary saltmarsh: transport and deposition of radionuclides

    International Nuclear Information System (INIS)

    Routine discharges of low-level liquid radioactive waste by British Nuclear Fuels plc (BNFL) at Sellafield and Springfields have resulted in enhanced levels of radionuclides in sediments of the Ribble Estuary, NW England, UK. Variations in radionuclide concentrations (137Cs, 230Th, and 239240Pu) with depth in a mature saltmarsh core were analysed in order to investigate historical discharge trends and waste-dispersal mechanisms. Core samples from Longton/Hutton Marsh were analysed by gamma-spectrometry and α-spectrometry for radionuclides and by laser granulometry to establish grain-size variations with depth. Distinct subsurface maxima were present for 137Cs and 239240Pu with activities as high as 4500 Bq kg-1 for 137Cs and 600 Bq kg-1 for 239240Pu. Thorium-230 exhibited complex activity profiles with depth, specific activities ranging between 200 and 2400 Bq kg-1. The vertical distributions of Sellafield-derived radionuclides (137Cs and 239240Pu) in mature saltmarsh deposits reflect the time-integrated discharge pattern from Sellafield, implying a transport mechanism that has involved the mixing of sediment labelled with radioactivity from recent discharges and sediment labelled from historical discharge events before deposition. A mechanism involving the transport of contaminated silt therefore seems to dominate. The vertical distribution of Springfields-derived 230Th in the same areas reflects the annual gross-α discharge pattern from BNFL Springfields. In contrast to the Sellafield-derived radionuclides, a fairly rapid transport mechanism from source to sink is implied, with little or no time for mixing with radionuclides discharged years earlier. (Copyright (c) 1999 Elsevier Science B.V., Amsterdam. All rights reserved.)

  18. LEACHING OF SLAG FROM STEEL RECYCLING: RADIONUCLIDES AND STABLE ELEMENTS. DATA REPORT, JAN.15, 1997, REVISED SEPT.9, 1997

    Energy Technology Data Exchange (ETDEWEB)

    FUHRMANN,M.SCHOONEN,M.

    2003-07-31

    Of primary importance to this study are releases of radionuclides from slags. However, releases of other constituents also provide valuable information on releases of elements that may be toxic (e.g. Cr) or that may be used as analogs for radionuclides (e.g. K for Cs). In addition, leaching of bulk constituents from the slag gives information on weathering rates of the bulk material that can be used to estimate releases of non-leachable elements. Consequently, we have examined leaching of: radionuclides from those sloags that contain them; bulk elemental constituents of the slags; anionic constituents; trace elements, through spot checks of concentrations in leachates. Analysis by ICP of elemental constituents in leachates from radioactive samples was limited to those leachate samples that contained no detectable radionuclides, to avoid contamination of the ICP. In this data report we present leaching results for five slags that were produced by recycling steel. Two of the slags were generated at facilities that treat radioactively contaminated scrap, consequently the slag contains radionuclides. The slag from the other three was not contaminated. Because of this, we were able to examine the chemical composition of the slag and of the leachate generated during tests of these slags. For these materials we believe that leach rates of the stable elements can be used as analogs for radionuclides if the same steel processing method were used for radioactive material.

  19. Models for transport and fate of carbon, nutrients and point source released radionuclides to an aquatic ecosystem

    International Nuclear Information System (INIS)

    In this report three ecosystem models are described in terms of structure, initial data, and results. All models are dynamic, mass-balanced and describe the transport and fate of elements in an open aquatic ecosystem. The models are based on ecologically sound principles, provide model results with high resolution and transparency, and are constrained by the nutrient dynamics of the ecosystem itself. The processes driving the transport in all the models are both the biological processes such as primary production, consumption, respiration and excretion, and abiotic e.g. water exchange and air-sea exchange. The first model, the CNP-model, describes the distribution and fluxes of carbon and nutrients for the coastal ecosystem off Forsmark. The second model, the C-14 model, is an extension of the CNP-model and describes the transport and distribution of hypothetically released C-14 from the underground repository SFR-1 to the ecosystem above. The third model, the RN-model, is a generic radionuclide flow model that models the transport and distribution of radionuclides other than C-14 hypothetically discharged to the ecosystem. The model also analyses the importance of some radionuclide specific mechanisms for the radionuclide flow. The generic radionuclide model is also based on the CNP-model, but has radionuclide specific mechanisms connected to each compartment

  20. Models for transport and fate of carbon, nutrients and point source released radionuclides to an aquatic ecosystem

    Energy Technology Data Exchange (ETDEWEB)

    Kumblad, Linda [Stockholm Univ. (Sweden). Dept. of Systems Ecology; Kautsky, Ulrik [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

    2004-09-01

    In this report three ecosystem models are described in terms of structure, initial data, and results. All models are dynamic, mass-balanced and describe the transport and fate of elements in an open aquatic ecosystem. The models are based on ecologically sound principles, provide model results with high resolution and transparency, and are constrained by the nutrient dynamics of the ecosystem itself. The processes driving the transport in all the models are both the biological processes such as primary production, consumption, respiration and excretion, and abiotic e.g. water exchange and air-sea exchange. The first model, the CNP-model, describes the distribution and fluxes of carbon and nutrients for the coastal ecosystem off Forsmark. The second model, the C-14 model, is an extension of the CNP-model and describes the transport and distribution of hypothetically released C-14 from the underground repository SFR-1 to the ecosystem above. The third model, the RN-model, is a generic radionuclide flow model that models the transport and distribution of radionuclides other than C-14 hypothetically discharged to the ecosystem. The model also analyses the importance of some radionuclide specific mechanisms for the radionuclide flow. The generic radionuclide model is also based on the CNP-model, but has radionuclide specific mechanisms connected to each compartment.

  1. Radioactivity and the environment: technical approaches to understand the role of arbuscular mycorrhizal plants in radionuclide bioaccumulation

    Directory of Open Access Journals (Sweden)

    Helena S. Davies

    2015-07-01

    Full Text Available Phytoaccumulation of radionuclides is of significant interest with regards to monitoring radionuclide build-up in food chains, developing methods for environmental bioremediation and for ecological management. There are many gaps in our understanding of the characteristics and mechanisms of plant radionuclide accumulation, including the importance of symbiotically-associated arbuscular mycorrhizal (AM fungi. We first briefly review the evidence that demonstrates the ability of AM fungi to enhance the translocation of 238U into plant root tissues, and how fungal association may prevent further mobilization into shoot tissues. We then focus on approaches that should further advance our knowledge of AM fungi-plant radionuclide accumulation. Current research has mostly used artificial cultivation methods and we consider how more ecologically-relevant analysis might be performed. The use of synchrotron-based X-ray fluorescence imaging and absorption spectroscopy techniques to understand the mechanisms of radionuclide transfer from soil to plant via AM fungi is evaluated. Without such further knowledge, the behavior and mobilization of radionuclides cannot be accurately modelled and the potential risks cannot be accurately predicted.

  2. Remediation of radionuclide pollutants through biosorption - an overview

    Energy Technology Data Exchange (ETDEWEB)

    Das, Nilanjana [Environmental Biotechnology Division, School of Biosciences and Technology, VIT University, Vellore (India)

    2012-01-15

    The development of nuclear science and technology has led to the increase of nuclear wastes containing radionuclides to be released and disposed in the environment. Pollution caused by radionuclides is a serious problem throughout the world. To solve the problem, substantial research efforts have been directed worldwide to adopt sustainable technologies for the treatment of radionuclide containing wastes. Biosorption represents a technological innovation as well as a cost effective excellent remediation technology for cleaning up radionuclides from aqueous environment. A variety of biomaterials viz. algae, fungi, bacteria, plant biomass, etc. have been reported for radionuclide remediation with encouraging results. This paper reviews the achievements and current status of radionuclide remediation through biosorption which will provide insights into this research frontier. (Copyright copyright 2012 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  3. Database for long lived radionuclides (LLRN). CEA working group report

    International Nuclear Information System (INIS)

    This report constitutes a data base for long lived radionuclides (with half lives ranging from 30 to 1014 years) presenting informations on seven different topics: 'Radioactive data' gathers fundamental data characterising radioactive properties of considered radionuclides (half-life, disintegration mode, radiation energy,...); 'Formation and inventory' collects data on radionuclide formation ways as well as quantities formed during fuel irradiation; 'Biological effects' gives data characterising both radiotoxicity for each radionuclide and chemical toxicity for the considered element; 'Partitioning' specifies element repartition according to the different ways of Purex reprocessing and complementary partitioning processes possible for isolating chemical elements corresponding to the considered radionuclides; 'Transmutation' provides data allowing in part to evaluate the feasibility and destruction performances of radionuclides by transmutation with neutrons; 'Behaviour in waste packages' gathers some data relative to the properties of waste packages confinement. Only data on vitrified waste packages are given there; 'Behaviour in diluted solution' provides data used for element migration calculations. (author)

  4. Radionuclide imaging of infection: what the future holds

    Energy Technology Data Exchange (ETDEWEB)

    Palestro, Christopher J. [Yeshiva University, NY (United States). Albert Einstein College of Medicine]. E-mail: palestro@lij.edu

    2008-12-15

    Nuclear Medicine plays an important role in the evaluation of patients suspected of harboring infection. Gallium imaging is especially useful for opportunistic infections and spinal osteomyelitis. In vitro labeled leukocyte imaging is the current radionuclide gold standard for imaging most infections, in immunocompetent patients, including cardiovascular, postoperative, and musculoskeletal infections (except spinal osteomyelitis). Several in-vivo leukocyte labeling methods have been investigated, but none are widely used. Results obtained with radiolabeled antibiotics have been disappointing. Data on FDG are still emerging, but this agent appears to be especially valuable in fever of unknown origin, spinal osteomyelitis, vasculitis and sarcoidosis. It is conceivable that in the near future, FDG-PET and PET/CT will replace gallium for many indications. Investigators also are studying ways to label leukocytes with positron emitters in order to combine the advantages of PET with those of labeled leukocytes. (author)

  5. Radionuclide imaging in the evaluation of osteomyelitis and septic arthritis

    International Nuclear Information System (INIS)

    Despite controversy over its exact role, radionuclide imaging plays an important role in the evaluation of patients suspected of having osteomyelitis. The differentiation between osteomyelitis and cellulitis is best accomplished by using a three-phase technique using Tc-99m methylene diphosphonate (MDP). Frequently, it is necessary to obtain multiple projections and magnification views to adequately assess suspected areas. It is recommended that a Ga-67 or In-111 leukocyte scan be performed in those cases where osteomyelitis is strongly suspected clinically and the routine bone scan is equivocal or normal. Repeated bone scan after 48 to 72 h may demonstrate increased radioactivity in the case of early osteomyelitis with the initial photon-deficient lesion. In-111 leukocyte imaging is useful for the evaluation of suspected osteomyelitis complicating recent fracture or operation, but must be used in conjunction with clinical and radiographic correlation. The recognition of certain imaging patterns appears helpful to separate osteomyelitis from septic arthritis or cellulitis. 83 references

  6. Natural radionuclides as dirt tracers in sugar cane consignments

    International Nuclear Information System (INIS)

    Soil is usually carried out to the mills, as an impurity in sugar cane, leading to economic drawbacks for the industry. The quantification of this dirt is important to identify its causes and for routine quality control. Several methods have been used for this purpose, however, no single one has been pointed out as an industrial standard. The use of a γ-ray emitting radionuclide of natural occurence was investigated and, after several soil and cane radioactivity analyses, 212Pb was chosen as the best tracer. Calibration curves developed with the addition of soil in clean cane, from 0 to 10% (dry mass), demonstrated the linearity of the method. Analyses of eleven samples taken from consignments showed that the procedure was consistent and reliable when compared to the traditional ash method. (author)

  7. Radionuclide imaging in the evaluation of osteomyelitis and septic arthritis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, E.E.; Haynie, T.P.; Podoloff, D.A.; Lowry, P.A.; Harle, T.S. (Univ. of Texas M.D. Anderson Hospital, Houston (USA))

    1989-01-01

    Despite controversy over its exact role, radionuclide imaging plays an important role in the evaluation of patients suspected of having osteomyelitis. The differentiation between osteomyelitis and cellulitis is best accomplished by using a three-phase technique using Tc-99m methylene diphosphonate (MDP). Frequently, it is necessary to obtain multiple projections and magnification views to adequately assess suspected areas. It is recommended that a Ga-67 or In-111 leukocyte scan be performed in those cases where osteomyelitis is strongly suspected clinically and the routine bone scan is equivocal or normal. Repeated bone scan after 48 to 72 h may demonstrate increased radioactivity in the case of early osteomyelitis with the initial photon-deficient lesion. In-111 leukocyte imaging is useful for the evaluation of suspected osteomyelitis complicating recent fracture or operation, but must be used in conjunction with clinical and radiographic correlation. The recognition of certain imaging patterns appears helpful to separate osteomyelitis from septic arthritis or cellulitis. 83 references.

  8. Application of radionuclides for diagnostics and therapy in Australia

    International Nuclear Information System (INIS)

    Data on production and use of radionuclides for diagnostics and therapy of diseases, development of nuclear medicine in Australia are reviewed. HIFAR operation for medicine purposes is noted; characteristics of the nuclear reactor HIFAR and new nuclear reactor under construction are performed. Australian market of radionuclides for medicine and prediction of their consumption are presented. Tendency for application of cyclotron radionuclides in medicine is demonstrated

  9. Forest Fires and Resuspension of Radionuclides into the Atmosphere

    OpenAIRE

    Fernando P. Carvalho; Joao M. Oliveira; Margarida Malta

    2012-01-01

    Problem statement: Forest fires are especially frequent around the Mediterranean Sea basin in the summer period and might be able to release naturally-occurring and man-made radionuclides from plant biomass and inject them into the atmosphere. The impact of this radioactivity on populations was not investigated before. Approach: Radionuclide analysis was performed in plants, in smoke from plant burning and in cigarette smoke to determine radionuclide concentrations by alpha spectrometry. Resu...

  10. A model of accumulation of radionuclides in biosphere originating from groundwater contamination

    Energy Technology Data Exchange (ETDEWEB)

    Gaerdenaes, Annemieke [Swedish Univ. of Agricultural Sciences, Uppsala (Sweden). Dept. of Soil Sciences; Jansson, Per-Erik; Karlberg, Louise [Royal Inst. of Technology, Stockholm (Sweden). Dept. Land and Water Resources

    2006-03-15

    radioactive element is represented as a state variable in different plant parts (stem, leaves, roots and grain) and in soil layers as attached to soil organic matter fractions (litter and humus), solved in soil water solution and adsorbed to soil particles. The importance of the different plant uptake models and their parameterization for accumulation of radionuclides in the biosphere was demonstrated by a model application of a mature boreal forest for a 20 years period with an initial single pulse groundwater contamination. The passive uptake approach was used to demonstrate importance of root depth, allocation to leaves and different scaling to the water uptake rate. The active uptake approach was used to demonstrate the importance of adsorption fraction, bioavailability and optimum ratio of leaf carbon and radionuclide. After 20 years, 9% of the originally added radionuclide had accumulated in the biosphere when assuming no plant uptake. Corresponding numbers for passive and active uptake were 12-37% and 35-44% respectively. The percentages accumulated using passive uptake was most sensitive to tested range of rooting depth and ones using active uptake to tested range of optimum ratio of leaf carbon and radionuclide. We conclude that the introduced module was able to simulate different possible plant uptake mechanisms and hydrological conditions. Further dynamically modeling studies are important to analyze the effect of a continuous contamination on long term (10,000 years) accumulation in biosphere for various specific radionuclides, ecosystems and climatic conditions.

  11. A model of accumulation of radionuclides in biosphere originating from groundwater contamination

    International Nuclear Information System (INIS)

    radioactive element is represented as a state variable in different plant parts (stem, leaves, roots and grain) and in soil layers as attached to soil organic matter fractions (litter and humus), solved in soil water solution and adsorbed to soil particles. The importance of the different plant uptake models and their parameterization for accumulation of radionuclides in the biosphere was demonstrated by a model application of a mature boreal forest for a 20 years period with an initial single pulse groundwater contamination. The passive uptake approach was used to demonstrate importance of root depth, allocation to leaves and different scaling to the water uptake rate. The active uptake approach was used to demonstrate the importance of adsorption fraction, bioavailability and optimum ratio of leaf carbon and radionuclide. After 20 years, 9% of the originally added radionuclide had accumulated in the biosphere when assuming no plant uptake. Corresponding numbers for passive and active uptake were 12-37% and 35-44% respectively. The percentages accumulated using passive uptake was most sensitive to tested range of rooting depth and ones using active uptake to tested range of optimum ratio of leaf carbon and radionuclide. We conclude that the introduced module was able to simulate different possible plant uptake mechanisms and hydrological conditions. Further dynamically modeling studies are important to analyze the effect of a continuous contamination on long term (10,000 years) accumulation in biosphere for various specific radionuclides, ecosystems and climatic conditions

  12. Radionuclide-Based Cancer Imaging Targeting the Carcinoembryonic Antigen

    Directory of Open Access Journals (Sweden)

    Hao Hong

    2008-01-01

    Full Text Available Carcinoembryonic antigen (CEA, highly expressed in many cancer types, is an important target for cancer diagnosis and therapy. Radionuclide-based imaging techniques (gamma camera, single photon emission computed tomography [SPECT] and positron emission tomography [PET] have been extensively explored for CEA-targeted cancer imaging both preclinically and clinically. Briefly, these studies can be divided into three major categories: antibody-based, antibody fragment-based and pretargeted imaging. Radiolabeled anti-CEA antibodies, reported the earliest among the three categories, typically gave suboptimal tumor contrast due to the prolonged circulation life time of intact antibodies. Subsequently, a number of engineered anti-CEA antibody fragments (e.g. Fab’, scFv, minibody, diabody and scFv-Fc have been labeled with a variety of radioisotopes for CEA imaging, many of which have entered clinical investigation. CEA-Scan (a 99mTc-labeled anti-CEA Fab’ fragment has already been approved by the United States Food and Drug Administration for cancer imaging. Meanwhile, pretargeting strategies have also been developed for CEA imaging which can give much better tumor contrast than the other two methods, if the system is designed properly. In this review article, we will summarize the current state-of-the-art of radionuclide-based cancer imaging targeting CEA. Generally, isotopes with short half-lives (e.g. 18F and 99mTc are more suitable for labeling small engineered antibody fragments while the isotopes with longer half-lives (e.g. 123I and 111In are needed for antibody labeling to match its relatively long circulation half-life. With further improvement in tumor targeting efficacy and radiolabeling strategies, novel CEA-targeted agents may play an important role in cancer patient management, paving the way to “personalized medicine”.

  13. Release rates of radionuclides into dripping ground water

    International Nuclear Information System (INIS)

    Packages of high-level waste are to be emplaced in unsaturated tuff at the proposed Yucca Mountain repository. Each cylindrical waste package is separated from surrounding rock by a 2-cm air gap. A possible mechanism for release of radionuclides is the dripping of ground water onto waste packages. Drips are assumed to penetrate cracks in failed container and to dissolve radionuclides as the partly failed container fills and overflows. For this wet-drip scenario, with assumed constant drip rate, we have developed analytical solutions for the time-dependent release rates of radionuclides to the surrounding rock. Release rates have been calculated for key radionuclides. 7 refs., 3 figs

  14. Concentration of some radionuclides in some popular sudanese medicinal plants

    International Nuclear Information System (INIS)

    In this study was measured concentration of naturally occurring radionuclides 238U, 232Th and 40K in samples of sudanese medicinal plants. The radionuclide activity concentrations in samples analyzed ranged from 4.09 to 41.07 Bq kg-1 for 238Th and from 353.14 to 2270.21 Bq kg-1 for 40k. No trace of artificial radionuclide was determined in all the samples. The effective dose due to the presence of these radionuclides was estimated and found to be 0.524 mSv/year which is well below the permissible levels. (Author)

  15. Mathematical simulation of sediment and radionuclide transport in estuaries

    Energy Technology Data Exchange (ETDEWEB)

    Onishi, Y.; Trent, D.S.

    1982-11-01

    The finite element model LFESCOT (Flow, Energy, Salinity, Sediment and Contaminant Transport Model) was synthesized under this study to simulate radionuclide transport in estuaries to obtain accurate radionuclide distributions which are affected by these factors: time variance, three-dimensional flow, temperature, salinity, and sediments. Because sediment transport and radionuclide adsorption/desorption depend strongly on sizes or types of sediments, FLESCOT simulates sediment and a sediment-sorbed radionuclide for the total of three sediment-size fractions (or sediment types) of both cohesive and noncohesive sediments. It also calculates changes of estuarine bed conditions, including bed elevation changes due to sediment erosion/deposition, and three-dimensional distributions of three bed sediment sizes and sediment-sorbed radionuclides within the bed. Although the model was synthesized for radionuclide transport, it is general enough to also handle other contaminants such as heavy metals, pesticides, or toxic chemicals. The model was checked for its capability for flow, water surface elevation change, salinity, sediment and radionuclide transport under various simple conditions first, confirming the general validity of the model's computational schemes. These tests also revealed that FLESCOT can use large aspect ratios of computational cells, which are necessary in handling long estuarine study areas. After these simple tests, FLESCOT was applied to the Hudson River estuary between Chelsea and the mouth of the river to examine how well the model can predict radionuclide transport through simulating tidally influenced three-dimensional flow, salinity, sediment and radionuclide movements with their interactions.

  16. Mathematical simulation of sediment and radionuclide transport in estuaries

    International Nuclear Information System (INIS)

    The finite element model LFESCOT (Flow, Energy, Salinity, Sediment and Contaminant Transport Model) was synthesized under this study to simulate radionuclide transport in estuaries to obtain accurate radionuclide distributions which are affected by these factors: time variance, three-dimensional flow, temperature, salinity, and sediments. Because sediment transport and radionuclide adsorption/desorption depend strongly on sizes or types of sediments, FLESCOT simulates sediment and a sediment-sorbed radionuclide for the total of three sediment-size fractions (or sediment types) of both cohesive and noncohesive sediments. It also calculates changes of estuarine bed conditions, including bed elevation changes due to sediment erosion/deposition, and three-dimensional distributions of three bed sediment sizes and sediment-sorbed radionuclides within the bed. Although the model was synthesized for radionuclide transport, it is general enough to also handle other contaminants such as heavy metals, pesticides, or toxic chemicals. The model was checked for its capability for flow, water surface elevation change, salinity, sediment and radionuclide transport under various simple conditions first, confirming the general validity of the model's computational schemes. These tests also revealed that FLESCOT can use large aspect ratios of computational cells, which are necessary in handling long estuarine study areas. After these simple tests, FLESCOT was applied to the Hudson River estuary between Chelsea and the mouth of the river to examine how well the model can predict radionuclide transport through simulating tidally influenced three-dimensional flow, salinity, sediment and radionuclide movements with their interactions

  17. Migration of radionuclides following shallow land burial

    International Nuclear Information System (INIS)

    The site of a former nuclear laboratory and shallow land burial facility 25 km southwest of Chicago (USA) has been examined for radionuclide migration and residual radioactive materials. The radioactivity was produced during operations with the first nuclear reactors and associated research from 1943 to 1955. The chronology of events and details of the decommissioning procedures, including reactor burial, are described. Surface soil, surface water, soil borings drilled through and around the facility, and water from the dolomite aquifer and glacial till overburden were analyzed for a variety of radionuclides. The only nuclide found to have migrated out of the burial site is hydrogen-3, as tritiated water. This nuclide was detected in surface water, soil water, and nearby picnic wells. The concentrations in the wells show a seasonal fluctuation, from 0.1 nCi/t in the summer to 14 nCi/l in the recharging of the groundwater winter, that is attributed to by spring rains. Water migration rates in the glacial till and dolomite were estimated by several methods. The time of travel of water to the nearest well, 400 m from the facility, is estimated to be 58 months. The vertical and horizontal distribution of tritium in the glacial till was measured. The origin of the tritium, neutron-irradiated lithium, was established from measurements of the hydrogen isotopic ratios. Concentrations of other radionuclides in soil and water were normal, except for plutonium (at about twice fallout concentrations) in the first 2 m below the buried material. The solid-element nuclides have migrated very little. Exposure pathways and their associated doses, and procedures for retarding further migration are discUssed. (author)

  18. Willow wood production on radionuclide polluted areas

    Directory of Open Access Journals (Sweden)

    Rodkin Oleg I.

    2010-01-01

    Full Text Available ABSTRACT: One of the key environmental problems in Belarus is effective use of agricultural lands contaminated by radionuclide due to the Chernobyl disaster. The alternative method to traditional agricultural crops is fast growing willow cultivation. It is possible to use biomass of willow as renewable energy source. The goal of our investigation was the estimation of environmental aspects of willow wood production on polluted areas. The field study experiments (2007-2010 were conducted at Krichev district of Mogilev region in eastern Belarus. This region characterized by high level of Cs-137 contamination as well as high level of heavy metals pollution. In the first stage of experiments, the concentration of cesium-137 in different parts of willow biomass had been measured and transfer factor calculated. The measuring had been done for leaves, roots, and wood. To control cesium-137 accumulation in willow biomass we apply different types (nitrogen N, phosphorus P and potassium K and dose of fertilizer. The experiments show that potassium mineral fertilizer is the key factor for radionuclide accumulation control. The optimal dose of potassium is 90 kg per hectare. On the base of experimental results the model of cesium-137 accumulation in the wood for a 21 year has been developed. In accordance with calculation to the end of willow cultivation (21 year concentration of cesium-137 in wood will not be higher than permitted even with the level of cesium-137 contamination in the soil 1480 kBq/m2 (maximum 140 kqB/m2 with permitted level for firewood is 740 Bq/kg.. The concentration of cesium-137 in the roots increases gradually and get maximum in 21 year (3000 kqB/m2. Our results confirm that in the sum about 0.8 million hectares of radionuclide polluted arable lands partly excluded from agricultural practice in Belarus could be used for willow biomass production.

  19. Latest radionuclide-handbook for laboratory users

    International Nuclear Information System (INIS)

    This radionuclide handbook is closing a gap between the metrology data banks and the daily work of laboratory users in the handling of radio isotopic data. Considering the actual ''Version 5.1.5 (July 2015) about 250 radio-isotopes are included and subdivided into separate chapters: natural, man-made, calibration and nuclear-medicine isotopes, actinides, low-background application, lists of isotope- and material properties as well as references and isotope index. Taking all the detailed information into consideration the handbook considerably facilitates the daily-life of laboratory users in the handling of radio isotopic data and therefore improves quality assurance.

  20. Pyomyositis diagnosed by radionuclide imaging and ultrasonography

    International Nuclear Information System (INIS)

    Pyomyositis is a primary bacterial infection of skeletal muscle which is usually associated with abscess formation. Although it is a common disease in tropical countries, it is rare in temperate zones, with only 15 cases reported in the United States. We recently evaluated a patient with primary muscle abscess, using technetium-99m stannous pyrophosphate (/sup 99m/Tc-PYP) bone scanning, gallium-67 citrate (67Ga) scanning, and sonography. To our knowledge, the radionuclide and sonographic diagnosis of the disease has not been previously reported in this country

  1. Naturally occurring radionuclides and Earth sciences

    Directory of Open Access Journals (Sweden)

    G. Ferrara

    1997-06-01

    Full Text Available Naturally occurring radionuclides are used in Earth sciences for two fundamental purposes: age determination of rocks and minerals and studies of variation of the isotopic composition of radiogenic nuclides. The methodologies that are in use today allow us to determine ages spanning from the Earth's age to the late Quaternary. The variations of isotopic composition of radiogenic nuclides can be applied to problems of mantle evolution, magma genesis and characterization with respect to different geodynamic situations and can provide valuable information not obtainable by elemental geochemistry.

  2. Radionuclides in the Great Lakes basin.

    OpenAIRE

    Ahier, B A; Tracy, B L

    1995-01-01

    The Great Lakes basin is of radiologic interest due to the large population within its boundaries that may be exposed to various sources of ionizing radiation. Specific radionuclides of interest in the basin arising from natural and artificial sources include 3H, 14C, 90Sr, 129I, 131I, 137Cs, 222Rn, 226Ra, 235U, 238U, 239Pu, and 241Am. The greatest contribution to total radiation exposure is the natural background radiation that provides an average dose of about 2.6 mSv/year to all basin resi...

  3. Preparation of radiopharmaceuticals labeled with metal radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Welch, M.J.

    1992-06-01

    We recently developed a useful zinc-62/copper-62 generator and are presently evaluating copper-62 radiopharmaceuticals for clinical studies. While developing these copper-62 radiopharmaceuticals, in collaboration with the University of Missouri Research Reactor, Columbia we have also explored copper-64 radiopharmaceuticals. The PET images we obtained with copper-64 tracers were of such high quality that we have developed and evaluated copper-64 labeled antibodies for PET imaging. The major research activities described herein include: the development and assessment of gallium-68 radiopharmaceuticals; the development and evaluation of a new zinc-62/copper-62 generator and the assessment of copper-62 radiopharmaceuticals; mechanistic studies on proteins labeled with metal radionuclides.

  4. Migration of radionuclides in the geosphere

    International Nuclear Information System (INIS)

    This report contains 13 papers presented at the plenary meeting on the coordinated project MIRAGE (Migration of Radionuclides in the Geosphere) which is in its third phase in the frame work of the 4th five year research program on management and disposal of radioactive waste (1990-1994). 12 papers in the INIS scope have been analyzed and describe the present status of various research activities, within the large integrated multinational subprojects such as: Colloids and organic materials in aquifer systems, processes of geochemical modelling (CHEMVAL project), migration experiments through different geological media, natural analogue studies

  5. Preparation of radiopharmaceuticals labeled with metal radionuclides

    International Nuclear Information System (INIS)

    We recently developed a useful zinc-62/copper-62 generator and are presently evaluating copper-62 radiopharmaceuticals for clinical studies. While developing these copper-62 radiopharmaceuticals, in collaboration with the University of Missouri Research Reactor, Columbia we have also explored copper-64 radiopharmaceuticals. The PET images we obtained with copper-64 tracers were of such high quality that we have developed and evaluated copper-64 labeled antibodies for PET imaging. The major research activities described herein include: the development and assessment of gallium-68 radiopharmaceuticals; the development and evaluation of a new zinc-62/copper-62 generator and the assessment of copper-62 radiopharmaceuticals; mechanistic studies on proteins labeled with metal radionuclides

  6. Conference on radionuclide labelled cellular blood elements

    International Nuclear Information System (INIS)

    The South African Medical Research Council presented this conference on radionuclide labelled cellular blood elements with application in atherosclerosis and thrombosis. The conference was held in Bloemfontein from 3-6 February 1986. This work only consists of the abstracts of the seminars that were delivered on the conference. The radioisotopes that occur most of the time in the abstracts include Indium 111, Indium 114, Chromium 51, Iodine 125, Iodine 131 and Carbon 14. Especially Indium 111 seems to be the method of choice for all labelling

  7. Possible applications of radionuclide techniques in criminology

    International Nuclear Information System (INIS)

    The use of radioindicator methods in dactyloscopy is described, in which is used the bond of suitable radioindicators to certain components of the sweat secretion with subsequent detection of the local distribution of these radionuclides using the autoradiographic method. The use of autoradiography and gamma spectrometry is given in ballistics, neutron activation analysis and X-ray fluorescence analysis in the investigation of motor car accidents and in the verification of historical objects, in forensic medicine, the use of autoradiography in the expertise of photographs, beta radiography in graphology and the use of radioactive labelling for trapping criminals. (J.P.)

  8. The Problem of Assessment for Radionuclide and Chemical Hazard to People Heredity and Health

    International Nuclear Information System (INIS)

    In the 21th century the assessment of the hazard to human heredity and health from the radionuclide and chemical environmental pollution becomes of prime social importance since it is related to the problems of utilization of great amounts of radioactive and chemical wastes, spent nuclear fuel, weapon plutonium, nuclear reactors and emergency discharges of isotopes which in total is higher than 1 billion Ci. Long-term cytogenetic monitoring of nuclear and chemical plant workers, local human populations of radioactive waste areas and radionuclide polluted territories has revealed that the level and spectrum of induced chromosome aberrations in blood lymphocytes correlate with the type, dose and duration of exposure. There is very strong evidence that the yield of chromosome aberrations (Y) is related to the dose (D) by the equation: Y=Ao+aD+bD2. Therefore the radiation/radionuclide risk (R(D) ) will correspond to a absorbed dose and its aberrational/mutational consequences ('doubling dose' coefficient). Increased levels of chromosome aberrations in the human body very often precede the development of several syndromes: chronic fatigue, secondary immune deficiency, early aging, reproductive dysfunction, oncological diseases and etc. The increased levels of chromosome aberrations in blood lymphocytes can serve as objective bio indicators of radiation and chemical risk to human heredity and health. Thus, monitoring of chromosome and genome aberrations must be of strategical importance in the system of governmental service for minimization of radionuclide and chemical hazard to human heredity and health the necessity of organization of which has already matured. The above mentioned confirms the necessity of founding a European network for ecological-genetic monitoring with 'Internet' translation of information on radionuclide composition and chromosome aberration levels in people, inhabiting polluted areas

  9. Recent developments in assessment of long-term radionuclide behavior in the geosphere-biosphere subsystem.

    Science.gov (United States)

    Smith, G M; Smith, K L; Kowe, R; Pérez-Sánchez, D; Thorne, M; Thiry, Y; Read, D; Molinero, J

    2014-05-01

    Decisions on permitting, controlling and monitoring releases of radioactivity into the environment rely on a great variety of factors. Important among these is the prospective assessment of radionuclide behavior in the environment, including migration and accumulation among and within specific environmental media, and the resulting environmental and human health impacts. Models and techniques to undertake such assessments have been developed over several decades based on knowledge of the ecosystems involved, as well as monitoring of previous radionuclide releases to the environment, laboratory experiments and other related research. This paper presents developments in the assessment of radiation doses and related research for some of the key radionuclides identified as of potential significance in the context of releases to the biosphere from disposal facilities for solid radioactive waste. Since releases to the biosphere from disposal facilities involve transfers from the geosphere to the biosphere, an important aspect is the combined effects of surface hydrology, near-surface hydrogeology and chemical gradients on speciation and radionuclide mobility in the zone in which the geosphere and biosphere overlap (herein described as the geosphere-biosphere subsystem). In turn, these aspects of the environment can be modified as a result of environmental change over the thousands of years that have to be considered in radioactive waste disposal safety assessments. Building on the experience from improved understanding of the behavior of the key radionuclides, this paper proceeds to describe development of a generic methodology for representing the processes and environmental changes that are characteristic of the interface between the geosphere and the biosphere. The information that is provided and the methodology that is described are based on international collaborative work implemented through the BIOPROTA forum, www.bioprota.org.

  10. A CFD approach to the atmospheric dispersion of radionuclides in the vicinity of NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Sampaio, Paulo A.B. de; Goncalves Junior, Milton A.; Lapa, Celso M.F. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)]. E-mails: sampaio@ien.gov.br; miago@ien.gov.br; lapa@ien.gov.br

    2007-07-01

    Most studies of atmospheric dispersion of radionuclides released from Nuclear Power Plants (NPPs) are based on Gaussian plume models or on the use of a convection-diffusion equation. Such methods, which do not involve solving the flow problem, are useful in the atmospheric mesoscale, of the order of 2-2000 km from the NPP. However, they do not account for the turbulence generated by the interaction of the wind with obstacles and with the released material stream, which are the dominant factors in the local scale, of the order of 0-2 km from the source of emission. In order to study the dispersion of radionuclides in the vicinity of NPPs, the authors advocate the use of Computational Fluid Dynamics (CFD). The physical model is based on the Navier- Stokes equations, a convection-diffusion energy equation, and transport equations for the radionuclides. The stabilized finite element formulation employed results in a Large Eddy Simulation procedure, where no explicit subgrid modeling is required. The code uses adaptive techniques combining error estimation and remeshing. It has been implemented in a Beowulf parallel computing system using domain decomposition and the Message Passing Interface (MPI) for communication among processors. Both controlled emissions from a chimney and severe accidents have been simulated, showing the importance of the local phenomena on the dispersion of radionuclides. (author)

  11. Dependency of soil activity concentration on soil -biota concentration ratio of radionuclides for earthworm

    Energy Technology Data Exchange (ETDEWEB)

    Keum, Dong Kwon; Kim, Byeong Ho; Jun, In; Lim, Kwang Muk; Choi, Yong Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    The transfer of radionuclides to wildlife (non-human biota) is normally quantified using an equilibrium concentration ratio (CR{sub eq}), defined as the radionuclide activity concentration in the whole organism (fresh weight) divided by that in the media (dry weight for soil). The present study describes the effect of soil radionuclide activity concentration on the transfer of {sup 137}Cs, {sup 85}Sr and {sup 65}Zn to a functionally important wildlife group, annelids, using a commonly studied experimental worm (E.andrei). Time-dependent whole body concentration ratios of {sup 137}Cs, {sup 85}Sr and {sup 65}Zn for the earthworm were experimentally measured for artificially contaminated soils with three different activity concentrations for each radionuclide which were considerably higher than normal background levels. Two parameters of a first order kinetic model, the equilibrium concentration ratio (CR{sub eq}) and the effective loss rate constant (k), were estimated by comparison of experimental CR results with the model prediction

  12. Development of COLLAGE 3; Role for colloids in the transport of radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Klos, Richard (Aleksandria Sciences, Sheffield (United Kingdom)); Bath, Adrian (Intellisci Ltd., Loughborough (United Kingdom))

    2010-03-15

    The issue of colloid-facilitated radionuclide transport (CFRT) was last addressed by the Swedish nuclear regulators in 2001 - 2002. SKI had commissioned the Collage code with subsequent development as Collage 2. This code was employed to investigate the potential role for colloids to have been involved in the transport of radionuclides at the Nevada Test Site and to examine the implications for CFRT in the Swedish disposal programme. It was concluded that colloids could not be ruled out as a mechanism for rapid transport and early release from the geosphere. Recently the 'bentonite erosion scenario' has become of concern. In it the generation of large quantities of bentonite colloids in fractures as a result of fresh water ingress at repository depth is possible. Potentially, these could carry radiologically significant quantities of radionuclides to an early release to the surface system. The objectives of this work are to update the knowledge of colloid-facilitated radionuclide transport through a fractured geosphere and to provide review capability within the SSM. Recent developments in CFRT (reviewed here) indicate that additional parameters needed to be added to the existing Collage 2 plus code in order to adequately represent colloid transport in fractures. This report looks at modifications to the model and discusses the implications of the implementation of the new processes. Authors conclude that the process of colloid filtration is an important mitigating mechanism. A new code - Collage 3 - is demonstrated and suggestions for further work are given

  13. Proceedings of the international symposium: Transfer of radionuclides in biosphere. Prediction and assessment

    International Nuclear Information System (INIS)

    The International Symposium : Transfer of Radionuclides in Biosphere - Prediction and Assessment was held at Mito on the 18th and 19th of December 2002. This International Symposium was organized by the Interchange Committee on Radionuclide Transfer in Soil Ecosphere. This project is the 3rd Phase Crossover Research, which is engaged in cooperation with five organizations: Japan Atomic Energy Research Institute (JAERI), Meteorological Research Institute (MRI), National Institute of Radiological Sciences (NIRS), RIKEN (Institute of Physical and Chemical Research) and Institute for Environmental Sciences (IES). The main objective of this symposium is to discuss and exchange recent findings and ideas in the area of the behavior and transfer of radionuclides in biosphere. One of the important topics in this symposium is to discuss a suitable transfer model and transfer parameters which may be adapted for Southeast Asian countries including Japan, as environmental conditions and foodstuffs in this region are significantly different from those in Europe and North America. It will be hoped that the predictions of the consequences of the release of radionuclides in the terrestrial environment will be improved through exchange of views and new results. The symposium consisted of 12 invited lectures and 44 poster presentations. The 117 participants attended the symposium, including 19 foreigners coming from 12 countries. (author)

  14. Modelling and experimental studies on the transfer of radionuclides to fruit

    International Nuclear Information System (INIS)

    Although fruit is an important component of the diet, the extent to which it contributes to radiological exposure remains unclear, partially as a consequence of uncertainties in models and data used to assess transfer of radionuclides in the food chain. A Fruits Working Group operated as part of the IAEA BIOMASS (BIOsphere Modelling and ASSessment) programme from 1997 to 2000, with the aim of improving the robustness of the models that are used for radiological assessment. The Group completed a number of modelling and experimental activities including: (i) a review of experimental, field and modelling information on the transfer of radionuclides to fruit; (ii) discussion of recently completed or ongoing experimental studies; (iii) development of a database on the transfer of radionuclides to fruit; (iv) development of a conceptual model for fruit and (v) two model intercomparison studies and a model validation study. The Group achieved significant advances in understanding the processes involved in transfer of radionuclides to fruit. The work demonstrated that further experimental and modelling studies are required to ensure that the current generation of models can be applied to a wide range of scenarios

  15. Recent developments in assessment of long-term radionuclide behavior in the geosphere-biosphere subsystem

    International Nuclear Information System (INIS)

    Decisions on permitting, controlling and monitoring releases of radioactivity into the environment rely on a great variety of factors. Important among these is the prospective assessment of radionuclide behavior in the environment, including migration and accumulation among and within specific environmental media, and the resulting environmental and human health impacts. Models and techniques to undertake such assessments have been developed over several decades based on knowledge of the ecosystems involved, as well as monitoring of previous radionuclide releases to the environment, laboratory experiments and other related research. This paper presents developments in the assessment of radiation doses and related research for some of the key radionuclides identified as of potential significance in the context of releases to the biosphere from disposal facilities for solid radioactive waste. Since releases to the biosphere from disposal facilities involve transfers from the geosphere to the biosphere, an important aspect is the combined effects of surface hydrology, near-surface hydrogeology and chemical gradients on speciation and radionuclide mobility in the zone in which the geosphere and biosphere overlap (herein described as the geosphere-biosphere subsystem). In turn, these aspects of the environment can be modified as a result of environmental change over the thousands of years that have to be considered in radioactive waste disposal safety assessments. Building on the experience from improved understanding of the behavior of the key radionuclides, this paper proceeds to describe development of a generic methodology for representing the processes and environmental changes that are characteristic of the interface between the geosphere and the biosphere. The information that is provided and the methodology that is described are based on international collaborative work implemented through the BIOPROTA forum, (www.bioprota.org). - Highlights: • Geological

  16. IMPORTANT NOTIFICATION

    CERN Multimedia

    HR Department

    2009-01-01

    Green plates, removals and importation of personal effects Please note that, as from 1 April 2009, formalities relating to K and CD special series French vehicle plates (green plates), removals and importation of personal effects into France and Switzerland will be dealt with by GS Department (Building 73/3-014, tel. 73683/74407). Importation and purchase of tax-free vehicles in Switzerland, as well as diplomatic privileges, will continue to be dealt with by the Installation Service of HR Department (Building 33/1-011, tel. 73962). HR and GS Departments

  17. Critical review: Radionuclide transport, sediment transport, and water quality mathematical modeling; and radionuclide adsorption/desorption mechanisms

    Energy Technology Data Exchange (ETDEWEB)

    Onishi, Y.; Serne, R.J.; Arnold, E.M.; Cowan, C.E.; Thompson, F.L. [Pacific Northwest Lab., Richland, WA (United States)

    1981-01-01

    This report describes the results of a detailed literature review of radionuclide transport models applicable to rivers, estuaries, coastal waters, the Great Lakes, and impoundments. Some representatives sediment transport and water quality models were also reviewed to evaluate if they can be readily adapted to radionuclide transport modeling. The review showed that most available transport models were developed for dissolved radionuclide in rivers. These models include the mechanisms of advection, dispersion, and radionuclide decay. Since the models do not include sediment and radionuclide interactions, they are best suited for simulating short-term radionuclide migration where: (1) radionuclides have small distribution coefficients; (2) sediment concentrations in receiving water bodies are very low. Only 5 of the reviewed models include full sediment and radionuclide interactions: CHMSED developed by Fields; FETRA SERATRA, and TODAM developed by Onishi et al, and a model developed by Shull and Gloyna. The 5 models are applicable to cases where: (1) the distribution coefficient is large; (2) sediment concentrations are high; or (3) long-term migration and accumulation are under consideration. The report also discusses radionuclide absorption/desorption distribution ratios and addresses adsorption/desorption mechanisms and their controlling processes for 25 elements under surface water conditions. These elements are: Am, Sb, C, Ce, Cm, Co, Cr, Cs, Eu, I, Fe, Mn, Np, P, Pu, Pm, Ra, Ru, Sr, Tc, Th, {sup 3}H, U, Zn and Zr.

  18. Forest Fires and Resuspension of Radionuclides into the Atmosphere

    Directory of Open Access Journals (Sweden)

    Fernando P. Carvalho

    2012-01-01

    Full Text Available Problem statement: Forest fires are especially frequent around the Mediterranean Sea basin in the summer period and might be able to release naturally-occurring and man-made radionuclides from plant biomass and inject them into the atmosphere. The impact of this radioactivity on populations was not investigated before. Approach: Radionuclide analysis was performed in plants, in smoke from plant burning and in cigarette smoke to determine radionuclide concentrations by alpha spectrometry. Results: Concentrations of 210Pb and 210Po in trees such as olive trees, showed low concentrations in roots, trunk and leaves and minor translocation of radionuclides from the root to aerial parts. Soil to plant transfer ratios for 210Po and 210Pb in several plants were in the range from 10-4 to 10-2. Radionuclides from atmospheric depositions may be accumulated in plants by foliar uptake and for 210Pb this seems the main pathway, with plant aerial parts displaying 210Po/210Pb ratios around 0.1, which is similar to the radionuclide ratios determined in atmospheric depositions. Experimental burning of wood from several tree species showed enhanced radionuclide concentrations in smoke compared to plant materials. Investigation of 210Po release from tobacco leaves used in cigarettes, showed especially enhanced concentrations of this radionuclide in the cigarette smoke particles. Conclusion: Radionuclide concentrations in cigarette smoke expose the lung tissues of regular smokers to high concentrations of 210Po that were considered carcinogenic. Although radionuclide concentrations in other plants analyzed were generally lower than in tobacco, globally the radionuclide activity in the plant biomass is elevated. Inhaled smoke particles from forest fires are likely to contribute to enhanced radiation doses in the human lung.

  19. Traces of natural radionuclides in animal food

    Energy Technology Data Exchange (ETDEWEB)

    Merli, Isabella Desan; Guazzelli da Silveira, Marcilei A. [Centro Universitário da FEI, São Bernardo do Campo (Brazil); Medina, Nilberto H. [Instituto de Física da USP, São Paulo (Brazil)

    2014-11-11

    Naturally occurring radioactive materials are present everywhere, e.g., in soil, air, housing materials, food, etc. Therefore, human beings and animals receive internal exposure from radioactive elements inside their bodies through breathing and alimentation. Gamma radiation has enough energy to remove an electron from the atom and compromise the rearrangement of electrons in the search for a more stable configuration which can disturb molecule chemical bonding. Food ingestion is one of the most common forms of radioisotopes absorption. The goal of this work is the measurement of natural gamma radiation rates from natural radioisotopes present in animal food. To determine the concentration of natural radionuclides present in animal food gamma-ray spectrometry was applied. We have prepared animal food samples for poultry, fish, dogs, cats and cattle. The two highest total ingestion effective doses observed refers to a sample of mineral salt cattle, 95.3(15) μSv/year, rabbit chow, with a value of 48(5) μSv/year, and cattle mineral salt, with a value of 69(7) μSv/year, while the annual total dose value from terrestrial intake radionuclide is of the order of 290 μSv/year.

  20. Long-term environmental behaviour of radionuclides

    International Nuclear Information System (INIS)

    The radioactive pollution of the environment results from the atmospheric nuclear weapons testing (during the mid-years of twentieth century), from the development of the civilian nuclear industry and from accidents such as Chernobyl. Assessing the resulting radiation that humans might receive requires a good understanding of the long-term behaviour of radionuclides in the environment. This document reports on a joint European effort to advance this understanding, 3 multinational projects have been coordinated: PEACE, EPORA and LANDSCAPE. This report proposes an overview of the results obtained and they are presented in 6 different themes: i) redistribution in the soil-plant system, ii) modelling, iii) countermeasures, iv) runoff v) spatial variations, and vi) dose assessment. The long term behaviour of the radionuclides 137Cs, 90Sr and 239-240Pu is studied through various approaches, these approaches range from in-situ experiments designed to exploit past contamination events to laboratory simulations. A broad scope of different ecosystems ranging from arctic and boreal regions down to mediterranean ones has been considered. (A.C.)

  1. Radionuclide studies in paediatric nephro-urology

    Energy Technology Data Exchange (ETDEWEB)

    Piepsz, Amy E-mail: amypiepsz@yahoo.com

    2002-08-01

    The main tool of radionuclide techniques applied to paediatric uro-nephrology is the quantitation of function, which is an information not easily obtained by other diagnostic modalities. The radiation burden is low. Drug sedation is only rarely needed, whatever the age of the patient. Accurate determination of glomerular filtration rate can be obtained by means of an intravenous injection of Cr-51 EDTA and one or two blood samples. Tc-99m DMSA scintigraphy is an accurate method for evaluation of regional cortical impairment during acute pyelonephritis and later on, for detection of permanent scarring. Tc-99m MAG3 renography is nowadays a well-standardized method for accurate estimation of the split renal function and of renal drainage with or without furosemide challenge. This technique is particularly indicated in uni- or bilateral uropathies with or without renal and/or ureteral dilatation. Direct and indirect radionuclide cystography are two alternative modalities for X-ray MCUG. Their relative place in the strategy of management of vesicoureteral reflux is discussed.

  2. Migration of radionuclides following shallow land burial

    International Nuclear Information System (INIS)

    A study of radionuclide migration was conducted at a facility used from 1944 to 1949 for the shallow land burial of radwaste produced during operations with two reactors and related nuclear research. It is situated in glacial drift 45 m thick. Underlying the drift is a generally level Silurian dolomite bedrock 60 m thick. The thickness of the drift decreases as the surface slopes downhill (north) until the dolomite reaches the surface and forms the bed of a river, 700 m to the north. This study was begun after tritiated water was detected in two picnic wells north of the facility, between the burial plot and the river. Surface and subsurface measurements indicate that tritium is migrating out of the burial site, but no other radionuclides have left the plot. The tritium concentrations decrease with distance from the plot. Tritium was found in the subsoil at all depths sampled, so the ground beneath and immediately around the plot contains tritium down to the dolomite aquifer. Time of travel of water from the burial plot to the nearest well is estimated to be 54 months. This would imply the peak concentration would reach the dolomite in about 35 years. By this time, 86% of the tritium would have disappeared by radioactive decay. The cyclical nature of the tritium content in the two wells implies that tritiated water is carried from the burial site by the spring rains when they recharge the groundwater supply

  3. Radionuclide studies in paediatric nephro-urology

    International Nuclear Information System (INIS)

    The main tool of radionuclide techniques applied to paediatric uro-nephrology is the quantitation of function, which is an information not easily obtained by other diagnostic modalities. The radiation burden is low. Drug sedation is only rarely needed, whatever the age of the patient. Accurate determination of glomerular filtration rate can be obtained by means of an intravenous injection of Cr-51 EDTA and one or two blood samples. Tc-99m DMSA scintigraphy is an accurate method for evaluation of regional cortical impairment during acute pyelonephritis and later on, for detection of permanent scarring. Tc-99m MAG3 renography is nowadays a well-standardized method for accurate estimation of the split renal function and of renal drainage with or without furosemide challenge. This technique is particularly indicated in uni- or bilateral uropathies with or without renal and/or ureteral dilatation. Direct and indirect radionuclide cystography are two alternative modalities for X-ray MCUG. Their relative place in the strategy of management of vesicoureteral reflux is discussed

  4. Radionuclides and the normal bone scan

    International Nuclear Information System (INIS)

    Recently, Eisenhut and co-workers have described development of iodine-131 labeled diphosphonates for palliative treatment of bone metastases. The compound labeled was alpha-amino (4-hydroxybenzylidene) diphosphonate (BDP3). Other beta-emitting radionuclides have been used for treatment of intractable pain secondary to bone metastases. These include strontium-89, which has some difficulties, particularly in terms of disposal of the excretions due to the long physical half-life of the life of the radionuclide. Yttrium-90 has also been used but has a relatively high hepatic uptake. Phosphorus-32 labeled compounds have also been used. Although palliation has been described, bone marrow depression has also occurred. Rhenium-186 also has been suggested, however, high renal uptake is a problem. At present, the iodine-131 labeled BDP3 appears to be the best of the available therapeutic radiopharmaceuticals. One of the major disadvantages in use of this compound is the production of gamma photons. While undesirable from a dosimetry viewpoint, gamma photons do, however, permit imaging if desired

  5. Transport of radionuclides in the groundwater environment

    International Nuclear Information System (INIS)

    Various factors influencing the transport of radionuclides by groundwater were studied. Sorption of 137Cs, 60Co, 241Am and (152,154)Eu by soil samples of the Inshas area was carried out. Mineralogical analyses of the soil samples were carried out. The amount sorbed per gram soil, (X/m), increased as the carrier concentration (C) increased from 10-9 to 10-1 mol) following a Freundlich type isotherm. The distribution coefficient, Kd, of the radionuclides was found to be affected by pH. The presence of K+, Ca2+ and Fe3+ as competing ions decreases the sorption capacity of the radioisotopes studied. The presence of complexing agents has a significant effect on the mobility of these radioisotopes. On the basis of the results obtained an attempt is being made to calculate the different transport rates of the relevant isotopes in the investigated media. A mathematical model for the dispersion of the investigated radioisotopes in the groundwater environment was also elucidated. It is concluded that the choice of the Inshas area, as a repository site, for disposal of low level radioactive waste is to be recommended. (author). 18 refs, 4 figs, 2 tabs

  6. Long-term environmental behaviour of radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Brechignac, F.; Moberg, L.; Suomela, M

    2000-04-01

    The radioactive pollution of the environment results from the atmospheric nuclear weapons testing (during the mid-years of twentieth century), from the development of the civilian nuclear industry and from accidents such as Chernobyl. Assessing the resulting radiation that humans might receive requires a good understanding of the long-term behaviour of radionuclides in the environment. This document reports on a joint European effort to advance this understanding, 3 multinational projects have been coordinated: PEACE, EPORA and LANDSCAPE. This report proposes an overview of the results obtained and they are presented in 6 different themes: (i) redistribution in the soil-plant system, (ii) modelling, (iii) countermeasures, (iv) runoff (v) spatial variations, and (vi) dose assessment. The long term behaviour of the radionuclides {sup 137}Cs, {sup 90}Sr and {sup 239-240}Pu is studied through various approaches, these approaches range from in-situ experiments designed to exploit past contamination events to laboratory simulations. A broad scope of different ecosystems ranging from arctic and boreal regions down to mediterranean ones has been considered. (A.C.)

  7. Radionuclide release from research reactor spent fuel

    International Nuclear Information System (INIS)

    Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions were performed. The results obtained indicate slow corrosion rates for the UO2 fuel matrix. Special fuel-types (mostly dispersed fuels, high enriched in 235U, cladded with aluminium) are used in German research reactors, whereas in German nuclear power plants, UO2-fuel (LWR fuel, enrichment in 235U up to 5%, zircaloy as cladding) is used. Irradiated research reactor fuels contribute less than 1% to the total waste volume. In Germany, the state is responsible for fuel operation and for fuel back-end options. The institute for energy research (IEF-6) at the Research Center Juelich performs investigation with irradiated research reactor spent fuels under repository relevant conditions. In the study, the corrosion of research reactor spent fuel has been investigated in MgCl2-rich salt brine and the radionuclide release fractions have been determined. Leaching experiments in brine with two different research reactor fuel-types were performed in a hot cell facility in order to determine the corrosion behaviour and the radionuclide release fractions. The corrosion of two dispersed research reactor fuel-types (UAlx-Al and U3Si2-Al) was studied in 400 mL MgCl2-rich salt brine in the presence of Fe2+ under static and initially anoxic conditions. Within these experimental parameters, both fuel types corroded in the experimental time period of 3.5 years completely, and secondary alteration phases were formed. After complete corrosion of the used research reactor fuel samples, the inventories of Cs and Sr were quantitatively detected in solution. Solution concentrations of Am and Eu were lower than the solubility of Am(OH)3(s) and Eu(OH)3(s) solid phases respectively, and may be controlled by sorption processes. Pu concentrations may be controlled by Pu(IV) polymer species, but the presence of Pu(V) and Pu(IV) oxyhydroxides species due to radiolytic effects cannot completely be

  8. Radionuclide reporter gene imaging for cardiac gene therapy

    Energy Technology Data Exchange (ETDEWEB)

    Inubushi, Masayuki [Hokkaido University Graduate School of Medicine, Department of Molecular Imaging, Sapporo (Japan); Tamaki, Nagara [Hokkaido University Graduate School of Medicine, Department of Nuclear Medicine, Sapporo (Japan)

    2007-06-15

    In the field of cardiac gene therapy, angiogenic gene therapy has been most extensively investigated. The first clinical trial of cardiac angiogenic gene therapy was reported in 1998, and at the peak, more than 20 clinical trial protocols were under evaluation. However, most trials have ceased owing to the lack of decisive proof of therapeutic effects and the potential risks of viral vectors. In order to further advance cardiac angiogenic gene therapy, remaining open issues need to be resolved: there needs to be improvement of gene transfer methods, regulation of gene expression, development of much safer vectors and optimisation of therapeutic genes. For these purposes, imaging of gene expression in living organisms is of great importance. In radionuclide reporter gene imaging, ''reporter genes'' transferred into cell nuclei encode for a protein that retains a complementary ''reporter probe'' of a positron or single-photon emitter; thus expression of the reporter genes can be imaged with positron emission tomography or single-photon emission computed tomography. Accordingly, in the setting of gene therapy, the location, magnitude and duration of the therapeutic gene co-expression with the reporter genes can be monitored non-invasively. In the near future, gene therapy may evolve into combination therapy with stem/progenitor cell transplantation, so-called cell-based gene therapy or gene-modified cell therapy. Radionuclide reporter gene imaging is now expected to contribute in providing evidence on the usefulness of this novel therapeutic approach, as well as in investigating the molecular mechanisms underlying neovascularisation and safety issues relevant to further progress in conventional gene therapy. (orig.)

  9. Unsaturated moisture and radionuclide transport: laboratory analysis and modeling

    International Nuclear Information System (INIS)

    This report describes several laboratory procedures and computer model simulations used to evaluate the transport of water and radionuclides through unsaturated Hanford soils. The unsaturated hydraulic conductivity was measured using the steady state methods of Klute and the transient state method of Rose. These experimental data were compared to other conductivity models. Good agreement was found between all methods in the wet range; however, disagreement was found in the dry range. None of the conductivity models explicity addresses the water vapor component of the conductivity. This may explain the under prediction of the hydraulic conductivity in the dry range where vapor transport is important. Radionuclide transport through unsaturated media was investigated by using two solute transport models to describe the transport of tritium and strontium-85 in laboratory columns. A two parameter convective-dispersive model was compared with a four parameter mobile-immobile water model. Both models adequately described the movement of tritium and strontium through small (5 cm x 27.5 cm) columns and the movement of tritium and strontium through a large (0.5 m x 1.7) column. The dispersion coefficient was found to be sensitive to changes in both velocity and column length. The mobile-immoble water equations were not as sensitive to changes in experimental scales as the convective-dispersive equation. Both models were relatively successful in describing the rapid flush of strontium-85 from a column initially leached with a low salt solution followed by a high salt solution, a phenomona called the snow plow effect. The four parameter mobile-immobile water model predicted the initial release of the strontium more accurately than the two parameter convective-dispersive model. Both models confirm enhanced mobility of strontium-85 with leaching solutions of increased salt concentration

  10. Quality assurance in the analysis of natural radionuclides - measures and results

    Energy Technology Data Exchange (ETDEWEB)

    Bothe, M. [Nuclear Engineering and Analytics Rossendorf, Inc. (VKTA), Dresden (Germany)

    1997-03-01

    In the Laboratory for Environmental and Radionuclide Analytics we analyze several natural and also some artificial radionuclides in different materials. For the determination of radionuclides we use various analytical methods. (orig./DG)

  11. Removal of radionuclides by analcime-bearing rocks

    International Nuclear Information System (INIS)

    The study of the removal of radionuclides (uranium, radium and thorium) in static conditions from aqueous solutions by analcime-bearing rocks and pure analcime was carried out. The high removal efficiency of all studied radionuclides by analcime-bearing rocks was determined. Analcime was efficient in removing of thorium only

  12. Nevada test site radionuclide inventory and distribution: project operations plan

    International Nuclear Information System (INIS)

    This document is the operational plan for conducting the Radionuclide Inventory and Distribution Program (RIDP) at the Nevada Test Site (NTS). The basic objective of this program is to inventory the significant radionuclides of NTS origin in NTS surface soil. The expected duration of the program is five years. This plan includes the program objectives, methods, organization, and schedules

  13. Modelling of radionuclide transfer processes in soils and ground waters

    International Nuclear Information System (INIS)

    Relations between convective and diffusion mechanisms of transfer are considered. The properties of soils and radionuclide adsorption isotherms are discussed. The problem of a vertical radionuclide migration in soils is solved as well as hydrodynamic problem. The problem of contamination transfer from storage facilities is formulated. Methods of its solution are discussed. 7 refs.; 2 figs.; 1 tabs

  14. 21 CFR 892.5750 - Radionuclide radiation therapy system.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Radionuclide radiation therapy system. 892.5750 Section 892.5750 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICAL DEVICES RADIOLOGY DEVICES Therapeutic Devices § 892.5750 Radionuclide radiation...

  15. Summarization on the synthesis and radionuclide-labeling of peptide nucleic acid for an oligonucleotide analogue

    International Nuclear Information System (INIS)

    Peptide nucleic acid (PNA), which is one kind of antisense nucleic acid compounds and an oligonucleotide analogue that binds strongly to DNA and RNA in a sequence specific manner, has its unique advantages in the field of molecular diagnostics and treatment of diseases. Now, people gradually attach more importance to PNA. To optimize the application of PNA in genetic re- search and therapy, a great number of backbone modifications on the newly- type structures of PNA were synthesized to improve its physicochemical proper- ties, such as hybridization speciality, solubility in biofluid, or cell permeability. The modified PNA labeled with radionuclides, which can obtain the aim at specific target and minimal non-target trauma, has important role in research and application of tumorous genitherapy. Here a review on the basic synthesis idea and several primary synthetic methods of PNA analogs was given, and also correlative studies and expectation on the compounds belonging to PNA series labeled with radionuclides were included. (authors)

  16. ACCUMULATION OF RADIONUCLIDES BY PYLAISIELLA MOSS (PYLAISIA POLYANTHA UNDER URBOECOSYSTEM CONDITIONS

    Directory of Open Access Journals (Sweden)

    T. V. Varduni

    2014-01-01

    Full Text Available Contamination of environment by radionuclides in territories under urboecosystem conditions is actual problem. The search of new express methods for radioactivity determination of environment is important task of research. In present work it was shown that mosses are bioindicators of radioactive contamination, because they accumulate radioactive substances in high concentrations. Using of bryoindication methods are promising techniques for the assessment of the contamination of ecosystems with radionuclides. The use of epiphytic mosses is the most efficient technique for assessing the contents of radionuclides in the surface air layer. The epiphytic moss (Pylaisia polyantha growing in different zones of the city of Rostov-on-Don, was used for the radioactivity biomonitoring of urbosystems. The accumulation features of radionuclides in the epitaphic pylaisiella moss (Pylaisia polyantha in the territory of the city of Rostov-on-Don have been considered. It was shown that Pylaisia polyantha is effective indicator of radioactivity for biomonitoring. The activity concentration of 137Cs, 226Ra, 40K and 232Th in the samples of moss, soils and aerosol air have been compared. The capacity of Pylaisia polyantha to accumulate radionuclides has been estimated for four radionuclides (137Cs, 226Ra, 232Th and 40K with consideration for the background level. On the basis of radionuclide analysis, zones in the city of Rostov-on-Don with the highest accumulation coefficients of 137Cs, 226Ra, 40K and 232Th were revealed. These were primarily the zones with both industrial and traffic loads and the motor transport zones. The results of investigation showed that the epiphytic moss (Pylaisia polyantha can be used as indicator of radioactivity pollution in different polluted zones.

  17. Leachability of Natural Radionuclides and Rare Earth Elements in Brazilian Phosphate Fertilizers and Phosphogypsum

    International Nuclear Information System (INIS)

    The Brazilian phosphate fertilizers are obtained by wet reaction of the igneous phosphate rock with concentrated sulphuric acid, giving as final product phosphoric acid and dehydrated calcium sulphate (phosphogypsum - PG) as by-product. The level of impurities (metals and radionuclides, among others) present in the phosphate rock used as raw material is distributed among products and by-products. In Brazil, PG has been used for many years in agriculture as a soil amendment. The characterization of natural radionuclides elements in Brazilian PG and the most used phosphate fertilizers, single super phosphate (SSP), triple super phosphate (TSP), monoammonium phosphate (MAP) and diammonium phosphate (DAP) has been already published by the same authors. However, for a long-term safe application of these fertilizers and PG it is important to study the availability of these elements to the environment. For this purpose, the evaluation of radionuclides and rare earth elements concentration in the labile fraction is more suitable than the total concentration, since this fraction is more available for the absorption by plants and water contamination. In order to evaluate the available fraction of these elements to the environment, PG and phosphate fertilizers samples were leached with water and EDTA solution. The total and leached concentrations of radionuclides (226Ra, 228Ra and 210Pb) were determined by using high-resolution gamma spectrometry and by measuring the gross alpha and beta counting after a radiochemical separation of the elements of interest, respectively. The concentration of rare earth elements - REEs (Ce, Eu, La, Lu, Sm, Tb and Yb), U and Th were determined by instrumental neutron activation analysis. The results obtained using the methodology with mild leaching with EDTA and with water showed that the radionuclides and REEs although present in the PG are not available to the environment. (author)

  18. Measurement of shunt amount using radionuclide angiocardiography: accuracy according to level of shunt and associated lesion

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yang Min [Sejong General Hospital, Bucheon (Korea, Republic of)

    2006-08-15

    Determination of pulmonary to systemic blood flow ratio (QP/QS) is important for the management of patients with left-to-right shunt. This study was performed to assess the agreement of Qp/Qs ratio using the radionuclide method and oxymetry, to investigate the factors influencing the agreement, and to know how interchangeable the results of each technique. We compared the Qp/Qs measured by single-pass radionuclide angiocardiography and oxymetry during catheterization in 207 patients who underwent both studies. In radionuclide method, Qp/Qs was calculated from the pulmonary time-activity curves using a gamma variate fit. The correlation and Bland-Altman analysis were performed according to the levels of shunt and associated lesions. The mean Qp/Qs was 1.83 {+-} 0.50 by radionuclide, and 1.74 {+-} 0.51 by oxymetry. The overall correlation coefficient was 0.86 ({rho} 0.001), and Bland-Altman range of agreement encompassing 4SD was 1.05. For atrial septal defect, ventricular septal defect, patent ductus arteriosus, tricuspid and mitral insufficiency, the correlation coefficient was 0.78, 0.90, 0.84, 0.63 and 0.44 and Bland-Altman range was 1.52, 0.74, 0.96, 1.57 and 1.50, respectively. There is good agreement but wide variance between the Qp/Qs ratios by radionuclide method and oxymetry. Associated atrioventricular valvar insufficiency decreases the correlation coefficient and widens the variance. Wide overall variance suggests that Qp/Qs measurements by two techniques should not be used interchangeably.

  19. Effect of Reducing Groundwater on the Retardation of Redox-Sensitive Radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Hu, Q; Zavarin, M; Rose, T P

    2008-04-21

    Laboratory batch sorption experiments were used to investigate variations in the retardation behavior of redox-sensitive radionuclides. Water-rock compositions used during these experiments were designed to simulate subsurface conditions at the Nevada Test Site (NTS), where a suite of radionuclides were deposited as a result of underground nuclear testing. Experimental redox conditions were controlled by varying the oxygen content inside an enclosed glove box and by adding reductants into the testing solutions. Under atmospheric (oxidizing) conditions, the radionuclide distribution coefficients varied with the mineralogical composition of the sorbent and the water chemistry. Under reducing conditions, distribution coefficients showed marked increases for {sup 99}Tc and {sup 237}Np in devitrified tuff, but much smaller variations in alluvium, carbonate rock, and zeolitic tuff. This effect was particularly important for {sup 99}Tc, which tends to be mobile under oxidizing conditions. Unlike other redox-sensitive radionuclides, iodine sorption may decrease under reducing conditions when I{sup -} is the predominant species. Overall, sorption of U to alluvium, devitrified tuff, and zeolitic tuff under atmospheric conditions was less than in the glove-box tests. However, the mildly reducing conditions achieved here were not likely to result in substantial U(VI) reduction to U(IV). Sorption of Pu was not affected by the decreasing redox conditions achieved in this study, as the predominant sorbed Pu species in all conditions was expected to be the low-solubility and strongly sorbing Pu(OH){sub 4}. Depending on the aquifer lithology, the occurrence of reducing conditions along a groundwater flowpath could potentially contribute to the retardation of redox-sensitive radionuclides {sup 99}Tc and {sup 237}Np, which are commonly identified as long-term dose contributors in the risk assessment in various nuclear facilities.

  20. Modelling for radiological and radioecological consequences of an accidental radionuclide release at Sea

    International Nuclear Information System (INIS)

    Full text: Scenarios concerning accidental releases of radionuclides into water bodies can be found in the open literature, mostly in connection with nuclear power plants located either onshore or inland. However, meager attention has been given to nuclear reactors used as energy sources for propulsion at sea, which are also subject to accidents. Such potential accidents may involve the loss of part of the reactor core to the surrounding water body. In addition of the initial instantaneous releases, one can estimate delayed source terms based on the rate at which radionuclides are dissolved or leached from the solidified material, like part of the core or structural materials in contact with water. Most of such solidified material might be a mixture of uranium, zirconium, iron, calcium, silica, fission and activation products, and transuranium elements as oxides, forming a glassy type solid. Transport models were used to calculate radionuclide concentrations in water resulting from short and delayed source terms. Oceanographic data used in the calculations were taken either from the open literature or from unclassified reports of the Brazilian Navy, being, however, as generic as possible. Time-dependent concentration functions for radionuclides in aquatic food following an accidental release reflect the net result of intake and elimination processes. However, to avoid the complexities of multiple parameters involved in such processes, the model accounts only for trophic transfer of radionuclides, and yet avoids the necessity of analyzing the details of each transfer step used to determine fish, crustacea, molluscs and seaweed accumulation. Swimming and other aquatic sports are not included in the model used for dose calculations because of theirs relatively low importance in comparison with the pathways concerning ingestion of aquatic food

  1. Radionuclide migration in groundwater. Annual progress report for 1982

    Energy Technology Data Exchange (ETDEWEB)

    Robertson, D.E.; Toste, A.P.; Abel, K.H.; Brodzinski, R.L.

    1984-01-01

    Research has continued at a low-level waste disposal facility to characterize the physicochemical species of radionuclides migrating in groundwater. This facility consists of an unlined basin and connecting trench which receives effluent water containing low levels of a wide variety of fission and activation products and trace amounts of transuranic radionuclides. The effluent water percolates through the soil and a small fraction of it emerges at seepage springs located some 260 meters from the trench. The disposal basin and trench are very efficient in retaining most of the radionuclides, but trace amounts of a number of radionuclides existing in mobile chemical forms migrate in the groundwater from the trench to the springs. This facility provides the opportunity for characterizing the rates and mechanisms of radionuclide migration in groundwaters, identifying retardation processes, and validating geochemical models. 13 references, 25 figures, 23 tables.

  2. Quantitative modeling of Cerenkov light production efficiency from medical radionuclides.

    Science.gov (United States)

    Beattie, Bradley J; Thorek, Daniel L J; Schmidtlein, Charles R; Pentlow, Keith S; Humm, John L; Hielscher, Andreas H

    2012-01-01

    There has been recent and growing interest in applying Cerenkov radiation (CR) for biological applications. Knowledge of the production efficiency and other characteristics of the CR produced by various radionuclides would help in accessing the feasibility of proposed applications and guide the choice of radionuclides. To generate this information we developed models of CR production efficiency based on the Frank-Tamm equation and models of CR distribution based on Monte-Carlo simulations of photon and β particle transport. All models were validated against direct measurements using multiple radionuclides and then applied to a number of radionuclides commonly used in biomedical applications. We show that two radionuclides, Ac-225 and In-111, which have been reported to produce CR in water, do not in fact produce CR directly. We also propose a simple means of using this information to calibrate high sensitivity luminescence imaging systems and show evidence suggesting that this calibration may be more accurate than methods in routine current use.

  3. Method of combined radionuclide assessment of the greater and uteroplacental circulation in plural pregnency

    International Nuclear Information System (INIS)

    The paper is concerned with the results of the clinical testing of a combined radionuclide method of assessment of the greater and uteroplacentral circulation in 15 women with plural pregnancy. The method permits the detection of hemodynamic changes without increasing radiation exposure to the mother's body and fetuses, the determination of a type of plural pregnancy (monochorionic or dichorial twins), and the prediction of pregnancy outcome that is very important for the choice of appropriate and timely therapy

  4. Radionuclide composition in nuclear fuel waste. Calculations performed by ORIGEN2

    International Nuclear Information System (INIS)

    The report accounts for results from calculations on the content of radionuclides in nuclear fuel waste. It also accounts for the results from calculations on the neutron flow from spent fuel, which is very important during transports. The calculations have been performed using the ORIGEN2 software. The results have been compared to other results from earlier versions of ORIGEN and some differences have been discovered. This is due to the updating of the software. 7 refs, 10 figs, 15 tabs

  5. The origin of $^{60}$Fe and other short-lived radionuclides in the early solar system

    OpenAIRE

    Gounelle, Matthieu; Meibom, Anders

    2008-01-01

    Establishing the origin of short-lived radionuclides (SLRs) with half-lives $\\leq$ 100 Myr has important implications for the astrophysical context of our Sun's birth place. We review here the different origins proposed for the variety of SLRs present in the solar accretion disk 4.57 Ga ago. Special emphasis is given to an enhanced Galactic background origin for $^{60}$Fe which was inherited from several supernovae belonging to previous episodes of star formation, rather than from a nearby, c...

  6. Radionuclide solubility control by solid solutions

    Energy Technology Data Exchange (ETDEWEB)

    Brandt, F.; Klinkenberg, M.; Rozov, K.; Bosbach, D. [Forschungszentrum Juelich GmbH (Germany). Inst. of Energy and Climate Research - Nuclear Waste Management and Reactor Safety (IEK-6); Vinograd, V. [Frankfurt Univ. (Germany). Inst. of Geosciences

    2015-07-01

    The migration of radionuclides in the geosphere is to a large extend controlled by sorption processes onto minerals and colloids. On a molecular level, sorption phenomena involve surface complexation, ion exchange as well as solid solution formation. The formation of solid solutions leads to the structural incorporation of radionuclides in a host structure. Such solid solutions are ubiquitous in natural systems - most minerals in nature are atomistic mixtures of elements rather than pure compounds because their formation leads to a thermodynamically more stable situation compared to the formation of pure compounds. However, due to a lack of reliable data for the expected scenario at close-to equilibrium conditions, solid solution systems have so far not been considered in long-term safety assessments for nuclear waste repositories. In recent years, various solid-solution aqueous solution systems have been studied. Here we present state-of-the art results regarding the formation of (Ra,Ba)SO{sub 4} solid solutions. In some scenarios describing a waste repository system for spent nuclear fuel in crystalline rocks {sup 226}Ra dominates the radiological impact to the environment associated with the potential release of radionuclides from the repository in the future. The solubility of Ra in equilibrium with (Ra,Ba)SO{sub 4} is much lower than the one calculated with RaSO{sub 4} as solubility limiting phase. Especially, the available literature data for the interaction parameter W{sub BaRa}, which describes the non-ideality of the solid solution, vary by about one order of magnitude (Zhu, 2004; Curti et al., 2010). The final {sup 226}Ra concentration in this system is extremely sensitive to the amount of barite, the difference in the solubility products of the end-member phases, and the degree of non-ideality of the solid solution phase. Here, we have enhanced the fundamental understanding regarding (1) the thermodynamics of (Ra,Ba)SO{sub 4} solid solutions and (2) the

  7. The IMS radionuclide network of the CTBT

    International Nuclear Information System (INIS)

    The Comprehensive Nuclear Test-Ban Treaty calls for the establishment of a world-wide network of monitoring stations (IMS, International Monitoring System). In total 321 monitoring stations will be installed: 50 primary seismic, 120 auxiliary seismic, 11 hydroacoustic, 60 infrasound and 80 radionuclide. The 80 radionuclide stations collect particulate from the air and measure its radioactivity. Among these radionuclide stations, 40 of them will also have the capability of measuring the concentration in the air of the noble gas Xenon. The particulate stations will have a cycle of 1 day collection, 1 day decay time and 1 day acquisition time whereas the noble gas stations will have 1 day of collection and 1 day of acquisition time. Equipment for particulate station consists of a high volume air sampler (flow rate ≥ 500 m-3 h-1 at standard pressure and temperature) and a HPGe detector system with a relative efficiency of at least 40 %. Stations can be manually or automatically operated depending on the choice of the host country. The technical specification of the equipment to be used, the distribution and the number of stations around the world were chosen in such a way to be able to detect nuclear explosions according to the following criterion: 90 % detection probability within approximately 14 days for a 1 kt nuclear explosion in the atmosphere or from venting by an underground or underwater detonation. All data collected are converted in a standard format and sent directly to Vienna where they are analysed. Most of the stations will send data through a very reliable satellite link. In fact it is required that particulate stations will send spectral data within 72 hours of collection start, within 48 hours for noble gas stations. In addition every station should reach 95 % of data availability; in particular it is required that the maximum consecutive down time is 7 days and a maximum of 15 days annually. In case of suspicious events detected by the stations

  8. U/Th series radionuclides as coastal groundwater tracers

    Science.gov (United States)

    Swarzenski, P.W.

    2007-01-01

    The study of coastal groundwater has recently surfaced as an active interdisciplinary area of research, driven foremost by its importance as a poorly quantified pathway for subsurface material transport into coastal ecosystems. Key issue in coastal groundwater research include a complete geochemical characterization of the groundwater(s); quantification of the kinetics of subsurface transport, including rock-water interactions; determination of groundwater ages; tracing of groundwater discharge into coastal waters using radiochemical fingerprints; and an assessment of the potential ecological impact of such subsurface flow to a reviving water body. For such applications, the isotopic systemics of select naturally occurring radionucludes in the U/Th series has proven to be particularly useful. These radionuclides (e.g., U, Th, Ram and Rn) are ubiquitous in all groundwaters ad are represented by several isotopes with widely different half-lives and chemistries (Figure 1). As a result, varied biogeochemical processes occurring over a broad range of time scales can be studied. In source rock, most U/Th series isotopes in secular equilibrium; that is, the rate of decay of a daughter isotope is equal to that of it radiogenic parent, and so will have equal activities (in this context, the specific activity is simply a measure of the amount of radioactivity per unit amount). In contrast, these nuclides exhibit strong fractionations within the surrounding groundwaters because of their respective physiochemical differences. Disequilibria in U/Th series radionuclides can thus be used to identify distinct water masses, quantify release rates from source rocks, assess groundwater migration rates, and assess groundwater discharge rates in coastal waters., Large isotopic variations also have the potential for providing precise fingerprints for groundwaters from specific aquifers and have been explored as a means for calculating groundwater ages and estuarine water mass transit

  9. Prospects for the methods of radionuclide production

    International Nuclear Information System (INIS)

    Methods of radionuclide production for the nuclear-medicine purposes are described. In a budget approach, the application of low-energy accelerators is especially advantageous. Intense flux of bremsstrahlung at electron accelerators or high-current cyclotron beams of alpha particles must supply a great yield for many isotopes. The choice of a target material and of the projectile energy provides enough variation for concrete species formation. The innovating procedures are here proposed for optimizing of methods, for instance, application of the noble-gas target for production and transport of activities. The known and new variants of the 'generator' scheme are discussed. Many isotopes are listed as promising in the context of the therapeutic and theragnostic applications. Among them are isotopes/isomers emitting soft radiation for the selective and careful body treatment, also the positron emitters for PET, and the halogen and alkali-metal species convenient for chemical separation.

  10. Biosorption of radionuclides by fungal biomass

    International Nuclear Information System (INIS)

    Four kinds of bioreactor were evaluated for thorium removal by fungal biomass. An air-lift bioreactor removed approximately 90-95% of the thorium supplied over extended time periods and exhibited a well-defined breakthrough point after biosorbent saturation. The air-lift bioreactor promoted efficient circulation and effective contact between the thorium solution and the mycelial pellets. Of several fungal species tested, Rhizopus arrhizus and Aspergillus niger were the most effective biosorbents. The efficiency of thorium biosorption by A. niger was markedly reduced in the presence of other inorganic solutes while thorium biosorption by R. arrhizus was relatively unaffected. Air-lift bioreactors containing R. arrhizus biomass could effectively remove thorium from acidic solution over a wide range of initial thorium concentrations. The biotechnological application and significance of these results are discussed in the wider context of fungal biosorption of radionuclides. (author)

  11. Prospects for the methods of radionuclide production

    Science.gov (United States)

    Karamian, S. A.; Dmitriev, S. N.

    2015-03-01

    In the present report, methods of radionuclide production for the nuclear-medicine purposes are described. In a budget approach, the application of low-energy accelerators is especially advantageous. Intense flux of bremsstrahlung at electron accelerators or high-current cyclotron beams of alpha particles must supply a great yield for many isotopes. The choice of a target material and of the projectile energy provides enough variation for concrete species formation. The innovating procedures are here proposed for optimizing of methods, for instance, application of the noble-gas target for production and transport of activities. The known and new variants of the "generator" scheme are discussed. Many isotopes are listed as promising in the context of the therapeutic and theragnostic applications. Among them are isotopes/isomers emitting soft radiation for the selective and careful body treatment, also the positron emitters for PET, and the halogen and alkali-metal species convenient for chemical separation.

  12. Prospects for the methods of radionuclide production

    Energy Technology Data Exchange (ETDEWEB)

    Karamian, S. A., E-mail: karamian@nrmail.jinr.ru; Dmitriev, S. N. [Joint Institute for Nuclear Research, FLNR, 141980, Dubna, Moscow region (Russian Federation)

    2015-03-30

    In the present report, methods of radionuclide production for the nuclear-medicine purposes are described. In a budget approach, the application of low-energy accelerators is especially advantageous. Intense flux of bremsstrahlung at electron accelerators or high-current cyclotron beams of alpha particles must supply a great yield for many isotopes. The choice of a target material and of the projectile energy provides enough variation for concrete species formation. The innovating procedures are here proposed for optimizing of methods, for instance, application of the noble-gas target for production and transport of activities. The known and new variants of the “generator” scheme are discussed. Many isotopes are listed as promising in the context of the therapeutic and theragnostic applications. Among them are isotopes/isomers emitting soft radiation for the selective and careful body treatment, also the positron emitters for PET, and the halogen and alkali-metal species convenient for chemical separation.

  13. Cadastral valuation of land contaminated with radionuclides

    Science.gov (United States)

    Ratnikov, A. N.; Sapozhnikov, P. M.; Sanzharova, N. I.; Sviridenko, D. G.; Zhigareva, T. L.; Popova, G. I.; Panov, A. V.; Kozlova, I. Yu.

    2016-01-01

    The methodology and procedure for cadastral valuation of land in the areas contaminated with radionuclides are presented. The efficiency of rehabilitation measures applied to decrease crop contamination to the levels satisfying sanitary-hygienic norms is discussed. The differentiation of cadastral value of radioactively contaminated agricultural lands for the particular farms and land plots is suggested. An example of cadastral valuation of agricultural land contaminated during the Chernobyl Nuclear Power Plant accident is given. It is shown that the use of sandy and loamy sandy soddy-podzolic soils with the 137Cs contamination of 37-185 and >185 kBq/m2 for crop growing is unfeasible. The growing of grain crops and potatoes on clay loamy soddy-podzolic soils with the 137Cs contamination of 555-740 kBq/m2 is unprofitable. The maximum cadastral value of radioactively contaminated lands is typical of leached chernozems.

  14. SPECT quantification of regional radionuclide distributions

    International Nuclear Information System (INIS)

    SPECT quantification of regional radionuclide activities within the human body is affected by several physical and instrumental factors including attenuation of photons within the patient, Compton scattered events, the system's finite spatial resolution and object size, finite number of detected events, partial volume effects, the radiopharmaceutical biokinetics, and patient and/or organ motion. Furthermore, other instrumentation factors such as calibration of the center-of-rotation, sampling, and detector nonuniformities will affect the SPECT measurement process. These factors are described, together with examples of compensation methods that are currently available for improving SPECT quantification. SPECT offers the potential to improve in vivo estimates of absorbed dose, provided the acquisition, reconstruction, and compensation procedures are adequately implemented and utilized. 53 references, 2 figures

  15. Radionuclide molecular target therapy for lung cancer

    International Nuclear Information System (INIS)

    Lung cancer harms people's health or even lives severely. Currently, the morbidity and mortality of lung cancer are ascending all over the world. Accounting for 38.08% of malignant tumor caused death in male and 16% in female in cities,ranking top in both sex. Especially, the therapy of non-small cell lung cancer has not been obviously improved for many years. Recently, sodium/iodide transporter gene transfection and the therapy of molecular target drugs mediated radionuclide are being taken into account and become the new research directions in treatment of advanced lung cancer patients with the development of technology and theory for medical molecular biology and the new knowledge of lung cancer's pathogenesis. (authors)

  16. Database for radionuclide transport in the biosphere

    International Nuclear Information System (INIS)

    The biosphere model is the final link in the chain of radionuclide transport models, used for radiation dose calculations from high level waste repositories. This report presents the data needed for biosphere calculations and discusses them where necessary. The first part is dedicated to the nuclide specific parameters like distribution coefficients (water - soil), concentration ratios (soil - plant) and distribution factors (for milk, meat etc.) which are reported in the literature. The second part contains the choice of regions, their division into compartments and the discussion of nutritional habits for man and animals. At the end a theoretical population for each region is estimated based on the consumption rates and on the yield of agricultural products, assuming an autonomous nutrition. (Auth.)

  17. Natural analogues and radionuclide transport model validation

    International Nuclear Information System (INIS)

    In this paper, some possible roles for natural analogues are discussed from the point of view of those involved with the development of mathematical models for radionuclide transport and with the use of these models in repository safety assessments. The characteristic features of a safety assessment are outlined in order to address the questions of where natural analogues can be used to improve our understanding of the processes involved and where they can assist in validating the models that are used. Natural analogues have the potential to provide useful information about some critical processes, especially long-term chemical processes and migration rates. There is likely to be considerable uncertainty and ambiguity associated with the interpretation of natural analogues, and thus it is their general features which should be emphasized, and models with appropriate levels of sophistication should be used. Experience gained in modelling the Koongarra uranium deposit in northern Australia is drawn upon. (author)

  18. Radionuclide localization of lower gastrointestinal hemorrhage

    International Nuclear Information System (INIS)

    The authors prospectively evaluated the usefulness of abdominal radionuclide scintigraphy using /sup 99m/Tc-labeled red cells as a means of monitoring for intermittent gastrointestinal bleeding over a 24-hour period in both control and actively bleeding populations. Of 32 patients with documented hemorrhage, 29 had positive scintiscans (sensitivity, 91%; 9% false negatives). Of 18 nonbleeding patients, 17 had negative scintiscans (specificity, 95%; 5% false positives). 12 of 29 patients bled from 6 to 24 hours after the study was begun. Scintiscans were positive in patient with transfusion requirements of greater than or equal to 500 ml/24 hr. The authors conclude that abdominal scintigraphy with /sup 99m/Tc-labeled red cells is an effective method of detecting gastrointestinal bleeding

  19. Hydroponic phytoremediation of heavy metals and radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Hartong, J.; Szpak, J.; Hamric, T.; Cutright, T.

    1998-07-01

    It is estimated that the Departments of Defense, Energy, and Agriculture will spend up to 300 billion federal dollars on environmental remediation during the next century. Current remediation processes can be expensive, non-aesthetic, and non-versatile. Therefore, the need exists for more innovative and cost effective solutions. Phytoremediation, the use of vegetation for the remediation of contaminated sediments, soils, and ground water, is an emerging technology for treating several categories of persistent, toxic contaminants. Although effective, phytoremediation is still in a developmental stage, and therefore is not a widely accepted technology by regulatory agencies and public groups. Research is currently being conducted to validate the processes effectiveness as well as increase regulatory and community acceptance. This research will focus on the ability of plants to treat an aquifer contaminated with heavy metals and radionuclides. Specifically, the effectiveness of hydroponically grown dwarf sunflowers and mustard seed will be investigated.

  20. Natural radionuclides in bottled water in Austria

    International Nuclear Information System (INIS)

    Concentration levels of 226Ra, 222Rn and 210Pb were analyzed in domestic bottled waters commercially available in Austria. Concentrations up to 0.23 Bq/l, with a geometric mean of 0.041 Bq/l were found for 226Ra. Concentrations for 222Rn ranged from 226Ra range from 0.001 to 0.22 mSv/y and of 210Pb from 0.0003 to 0.05 mSv/y. Ingestion doses from 222Rn are low compared to those from 226Ra and 210Pb, ranging from 0.0001 to 0.011 mSv/y for adults and children, respectively. The doses are compared to the total ingestion dose from dietary intake of natural radionuclides on an annual basis

  1. Radionuclide fractionation in a forest soil profile

    International Nuclear Information System (INIS)

    Two alternative approaches, a sequential extraction scheme and the calculation of the variation of the distribution coefficient of radiocaesium in different K-CaNH4 scenarios, were used to study the behaviour and fractionation of this radionuclide in a forest soil profile. The first approach was applied to samples originating from an experiment in which the original L(litter) layer was replaced by an L layer contaminated with a radioactive aerosol, allowing a downward migration of radiocaesium. The samples belonged to different stages after the contamination. The second approach was applied to samples contaminated with soluble radiocaesium. The results indicate that the mineral matter seems to govern the behaviour of radiocaesium in case of direct condensed deposition or when radiocaesium is released from structural components of the organic matter phase. (author). 16 refs., 2 figs., 1 tab

  2. In vitro radionuclide techniques in medical diagnosis

    International Nuclear Information System (INIS)

    The use of radionuclide based microanalytical techniques for medical diagnosis has been increasing in recent years. Several such methods are in routine use in advanced laboratories in the industrialized world, but are often beyond the capability of developing countries. The IAEA has organized several training activities and seminars to bring the benefits of such advances to laboratories in developing Member States. The most recent was an interregional training course in Tokyo, March 1996, in collaboration with the Japanese Atomic Energy Research Institute (JAERI). The course was conducted by international experts, local staff, and IAEA staff. With the intention of giving the main techniques used at the course to a wider distribution they have been compiled into the present technical document. It is hoped that laboratories in developing Member States that did not have participants at the training course will find the information provided useful and sufficiently detailed to enable their application in their home institutions

  3. Chancellor Water Colloids: Characterization and Radionuclide Association

    Energy Technology Data Exchange (ETDEWEB)

    Abdel-Fattah, Amr I. [Los Alamos National Laboratory

    2012-06-18

    Concluding remarks about this paper are: (1) Gravitational settling, zeta potential, and ultrafiltration data indicate the existence of a colloidal phase of both the alpha and beta emitters in the Chancellor water; (2) The low activity combined with high dispersion homogeneity of the Chancellor water indicate that both alpha and beta emitters are not intrinsic colloids; (3) Radionuclides in the Chancellor water, particularly Pu, coexist as dissolved aqueous and sorbed phases - in other words the radionuclides are partitioned between the aqueous phase and the colloidal phase; (4) The presence of Pu as a dissolved species in the aqueous phase, suggests the possibility of Pu in the (V) oxidation state - this conclusion is supported by the similarity of the k{sub d} value of Pu determined in the current study to that determined for Pu(V) sorbed onto smectite colloids, and the similar electrokinetic behavior of the Chancellor water colloids to smectite colloids; (5) About 50% of the Pu(V) is in the aqueous phase and 50% is sorbed on colloids (mass concentration of colloids in the Chancellor water is 0.12 g/L); (6) The k{sub d} of the Pu and the beta emitters (fission products) between aqueous and colloidal phases in the Chancellor water is {approx}8.0 x 10{sup 3} mL/g using two different activity measurement techniques (LSC and alpha spectroscopy); (7) The gravitational settling and size distributions of the association colloids indicate that the properties (at least the physical ones) of the colloids to which the alpha emitters are associated with seem to be different that the properties of the colloids to which the beta emitters are associated with - the beta emitters are associated with very small particles ({approx}50 - 120 nm), while the alpha emitters are associated with relatively larger particles; and (8) The Chancellor water colloids are extremely stable under the natural pH and ionic strength conditions, indicating high potential for transport in the

  4. The glass block site radionuclide migration study

    International Nuclear Information System (INIS)

    In 1960 25 nepheline syenite glass blocks containing 14 TBq of mixed fission products in 50 kg of glass were placed below the water table in a shallow sand aquifer at Chalk River Laboratories. Experimental studies undertaken at the site since 1960 have included detailed mapping of the plume of 90Sr in 1963, 1966 and 1971. Mathematical modeling studies have employed the radiostrontium plume data in determining the split between ion exchange and chemisorption of 90Sr, and in obtaining reaction rate data for chemisorption. The distribution of 137Cs on downgradient soils was mapped in 1963 and 1979. An extended plume of low-level 137Cs contamination observed in the 1979 study prompted an investigation of the role of particulate materials in radionuclide transport. IN 1983, large volume groundwater sampling and separation of cationic, anionic, and neutral dissolved species, as well as particulates, detected anionic and cationic dissolved europium isotopes (154 and 155), and again encountered particulate 137Cs. A variety of investigations of cesium and strontium sorption have provided a data base on sediment mineralogy, particle surface features, and information on sorption sites and processes. The year 1990 saw the inauguration of a three-year program to update investigations of radionuclide release, transport, and sorption at the glass block site. The first stage of the program has been a detailed definition and simulation of the hydrogeologic setting. Plume mapping and aqueous speciation studies are in progress. This paper summarizes past investigations, reviews the status of the current program, and discusses components of future studies, including investigations of sediment sorption mechanisms. (Author) (17 refs., 8 figs.)

  5. Compilation of data for radionuclide transport analysis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-11-01

    This report is one of the supporting documents to the updated safety assessment (project SAFE) of the Swedish repository for low and intermediate level waste, SFR 1. A number of calculation cases for quantitative analysis of radionuclide release and dose to man are defined based on the expected evolution of the repository, geosphere and biosphere in the Base Scenario and other scenarios selected. The data required by the selected near field, geosphere and biosphere models are given and the values selected for the calculations are compiled in tables. The main sources for the selected values of the migration parameters in the repository and geosphere models are the safety assessment of a deep repository for spent fuel, SR 97, and the preliminary safety assessment of a repository for long-lived, low- and intermediate level waste, SFL 3-5. For the biosphere models, both site-specific data and generic values of the parameters are selected. The applicability of the selected parameter values is discussed and the uncertainty is qualitatively addressed for data to the repository and geosphere migration models. Parameter values selected for these models are in general pessimistic in order not to underestimate the radionuclide release rates. It is judged that this approach combined with the selected calculation cases will illustrate the effects of uncertainties in processes and events that affects the evolution of the system as well as in quantitative data that describes this. The biosphere model allows for probabilistic calculations and the uncertainty in input data are quantified by giving minimum, maximum and mean values as well as the type of probability distribution function.

  6. Colloid-Associated Radionuclide Concentration Limits: ANL

    International Nuclear Information System (INIS)

    The purpose and scope of this report is to describe the analysis of available colloidal data from waste form corrosion tests at Argonne National Laboratory (ANL) to extract characteristics of these colloids that can be used in modeling their contribution to the source term for sparingly soluble radioelements (e.g., Pu). Specifically, the focus is on developing a useful description of the following waste form colloid characteristics: (1) composition, (2) size distribution, and (3) quantification of the rate of waste form colloid generation. The composition and size distribution information are intended to support analysis of the potential transport of the sparingly soluble radionuclides associated with the waste form colloids. The rate of colloid generation is intended to support analysis of the waste form colloid-associated radionuclide concentrations. In addressing the above characteristics, available data are interpreted to address mechanisms controlling colloid formation and stability. This report was developed in accordance with the ''Technical Work Plan for Waste Form Degradation Process Model Report for SR'' (CRWMS M and O 2000). Because the end objective is to support the source term modeling we have organized the conclusions into two categories: (1) data analysis conclusions and (2) recommendations for colloid source term modeling. The second category is included to facilitate use of the conclusions from the data analysis in the abstraction of a colloid source term model. The data analyses and conclusions that are presented in this report are based on small-scale laboratory tests conducted on a limited number of waste glass compositions and spent fuel types

  7. Introduction to radiobiology of targeted radionuclide therapy

    Directory of Open Access Journals (Sweden)

    Jean-Pierre ePOUGET

    2015-03-01

    Full Text Available During the last decades, new radionuclide-based targeted therapies have emerged as efficient tools for cancer treatment. Targeted radionuclide therapies (TRT are based on a multidisciplinary approach that involves the cooperation of specialists in several research fields. Among them, radiobiologists investigate the biological effects of ionizing radiation, specifically the molecular and cellular mechanisms involved in the radiation response. Most of the knowledge about radiation effects concerns external beam radiation therapy (EBRT and radiobiology has then strongly contributed to the development of this therapeutic approach. Similarly, radiobiology and dosimetry are also assumed to be ways for improving TRT, in particular in the therapy of solid tumors which are radioresistant. However, extrapolation of EBRT radiobiology to TRT is not straightforward. Indeed, the specific physical characteristics of TRT (heterogeneous and mixed irradiation, protracted exposure and low absorbed dose rate differ from those of conventional EBRT (homogeneous irradiation, short exposure and high absorbed dose rate, and consequently the response of irradiated tissues might be different. Therefore, specific TRT radiobiology needs to be explored. Determining dose-effect correlation is also a prerequisite for rigorous preclinical radiobiology studies because dosimetry provides the necessary referential to all TRT situations. It is required too for developing patient-tailored TRT in the clinic in order to estimate the best dose for tumor control, while protecting the healthy tissues, thereby improving therapeutic efficacy. Finally, it will allow to determine the relative contribution of targeted effects (assumed to be dose-related and non-targeted effects (assumed to be non-dose-related of ionizing radiation. However, conversely to EBRT where it is routinely used, dosimetry is still challenging in TRT. Therefore, it constitutes with radiobiology, one of the main

  8. Compilation of data for radionuclide transport analysis

    International Nuclear Information System (INIS)

    This report is one of the supporting documents to the updated safety assessment (project SAFE) of the Swedish repository for low and intermediate level waste, SFR 1. A number of calculation cases for quantitative analysis of radionuclide release and dose to man are defined based on the expected evolution of the repository, geosphere and biosphere in the Base Scenario and other scenarios selected. The data required by the selected near field, geosphere and biosphere models are given and the values selected for the calculations are compiled in tables. The main sources for the selected values of the migration parameters in the repository and geosphere models are the safety assessment of a deep repository for spent fuel, SR 97, and the preliminary safety assessment of a repository for long-lived, low- and intermediate level waste, SFL 3-5. For the biosphere models, both site-specific data and generic values of the parameters are selected. The applicability of the selected parameter values is discussed and the uncertainty is qualitatively addressed for data to the repository and geosphere migration models. Parameter values selected for these models are in general pessimistic in order not to underestimate the radionuclide release rates. It is judged that this approach combined with the selected calculation cases will illustrate the effects of uncertainties in processes and events that affects the evolution of the system as well as in quantitative data that describes this. The biosphere model allows for probabilistic calculations and the uncertainty in input data are quantified by giving minimum, maximum and mean values as well as the type of probability distribution function

  9. Anthropogenic radionuclides in sediment in the Japan Sea: distribution and transport processes of particulate radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Otosaka, S. [Marine Research Laboratory, Japan Atomic Energy Research Institute, 4-24, Minato-machi, Mutsu, Aomori 035-0064 (Japan)]. E-mail: otosaka.shigeyoshi@jaea.go.jp; Amano, H. [Marine Research Laboratory, Japan Atomic Energy Research Institute, 4-24, Minato-machi, Mutsu, Aomori 035-0064 (Japan); Ito, T. [Marine Research Laboratory, Japan Atomic Energy Research Institute, 4-24, Minato-machi, Mutsu, Aomori 035-0064 (Japan); Kawamura, H. [Research Group for Marine Environment, Japan Atomic Energy Research Institute, Tokai-Mura, Ibaraki 319-1195 (Japan); Kobayashi, T. [Marine Research Laboratory, Japan Atomic Energy Research Institute, 4-24, Minato-machi, Mutsu, Aomori 035-0064 (Japan); Research Group for Marine Environment, Japan Atomic Energy Research Institute, Tokai-Mura, Ibaraki 319-1195 (Japan); Suzuki, T. [Marine Research Laboratory, Japan Atomic Energy Research Institute, 4-24, Minato-machi, Mutsu, Aomori 035-0064 (Japan); Togawa, O. [Marine Research Laboratory, Japan Atomic Energy Research Institute, 4-24, Minato-machi, Mutsu, Aomori 035-0064 (Japan); Research Group for Marine Environment, Japan Atomic Energy Research Institute, Tokai-Mura, Ibaraki 319-1195 (Japan); Chaykovskaya, E.L. [Far Eastern Regional Hydrometeorological Research Institute, 24, Fontanaya St., Vladivostok, 690990 (Russian Federation); Lishavskaya, T.S. [Far Eastern Regional Hydrometeorological Research Institute, 24, Fontanaya St., Vladivostok, 690990 (Russian Federation); Novichkov, V.P. [Moscow State Engineering Physical Institute, 31, Kashirskiy Road, Moscow, 115409 (Russian Federation); Karasev, E.V. [Far Eastern Regional Hydrometeorological Research Institute, 24, Fontanaya St., Vladivostok, 690990 (Russian Federation); Tkalin, A.V.; Volkov, Y.N. [Far Eastern Regional Hydrometeorological Research Institute, 24, Fontanaya St., Vladivostok, 690990 (Russian Federation)

    2006-07-01

    Distributions of anthropogenic radionuclides ({sup 9}Sr, {sup 137}Cs and {sup 239+24}Pu) in seabed sediment in the Japan Sea were collected during the period 1998-2002. Concentration of {sup 9}Sr, {sup 137}Cs and {sup 239+24}Pu in seabed sediment was 0.07-1.6 Bq kg{sup -1}, 0.4-9.1 Bq kg{sup -1} and 0.002-1.9 Bq kg{sup -1}, respectively. In the northern basin of the sea (Japan Basin), {sup 239+24}Pu/{sup 137}Cs ratios in seabed sediment were higher and their variation was smaller compared to that in the southeastern regions of the sea. The higher {sup 239+24}Pu/{sup 137}Cs ratios throughout the Japan Basin were considered to reflect production of Pu-enriched particles in the surface layer and substantial sinking of particulate materials in this region. In the southern regions of the Japan Sea (<38{sup o}N), both inventories and {sup 239+24}Pu/{sup 137}Cs ratios in sediment were larger than those in the other regions. In the southern Japan Sea, observations suggested that supply of particulate radionuclides by the Tsushima Warm Current mainly enhanced accumulation of the radionuclides in this region.

  10. Building confidence in radionuclide transport models for fractured rock: the Nagra/JNC radionuclide retardation programme

    International Nuclear Information System (INIS)

    The joint Nagra/JNC Radionuclide Retardation Programme has now been ongoing for 15 years with the main aim of direct testing of radionuclide transport models in as realistic a manner as possible. A large programme of field, laboratory and natural analogue studies has been carried out at the Grimsel Test Site in the central Swiss Alps and the Kamaishi In Situ Test Site in north-east Japan. The understanding and modelling of both the processes and the structures influencing radionuclide transport/retardation in fractured host rocks have matured as has the experimental technology, which has contributed to develop confidence in the applicability of the underlying research models in a repository performance assessment. In this paper, the successes and set-backs of this programme are discussed as is the general approach to the thorough testing of the process models and of model assumptions. In addition, a set of key findings is presented, involving discussions on the enhancement of confidence through the program. Copyright (2001) Material Research Society

  11. Development of a technique of the rapid analysis for forecasting of possible radionuclides accumulation in the harvest of agricultural crops

    International Nuclear Information System (INIS)

    and specific feature of plants. For forecasting of possible level of pollution of a harvest by radionuclides with using of coefficients of accumulation it is necessary to define it beforehand. Then the forecast is carried out by simple multiplication of the contents of radionuclide in ground (Bq/kg) and coefficients of accumulation of radionuclides in a harvest of plants. Researches of the possible levels of pollution by caesium - 137 of a harvest and in young plants yielded results in many respects similar to results on strontium - 90. Hence it is possible to use both coefficients - Ct and Ca to both long-lived radionuclides and, probably, to other similar isotopes. Thus, the developed method of rapid analysis and it modifications allow to reduce greatly time in similar researches, that in itself it is important, but also will allow to expand significantly the range of objects of researches both radionuclides and agriculture plants.

  12. Atmospheric resuspension of radionuclides. Model testing using Chernobyl data

    International Nuclear Information System (INIS)

    Resuspension can be an important secondary source of contamination after a release has stopped, as well as a source of contamination for people and areas not exposed to the original release. The inhalation of resuspended radionuclides contributes to the overall dose received by exposed individuals. Based on measurements collected after the Chernobyl accident, Scenario R was developed to provide an opportunity to test existing mathematical models of contamination resuspension. In particular, this scenario provided the opportunity to examine data and test models for atmospheric resuspension of radionuclides at several different locations from the release, to investigate resuspension processes on both local and regional scales, and to investigate the importance of seasonal variations of these processes. Participants in the test exercise were provided with information for three different types of locations: (1) within the 30-km zone, where local resuspension processes are expected to dominate; (2) a large urban location (Kiev) 120 km from the release site, where vehicular traffic is expected to be the dominant mechanism for resuspension; and (3) an agricultural area 40-60 km from the release site, where highly contaminated upwind 'hot spots' are expected to be important. Input information included characteristics of the ground contamination around specific sites, climatological data for the sites, characteristics of the terrain and topography, and locations of the sampling sites. Participants were requested to predict the average (quarterly and yearly) concentrations of 137 Cs in air at specified locations due to resuspension of Chernobyl fallout; predictions for 90 Sr and 239 + 240 Pu were also requested for one location and time point. Predictions for specified resuspension factors and rates were also requested. Most participants used empirical models for the resuspension factor as a function of time K(t), as opposed to process-based models. While many of these

  13. Nanomaterial-based adsorbents. The prospect of developing new generation radionuclide generators to meet future research and clinical demands

    International Nuclear Information System (INIS)

    Nanostructured materials by virtue of huge surface to volume ratios, altered physical properties, tailored surface chemistry, favorable adsorption characteristics, and enhanced surface reactivity resulting from the nanoscale dimensions, have attracted considerable attention as a new class of adsorbent material in column chromatographic separation. This emerging class of adsorbent represents an innovative paradigm and is expected to play an important role in the development of radionuclide generators for nuclear medicine. The optimal combination of suitable nanomaterial and appropriate parent/daughter radionuclide pair forms the basis of such generators. Development of such generators is currently under intensive investigations and the utility of such systems is expected to pave the way for broad panoply of diagnostic and therapeutic applications in nuclear medicine. While nanomaterial-based radionuclide generator is still in its infancy, the use of such novel class of adsorbents is expected to have potential impact on shaping the radionuclide generator technology of future generation. This review provides a comprehensive summary on the utility of nanomaterials as effective adsorbents in the development column chromatographic radionuclide generators for medical applications. This overview outlines a critical assessment of role of the nanosorbents, recent developments, the contemporary status, and key challenges and apertures to the near future. (author)

  14. Genotoxic endpoints in the earthworms sub-lethal assay to evaluate natural soils contaminated by metals and radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Lourenco, Joana I., E-mail: joanalourenco@ua.pt [CESAM and Departamento de Biologia, Universidade de Aveiro, Campus Universitario de Santiago, 3810-193 Aveiro (Portugal); Pereira, Ruth O., E-mail: ruthp@ua.pt [CESAM and Departamento de Biologia, Universidade de Aveiro, Campus Universitario de Santiago, 3810-193 Aveiro (Portugal); Silva, Ana C., E-mail: ana.cmj@ua.pt [CESAM and Departamento de Biologia, Universidade de Aveiro, Campus Universitario de Santiago, 3810-193 Aveiro (Portugal); Morgado, Jose M., E-mail: jmtmorgado@gmail.com [Centro de Histocompatibilidade do Centro, Praceta Prof. Mota Pinto, Edificio S. Jeronimo, 4o piso, Apartado 9041, 3001-301 Coimbra (Portugal); Carvalho, Fernando P., E-mail: fernando.carvalho@itn.pt [Instituto Tecnologico Nuclear, Estrada Nacional 10, 2686-953 Sacavem (Portugal); Oliveira, Joao M., E-mail: joaomota@itn.pt [Instituto Tecnologico Nuclear, Estrada Nacional 10, 2686-953 Sacavem (Portugal); Malta, Margarida P., E-mail: margm@itn.pt [Instituto Tecnologico Nuclear, Estrada Nacional 10, 2686-953 Sacavem (Portugal); Paiva, Artur A., E-mail: apaiva@histocentro.min-saude.pt [Centro de Histocompatibilidade do Centro, Praceta Prof. Mota Pinto, Edificio S. Jeronimo, 4o piso, Apartado 9041, 3001-301 Coimbra (Portugal); Mendo, Sonia A., E-mail: smendo@ua.pt [CESAM and Departamento de Biologia, Universidade de Aveiro, Campus Universitario de Santiago, 3810-193 Aveiro (Portugal); Goncalves, Fernando J., E-mail: fjmg@ua.pt [CESAM and Departamento de Biologia, Universidade de Aveiro, Campus Universitario de Santiago, 3810-193 Aveiro (Portugal)

    2011-02-15

    Eisenia andrei was exposed, for 56 days, to a contaminated soil from an abandoned uranium mine and to the natural reference soil LUFA 2.2. The organisms were sampled after 0, 1, 2, 7, 14 and 56 days of exposure, to assess metals bioaccumulation, coelomocytes DNA integrity and cytotoxicity. Radionuclides bioaccumulation and growth were also determined at 0 h, 14 and 56 days of exposure. Results have shown the bioaccumulation of metals and radionuclides, as well as, growth reduction, DNA damages and cytotoxicity in earthworms exposed to contaminated soil. The usefulness of the comet assay and flow cytometry, to evaluate the toxicity of contaminants such as metals and radionuclides in earthworms are herein reported. We also demonstrated that DNA strand breakage and immune cells frequency are important endpoints to be employed in the earthworm reproduction assay, for the evaluation of soil geno and cytotoxicity, as part of the risk assessment of contaminated areas. This is the first study that integrates DNA damage and cytotoxicity evaluation, growth and bioaccumulation of metals and radionuclides in a sub lethal assay, for earthworms exposed to soil contaminated with metals and radionuclides.

  15. Bioavailability pf radionuclides {sup 226}Ra, {sup 228}Ra and {sup 210}Pb present in Brazilian phosphogypsum and phosphate fertilizers

    Energy Technology Data Exchange (ETDEWEB)

    Russo, Ana Carolina; Saueia, Catia H.R.; Mazzilli, Barbara P., E-mail: chsaueia@ipen.br [Instituto de Pesquisas Energeticas e Nucleares(IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    Phosphogypsum (PG) is a by-product of phosphate fertilizers industries. The USEPA classified PG as a - Technologically Enhanced Naturally Occurring Radioactive Material (TENORM). Its worldwide production on 2006 was estimated in 150 million tons. Annually the three main phosphate industries in Brazil are responsible for 5.5x106 tons of phosphogypsum, which is stored in stacks. The level of radionuclides present in phosphogypsum is well-known and makes its disposal or reutilization an environmental concern. Part of this byproduct can be reused, for example, to improve fertility of agricultural soils. To assess the long term environmental impact of radioactive contamination of ecosystems, information on source term including radionuclide speciation, mobility and biological uptakes have high importance. This paper intends to evaluate the bioavailability of the radionuclides {sup 226}Ra, {sup 228}Ra and {sup 210}Pb to the environment by following a procedure established by the EC (European Community), which includes a single EDTA-NH{sub 4} 0.05M extraction at pH 7.0 prior to the analyses. These results is compared with the total activity concentration of these radionuclides in Brazilian PG and the most used phosphate fertilizers (SSP, TSP, MAP and DAP). This procedure intends to represent on a more realistic way the leaching of radionuclides from PG and fertilizers to soil and agricultural products. (author)

  16. Bioavailability pf radionuclides 226Ra, 228Ra and 210Pb present in Brazilian phosphogypsum and phosphate fertilizers

    International Nuclear Information System (INIS)

    Phosphogypsum (PG) is a by-product of phosphate fertilizers industries. The USEPA classified PG as a - Technologically Enhanced Naturally Occurring Radioactive Material (TENORM). Its worldwide production on 2006 was estimated in 150 million tons. Annually the three main phosphate industries in Brazil are responsible for 5.5x106 tons of phosphogypsum, which is stored in stacks. The level of radionuclides present in phosphogypsum is well-known and makes its disposal or reutilization an environmental concern. Part of this byproduct can be reused, for example, to improve fertility of agricultural soils. To assess the long term environmental impact of radioactive contamination of ecosystems, information on source term including radionuclide speciation, mobility and biological uptakes have high importance. This paper intends to evaluate the bioavailability of the radionuclides 226Ra, 228Ra and 210Pb to the environment by following a procedure established by the EC (European Community), which includes a single EDTA-NH4 0.05M extraction at pH 7.0 prior to the analyses. These results is compared with the total activity concentration of these radionuclides in Brazilian PG and the most used phosphate fertilizers (SSP, TSP, MAP and DAP). This procedure intends to represent on a more realistic way the leaching of radionuclides from PG and fertilizers to soil and agricultural products. (author)

  17. Radionuclide Incorporation in Secondary Crystalline Minerals Resulting from Chemical Weathering of Selected Waste Glasses: Progress Report: Task kd.5b

    Energy Technology Data Exchange (ETDEWEB)

    Mattigod, Shas V.; Serne, R. Jeffrey; Legore, Virginia L.; Parker, Kent E.; Orr, Robert D.; McCready, David E.; Young, James S.

    2003-09-29

    Experiments were conducted by Pacific Northwest National Laboratory to evaluate potential incorporation of radionuclides in secondary mineral phases that form from weathering vitrified nuclear waste glasses. These experiments were conducted as part of the Immobilized Low-Activity Waste-Performance Assessment (ILAW-PA) to generate data on radionuclide mobilization and transport in a near-field environment of disposed vitrified wastes. The results of these experiments demonstrated that radionuclide sequestration can be significantly enhanced by promoting the formation of cage structured minerals such as sodalite from weathering glasses. These results have important implications regarding radionuclide sequestration/mobilization aspects that are not currently accounted for in the ILAW PA. Additional studies are required to confirm the results and to develop an improved understanding of the mechanisms of sequestration of radionuclides into the secondary and tertiary weathering products of the ILAW glass to help refine how contaminants are released from the near-field disposal region out into the accessible environment. Of particular interest is to determine whether the contaminants remain sequestered in the glass weathering products for hundreds to thousands of years. If the sequestration can be shown to continue for long periods, another immobilization process can be added to the PA analysis and predicted risks should be lower than past predictions.

  18. Vertical distribution of natural radionuclides in soil: Assessment of external exposure of population in cultivated and undisturbed areas

    Energy Technology Data Exchange (ETDEWEB)

    Nenadovic, Snezana [Laboratory for Material Science, Institute of Nuclear Sciences ' Vinca' , University of Belgrade, Belgrade (Serbia); Nenadovic, Milos [Laboratory for Atomic Physics, Institute of Nuclear Sciences ' Vinca' , University of Belgrade, Belgrade (Serbia); Kljajevic, Ljiljana, E-mail: ljiljana@vinca.rs [Laboratory for Material Science, Institute of Nuclear Sciences ' Vinca' , University of Belgrade, Belgrade (Serbia); Vukanac, Ivana [Laboratory for Nuclear and Plasma Physics, Institute of Nuclear Sciences ' Vinca' , University of Belgrade, Belgrade (Serbia); Poznanovic, Maja [Geological Institute of Serbia, Chemical laboratory, University of Belgrade, Belgrade (Serbia); Mihajlovic-Radosavljevic, Ana [Laboratory for Material Science, Institute of Nuclear Sciences ' Vinca' , University of Belgrade, Belgrade (Serbia); Pavlovic, Vladimir [Faculty of Agriculture, University of Belgrade, Belgrade (Serbia)

    2012-07-01

    In the present work, naturally occurring radionuclides {sup 238}U, {sup 232}Th and {sup 40}K were measured in soil samples from the cultivated and undisturbed areas in Rudovci, municipality of Lazarevac, Serbia. There were three profiles, each profile divided into four horizons, giving the twelve soil samples. The specific activity of {sup 238}U, {sup 232}Th and {sup 40}K in soil and sediment samples was determined by gamma spectrometry using the HPGe semiconductor detector. Obtained activity concentrations ranged from 28.0 to 44.0 Bq/kg for {sup 238}U, from 59.4 to 71.4 Bq/kg for {sup 232}Th and from 335.0 to 517.0 Bq/kg for {sup 40}K. The evaluation of the radiological hazards originated from {sup 238}U, {sup 232}Th and {sup 40}K in the samples, the absorbed dose rate (D) and the annual effective dose rate (E), calculated in accordance with the UNSCEAR 2000 report, are presented in this paper. - Highlights: Black-Right-Pointing-Pointer Radionuclides {sup 238}U, {sup 232}Th and {sup 40}K in different profile of soil are measured. Black-Right-Pointing-Pointer Gamma spectrometry specific activity of radionuclides was determined. Black-Right-Pointing-Pointer Correlation between the physical-chemical parameters of soil and natural radionuclides is important. Black-Right-Pointing-Pointer Concentrations of radionuclides are not extremely changed at the profiles.

  19. MIRD Pamphlet No. 22 (Unabridged): Radiobiology and Dosimetry of alpha-Particle Emitters for Targeted Radionuclide Therapy

    Energy Technology Data Exchange (ETDEWEB)

    Sgouros, George; Roeske, John C.; McDevitt, Michael S.; Palm, Stig; Allen, Barry J.; Fisher, Darrell R.; Brill, Bertrand A.; Song, Hong; Howell, R. W.; Akabani, Gamal

    2010-02-28

    The potential of alpha-particle emitters to treat cancer has been recognized since the early 1900s. Advances in the targeted delivery of radionuclides, in radionuclide conjugation chemistry, and in the increased availability of alpha-emitters appropriate for clinical use have recently led to patient trials of alpha-particle-emitter labeled radiopharmaceuticals. Although alpha-emitters have been studied for many decades, their current use in humans for targeted therapy is an important milestone. The objective of this work is to review those aspects of the field that are pertinent to targeted alpha-particle-emitter therapy and to provide guidance and recommendations for human alpha-particle-emitter dosimetry.

  20. The soil fertility role in radionuclide accumulation in agricultural production and reduction of irradiation doses of population

    International Nuclear Information System (INIS)

    The soil reaction, humus content, calcium, magnesium and potassium status, as well as water regime are the most important soil properties, which determine Cs-137 and Sr-90 transfer to plants. The optimal ranges of soil fertility parameters for the lowest transferring of radionuclides to the yield of agricultural crops were found. The efficiency of agrochemical protective measures on radioactively contaminated land of Gomel, Mogilev and Brest regions of Belarus is discussed. Balanced rates of fertilizers on the background of liming of acid soils allow the significant reduction of radionuclide concentration in foodstuff of local production and irradiation doses of population and provides the profitable increase of crop yields (author)