Bibliografias temáticas / Radioisotopes – Safety measures

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Literatura científica selecionada sobre o tema "Radioisotopes – Safety measures"

Autor: Grafiati

Publicado: 4 de junho de 2021

Última modificação: 11 de fevereiro de 2022

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Artigos de revistas sobre o assunto "Radioisotopes – Safety measures"

IIMOTO, Takeshi, Keiji KIMURA, Eriko HAYASHI, Tomoko M. NAKANISHI, Toshiso KOSAKO e Nobuyuki SUGIURA. "Internal/International Situation on Safety for Nuclear Materials, and Discussion on Measures in Facilities". RADIOISOTOPES 57, n.º 6 (2008): 393–403. http://dx.doi.org/10.3769/radioisotopes.57.393.

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Kambali, Imam, Indra Saptiama e Hari Suryanto. "Residual Radioisotopes Generated from Neutron Irradiated Aluminum Capsules". Aceh International Journal of Science and Technology 6, n.º 3 (31 de dezembro de 2017): 104–10. http://dx.doi.org/10.13170/aijst.6.3.8116.

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Aluminum (Al) is often used to house a molybdenum oxide (MoO3) target for neutron or proton-produced technetium-99m (99mTc) radioisotope. During neutron or proton bombardment of an Al body, residual radioisotopes could be generated following nuclear reactions between the incoming particles and the Al body. In this research, residual radioisotopes produced following nuclear reactor based-neutron irradiation of Al body were experimentally measured using a portable gamma ray spectroscopy system; whereas TALYS 2015 calculated data were used to evaluate various nuclear reactions for the by-product identification. As a comparison, Al body used in a cyclotron-based 99mTc production was also analyzed. Experimental data indicated that relatively long-lived radioisotopes such as 26Al, 22Na and 24Na were identified in the Al body following nuclear reactor-based 99mTc production, whereas the presence of 27Mg radioisotope was, for the first time, experimentally detected in both the Al bodies for nuclear reactor-based and cyclotron-based 99mTc production. A special safety attention should be paid to the radiation workers when producing 99mTc using a nuclear reactor since it generates 26Al (half life = 716,600 years).

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Sarshough, Samira, Kamal Hadad e Reza Faghihi. "Particle size and concentration effects on low energy X-ray attenuation in nanostructure and microstructure materials". Nuclear Technology and Radiation Protection 33, n.º 1 (2018): 75–80. http://dx.doi.org/10.2298/ntrp1801075s.

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The effects of microsize and nanosize particles in composite structures as well as the incident radiation energy on X-ray attenuation is the focus of this study. To examine these effects, composite samples with different particle sizes of Al2O3 and with different thicknesses were prepared. Characteristic X-rays are applied as monochromatic X-rays and measurements were performed using an X-ray tube with a secondary excitation source instead of radioisotopes. In order to improve the efficiency and minimize the background effects a special detection system was designed and prepared. The linear attenuation coefficients of these samples are measured for X-ray photo energies of 6.40-28.49 keV. The results show that these low energy X-ray beams are more attenuated by nano-structured material compared to the micro-structured one.

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Salman, Muhammad, Christina Macano, Rishabha D. Sharma e Alfonso Antequerra. "Magnetic nanoparticle technique versus radioisotope technique in detection of sentinel lymph node in early breast cancer: a systematic review and meta-analysis". International Surgery Journal 8, n.º 6 (28 de maio de 2021): 1870. http://dx.doi.org/10.18203/2349-2902.isj20212284.

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Sentinel lymph node biopsy is the standard technique to stage the axilla in early breast cancer. The gold standard is the dual technique of radioisotope and blue dye injection. The drawbacks of dual technique include handling and disposal of radioactive material. Equally reliable, user and patient friendly, magnetic tracer super paramagnetic iron oxide, was compared with the radioisotope tracer in detection of Sentinel lymph node in a clinically node negative axilla in early breast cancer in this meta-analysis, with emphasis on the utility and safety of both techniques. PubMed, Medline were searched from April 2015 to October 2019. 1395 patients’ data was included from seven homogenous studies in this meta-analysis. A statistical analysis was performed using STATA 16.1 version for sentinel lymph node detection rate using standard technique, magnetic tracer technique and both techniques. Ratio of successes and failures of the outcomes was measured and analysed. A paired two sample ‘Z’ test was performed to compare between the standard technique and magnetic tracer techniques. The standardised mean difference of ratio of success rate between two techniques was; 1.013334 with a p value of 0.3136.The standardised mean difference of ratio of failure rate between two techniques was 1.016667, with a p value of 0.3132. Success and failure rate showed statistically no significant difference between the two techniques. This two-way analysis with paired two sample ‘Z’ test confirms that neither standard technique nor magnetic tracer techniques are superior or inferior to each other.

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Ateia, Embarka, Olivera Ciraj-Bjelac, Milojko Kovacevic, Petar Belicev, Bratislav Cvetkovic e Ivan Anicin. "Additional dose assessment from the activation of high-energy linear accelerators used in radiation therapy". Nuclear Technology and Radiation Protection 23, n.º 2 (2008): 58–64. http://dx.doi.org/10.2298/ntrp0802058a.

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It is well known that medical linear accelerators generate activation products when operated above certain electron (photon) energies. The aim of the present work is to assess the activation behavior of a medium-energy radiotherapy linear accelerator by applying in situ gamma-ray spectrometry and dose measurements, and to estimate the additional dose to radiotherapy staff on the basis of these results. Spectral analysis was performed parallel to dose rate measurements in the isocenter of the linear accelerator, immediately after the termination of irradiation. The following radioisotopes were detected by spectral analysis: 28Al, 62Cu, 56Mn, 64Cu, 187W, and 57Ni. The short-lived isotopes such as 28Al and 62Cu are the most important factors of the clinical routine, while the contribution to the radiation dose of medium-lived isotopes such as 56Mn, 57Ni, 64Cu, and 187W increases during the working day. Measured dose rates at the isocenter ranged from 2.2 ?Sv/h to 10 ?Sv/h in various measuring points of interest for the members of the radiotherapy staff. Within the period of 10 minutes, the dose rate decreased to values of 0.8 ?Sv/h. According to actual workloads in radiotherapy departments, a realistic exposure scenario was set, resulting in a maximal additional annual whole body dose to the radiotherapy staff of about 3.5 mSv.

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Fairweather-Tait, Susan J., e Agnès de Sesmaisons. "Approaches used to estimate bioavailability when deriving dietary reference values for iron and zinc in adults". Proceedings of the Nutrition Society 78, n.º 1 (27 de julho de 2018): 27–33. http://dx.doi.org/10.1017/s0029665118000484.

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This review aims to describe approaches used to estimate bioavailability when deriving dietary reference values (DRV) for iron and zinc using the factorial approach. Various values have been applied by different expert bodies to convert absorbed iron or zinc into dietary intakes, and these are summarised in this review. The European Food Safety Authority (EFSA) derived zinc requirements from a trivariate saturation response model describing the relationship between zinc absorption and dietary zinc and phytate. The average requirement for men and women was determined as the intercept of the total absorbed zinc needed to meet physiological requirements, calculated according to body weight, with phytate intake levels of 300, 600, 900 and 1200 mg/d, which are representative of mean/median intakes observed in European populations. For iron, the method employed by EFSA was to use whole body iron losses, determined from radioisotope dilution studies, to calculate the quantity of absorbed iron required to maintain null balance. Absorption from the diet was estimated from a probability model based on measures of iron intake and status and physiological requirements for absorbed iron. Average dietary requirements were derived for men and pre- and post-menopausal women. Taking into consideration the complexity of deriving DRV for iron and zinc, mainly due to the limited knowledge on dietary bioavailability, it appears that EFSA has made maximum use of the most relevant up-to-date data to develop novel and transparent DRV for these nutrients.

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Kulseng, Carl Petter Skaar, e Jon Christoffer Sandstrøm. "Effective doses to staff and dose rates emitted from patients undergoing positron emission tomography utilizing 18F- Fluorodeoxglucose". Radiography Open 2, n.º 1 (30 de novembro de 2015): 1–14. http://dx.doi.org/10.7577/radopen.1526.

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IntroductionThe purpose of this two--folded quantitative study was to determine the radiation doses received by staff during 2014 at the PET--department at St. Olavs Hospital in Trondheim, Norway. Although studies show that the doses received by staff performing such examinations are far beneath the limits set by regulation, there was a need to determine how much radiation the staff at this clinic actually was exposed to. We investigated in detail both dose rates emitted by 18 F from different parts of the body to the surroundings along with effective doses to staff during 2014.MethodPart one - Dose rates from 20 patients undergoing FDG-PET/CT--scans were measured with dosimeter RadEye B20 (Thermo Scientific, USA) from five measuring points at three different stages of a standard whole body PET-scan utilizing 18 F-FDG.Part two - Effective doses to five radiographers and four bioengineers were registered daily during 2014. The effective dose measurements were done daily by the staff with personal dosimeter RadEye EPD MK2+ (Thermo Scientific, USA). The dosimeter was worn at chest level. The automatic injector Medrad Intego (Bayer, Germany) administrate the radioactive doses.ResultsPart one - Dose rates emitted from different parts of patients show significant differences. The highest dose rate was measured from the head and sternum of the patients. The knees emit the least dose rate of all body parts and was considerably lower from one meterdistance.Part two - The average effective doses were far below the recommended limits for occupational radiation. The total average effective dose per member of staff was 0.13 mSv in 2014 and the daily average dose was 4.91 μSv/day.ConclusionPart one - 18 F-FDG showed irregular distribution in the body, the lowest dose rates originated from the lower extremities and reflects the metabolism of glucose in the body at rest.Part two - We found significant differences between staff working with both CT and the radioisotope injection compared to the staff working solely with one of these tasks. Nevertheless, all effective- doses were safely within the guideline limits for occupational radiation.

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McKay, Rana R., Heather Jacene, Pamela J. Atherton, Gabriela Perez Burbano, Archana Ajmera, Shiva Baghaie, Janet Koball et al. "A randomized trial of radium-223 (Ra-223) dichloride and cabozantinib in patients (pts) with advanced renal cell carcinoma (RCC) with bone metastases (RADICAL/Alliance A031801)." Journal of Clinical Oncology 39, n.º 15_suppl (20 de maio de 2021): TPS4593. http://dx.doi.org/10.1200/jco.2021.39.15_suppl.tps4593.

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TPS4593 Background: Bone metastases are prevalent in approximately 30% of pts with advanced RCC. Pts with bone metastases have a worse prognosis compared to pts without bone metastases and are at risk of symptomatic skeletal events (SSEs). Cabozantinib, a multitargeted inhibitor of multiple kinases, including vascular endothelial growth factor (VEGF) receptor and MET, has improved survival in pts with metastatic RCC and has enhanced activity in bone. Ra-223, an alpha-emitting radioisotope with natural bone-seeking proclivity, has been shown to prolong survival in men with castration-resistant prostate cancer. We previously conducted a pilot study of Ra-223 with VEGF inhibition and demonstrated safety and declines in markers of bone formation and resorption with the combination (McKay et al, CCR 2018). Given that decreasing rates of SSEs and improving outcomes for pts with RCC with bone metastases are unmet needs in pts with RCC, we designed a randomized phase 2 study through the National Clinical Trials Network (NCTN) investigating cabozantinib with or without Ra-223 in patients with RCC with bone metastases. Methods: This is an open-label multicenter study. Eligible pts have metastatic RCC of any histology with ≥2 metastatic bone lesions untreated with prior radiation therapy and no more than 2 prior lines of systemic therapy. Pts with non-clear cell RCC are eligible and will be capped at 20% of the total accrual goal. Pts must have a Karnofsky performance status of ≥60%, have symptomatic bone pain defined as a prior SSE or need of analgesics, and be on osteoclast-targeted therapy unless otherwise contraindicated. Pts are randomized 1:1 to cabozantinib with (Arm A) or without (Arm B) Ra-223. Starting dose of cabozantinib for Arm A is 40 mg by mouth daily to be escalated to 60 mg daily after cycle 1 (1 cycle = 28 days) if no persistent grade 2 or grade ≥3 toxicity. Ra-223 is administered at a fixed dose of 1.49 microcurie/kg IV every 28 days x 6 doses. The primary endpoint is SSE-free survival. Secondary endpoints include safety, progression-free survival, overall survival, quality of life measures, and correlative analyses including liquid biopsy studies and tumor tissue analysis. The study has 90% power to detect an improvement in 6-month SSE-free survival rate from 65% to 78% with one-sided α = 0.025 significance. To ensure 191 evaluable patients, target accrual is 210 pts. This design includes a safety run-in and an interim analysis for futility when 50% of the expected number of events (72 SSE events) have been observed. Final data analysis will occur when 143 events have been observed. The study was activated in December 2019 and accrual is currently ongoing throughout the NCTN. Clinical trial information: NCT04071223.

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Chu, Bae P., Neeta Pandit-Taskar, Boglarka Gyurkocza, Qing Liang, Daniel Miodownik, Vijay Reddy, Mark S. Berger e Lawrence T. Dauer. "Feasibility of Administering Anti-CD45 Iodine (131I) Apamistamab [Iomab-B] for Re-Induction and Targeted Conditioning in Older Patients with Active, Relapsed or Refractory AML without Lead-Lined Rooms: Sierra Trial Experience at MSKCC". Blood 134, Supplement_1 (13 de novembro de 2019): 5839. http://dx.doi.org/10.1182/blood-2019-131230.

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Background: Patients ≥55 years of age with active, relapsed or refractory acute myeloid leukemia (R/R AML) who have failed standard induction and salvage therapies do not routinely undergo allogeneic hematopoietic cell transplantation (HCT) due to their inability to receive myeloablative conditioning and lack of efficacy. The SIERRA trial is a prospective, randomized, phase 3, open-label, multicenter trial designed to address this significant unmet need. Preliminary results have shown the re-induction and targeted conditioning therapy with Iomab-B can lead to successful engraftment. Because of the administered activity of 131I (300-1030 mCi, mean ~600 mCi), patients are isolated for several days after the drug administration before being discharged. Radiation safety procedures with rolling lead shields and blankets were implemented to ensure compliance with local regulations for therapeutic radioisotopes and the safe administration of Iomab-B. Methods: A corner room with private bathroom was selected as the patient room for drug administration and patient isolation. The room was prepared to prevent radioactive contamination. Rolling lead shields were utilized depending on the room configuration: 2 shields against the patient emitting radiation and closer to the door, or 3 shields total with 1 additional shield by the nurses' work station in the room. Lead blankets were placed under the patient bed. Extensive radiation safety training was provided to nursing staff who interacted with Iomab-B patients. The administration was performed in the room using an automatic pump system with Iomab-B drug vial placed in a lead pig during infusion (4-5 hours). Radiation dose rates at several locations were measured at the completion of administration. Radiation doses to nurses who provided care to patients were monitored with personal dosimeters throughout the course of treatment, while the patients remained in radiation isolation. Results: 10 Iomab-B patients were treated with 788 ± 192 (range: 543-1069 mCi). Exposure survey results were taken within 2 hours after therapeutic infusion outside the patient door (mean 0.64, range 0.06-1.95 mrem/hr) the hallway (0.01 mrem/hr, background levels) adjacent rooms (mean 0.747, range 0.2-1.82 mrem/hr) as well as above (mean 0.986, range 0.5-1.6 mrem/hr) and below (mean 1.398, range 0.81-1.88 mrem/hr) the room. All the exposure survey results were below the regulated public area limit, 2 mrem/hr. The dose to inpatient nurses caring for the patient was 9.42 ± 6.6 (range: 1-27 mrem), which is minimal comparing to annual occupational dose limit of 5,000 mrem. The rooms were surveyed for contamination after the patient was cleared from radiation isolation and removable surface contamination was below 200 dpm/100cm2, lower than the limit of 24,00 dpm/100cm2 Conclusion: The use of rolling lead shields and implementation of specific radiation safety procedures allows for the safe administration of Iomab-B and enable treatment of patients without the need for lead-lined rooms. Table Disclosures Pandit-Taskar: Y Mabs: Consultancy, Honoraria; Fusion Pharmaceuticals: Consultancy, Honoraria; Progenics: Consultancy, Honoraria; Medimmune: Consultancy, Honoraria; Actinium Pharmaceuticals, Inc: Consultancy, Honoraria. Gyurkocza:Actinium Pharmaceuticals: Research Funding. Liang:Actinium Pharmaceuticals: Employment. Reddy:Actinium Pharmaceuticals: Employment. Berger:Actinium Pharmaceuticals, Inc: Employment, Equity Ownership. Dauer:Actinium Pharmaceuticals, Inc: Other: MSKCC - NIH/NCI Cancer Center Support Grant P30 CA008748, Research Funding.

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Moldashi, D. N. "Methods for identifying system tasks of strategic management and improving efficiency of exploration enterprise". Gornye nauki i tekhnologii = Mining Science and Technology (Russia) 5, n.º 3 (19 de outubro de 2020): 266–84. http://dx.doi.org/10.17073/2500-0632-2020-3-266-284.

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A geological exploration company is a modern enterprise, possessing advanced techniques and carrying out full range of high quality exploration for all types of solid minerals in accordance with world standards, which is the center of competence in uranium geology, as well as provides its services in the field of exploration for solid minerals. To date, the tasks of ensuring replenishment of explored mineral reserves, increasing efficiency of their use, as well as increasing profitability and capitalization of enterprises of mining-and-processing industry remains relevant. To implement a set of measures for solving problems associated with prospecting, exploration, and exploitation of uranium deposits, it is urgently required to develop the following improved approaches and methods: modernization and re-equipment of methodological and technical base of the enterprise’s chemical analytical laboratory for implementation mineralogical and radioisotope methods of prospecting for uranium deposits; carrying out work to expand the scope of accreditation, environmental research, and training of specialists for field laboratories; creation of an information system for geological data bank, which allows organizing a single information space and ensuring availability of the necessary reliable data, as well as their safety/integrity and the data access control. The conducted research formed the basis for the development of mechanisms for achieving strategic targets and implementing strategic objectives of the enterprise. To ensure sustainable growth of key performance indicators of the enterprise, it is necessary to focus on long-term successful work. This is connected with restructuring of assets and diversification of the company's activities, development of innovative methods and facilities for prospecting and laboratory-and-technological research, improvement of the set of radioecological studies at exploration areas, and introduction of the principles of corporate and legal culture. Providing growing demands of affiliated mining enterprises for mineable resources by replenishing the uranium resource base should be based on active prospecting, exploration, and discovery of new uranium deposits, as well as formation of highly efficient professional personnel. To improve management efficiency, the enterprise should activate and improve the quality of exploration, as well as diversify the company's activities and reduce possible risks. Implementation of this approach is possible through the formation of highly efficient professional personnel based on the recognition of high economic value of human resources. In addition, it is necessary to actively conduct exploration in promising areas for discovering new deposits and, correspondingly, increasing and replenishing the company's uranium reserves and increasing its assets. This will allow prolonging the life of the company’s mines until 2040 due to increasing additional explored reserves.

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Teses / dissertações sobre o assunto "Radioisotopes – Safety measures"

Turcanu, Catrinel. "Multi-criteria decision aiding model for the evaluation of agricultural countermeasures after an accidental release of radionuclides to the environment". Doctoral thesis, Universite Libre de Bruxelles, 2007. http://hdl.handle.net/2013/ULB-DIPOT:oai:dipot.ulb.ac.be:2013/210642.

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Multi-criteria decision aid has emerged from the operational research field as the answer given to a couple of important questions encountered in complex decisions problems. Firstly, as decision aiding tools, such methods do not replace the decision maker with a mathematical model, but support him to construct his solution by describing and evaluating his options. Secondly, instead of using a unique criterion capturing all aspects of the problem, in the multi-criteria decision aid methods one seeks to build multiple criteria, representing several points of view.

This work explores the application of multi-criteria decision aid methods for optimising food chain countermeasure strategies after a radioactive release to the environment.

The core of the thesis is dedicated to formulating general lines for the development of a multi-criteria decision aid model. This includes the definition of potential actions, construction of evaluation criteria and preference modelling and is essentially based on the results of a stakeholders’ process. The work is centred on the management of contaminated milk in order to provide a concrete focus and because of its importance as an ingestion pathway in short term after an accident.

Among other issues, the public acceptance of milk countermeasures as a key evaluation criterion is analysed in detail. A comparison of acceptance based on stochastic dominance is proposed and, based on that, a countermeasures’ acceptance ranking is deduced.

In order to assess “global preferences” taking into account all the evaluation criteria, an ordinal method is chosen. This method allows expressing the relative importance of criteria in a qualitative way instead of using, for instance, numerical weights. Some algorithms that can be used for robustness analysis are also proposed. This type of analysis is an alternative to sensitivity analysis in what concerns data uncertainty and imprecision and seeks to determine how and if a model result or conclusion obtained for a specific instance of a model’s parameters holds over the entire domain of acceptable values for these parameters.

The integrated multi-criteria decision aid approach proposed makes use of outranking and interactive methodologies and is implemented and tested through a number of case studies and prototype tools.
Doctorat en Sciences de l'ingénieur
info:eu-repo/semantics/nonPublished

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Bartolo, William Charles Francis Safety Science Faculty of Science UNSW. "Radioisotope laboratory safety auditing, compliance and associated problems in NSW". 2007. http://handle.unsw.edu.au/1959.4/40787.

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This thesis reports on the modification of the "Safecode" computer-program to monitor the safety of radio-isotope laboratories, and its application to 24 compliance audits in NSW during the period 1999 to 2006. Additionally, an attempt was made to predict the level of risk to persons working within those laboratories. Based on the current NSW radiation control legislation and the relevant Australian Standards a comprehensive audit checklist was developed for this project. Each safety requirement in those documents was used to develop a question, resulting in 187 questions in the checklist. The questions were grouped into the following seven Topic Elements: Licensing and Registration; Radiation Safety Administration; Personal and Area Monitoring; Dose Limit Compliance; Documentation/Records; RSO/RSC Qualifications and Duties; and Facilities. A novel feature was the allocation of "weighting factors" to individual questions and Elements. The computer program facilitated analysis of data and provided output in spreadsheet and graphical form. .The on-site physical audits were conducted using the project check-list, and were supplemented by discussions with the client's representative. The results showed significant variation between sites with overall compliance scores ranging from 37% to 94%. The reasons for this large variation stem from differences in local management regime; the appointment of an RSO at one site; variation in the extent of adoption of relevant codes of practice; and legislative weaknesses. Further analysis of the data presented legal, advisory and combined scores for each Element for each site; and variations over time. The graphic displays of the results were appreciated by client management. The formula developed to predict risk, based on the physical parameters alone, showed little relationship to the total audit scores. Statistical analysis of the two data groups by correlation coefficient confirmed this general finding. Development of the formula however served to indicate deficiencies in the Question Set, and the importance of human factors in achieving a high degree of safety.

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Livros sobre o assunto "Radioisotopes – Safety measures"

University of Prince Edward Island. Radiation safety manual. Charlottetown: University of Prince Edward Island, 1987.

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Seshiumu no ABC. Tōkyō-to Bunkyō-ku: Nihon Aisotōpu Kyōkai, 2014.

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Polʹskiĭ, O. G. Radioizotopnye pribory i mery bezopasnosti pri ikh ėkspluatat͡s︡ii. Moskva: Ėnergoatomizdat, 1996.

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Japan) Hōiken Kankyō Seminā (20th 1992 Chiba-shi. Kankyō to kōshū no anzen no tame no apurōchi: Hōshasei kakushu no seitaikei ikō, taisha, senryō suitei. Chiba-shi: Hōshasen Igaku Sōgō Kenkyūjo, 1993.

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Tahseen, Kazi, Bīrīrā Jūdīth e Monterey Institute of International Studies. Center for Nonproliferation Studies., eds. Commercial radioactive sources: Surveying the security risks. Monterey, Calif: Monterey Institute of International Studies, Center for Nonproliferation Studies, 2003.

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Iman, Ronald L. PARTITION, a program for defining the source term/consequence analysis interface in the NUREG-1150 probabilistic risk assessments: User's guide. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

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International Commission on Radiological Protection. Committee II on Permissible Dose for Internal Radiation. Age-dependent doses to members of the public from intake of radionuclides: Part 1. ; a report. Oxford: Published for the International Commission on Radiological Protection by Pergamon Press, 1990.

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International Commission on Radiological Protection. Lung cancer risk from indoor exposures to radon daughters: A report. Oxford: Pergamon for the International Commission on Radiological Protection, 1987.

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International Commission on Radiological Protection. Lung cancer risk from indoor exposures to radon daughters: A report. Oxford: Published for the Commission by Pergamon Press, 1987.

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Rōdōshō, Japan, e Japan, eds. Denri hōshasen shōgai bōshi kisoku no kaisetsu. 3^a ed. Tōkyō: Chūō Rōdō Saigai Bōshi Kyōkai, 2011.

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Trabalhos de conferências sobre o assunto "Radioisotopes – Safety measures"

Aggarwal, S., G. Charters e D. Thacker. "Characterization and Decontamination of Contaminated Structures Using a Profiling Technology". In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4974.

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Certain radioisotopes (tritium, radium, cobalt, plutonium, and cesium) can penetrate porous concrete and contaminate the concrete well below the easily measured surface. Certain radioisotopes can penetrate concrete and contaminate the concrete well below the surface. The challenge is to determine the extent of the contamination problem and the magnitude of the problem in a real-time. Currently, concrete core bores are shipped to certified laboratories where the concrete residue is run through a battery of tests to determine the contaminants. The existing core boring operation volatilizes some of the contaminants (like tritium) and oftentimes cross-contaminates the area around the core bore site. The volatilization of the contaminants can lead to airborne problems in the immediate vicinity of the core bore. Cross-contamination can increase the contamination area and thereby increase the amount of waste generated. The goal is to avoid those field activities that could cause this type of release. The concrete profiling technology, TRUPROSM in conjunction with portable radiometric instrumentation produces a profile of radiological or chemical contamination through the material being studied. The data quality, quantity, and representativeness may be used to produce an activity profile from the hot spot surface into the material being sampled. This activity profile may then be expanded to ultimately characterize the facility and expedite waste segregation and facility closure at a reduced cost and risk. Performing a volumetric concrete or metal characterization safer and faster (without lab intervention) is the objective of this characterization technology. This way of determining contamination can save considerable time and money.

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Pavelescu, Alexandru Octavian, Dan Gabriel Cepraga, Konstantina Voukelatou e Renato Tinti. "Estimation of Clearance Potential Index and Hazard Factors of CANDU Fuel Bundle and Its Validation Based on the Measurements of Radioisotopes Inventories From Pickering Reactor Fuel". In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7086.

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This paper is related to the clearance potential levels, ingestion and inhalation hazard factors of the spent nuclear fuel and radioactive wastes. This study required a complex activity that consisted of more steps such as: the acquisition, setting up, validation and application of procedures, codes and libraries. The paper reflects the validation stage of this study. Its objective was to compare the measured inventories of selected actinide and fission products radionuclides in an element from the Pickering CANDU reactor with the inventories predicted using a recent version of the SCALE 5\ORIGEN-ARP code coupled with the time dependent cross sections library for the CANDU 28 reactor (produced by the sequence SCALE4.4a\SAS2H and SCALE4.4a\ORIGEN-S). In this way, the procedures, the codes and the libraries for the characterization of radioactive material in terms of radioactive inventories, clearance, and biological hazard factors could be qualified and validated, in support of the safety management of the radioactive wastes.

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Sinzinger, H., H. Glogar, H. Weidinger, H. Sochor, H. Auinger, M. Weissel, P. Fitscha, H. Bergmann e Susanne Granegger. "PROSTAGLANDIN E1 REDUCES ENDOCARDIAL PLATELET DEPOSITION AND INCREASES LEFT VENTRICULAR EJECTION FRACTION (LVEF) IN PATIENTS WITH CARDIOMYOPATHY (CMP)". In XIth International Congress on Thrombosis and Haemostasis. Schattauer GmbH, 1987. http://dx.doi.org/10.1055/s-0038-1643952.

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It is well known, that patients suffering from CMP exhibit a significantly enhanced thromboembolic risk. Thus, we examined in these patients platelet function (f3TG, PF4, TXB2-serum and plasma) and kinetics after 111-In-oxine sulphate (100μCi) labelling. In a total of 67 patients (50o,17g; 29-66a with a LVEF of < 30%) the following findings have been obtained.During γ-camera imaging and by engymetric monitoring using a portable detector system (Novo Int. Danmark) CMP-patients show an enhanced platelet deposition over the heart. Platelet half-life (1: 100-115h) is extremely shortened (< 50hrs). Prostaglandin (PG) E1 (prostavasin; α1-cyclodextrin PGE1; Sanol-Schwarz GmbH, Monheim, FRG) administered i.v. in a dose range of 5-50 ng/kg/min causes a significant (p< 0,01) increase in LVEF of 20-95% dose-dependently as measured by means of radioisotope technique.Furthermore, a diminution in the local platelet uptake over the heart starting at the 2nd day of continuous PGE1-infusion can be monitored.It is hypothetized, that PGE1 renders the endocardium less thrombogenic and increases LVEF by vasodilatation and decreasing the afterload. As PGE1 is metabo-lically degraded to a major extent during the first lung passage, the data after i.v. application are at least suggestive, that more stable PGE1-derivatives may contribute to this effect.It is therefore concluded, that PGE1 in a safe dose of 25ng/kg/min may appear in the future as an optimal long-term therapeutic agent in CMP-patients offering the benefit of significantly enhanced LVEF and decreased platelet deposition, which should result in a decreased thromboembolic risk in these patients.

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