Relevant bibliographies by topics / Sealed radioactive sources

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  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Sealed radioactive sources'

Author: Grafiati
Published: 4 June 2021
Last updated: 1 February 2022

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Journal articles on the topic "Sealed radioactive sources"

1

KOMIYA, Masao, Osamu SUZUKI, Keiji KUSAMA, Akihiko MINEMURA, Toru YOSHIDA, Itsuro KUZE, Wataru MORIMITSU, and Nobuo OSHITA. "Classification tests of sealed radioactive sources." RADIOISOTOPES 34, no. 12 (1985): 692–96. http://dx.doi.org/10.3769/radioisotopes.34.12_692.

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SUZUKI, Osamu, Kenichi HAYASHI, Shigeo TAZAWA, Yoshihide NAKAMURA, Toshio KIMURA, Wataru MORIMITSU, and Nobuo OSHITA. "Classification tests of sealed radioactive sources." RADIOISOTOPES 37, no. 9 (1988): 529–34. http://dx.doi.org/10.3769/radioisotopes.37.9_529.

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Pryor, Kathryn H. "Radiation Safety of Sealed Radioactive Sources." Health Physics 108, no. 2 (February 2015): 172–77. http://dx.doi.org/10.1097/hp.0000000000000225.

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Siarafera, Tatiana, Eleni Ntalla, Dimitris Mavrikis, Angelos Markopoulos, Alexandra Ioannidou, and Anastasia Savvidou. "Development of techniques based on Monte Carlo simulations for clearance of Co-57 and Ge-68/Ga-68 sealed radioactive sources." HNPS Proceedings 26 (April 1, 2019): 194. http://dx.doi.org/10.12681/hnps.1819.

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Sealed radioactive sources of Co-57 and Ge-68/Ga-68 are used for the calibration of various nuclear medicine systems like Gamma camera and PET imaging. After their useful life, these sealed sources need to be kept in control for decay until meeting the general clearance criterion. The aim of this work is to determine the activity of spent sealed radioactive sources of Ge-68 / Ga-68 and Co-57. For this purpose, techniques based on Monte Carlo simulation by the use of the MCNPX code was developed for evaluation of the 3”x3” NaI(Tl) scintillator efficiency for specific source–detector geometries. These techniques proved to be accurate.
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Pryor, Kathryn H. "End of Life Decisions for Sealed Radioactive Sources." Health Physics 110, no. 2 (February 2016): 168–74. http://dx.doi.org/10.1097/hp.0000000000000398.

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Osmanlioglu, Ahmet Erdal. "MANAGEMENT OF SPENT SEALED RADIOACTIVE SOURCES IN TURKEY." Health Physics 91, no. 3 (September 2006): 258–62. http://dx.doi.org/10.1097/01.hp.0000214659.60964.bf.

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SUZUKI, Osamu, Masao KOMIYA, Katsunori TAKAHASHI, and Toshiaki HAGIWARA. "Classification Test of Sealed Radioactive Sources for 192Ir Afterloading." RADIOISOTOPES 43, no. 8 (1994): 483–86. http://dx.doi.org/10.3769/radioisotopes.43.8_483.

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Park, Young Jin, K. B. Lee, J. M. Lee, T. S. Park, and S. H. Hwang. "Measurements of sealed radioactive sources by using isothermal microcalorimetry." Journal of Radioanalytical and Nuclear Chemistry 316, no. 3 (May 4, 2018): 1195–203. http://dx.doi.org/10.1007/s10967-018-5886-1.

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Hasan, M. A., Y. T. Selim, Y. F. Lasheen, and T. El-Zakla. "Conditioning of disused Ra-226 radioactive sealed sources in Egypt." Radioprotection 49, no. 3 (July 2014): 213–20. http://dx.doi.org/10.1051/radiopro/2014011.

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Mohamed, Yasser T. "Quality assurance program for spent radioactive sealed sources in Egypt." Quality Assurance Journal 12, no. 2 (April 2009): 79–85. http://dx.doi.org/10.1002/qaj.444.

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Dissertations / Theses on the topic "Sealed radioactive sources"

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VICENTE, ROBERTO. "Gestao de fontes radioativas seladas descartadas." reponame:Repositório Institucional do IPEN, 2002. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11038.

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Tese (Doutoramento)
IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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FERREIRA, ROBSON de J. "Desenvolvimento de metodologia para a caracterizacao de fontes radioativas seladas." reponame:Repositório Institucional do IPEN, 2010. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9570.

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IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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3

Ferreira, Robson de Jesus. "Desenvolvimento de metodologia para a caracterização de fontes radioativas seladas." Universidade de São Paulo, 2010. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-29082011-153026/.

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Fontes radioativas seladas são largamente empregadas no mundo. A Agência Internacional de Energia Atômica AIEA estima em dezenas de milhões de fontes radioativas no mundo. No Brasil, este número é próximo de 500 mil unidades, considerando-se as fontes de pára-raios e detectores de fumaça. Uma fonte selada pode tornar-se desnecessária, seja devido ao seu decaimento ou outro motivo, sendo classificada como fontes radioativas seladas fora de uso (FRS). No Brasil, a maioria das FRS é considerada rejeito radioativo e são encaminhadas a um dos institutos da CNEN. Sem uma estratégia definida para a deposição das FRS, estas são armazenadas aguardando uma solução. A Gerência de Rejeitos Radioativos - GRR do IPEN-CNEN/SP é o principal centro de recepção desse material e até meados de 2010 havia recebido cerca de 14.000 fontes. O processo proposto para a gestão dessas FRS consiste em retirá-las de suas blindagens originais e transferi-las a outra blindagem, projetada para esse fim. As operações de transferência são realizadas em uma cela quente, garantindo a segurança radiológica. Uma das exigências da CNEN é que todas as fontes seladas sejam caracterizadas. No processo estudado, a avaliação da atividade de cada fonte será feita utilizando-se um detector, do tipo câmara de ionização tipo poço. O presente trabalho tem por objetivo desenvolver uma metodologia para aferir ou determinar a atividade de FRS armazenadas na GRR de acordo com sua geometria e determinar suas incertezas.
Sealed radioactive sources are widely used in many applications of nuclear technology in industry, medicine, research and others. The International Atomic Energy Agency (IAEA) estimates tens of millions sources in the world. In Brazil, the number is about 500 thousand sources, if the Americium-241 sources present in radioactive lightning rods and smoke detectors are included in the inventory. At the end of the useful life, most sources become disused, constitute a radioactive waste, and are then termed spent sealed radioactive sources (SSRS). In Brazil, this waste is collected by the research institutes of the Nuclear Commission of Nuclear Energy and kept under centralized storage, awaiting definition of the final disposal route. The Waste Management Laboratory (WML) at the Nuclear and Energy Research Institute is the main storage center, having received until July 2010 about 14.000 disused sources, not including the tens of thousands of lightning rod and smoke detector sources. A program is underway in the WML to replacing the original shielding by a standard disposal package and to determining the radioisotope content and activity of each one. The identification of the radionuclides and the measurement of activities will be carried out with a well type ionization chamber. This work aims to develop a methodology for measuring or to determine the activity SSRS stored in the WML accordance with its geometry and determine their uncertainties.
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Gauglitz, Érica. "Estudo e levantamento de parâmetros para montagem de um laboratório de produção de fontes radioativas utilizadas na verificação de equipamentos." Universidade de São Paulo, 2010. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-08082011-143953/.

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Este trabalho apresenta o levantamento de parâmetros para implementação adequada e segura de pisos, portas, janelas, bancadas, capelas entre outros, de um laboratório radioquímico. A disposição de cada item segue orientações de guias, normas nacionais da Comissão Nacional de Energia Nuclear (CNEN) e internacional da Agencia Internacional de Energia Atômica (IAEA), com objetivo de garantir a proteção radiológica do trabalhador e do ambiente. A disposição adequada dos itens do laboratório radioquímico, garante a qualidade e segurança na produção de fontes radioativas seladas de 57Co 137Cs e 133Ba com atividades 185, 9.3 e 5.4 MBq respectivamente. Estas fontes são utilizadas na verificação de medidores de atividade, equipamento que todo Centro de Medicina Nuclear deve ter disponível segundo recomendações da norma CNEN-NN-3.05 Requisitos de Radioproteção e Segurança para Serviços de Medicina Nuclear para verificação da atividade de radiofármacos que serão administrados nos pacientes para fins de diagnóstico e terapia. Um medidor de atividade fora adquirido pelo laboratório de produção de fontes, com o qual foram realizados os testes de precisão, exatidão, reprodutibilidade e linearidade, que devem apresentar resultados dentro dos limites estabelecidos na norma CNEN-NN-3.05.
This paper presents a survey of parameters for the proper and safe flooring, doors, windows, fume hoods and others, in a radiochemical laboratory. The layout of each item follows guidelines and national standards of the National Commission of Nuclear Energy (CNEN) and the International Atomic Energy Agency (IAEA), aiming to ensure the radiological protection of workers and environment. The adequate items arrangement in the radiochemical laboratory ensures quality and safety in the production of 57Co 137Cs and 133Ba radioactive sealed sources, with activities 185, 9.3 and 5.4 MBq, respectively. These sources are used to verify meter activity equipment and should be available throughout the Nuclear Medicine Center, following the recommendations of CNEN-NN-3.05 standard \"Requirements for Radiation Protection and Safety Services for Nuclear Medicine\", to verify the activity of radiopharmaceuticals that are administered in patients, for diagnosis and therapy.
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FERREIRA, EDUARDO G. A. "Avaliação da alteração nas propriedades da pasta de cimento em ambiente de repositório." reponame:Repositório Institucional do IPEN, 2013. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10208.

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Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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6

Tiezzi, Rodrigo. "Desenvolvimento de fontes radioativas seladas imobilizadas em resina epóxi para verificação de detectores utilizados em Medicina Nuclear." Universidade de São Paulo, 2016. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-07032016-140958/.

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As fontes radioativas seladas são usadas na verificação de detectores de câmara de ionização, os quais medem a atividade dos radioisótopos usados nas mais diversas áreas, como na Medicina Nuclear. A medida da atividade dos radioisótopos deve ser feita com exatidão, pois será administrada em um paciente. Para garantir o adequado funcionamento dos detectores de câmara de ionização, são estipulados ensaios normatizados pela Agência Internacional de Energia Atômica (IAEA) e a Comissão Nacional de Energia Nuclear (CNEN) utilizando-se fontes radioativas seladas de Bário-133, Césio-137 e Cobalto-57. Os testes avaliam a exatidão, precisão, reprodutibilidade e linearidade da resposta do equipamento. O foco deste trabalho foi o estudo e o desenvolvimento dessas fontes radioativas padrão de Bário-133, Césio-137 e Cobalto-57, utilizando um polímero, no caso resina epóxi comerciais do tipo éter diglicidílico do bisfenol A e um agente de cura a base de poliamina modificada da dietilenotriamina ,para imobilizar o material radioativo. A matriz polimérica apresenta a função primordial de fixar e imobilizar o conteúdo radioativo não permitindo seu vazamento dentro dos limites técnicos exigidos pelas normas de proteção radiológica no quesito de características de uma fonte selada e, adicionalmente, ter a capacidade de reter a emanação de quaisquer gases que venham a se formar durante o processo de fabricação e do período de vida útil deste artefato. O processo de manufatura de uma fonte selada padrão consiste no envasamento, em um frasco de geometria padronizada, de uma quantidade, em volume fixo, de uma matriz polimérica no interior da qual é adicionada e dispersada homogeneamente uma quantidade precisa e exata em atividade de um material radioativo padrão. Nesse sentido, realizou-se um estudo para a escolha da resina epóxi, analisando suas características e propriedades. Foram realizados estudos e testes, verificando a máxima miscibilidade da resina com a água (solução ácida, simulando as condições da solução radiativa), perdas de propriedades mecânicas e térmicas, bem como o controle de dose radioativa para a completa cura (irradiadores de cobalto).Foram produzidas fontes de césio-137 e bário-133, realizou-se testes para determinação do grau de homogeneidade na dispersão do material radioativo na matriz e testes de imersão das fontes seladas produzidas para verificar a estanqueidade do sistema desenvolvido, obtendo um resultado satisfatório de acordo com as normas. Analisando todos os resultados obtidos, as fontes seladas podem ser confeccionadas em matriz epóxi DGEBA e endurecedor poliamínico DETA modificado, desde que a quantidade de material radioativo, na forma de solução ácida, adicionado à composição não ultrapasse um teor de 20%. A cura da resina epóxi pode ser melhorada em relação a ambiente, com uso da irradiação desde que seja exposta a uma dose ao redor de 33 kGy durante a cura. Nos testes de estanqueidade, verificou-se que as fontes são estanques, as medições da atividade da água utilizada nos testes mostraram um valor inferior a 185 Bq (de acordo com a International Standard Organization- Radiation protection sealed radioactive sources - ISO 9978), comprovando a eficiência da resina epóxi como material para selar o material radioativo. Tendo a finalidade de criar uma tecnologia nacional capaz de suprir a demanda deste produto no mercado interno e atingir excelência em qualidade através da acreditação e certificação do produto junto aos órgãos competentes.
The radioactive sealed sources are used in verification ionization chamber detectors, which measure the activity of radioisotopes used in several areas, such as in nuclear medicine. The measurement of the activity of radioisotopes must be made with accuracy, because it is administered to a patient. To ensure the proper functioning of the ionization chamber detectors, standardized tests are set by the International Atomic Energy Agency (IAEA) and the National Nuclear Energy Commission using sealed radioactive sources of Barium-133, Cesium-137 and Cobalt-57. The tests assess the accuracy, precision, reproducibility and linearity of response of the equipment. The focus of this work was the study and the development of these radioactive sources with standard Barium-133 and Cesium-137, using a polymer, in case commercial epoxy resin of diglycidyl ether of bisphenol A (DGEBA) and a curing agent based on modified polyamine diethylenetriamine (DETA), to immobilize the radioactive material. The polymeric matrix has the main function of fix and immobilize the radioactive contents not allowing them to leak within the technical limits required by the standards of radiological protection in the category of characteristics of a sealed source and additionally have the ability to retain the emanation of any gases that may be formed during the manufacture process and the useful life of this artifact. The manufacturing process of a sealed source standard consists of the potting ,into bottle standardized geometry, in fixed volume of a quantity of a polymeric matrix within which is added and dispersed homogeneously to need and exact amount in activity of the radioactive materials standards. Accordingly, a study was conducted for the choice of epoxy resin, analyzing its characteristics and properties. Studies and tests were performed, examining the maximum miscibility of the resin with the water (acidic solution, simulating the conditions of radioactive solution), loss of mechanical and thermal properties, as well as the radioactive dose control for complete curing (cobalt irradiators). For this work was produced a sources of barium-133 and cesium -137,tests were conducted to determination the degree of homogeneity in the dispersion of the radioactive material in the matrix and immersion tests of sealed sources produced to verify the leakage (ISO 9978) of the developed system, occurring obtaining a satisfactory result. With the purpose of creating a national technology able to meet the demand of this product in the domestic market and achieve excellence in quality through accreditation and certification of the product by the appropriate bodies.
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FERREIRA, EDUARDO G. A. "Modelagem descritiva do comportamento do cimento Portland em ambiente de repositório para rejeitos radioativos." reponame:Repositório Institucional do IPEN, 2017. http://repositorio.ipen.br:8080/xmlui/handle/123456789/28423.

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A deposição de rejeitos radioativos em repositórios geológicos profundos vem sendo estudada nos últimos anos em diversos países. Materiais à base de cimento são utilizados nesses repositórios como material estrutural, matriz de imobilização de rejeitos ou material de preenchimento. Compreender o desempenho desse material é essencial para garantir a segurança da instalação durante o seu tempo de vida útil (de milhares a centenas de milhares de anos, dependendo do tipo de rejeito). Este trabalho objetiva modelar o comportamento em longo prazo do cimento Portland e estudar a influência de diversos fatores na hidratação e na evolução desse material. A modelagem descritiva abordou a hidratação do cimento nas condições ambientais esperadas no repositório e os efeitos desses fatores em propriedades mecânicas, mineralógicas e morfológicas do cimento. Os fatores ambientais considerados relevantes neste trabalho foram: alta temperatura e pressão, penetração de água subterrânea contendo íons quimicamente agressivos ao cimento e a presença do campo de radiação proveniente dos rejeitos. Ensaios acelerados de degradação também foram realizados para corroborar com o modelo descrito. Observou-se uma sinergia entre diversos fatores na degradação do cimento, como a influência da temperatura e da radiação em reações deletérias ao material. O resultado da modelagem apontou três principais possíveis causas de falha nas barreiras artificiais: a) a formação de um caminho preferencial; b) a perda de resistência e coesão do material; e c) o aumento na corrosão das estruturas metálicas. A descrição do modelo apresentada é a base para a modelagem matemática e a análise de segurança dos repositórios estudados no Brasil.
Tese (Doutorado em Tecnologia Nuclear)
IPEN/T
Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP
CAPES:1231206
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Benega, Marcos Antonio Gimenes. "Estudo e desenvolvimento de fonte de fósforo-32 imobilizado em matriz polimérica para tratamento de câncer paravertebral e intracranial." Universidade de São Paulo, 2015. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-01042015-141830/.

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As últimas estimativas da Organização Mundial da Saúde mostram a ocorrência de 14,1 milhões de novos casos de câncer em 2012. Sendo que desses casos, 8,2 milhões virão a óbito. Os tumores paravertebrais e intracraniais, também chamados de cânceres do Sistema Nervoso Central, tem origem no cérebro, nervos cranianos e meninges. Uma nova modalidade de braquiterapia começou a ser usada nesta última década. Neste procedimento, placas poliméricas flexíveis, carregando fósforo-32, são colocadas próximas ou em contato ao tumor para o tratamento. Este tratamento apresenta vantagens em relação aos demais porque aplica uma alta taxa de dose no tumor poupando tecidos sadios. A produção destas placas ainda é pouco estudada, embora já existam resultados satisfatórios no seu uso para o tratamento dos cânceres do sistema nervoso central. Neste trabalho foram realizados estudos iniciais para a produção deste tipo de placas poliméricas para braquiterapia. Foram avaliadas as propriedades mecânicas e a capacidade de imobilização de material radioativo de duas resinas comercias, uma poliuretânica e outra epoxídica, com e sem presença de substrato de policarbonato. Os testes iniciais apontaram o uso da resina epoxídica como melhor alternativa e com o uso dela foram feitos os primeiros protótipos e testes. O uso do policarbonato como substrato não foi necessário em uma das metodologias, facilitando o procedimento, mas oferecendo uma barreira menor de segurança. Os ensaios de tração mostraram que a adição de solução ácida à resina epóxi alterou suas características mecânicas, mas houve uma pequena melhora em sua flexibilidade. Os testes de adesão evidenciaram uma melhor adesão da resina à face texturizada do policarbonato. A termogravimetria mostrou que a solução ácida adicionada a resina fica presa à estrutura mesmo com elevações de temperatura acima de 100°C. A resina epoxídica utilizada teve a capacidade de incorporar o material radioativo em forma de solução ácida e manter-se estanque após testes de esfregaço e imersão em líquido quente. De acordo com os resultados obtidos, a produção destas placas com resina epoxídica é possível e atende às normas internacionais de segurança contra vazamento de material radioativo para fontes utilizadas em braquiterapia.
The latest estimates of the World Health Organization show the occurrence of 14.1 million new cases of cancer in 2012. From these cases, 8.2 million will come to death. The paraspinal and intracranial tumors, also called central nervous system cancers, are originated in the brain, cranial nerves and meninges. A new brachytherapy modality began to be used in the last decade. In this procedure, flexible, polymeric plaques carrying phosphorus-32 are placed in contact or close to the tumor for treatment. This treatment has advantages over others because it applies a high dose rate in the tumor sparing healthy tissues. The production of these plaques is not well known, although there are satisfactory results in its use for the treatment of central nervous system cancers. This work carried out initial studies for the production of this type of polymer plaques for brachytherapy. The mechanical properties and immobilization capacity of radioactive material, from two commercial resins, epoxy and polyurethane, with or without the presence of polycarbonate as substrate were evaluated. Initial tests showed the use epoxy resin as the best alternative and the first prototypes and tests with use of it were made. The use of polycarbonate as a substrate was not required on one of the methodologies, facilitating the procedure but offering a lower security barrier. The tensile tests showed that addition of acid to the epoxy resin solution changed its mechanical properties, but there was a small improvement in flexibility. Adhesion tests showed better adhesion of the resin to the textured surface of the polycarbonate. The thermogravimetric analysis showed that the acid solution added to the resin structure is sealed even with temperature rises above 100°C. The epoxy resin used has the ability to incorporate the radioactive material in the form of acid solution and remain tight after wiping and immersion in hot liquid tests. According to the results, the production of these plaques with epoxy resin is possible and meets international safety standards for leakage of radioactive material in radioactive sources used in brachytherapy.
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MATĚJKA, Václav. "Vysokoaktivní zářiče ionizujícího záření - "HASS"." Master's thesis, 2013. http://www.nusl.cz/ntk/nusl-154734.

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The thesis is generally focused on summarization of the information related to the high activity sealed sources of ionizing radiation, known as HASS, which are widely used in a variety of sectors in whole world and the Czech Republic as well. The thesis discusses specific cases of actual use of HASS, technical specification, types of occurring radionuclides and examples of use. The biological effects of ionizing radiation on humans related to HASS and some examples of specific adverse events are also described. In the intentions of this thesis is to take into account not only risks arising from incorrect manipulation, but also risks associated with potentially abuse of HASS by terrorist organization. For these reasons, the thesis outlines the basic security requirements associated to the international standards and also mentioned in legislation of CR. In connection with these requirements the suggestion of particular security system on specific workplaces with HASS is than discussed. To supplement the reader's imagination of the real problems of HASS in the Czech Republic, there is created a statistical overview of all HASS located in the Czech Republic. This includes the total number of HASS and the largest area of use devided into various areas of application (medicine, industry, research/education, etc.), representation of most commonly used radionuclides, the geographical distribution of HASS in the Czech Republic and the distribution in terms of the most common activities. The State Office for Nuclear Safety Registry was used as a source for this statistical overview. In the discussion part of the thesis, the real possibility of abuse of HASS and also a possible ways of gain from the perspective of a potential lone striker or a wider terrorist organization is discussed. In general, the following thesis is a logical synthesis of relevant information allowing the reader to obtain a relatively comprehensive view on the whole issue of HASS, especially from the perspective of the broader field of radiation protection emphasized on achieving a socially acceptable security level of all high activity sources of ionizing radiation.
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Books on the topic "Sealed radioactive sources"

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M, Fenton D. An inventory of disused sealed radioactive sources in Ireland. Dublin: Radiological Protection Institute of Ireland, 1994.

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Administration of Radioactive Substances Advisory Committee. Notes for guidance on the clinical administration of radiopharmaceuticals and use of sealed radioactive sources. Didcot: National Radiological Protection Board for the Administration of Radioactive Substances Advisory Committee, 1998.

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Office, United States Government Accountability. Nuclear security: DOE needs better information to guide its expanded recovery of sealed radiological sources : report to the Chairman, Committee on Energy and Natural Resources, U.S. Senate. Washington, D.C.]: U.S. Government Accountability Office, 2005.

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4

Office, General Accounting. Nuclear nonproliferation: DOE action needed to ensure continued recovery of unwanted sealed radioactive sources : report to the ranking minority member, Subcommittee on Financial Management, the Budget, and International Security, Committee on Governmental Affairs, U.S. Senate. Washington, D.C. (P.O. Box 37050, Washington, D.C. 20013): U.S. General Accounting Office, 2003.

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Office, General Accounting. Nuclear security: Federal and state action needed to improve security of sealed radioactive sources : report to the Ranking Minority Member, Subcommittee on Financial Management, the Budget, and International Security, Committee on Governmental Affairs, U.S. Senate. Washington, D.C. (P.O. Box 37050, Washington 20013): U.S. General Accounting Office, 2003.

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Jankovich, J. Consolidated guidance about materials licenses: Applications for sealed source and device evaluation and registration : final report. Washington, DC: United States Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, 2015.

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Safety of Radiation Generators and Sealed Radioactive Sources (Safety Standards). Intl Atomic Energy Agency, 2006.

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Agency, International Atomic Energy, ed. Safety of radiation generators and sealed radioactive sources: Safety guide. Vienna: International Atomic Energy Agency, 2006.

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Management Of Disued Long Lived Sealed Radioactive Sources Llsrs (Iaea Tecdoc Series). International Atomic Energy Agency, 2003.

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U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., ed. Draft regulatory guide DG-0008 (previous draft was FC 407-4): Applications for the use of sealed sources in portable gauging devices. [Washington, D.C.]: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1995.

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Book chapters on the topic "Sealed radioactive sources"

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Jovanovic, Slobodan V., Ike Dimayuga, Nadereh St-Amant, and Raphael Galea. "Sealed Radioactive Sources." In Non-Proliferation Nuclear Forensics, 47–51. ASME Press, 2020. http://dx.doi.org/10.1115/1.862032_ch4.

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Hack, Klaus, Dieter Neuschütz, and Jürgen Korb. "Nuclide distribution between steelmaking phases upon melting of sealed radioactive sources hidden in scrap." In The SGTE Casebook. CRC Press, 2008. http://dx.doi.org/10.1201/9781439832516.ch12b.

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HACK, KLAUS, JÜRGEN KORB, and DIETER NEUSCHÜTZ. "Nuclide distribution between steelmaking phases upon melting of sealed radioactive sources hidden in scrap." In The SGTE Casebook, 178–87. Elsevier, 2008. http://dx.doi.org/10.1533/9781845693954.2.178.

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Conference papers on the topic "Sealed radioactive sources"

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Stefanova, Ira G. "Disposal of Spent Sealed Sources." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4972.

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Novi Han Repository is the only existing repository in Bulgaria for the disposal of radioactive waste from nuclear applications in industry, medicine and research. The disposal vault for spent sealed sources is not designed for disposal of powerful 137Cs and 60Co sources. Long-lived waste from nuclear applications are also not allowed for disposal at Novi Han Repository. As an operator of Novi Han Repository the Institute for Nuclear Research and Nuclear Energy initiated a program, for assessment of the possible utilization of deep shaft Gabra for disposal of such waste. The results of the preliminary study are discussed.
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Wang Wei and Yuan Kui. "Teleoperated manipulator for leak detection of sealed radioactive sources." In IEEE International Conference on Robotics and Automation, 2004. Proceedings. ICRA '04. 2004. IEEE, 2004. http://dx.doi.org/10.1109/robot.2004.1308066.

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Abeyta, Cristy, Jim Matzke, John Zarling, and J. Andrew Tompkins. "Problems With Packaged Sources in Foreign Countries." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40266.

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The Global Threat Reduction Initiative’s (GTRI) Off-Site Source Recovery Project (OSRP), which is administered by the Los Alamos National Laboratory (LANL), removes excess, unwanted, abandoned, or orphan radioactive sealed sources that pose a potential threat to national security, public health, and safety. In total, GTRI/OSRP has been able to recover more than 25,000 excess and unwanted sealed sources from over 825 sites. In addition to transuranic sources, the GTRI/OSRP mission now includes recovery of beta/gamma emitting sources, which are of concern to both the U.S. government and the International Atomic Energy Agency (IAEA). This paper provides a synopsis of cooperative efforts in foreign countries to remove excess and unwanted sealed sources by discussing three topical areas: 1) The Regional Partnership with the International Atomic Energy Agency; 2) Challenges in repatriating sealed sources; and 3) Options for repatriating sealed sources.
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Heard, R. G. "The Ultimate Solution: Disposal of Disused Sealed Radioactive Sources (DSRS)." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40029.

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The borehole disposal concept (BDC) was first presented to ICEM by Potier, J-M in 2005 [1]. This paper repeats the basics introduced by Potier and relates further developments. It also documents the history of the development of the BDC. For countries with no access to existing or planned geological disposal facilities for radioactive wastes, the only options for managing high activity or long-lived disused radioactive sources are to store them indefinitely, return them to the supplier or find an alternative method of disposal. Disused sealed radioactive sources (DSRS) pose an unacceptable radiological and security risk if not properly managed. Out of control sources have already led to many high-profile incidents or accidents. One needs only to remember the recent accident in India that occurred earlier this year. Countries without solutions in place need to consider the future management of DSRSs urgently. An on-going problem in developing countries is what to do with sources that cannot be returned to the suppliers, sources for which there is no further use, sources that have not been maintained in a working condition and sources that are no longer suitable for their intended purpose. Disposal in boreholes is intended to be simple and effective, meeting the same high standards of long-term radiological safety as any other type of radioactive waste disposal. It is believed that the BDC can be readily deployed with simple, cost-effective technologies. These are appropriate both to the relatively small amounts and activities of the wastes and the resources that can realistically be found in developing countries. The South African Nuclear Energy Corporation Ltd (Necsa) has carried out project development and demonstration activities since 1996. The project looked into the technical feasibility, safety and economic viability of BDC under the social, economic, environmental and infrastructural conditions currently prevalent in Africa. Implementation is near at hand with work being done in Ghana with support from the IAEA. Here the site selection is complete and studies are being carried out to test the site parameters for inclusion into the safety assessment.
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van Velzen, Leo, and Steven van der Marck. "Detection of Shielded Sealed Radioactive Sources in Radioactive Waste by Non-Destructive Assay Techniques." In ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59252.

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Experiences dealing are seldom reported on the detection of sealed radioactive sources (SRS) or its shielding in waste by non-destructive assay (NDA) methods in literature. Further the knowledge and experience in this field of waste characterization will vary from specialist till basic. The main aim of this paper is to give some guidance with the aid of an overview or scheme with which the possibility can be assessed of the detection and of a shielded SRS in (historic) waste packages. This aim could be reached by simulating the gamma flux emitted by a SRS at the outline of a standard 220 litres drum. The simulations have been performed with the Monte Carlo Neutron Photon transport code (MCNP). The results, visualized by means of iso-plots, are then be used for assessing the detection probability of the SRS by available NDA techniques. The following conclusions could be made: • “Heavy and dens” objects (e.g. shielded sealed radioactive source) can be detected and an indication of its location can be obtained by a sudden significant decrease of the gamma photon flux (cold-spot) at the outline of the drum. This cold-spot is caused by the “heavy or dens” object itself. A cold-spot can be detected the best by analyzing and visualizing the gamma photon flux from the backscatter area (e.g. range 100 keV up to 200 keV) and second best by analyzing the total gamma flux. • With relative simple radiological equipment (e.g. dose rate meter) the possible presence and an indication of the location of a shielded SRS can be estimated. • The detection possibility of detecting a shielded SRS depends not only on the applied NDA technique, but also on the applied effort (e.g. number of measurements, measuring time, applied measurement grid), the properties of the waste packages (e.g. density of the waste matrix and uniformity of the inside dispersed radioactivity), the location and the properties of the shielding of the SRS (e.g. geometry). • For confirmation and the determining of the exact location advanced NDA techniques (e.g. transmission computer tomography or other NDA that techniques gives three dimensional results) have to be applied.
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De pooter, Vincent, David Vanleeuw, Gunter Van Zaelen, and Marnix Braeckeveldt. "Strategy and Practice in Spent Sealed Sources Management in Belgium." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16335.

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Radioactive sources are used for a variety of purposes, e.g. in medical treatment and diagnosis, research applications, measurement, testing, detection and calibration in industry, educational activities in colleges and universities etc. As part of its mission, ONDRAF/NIRAS, the Belgian Radioactive Waste Management Agency, draws up an inventory of all radioactive substances and nuclear installations on the Belgian territory. In recent years this inventory has been used to launch specific campaigns for the collection of different types of radioactive sources. In addition to this, the Royal Decree of 23 May 2006 concerning the transposition into Belgian law of the Spent High Activity Sealed Sources and the Management of Orphan Sources Directive of the EU (2003/122/EURATOM) has led to an increase in the number of requests addressed to ONDRAF/NIRAS for the collection of these types of radioactive waste and to an intensified collaboration between ONDRAF/NIRAS and the Belgian Safety Authority FANC/AFCN towards an effective management of orphan sources. Specific properties of these spent sources such as their activity, external dose rate, weight, size and/or their invalid special form certificate may complicate the transport and final treatment and conditioning of this type of waste and that is why these operations require careful attention. An overview of the radioactive sources already collected as radioactive waste or still present in the nuclear installations, different cases and problems encountered are presented in this paper, as well as the waste management options adopted by ONDRAF/NIRAS to deal with this type of waste.
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Heard, R. G. "International Initiatives Addressing the Safety and Security of Disused Sealed Radioactive Sources (DSRS)." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40028.

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High activity radioactive sources provide great benefit to humanity through their utilization in agriculture, industry, medicine, research and education, and the vast majority are used in well-controlled environments. None-the-less, control has been lost over a small fraction of those sources resulting in accidents of which some had serious — even fatal — consequences. Indeed, accidents and incidents involving radioactive sources indicate that the existing regime for the control of sources needs improvement. Additionally, today’s global security environment requires more determined efforts to properly control radioactive sources. Consequently, the current regimes must be strengthened in order to ensure control over sources that are outside of regulatory control (orphan sources), as well as for sources that are vulnerable to loss, misuse, theft, or malicious use. Besides improving the existing situation, appropriate norms and standards at the national and international levels must continue to be developed to ensure the long-term sustainability of control over radioactive sources. In order to improve the existing situation, concerted national and international efforts are needed and, to some degree, are being implemented to strengthen the safety and security of sources in use, as well as to improve the control of disused sources located at numerous facilities throughout the world. More efforts must also be made to identify, recover, and bring into control orphan sources. The IAEA works closely with Member States to improve the safety and security of radioactive sources worldwide. Besides the IAEA Technical Assistance Programme and Technical Cooperation Fund, donor States provide significant financial contributions to the Nuclear Security Fund and/or direct technical support to other States to recover condition and transfer disused sources into safe and secure storage facilities and to upgrade the physical protection of sources that are in use. Under the USA-Russian Federation-IAEA (“Tripartite”) Initiative, for example, disused sources of a total activity of 2120 TBq (57251 Ci) were recovered and transported into safe and secure storage facilities in six countries of the former Soviet Union. Additionally, physical protection upgrades were performed in thirteen former Soviet Union republics at facilities using or storing high activity radioactive sources. Other donors have also provided funding for projects related to the safety and security of radioactive sources in the same region. Additionally, the EU and other countries are making regular and significant contributions to the IAEA for projects aimed at upgrading the safety and security of radioactive sources in South-Eastern Europe, the Middle East, Asia and Africa. Depending on the status of the radioactive source (in use, disused, or orphan) and the actual technical, safety and security situation, several options exist to ensure the source is properly brought or maintained under control. This paper will describe those options and the systematic approach followed by the IAEA in deciding on the most appropriate actions to take for the high activity sources that need to be recovered or removed from the countries under that request assistance.
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Assi, Muzna. "Radioactive Waste Management in Lebanon." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40058.

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The disused sealed radioactive sources including orphan sources in Lebanon, along with the growing industry of sealed radioactive sources in medical, industrial and research fields have posed a serious problem for authorities as well as users due to the lack of a national store for disused radioactive sources. Assistance from the International Atomic Energy Agency (IAEA) was requested to condition and store disused radium needles and tubes present at two facilities. The mission took place on July 25, 2001 and was organized by the IAEA in cooperation with the Lebanese Atomic Energy Commission (LAEC). Other disused radioactive sources were kept in the facilities till a safer and securer solution is provided; however orphan sources, found mainly during export control, were brought and stored temporarily in LAEC. The necessity of a safe and secure store became a must. Prior to October 2005, there was no clear legal basis for establishing such store for disused radioactive sources, until the ministerial decree no 15512 dated October 19, 2005 (related to the implementation of decree-law no 105/83) was issued which clearly stated that “The LAEC shall, in cooperation with the Ministry of Public Health, establish a practical mechanism for safe disposal of radioactive waste”. Following this, the work on inventory of disused sealed sources along with collecting orphan sources and placing them temporarily in LAEC was legally supported. Moreover, several missions were planned to repatriate category I and II sources, one of which was completed specifically in August 2009; other missions are being worked on. In 2008, a national technical cooperation project with the IAEA was launched. Under the Technical Cooperation (TC) project with reference number LEB3002, the project was entitled “Assistance in the establishment of a safe temporary national storage at the LAECfor orphan sources and radioactive waste” which cycle is 2009–2011. Under this project, a national store for radioactive sources in the third basement of LAEC is being established. The area is being reconstructed currently and will be equipped when ready under LEB3002 project. Along with this, a system for sealed disused sources management has been prepared, part of which is applied now and the rest will be applied upon the establishment of the store. This paper will cover the inventory collection process, the study for the establishment of this store, the present and prospective waste management system, and the waste acceptance criteria.
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Braeckeveldt, Marnix, Peter De Preter, Jan Michiels, Ste´phane Pepin, Manfred Schrauben, and An Wertelaers. "The Belgian Approach and Status on the Radiological Surveillance of Radioactive Substances in Metal Scrap and Non-Radioactive Waste and the Financing of Orphan Sources." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7096.

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Numerous facilities in the non-nuclear sector in Belgium (e.g. in the non-radioactive waste processing and management sector and in the metal recycling sector) have been equipped with measuring ports for detecting radioactive substances. These measuring ports prevent radioactive sources or radioactive contamination from ending up in the material fluxes treated by the sectors concerned. They thus play an important part in the protection of the workers and the people living in the neighbourhood of the facilities, as well as in the protection of the population and the environment in general. In 2006, Belgium’s federal nuclear control agency (FANC/AFCN) drew up guidelines for the operators of non-nuclear facilities with a measuring port for detecting radioactive substances. These guidelines describe the steps to be followed by the operators when the port’s alarm goes off. Following the publication of the European guideline 2003/122/Euratom of 22 December 2003 on the control of high-activity sealed radioactive sources and orphan sources, a procedure has been drawn up by FANC/AFCN and ONDRAF/NIRAS, the Belgian National Agency for Radioactive Waste and Enriched Fissile Materials, to identify the responsible to cover the costs relating to the further management of detected sealed sources and if not found to declare the sealed source as an orphan source. In this latter case and from mid-2006 the insolvency fund managed by ONDRAF/NIRAS covers the cost of radioactive waste management. At the request of the Belgian government, a financing proposal for the management of unsealed orphan sources as radioactive waste was also established by FANC/AFCN and ONDRAF/NIRAS. This proposal applies the same approach as for sealed sources and thus the financing of unsealed orphan sources will also be covered by the insolvency fund.
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Poskas, P., J. E. Adomaitis, and R. Kilda. "Management of Institutional Radioactive Waste in Lithuania." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4877.

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The growing number of radionuclide applications in Lithuania is mirrored by increasing demands for efficient management of the associated radioactive waste. For the effective control of radioactive sources a national authorization system based on the international requirements and recommendations was introduced, which also includes keeping and maintaining the State Register of Sources of lonising Radiation and Occupational Exposure. The principal aim of the Lithuania’s Radioactive Waste Management Agency is to manage and dispose all radioactive waste transferred to it. Radioactive waste generated during the use of sources in non-power applications are managed according to the basic radioactive waste management principles and requirements set out in the Lithuanian legislation and regulations. The spent sealed sources and other institutional waste are transported to the storage facilities at Ignalina NPP. About 35,000 spent sealed sources in about 500 packages are expected until year 2010 at Ignalina NPP storage facilities. The existing disposal facility for radioactive waste from research, medicine and industry at Maisiagala was built in the early 1960’s according to a concept typical of those applied in the former Soviet Union at that time. SKB (Sweden) with participation of Lithuanian Energy Institute has performed assessment of the long-term safety of the existing facility. It was shown that the existing facility does not provide safe long-term storage of the waste already disposed in the facility. Two alternatives were defined to remedy the situation. A first alternative is the construction of a surface barrier and a second one is a retrieval solution, whereby the already stored waste will be retrieved for conditioning, characterisation and interim storage at Ignalina NPP. Facilities for the processing of the institutional radioactive waste are required before submittal to Ignalina NPP for storage, since the present facilities are inadequate. Feasibility study to establish a new central facility has been performed by SKB International Consultants (Sweden) with participation of Lithuanian Energy Institute. This study has identified the process applied and equipment needed for a new facility. Reference design and Preliminary Safety Assessment have also been performed. Plans for the interim storage and disposal of the institutional waste are described in the paper. The aspects of finging safe disposal solutions for spent sealed sources in a near surface repositories are also discussed.
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Reports on the topic "Sealed radioactive sources"

1

Rueda, D., and C. Lau. Transportation of Sealed Radioactive Sources (49 CFR Sections 171-180). Office of Scientific and Technical Information (OSTI), January 2015. http://dx.doi.org/10.2172/1179403.

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Longley, Susan W., John Russell Cochran, Laura L. Price, and Kendra J. Lipinski. The adequacy of current import and export controls on sealed radioactive sources. Office of Scientific and Technical Information (OSTI), October 2003. http://dx.doi.org/10.2172/918343.

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Shott, Gregory. Special Analysis for the Disposal of the Materials and Energy Corporation Sealed Sources at the Area 5 Radioactive Waste Management Site. Office of Scientific and Technical Information (OSTI), May 2017. http://dx.doi.org/10.2172/1373420.

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Reed, Dawn, and Gregory Shott. Unreviewed Disposal Question Evaluation for the Disposal of the Sandia National Laboratories Sealed Sources at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada. Office of Scientific and Technical Information (OSTI), March 2018. http://dx.doi.org/10.2172/1508167.

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Reed, Dawn, and Gregory Shott. UNREVIEWED DISPOSAL QUESTION EVALUATION: Disposal of the Perma-Fix Environmental Services Macroencapsulated Sealed Sources at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada. Office of Scientific and Technical Information (OSTI), February 2019. http://dx.doi.org/10.2172/1601661.

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Shott, Gregory. Special Analysis for the Disposal of the Idaho National Laboratory Contact Handled Sealed Sources Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada. Office of Scientific and Technical Information (OSTI), August 2016. http://dx.doi.org/10.2172/1571646.

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Benac, D. J., and W. R. Schick. Sealed source and device design safety testing. Volume 5: Technical report on the findings of Task 4, Investigation of failed radioactive stainless steel troxler gauges. Office of Scientific and Technical Information (OSTI), October 1995. http://dx.doi.org/10.2172/137424.

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Author, Not Given. Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada. Office of Scientific and Technical Information (OSTI), August 2014. http://dx.doi.org/10.2172/1168835.

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