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Journal articles on the topic 'Sealed radioactive sources'

Author: Grafiati

Published: 4 June 2021

Last updated: 1 February 2022

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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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2

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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3

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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4

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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5

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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6

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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7

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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8

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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9

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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10

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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11

Yamawaki, Masato, Yoshinori Kobayashi, K. Ito, Mikio Matsumoto, Hidetake Ishizu, Akiyo Umino, Kanehisa Hattori, and Yoshihiro Watanabe. "Sealed ²²Na Sources for Positron Annihilation Lifetime Spectroscopy." Materials Science Forum 733 (November 2012): 310–13. http://dx.doi.org/10.4028/www.scientific.net/msf.733.310.

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Sealed radioactive sources of 22Na for positron annihilation lifetime spectroscopy (PALS), free from the legal regulations, are commercially available from an American company. However, thick foils are used to seal 22Na in these sources and large fractions of the positrons annihilate in the sealing materials. Further, it is pointed out that a long lifetime component over 1 ns appears in the positron lifetime spectrum acquired with the Kapton sealed source (POSK-22, IPL Inc.). In this research, attempts were made to develop high quality sealed positron sources, potentially free from regulations, for ubiquitous application of PALS. The sources prepared in the present work are of high quality and applicable to our new PALS, which does not require sample cutting and is potentially applicable to truly nondestructive, onsite inspection of various materials

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12

Mohamed, Yasser T. "Quality assurance management system for spent radioactive sealed sources in Egypt." Quality Assurance Journal 12, no. 2 (April 2009): 86–94. http://dx.doi.org/10.1002/qaj.445.

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13

Ya-anant, N., P. Nuanjan, A. Phattanasub, T. Akharawutchayanon, A. O-manee, N. Prasertchiewchan, and J. C. Benitez-Navarro. "Safety and security management of disused sealed radioactive sources in Thailand." Journal of Physics: Conference Series 611 (May 7, 2015): 012014. http://dx.doi.org/10.1088/1742-6596/611/1/012014.

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14

Cummings, Daniel G., James D. Sommers, Mary L. Adamic, Marcos Jimenez, Jeffrey J. Giglio, Kevin P. Carney, and Karl Grimm. "Characterization of sealed radioactive sources: uncertainty analysis to improve detection methods." Journal of Radioanalytical and Nuclear Chemistry 282, no. 3 (September 26, 2009): 923–28. http://dx.doi.org/10.1007/s10967-009-0368-0.

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15

Mohammed, Mohammed Siddig H., Essam M. Banoqitah, Ezzat Elmoujarkach, Abdulsalam M. Alhawsawi, and Fathi Djouider. "A virtual laboratory for radiotracer and sealed-source applications in industry." Nukleonika 66, no. 1 (March 1, 2021): 21–27. http://dx.doi.org/10.2478/nuka-2021-0003.

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Abstract Radioactive sealed sources and radiotracer techniques are used to diagnose industrial process units. This work introduces a workspace to simulate four sealed sources and radiotracer applications, namely, gamma scanning of distillation columns, gamma scanning of pipes, gamma transmission tomography, and radiotracer flow rate measurements. The workspace was created in Geant4 Application for Tomographic Emission (GATE) simulation toolkit and was called Industrial Radioisotope Applications Virtual Laboratory. The flexibility of GATE and the fact that it is an open-source software render it advantageous to radioisotope technology practitioners, educators, and students. The comparison of the simulation results with experimental results that are available in the literature showed the effectiveness of the virtual laboratory.

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16

Marpaung, T. "Reduction of Radioactive Waste Through the Reuse and Recycle Policy of the Sealed Radioactive Sources Management." Atom Indonesia 38, no. 2 (January 15, 2013): 57. http://dx.doi.org/10.17146/aij.2012.161.

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17

Mikamoto, Takahiro, Takahiro Yamada, and Tadahiro Kurosawa. "SIMPLIFIED PRACTICAL TEST METHOD FOR PORTABLE DOSE METERS USING SEVERAL SEALED RADIOACTIVE SOURCES." Radiation Protection Dosimetry 170, no. 1-4 (August 12, 2016): 141–44. http://dx.doi.org/10.1093/rpd/ncw164.

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18

Russ, Bob. "Draft Euratom Directive on the Control of High Activity Sealed Radioactive Sources (HASS)." Journal of Radiological Protection 21, no. 2 (May 30, 2001): 193–94. http://dx.doi.org/10.1088/0952-4746/21/2/610.

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19

Kim, Juyoul, Sukhoon Kim, and Seunghee Lee. "Characteristic analysis and optimum management plan of disused sealed radioactive sources in Korea." Annals of Nuclear Energy 102 (April 2017): 268–73. http://dx.doi.org/10.1016/j.anucene.2016.12.036.

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20

Lee, Seunghee, and Juyoul Kim. "Post-closure safety assessment of near surface disposal facilities for disused sealed radioactive sources." Nuclear Engineering and Design 313 (March 2017): 425–36. http://dx.doi.org/10.1016/j.nucengdes.2017.01.001.

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21

Beyala Ateba, J. F., J. F. Sabouang, A. Simo, M. Moyo, and H. Haieta. "RADIATION PROTECTION MEASURES TAKEN DURING REPATRIATION OF SEALED HIGH ACTIVITY RADIOACTIVE SOURCES IN CAMEROON." Radiation Protection Dosimetry 178, no. 3 (August 5, 2017): 254–59. http://dx.doi.org/10.1093/rpd/ncx104.

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22

Rolle, A., and B. Droste. "Safety during whole life time: important aspect in safety assessment of sealed radioactive sources." Packaging, Transport, Storage & Security of Radioactive Material 19, no. 3 (September 2008): 151–54. http://dx.doi.org/10.1179/174651008x344458.

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23

Ameyaw, F., M. Nyarku, J. Boffie, J. K. Gbadago, E. Boafo, and E. T. Glover. "Characterization of Radioisotope and Shield Content of Stored Disused Sealed Radioactive Sources in Ghana." Journal of Hazardous, Toxic, and Radioactive Waste 20, no. 3 (July 2016): 05016001. http://dx.doi.org/10.1061/(asce)hz.2153-5515.0000319.

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24

Neuschütz, Dieter, Denis Spirin, Klaus Hack, Ulrich Quade, and Jan Meier-Kortwig. "Nuclide Distribution between Steelmaking Phases upon Melting of Sealed Radioactive Sources Hidden in Scrap." steel research international 74, no. 11-12 (November 2003): 762–67. http://dx.doi.org/10.1002/srin.200300261.

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25

MARUYAMA, Takashi, and Kanae NISHIZAWA. "Handling Manual for Brachytherapy Sources. III. Practice of Radiation Protection of Therapeutic Uses of Small Sealed Radioactive Sources." RADIOISOTOPES 36, no. 4 (1987): 204–11. http://dx.doi.org/10.3769/radioisotopes.36.4_204.

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26

MARUYAMA, Takashi, and Kanae NISHIZAWA. "Handling Manual for Brachytherapy Sources. III. Practice of Radiation Protection for Therapeutic Uses of Small Sealed Radioactive Sources." RADIOISOTOPES 36, no. 5 (1987): 247–52. http://dx.doi.org/10.3769/radioisotopes.36.5_247.

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27

Prlić, Ivica, Marija Mihić, Gordana Marović, and Tomislav Meštrović. "Total Occupational Exposure During Characterisation, Conditioning, and Securing of Radioactive Sealed Sources: A New Dosimetric Concept Using Active Electronic Dosimeters." Archives of Industrial Hygiene and Toxicology 60, no. 1 (March 1, 2009): 53–60. http://dx.doi.org/10.2478/10004-1254-60-2009-1913.

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Total Occupational Exposure During Characterisation, Conditioning, and Securing of Radioactive Sealed Sources: A New Dosimetric Concept Using Active Electronic DosimetersRadiation dosimetry in protection against ionising radiation involves research of all possible pathways through which natural or man-made radioactive materials can contaminate a habitat and actually harm its biota. It also takes into account natural and artificial (man-made) electromagnetic ionizing radiation (γ and x radiation). This article presents a dosimetric study assessing exposure to man-made ionising radiation of local environment and total occupational exposure of two professional workers involved in characterisation, conditioning, and securing of unused radioactive sealed sources. The purpose of the study was to validate a new active electronic dosimeter (AED) of type ALARA OD and to develop a new monitoring method by tracing the external occupational exposure over real time. This method is used to continuously measure and record external radiation doses and, which is a novelty, establish dose rates receiving pattern as a function of real time. Occupational whole body dosimetric results obtained with AED were compared with results obtained with passive dosimetry (film badge and thermoluminiscence). Air, dust, and silicon sand samples were analysed by gamma-spectrometry to estimate internal exposure of the two workers to 222Rn due to inhalation or ingestion of dust and sand in indoor air. In order to establish total occupational exposure, control radon measurement was performed in the immediate environment and the external Hazard index (Hex) was calculated.

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28

Salehe, Mikidadi, and Chang-Lak Kim. "Borehole Disposal Concept: A Proposed Option for Disposal of Spent Sealed Radioactive Sources in Tanzania." Journal of the Nuclear Fuel Cycle and Waste Technology 11, no. 4 (December 30, 2013): 293–301. http://dx.doi.org/10.7733/jnfcwt-k.2013.11.4.293.

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29

Cota, Stela, Goro Hiromoto, Heidar Gharbieh, and Aurélio Silva. "Preliminary post-closure safety assessment for a borehole-type repository for disused sealed radioactive sources in Brazil." Progress in Nuclear Energy 103 (March 2018): 74–80. http://dx.doi.org/10.1016/j.pnucene.2017.11.005.

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30

Karachristou, I., St Chouvardas, G. Terzoudi, and A. Savidou. "Radiation Protection Calculations for the New Radioactive Waste Interim Storage Facility of NCSR “Demokritos"." HNPS Proceedings 21 (March 8, 2019): 141. http://dx.doi.org/10.12681/hnps.2019.

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The present study concerns the determination of the maximum acceptable contact dose rate per radioac- tive waste package for safekeeping at the New Radioactive Waste Interim Storage (NRWIS) of the National Centre for Scientific Research “Demokritos” (NCSR “D”). The NRWIS facility is used for temporary storage of spent/ orphan sealed sources, devices like lightning rods and primary radioactive waste. The contact dose rate per package is determined in a level that even in case the highest radiation background is built up in- side the storage facility, the doses to the workers will not exceed the maximum permissible doses. The total dose that a worker receives inside the facility should not exceed one half of the annual occupational dose constraint of 6 mSv. Furthermore in cases of the highest radiation background inside the facility, shielding calculations are performed.

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31

Van Der Merwe, N. J. "Mobile hot cell and borehole disposal integration for high activity disused radioactive sealed sources (DSRS) conditioning and final disposal." Physica Medica 41 (September 2017): S3. http://dx.doi.org/10.1016/s1120-1797(17)30275-2.

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32

Oforiwaa, Priscilla Obeng, An Hongxiang, Liang Manchun, and Liu Jianqin. "RESEARCH ON SAFETY ASSESSMENT OF DISPOSAL OPTIONS OF DISUSED SEALED RADIOACTIVE SOURCES IN GHANA – FOCUS ON DISPOSAL SYSTEM ANALYSIS." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019.27 (2019): 1011. http://dx.doi.org/10.1299/jsmeicone.2019.27.1011.

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33

Tokarevskyi, O., K. Fuzik, S. Kondratiev, and Z. Alekseeva. "Analysis of Safety Aspects of Disused Sealed Radiation Source Disposal." Nuclear and Radiation Safety, no. 2(86) (June 12, 2020): 72–80. http://dx.doi.org/10.32918/nrs.2020.2(86).09.

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Sealed radiation sources (SRS) are extensively used worldwide in agriculture, industry, medicine and different research areas. If further use of SRS is not envisaged, and the decision is made on declaration of these disused SRSs (DSRS) as radioactive waste (RW), then legislative and regulatory requirements for RW management are fully applicable from that point. Since DSRSs have essential distinctions from other types of RW, in particular, high specific activity, it is critically important to ensure safe management of DSRS, declared as RW, at all stages of their management including disposal. DSRS disposal as RW is the final phase of SRS lifecycle and final stage of their safe and reliable management. In this paper, there are considered safety issues for management of DSRS, declared as RW. Approaches to DSRS disposal recommended by IAEA, advantages and drawbacks of different disposal options for DSRS are analyzed. DSRS disposal needs shall be considered taking into account safety requirements for RW disposal. First, DSRS shall be attributed to specific RW class to address respective disposal needs. This is a challenging issue because the approaches for categorization of SRS and classification of RW are essentially different. DSRS declared as RW may be disposed of either together with other RW in the existing or planned RW disposal facilities, or in the disposal facilities designed and constructed specially for DSRS. Current situation with DSRS management in Ukraine is analyzed. DSRS management strategy in Ukraine envisages their long-term storage in the centralized facility for 50 years with subsequent transfer for disposal. At that, there are neither specified disposal facilities where DSRS will be disposed of, nor established generic waste acceptance criteria for DSRS disposal. Recommendations on further steps for solving challenging issues related to safe disposal of DSRS in Ukraine are provided. Solution of a set of challenging issues related to DSRS management revealed in the paper will promote implementation of comprehensive approach to safe disposal of DSRS in Ukraine.

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34

Gensolen, F., L. Ammour, M. Bautista, J. Heymes, S. Fieux, M. Kachel, F. Lefebvre, et al. "MAPSSIC, a communicating MAPS-based intracerebral positrons probe for deep brain imaging in awake and freely-moving rats." EPJ Web of Conferences 225 (2020): 09002. http://dx.doi.org/10.1051/epjconf/202022509002.

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Radioisotope imaging is a powerful tool to understand the biological mechanisms in-vivo, especially in the brain of small animals, providing a significant model to study the human brain. In this context, we have developed and built a pixelated intracerebral positron probe to be embedded on awake and freely moving small animals, typically rats. This pixelated probe will represent a key instrument for neuroscientists to study neural mechanisms and correlate them to behavioral experiments. We describe in this paper the simulations carried out to design the intracerebral sensor, its architecture, and the detection of positrons in a volume with a couple of sensors assembled back-to-back. We also depict the architecture of the wireless acquisition system. Finally, we present the first measurements performed in real-time by this miniaturized probe with sealed radioactive sources and a 18F solution.

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35

Vujović, Milan, and Miloš Vujisić. "Applicability of polymer and composite inner linings in containers for borehole disposal of sealed radioactive sources − A simulation-based study of radiation effects." Progress in Nuclear Energy 137 (July 2021): 103793. http://dx.doi.org/10.1016/j.pnucene.2021.103793.

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36

Chou, Jacquelyn W., Michelle Skornicki, and Joshua T. Cohen. "Unintended consequences of the potential phase-out of gamma irradiation." F1000Research 7 (March 21, 2018): 348. http://dx.doi.org/10.12688/f1000research.14090.1.

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The radioisotope cobalt-60 (Co-60) is important for commercial, medical, and agricultural applications. Its widespread use has meant that Co-60 can be found in less secured facilities, leading to the fear that unauthorized persons could obtain and use it to produce a “dirty bomb”. This potential security concern has led to government calls for phasing-out Co-60 and other radiation sources, despite ongoing safety and security regulations for handling, transport and use of radioactive sealed sources. This paper explores potential implications of phasing out radioisotopic technologies, including unintended safety and cost consequences for healthcare and food in the US and globally. The use of Co-60 for healthcare and agricultural applications is well-documented. Co-60 is used to sterilize single-use medical devices, tissue allografts, and a range of consumer products. Co-60 is used in Gamma Knife treatment of brain tumors in over 70,000 patients annually. Co-60 is also used to preserve food and kill insects and pathogens that cause food-borne illness. Co-60 is effective, reliable, and predictable. Limitations of alternative sterilization technologies include complex equipment, toxicities, incompatibilities with plastic, and physical hazards. Alternative ionizing radiation sources for wide-reaching applications, including e-beam and x-ray radiation, have advantages and drawbacks related to commercial scale capacity, penetrability, complexity and reliability. Identifying acceptable alternatives would require time, costs and lengthy regulatory review. FDA testing requirements and other hurdles would delay replacement of existing technologies and slow medical innovation, even delaying access to life-saving therapies. A phase-out would raise manufacturing costs, and reduce supply-chain efficiencies, potentially increasing consumer prices, and reducing supply. These consequences are poorly understood and merit additional research. Given Co-60’s importance across medical and non-medical fields, restrictions on Co-60 warrant careful consideration and evaluation before adoption.

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37

Rozental, Jose de Julio. "Two decades of radiological accidents direct causes, roots causes and consequences." Brazilian Archives of Biology and Technology 45, spe (September 2002): 125–33. http://dx.doi.org/10.1590/s1516-89132002000500018.

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Practically all Countries utilize radioisotopes in medicine, industry, agriculture and research. The extent to which ionizing radiation practices are employed varies considerably, depending largely upon social and economic conditions and the level of technical skills available in the country. An overview of the majority of practices and the associated hazards will be found in the <A HREF="#tabela4">Table IV</A> to <A HREF="#tabela7">VII</A> of this document. The practices in normal and abnormal operating conditions should follow the basic principles of radiation protection and the Safety of Radiation Sources, considering the IAEA Radiation Protection and the Safety of Radiation Sources, Safety Series 120 and the IAEA Recommendation of the Basic Safety Standards for Radiation Protection, Safety Series Nº 115. The Standards themselves underline the necessity to be able to predict the radiological consequences of emergency conditions and the investigations that should need to be done. This paper describes the major accidents that had happened in the last two decades, provides a methodology for analyses and gives a collection of lessons learned. This will help the Regulatory Authority to review the reasons of vulnerabilities, and to start a Radiation safety and Security Programme to introduce measurescapable to avoid the recurrence of similar events. Although a number of accidents with fatalities have caught the attention of the public in recent year, a safety record has accompanied the widespread use of radiation sources. However, the fact that accidents are uncommon should not give grounds for complacency. No radiological accident is acceptable. From a radiation safety and security of the sources standpoint, accident investigation is necessary to determine what happened, why, when, where and how it occurred and who was (were) involved and responsible. The investigation conclusion is an important process toward alertness and feedback to avoid careless attitudes by improving the comprehension of Safety Performance and Safety Culture. Accident investigation is the first step toward avoiding future injures and financial losses, by prevention of recur recurrence. On the other hand, accident investigation is also essential for the establishment of the responsibilities and liability for the consequences. This document discuss the main accidents that have happened in the last two decades, in terms of causes, consequences, similarities and lessons learned when sealed sources have been damaged, lost, stolen and abandoned. In considerable majority death and serious injuries were resulted from failures in the safety system for radiation sources and for the security of radioactive materials.

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38

Shingleton, Kathleen L., and David W. Lee. "Radioactive Sealed Source Accountability a Risk-Based Approach." Health Physics 74, no. 4 (April 1998): 435–41. http://dx.doi.org/10.1097/00004032-199804000-00003.

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39

Rogge, Ronald B., Ghaouti Bentoumi, F. (Ike) Dimayuga, Roxana Flacau, Gang Li, Liqian Li, and Bhaskar Sur. "NON-DESTRUCTIVE EXAMINATION USING NEUTRONS: A NUCLEAR WASTE AND ORPHANED SOURCE CHARACTERIZATION CASE STUDY APPLICABLE TO NUCLEAR FORENSICS." AECL Nuclear Review 4, no. 2 (December 1, 2015): 141–54. http://dx.doi.org/10.12943/cnr.2015.00051.

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Found unknown radioactive material is often contained in a package so the chemical and physical form of the material itself is unknown, and the detail of the packaging is likewise unknown. Together, these present a significant risk on how to handle the package for destructive examination of its contents. Whether of nefarious origin or the result of less stringent practices of yesteryear the material needs to be properly identified and characterized for appropriate disposition. Results of neutron imaging, neutron diffraction, and delayed neutron analysis as applied to an examination of sealed capsules containing unknown radioactive materials are presented. The results demonstrate that neutron-based non-destructive examination techniques can be employed for inspecting encapsulated radioactive samples to identify the materials, to elucidate the internal physical structure of the radioactive material and encapsulation, and to estimate the mass of fissile and fissionable materials within. This characterization of orphaned radioactive special nuclear material illustrates the potential for these techniques in nuclear forensics investigations.

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40

Kim, Sukhoon, Juyoul Kim, and Seunghee Lee. "Study of Classification and Disposal Method for Disused Sealed Radioactive Source in Korea." Journal of Nuclear Fuel Cycle and Waste Technology 14, no. 3 (September 30, 2016): 253–66. http://dx.doi.org/10.7733/jnfcwt.2016.14.3.253.

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41

Lee, Seunghee, and Juyoul Kim. "Preliminary Post-closure Safety Assessment of Disposal System for Disused Sealed Radioactive Source." Journal of Soil and Groundwater Environment 22, no. 4 (August 31, 2017): 33–48. http://dx.doi.org/10.7857/jsge.2017.22.4.033.

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42

Lee, Seunghee, Juyoul Kim, and Sukhoon Kim. "Preliminary Post-closure Safety Assessment of Disposal Options for Disused Sealed Radioactive Source." Economic and Environmental Geology 49, no. 4 (August 28, 2016): 301–14. http://dx.doi.org/10.9719/eeg.2016.49.4.301.

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43

Price, Jonathan G. "SEG Presidential Address: I Never Met a Rhyolite I Didn’t Like – Some of the Geology in Economic Geology." SEG Discovery, no. 57 (April 1, 2004): 1–13. http://dx.doi.org/10.5382/segnews.2004-57.fea.

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ABSTRACT Rhyolites and their deep-seated chemical equivalents, granites, are some of the most interesting rocks. They provide good examples of why it is important to look carefully at fresh rocks in terms of fıeld relationships, mineralogy, petrography, petrology, geochemistry, and alteration processes. Because of their evolved geochemisty, they commonly are important in terms of ore-forming processes. They are almost certainly the source of metal in many beryllium and lithium deposits and the source of heat for many other hydrothermal systems. From other perspectives, rhyolitic volcanic eruptions have the capacity of destroying civilizations, and their geochemistry (e.g., high contents of radioactive elements) is relevant to public policy decision-making.

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44

Corbey, Jordan F., Dallas D. Reilly, Lucas E. Sweet, and Timothy G. Lach. "Extraction of plutonium-containing microcrystals from Hanford soil using a focused ion beam for single-crystal X-ray diffraction analysis." Journal of Applied Crystallography 52, no. 6 (October 11, 2019): 1244–52. http://dx.doi.org/10.1107/s1600576719012299.

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Herein, the successful use of a focused ion beam/scanning electron microscope to prepare microsamples of radioactive single crystals for X-ray diffraction analysis is reported. This technique was used to extract and analyze crystalline Pu-containing particles as small as 28 µm3 from Hanford soil taken from the 216-Z-9 waste crib, which were then crystallographically characterized using single-crystal X-ray diffraction to confirm the cubic structure of PuO2. As a systematic proof of concept, the technique was first tested using UO2 crystals milled into cubic shapes with approximate volumes of 4620, 1331, 125, 8 and 1 µm3, in order to empirically determine the crystal size limits for characterization by a laboratory-based diffractometer with a sealed tube Mo or Ag anode X-ray source and a charge-coupled device detector.

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Marelli, Stefano, Edgar Manukyan, Hansruedi Maurer, Stewart A. Greenhalgh, and Alan G. Green. "Appraisal of waveform repeatability for crosshole and hole-to-tunnel seismic monitoring of radioactive waste repositories." GEOPHYSICS 75, no. 5 (September 2010): Q21—Q34. http://dx.doi.org/10.1190/1.3479552.

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Countries worldwide are seeking solutions for the permanent removal of high-level radioactive waste from the environment. Surrounding the waste with multiple engineered barriers and emplacement in deep geological repositories is widely accepted as a safe means of isolating it from the biosphere for the necessary [Formula: see text]. As a precautionary measure, society demands that repositories be monitored for [Formula: see text] after they are backfilled and sealed. Effective monitoring that does not compromise the engineered and natural barriers is challenging. To address this issue, we investigate the viability of crosshole and hole-to-tunnel seismic methods for remotely monitoring high level radioactive waste repositories. Measurements are made at two underground rock laboratories in Switzerland, one within granitic rock and one within clay-rich sediments. Numerical simulations demonstrate that temporal changes of the monitored features (i.e., bentonite plug, excavation damage zone, sand-filled microtunnel) should produce significant changes in the seismicwaveforms. Nevertheless, inversion for medium-property changes requires that true seismic waveform changes are not overwhelmed by recording variations. We find that a P-wave sparker source is highly repeatable up to frequencies of [Formula: see text] for propagation distances out to tens of meters involved in repository-scale monitoring. Hydrophone repeatability is limited by incoherent high frequency noise and variable hydrophone-borehole coupling conditions, but firmly grouted geophones within the tunnels yield consistent recordings. Three kinds of coherent noise contaminate the data: (1) mechanically induced electrical effects in the hydrophone chains; (2) high currents in the sparker cable, which cause it to oscillate radially as a line source; and (3) tube waves. Our investigations outline a quantitative methodology to assess data-quality requirements for successful monitoring. We suggest that full waveform seismic tomography can be used to monitor radioactive waste emplacement tunnels, provided that careful attention is paid to instrument fidelity and noise suppression.

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Arustamov, Arthur E., Michael I. Ojovan, and Michael B. Kachalov. "Lead and Lead-Based Alloys as Waste Matrix Materials." MRS Proceedings 556 (1999). http://dx.doi.org/10.1557/proc-556-961.

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AbstractMetals and alloys with relatively low melting temperatures such as lead and lead-based alloys are considered in Russia as prospective matrices for encapsulation of spent nuclear fuel in containers in preparation for final disposal in underground repositories. Now lead and leadbased alloys are being used for conditioning spent sealed radioactive sources at radioactive waste disposal facilities.

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Ojovan, M., V. Kascheev, and P. Poluektov. "Self-disposal option for highly-radioactive waste reconsidered." MRS Proceedings 1475 (2012). http://dx.doi.org/10.1557/opl.2012.611.

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ABSTRACTSelf-disposal option for heat-generating radioactive waste (HLW, spent fuel, sealed radioactive sources) known also as rock melting concept was considered in the 70s as a viable but alternative disposal option by both DOE in the USA and Atomic Industry Ministry in the USSR. Self-disposal is currently reconsidered with a novel purpose – to penetrate into the very deep Earth’s layers beneath the Moho’s discontinuity and to explore Earth interior. Self-descending heat generating capsules can be used for disposal of dangerous radioactive wastes in extremely deep layers of the Earth preventing any release of radionuclides into the biosphere. Descending of capsules continues until enough heat is generated by radionuclides to provide partial melting of surrounding rock. Estimates show that extreme depths of several tens and up to hundred km can be reached by capsules which could never be achieved by other techniques.

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Maset, Elvira Rosa. "Radioactive Waste and Spent Fuel Management in Argentina." MRS Proceedings 1475 (2012). http://dx.doi.org/10.1557/opl.2012.550.

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ABSTRACTSince its creation in 1950, the Argentine Atomic Energy Commission (CNEA), has worked on the development of applications for the peaceful use of nuclear energy. They include, among others, research and development activities in basic and nuclear technology areas, the operation of important facilities for the production of radioisotopes and the performance of tasks in connection with the nuclear fuel cycle, mining and uranium processing activities, manufacturing of fuel elements, production of heavy water and the operation of two nuclear power plants. Also demonstrating reprocessing programs have been developed.As a result of the above mentioned activities performed in the nuclear field by private and public entities, various types of radioactive waste have been and are produced during operation and maintenance of facilities and plants, and will be produced in their future decommissioning. CNEA is also responsible for the environmental remediation of the closed uranium mining and milling facilities and for the management of disused sealed sources from medical and industrial applications.Activities concerning radioactive waste management are carried on according not only to Nuclear Regulatory Authority requirements and International Atomic Energy Agency recommendations, but also to the national legal framework.The Law Nº 25.018, "Radioactive Waste Management Regime“(1998), created the National Program for Radioactive Waste Management (PNGRR), as part of CNEA organization.

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Fortner, Jeffrey, Scott Aase, and Don Reed. "Diogenic Transmutation Effects in a Crystalline Aluminosilicate Ceramic: a Tem Study." MRS Proceedings 713 (2002). http://dx.doi.org/10.1557/proc-713-jj11.37.

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ABSTRACTWe demonstrate the use of transmission electron microscopy (TEM) to study the effects of beta-decay of radioactive 137Cs to 137Ba in crystalline pollucite (CsAlSi2O6). Most prior work on radiation effects in materials has focused on structural damage from alpha radiation. Beta radiation, on the other hand, causes little atomic displacement, but the decay transmutation, that is, the radioactive decay of a radioisotope to an isotope of another element, results in progeny with different the valence and ionic radius. Cesium-137, a fission product of uranium, is a major contaminant at U.S. Department of Energy production facilities. Pollucite is an aluminosilicate ceramic with potential use for long-term storage of 137Cs. We focused on one of several available 137Cs sources originally fabricated in the 1970s and 1980s. These sources were small, sealed, stainless steel capsules containing pollucite in which varying amounts of the natural Cs had been replaced by radioactive 137Cs (t1/2 = 30.13 years). The sample chosen for TEM examination, aged for nearly 20 years, contained the most radiogenic barium and was expected to show the largest radiation effects. Bright field transmission images revealed a homogeneous crystalline matrix, with no evidence of distinct Ba phases or ex-solution phenomena resulting from the 137Cs transmutation. Electron diffraction patterns obtained from several portions of the sample were consistent with literature values for pollucite. These data suggest that little substantial damage was done to the crystal structure of this sample, despite the transmutation of nearly 1.5% of the total cesium to barium over the elapsed 20 years. Although our observations are limited, to our knowledge these are the only available data in which transmutation effects have been isolated from other radiation damage phenomena.

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Verma, Rajni, Gourav Kumar Jain, and Arun Chougule. "Implementation of safety and security standards for high dose rate brachytherapy sealed radioactive source used in a medical radiation facility." Radiation Medicine and Protection, November 2020. http://dx.doi.org/10.1016/j.radmp.2020.11.004.

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