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Relevant bibliographies by topics / Radiochemical laboratories

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Academic literature on the topic 'Radiochemical laboratories'

Author: Grafiati

Published: 4 June 2021

Last updated: 25 July 2024

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Journal articles on the topic "Radiochemical laboratories"

1

Merešová, J., A. Belanová, and M. Vršková. "Inter-laboratory comparison measurements of radiochemical laboratories in Slovakia." Applied Radiation and Isotopes 68, no. 7-8 (July 2010): 1282–85. http://dx.doi.org/10.1016/j.apradiso.2009.11.062.

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Leskinen, Anumaija, and Susanna Salminen-Paatero. "Development of 3H, 14C, 41Ca, 55Fe, 63Ni radiochemical analysis methods in activated concrete samples." Journal of Radioanalytical and Nuclear Chemistry 331, no. 1 (November 21, 2021): 31–41. http://dx.doi.org/10.1007/s10967-021-08073-4.

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AbstractDevelopment of 3H, 14C, 41Ca, 55Fe and 63Ni radiochemical analysis methods were carried out independently by two laboratories using both inactivate and activated concrete samples. Two preliminary radioanalytical procedures for the non-volatile radionuclides (41Ca, 55Fe, 63Ni) and one Thermal oxidation method for the volatile radionuclides (3H, 14C) were developed. The difficulties in the method development and analysis of results are discussed.

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Salminen-Paatero, Susanna, Xiaolin Hou, Grzegorz Olszewski, Lina Ekerljung, Annika Tovedal, Anna Vesterlund, Angelica Andersson, Satu Kangas, and Henrik Ramebäck. "Analyzing alpha emitting isotopes of Pu, Am and Cm from NPP water samples: an intercomparison of Nordic radiochemical laboratories." Journal of Radioanalytical and Nuclear Chemistry 329, no. 3 (July 28, 2021): 1447–58. http://dx.doi.org/10.1007/s10967-021-07913-7.

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AbstractRadioanalytical methods for the determination of isotopes of Pu, Am and Cm in water samples from nuclear power plants were compared and further developed in a Nordic project (Optimethod) through two intercomparison exercises among Nordic laboratories. With this intercomparison, the analytical performance of some laboratories was improved by modification of the analytical method and adopting new techniques. The obtained results from the two intercomparisons for alpha emitting transuranium isotopes are presented, and the lessons learnt from these intercomparison exercises are discussed.

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Leskinen, Anumaija, Celine Gautier, Antti Räty, Tommi Kekki, Elodie Laporte, Margaux Giuliani, Jacques Bubendorff, et al. "Intercomparison exercise on difficult to measure radionuclides in activated concrete—statistical analysis and comparison with activation calculations." Journal of Radioanalytical and Nuclear Chemistry 329, no. 2 (June 28, 2021): 945–58. http://dx.doi.org/10.1007/s10967-021-07824-7.

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AbstractThis paper reports the results obtained in a Nordic Nuclear Safety Research project during the second intercomparison exercise for the determination of difficult to measure radionuclides in decommissioning waste. Eight laboratories participated by carrying out radiochemical analysis of 3H, 14C, 36Cl, 41Ca, 55Fe and 63Ni in an activated concrete. In addition, gamma emitters, namely 152Eu and 60Co, were analysed. The assigned values were derived from the submitted results according to ISO 13,528 standard and the performance assessments were determined using z scores. The measured results

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Dollé, Frédéric, Sandrine Langle, Gaëlle Roger, Roger R. Fulton, Béatrice Lagnel-de Bruin, David J. Henderson, Françoise Hinnen, et al. "Synthesis and In-Vivo Evaluation of [11C]p-PVP-MEMA as a PET Radioligand for Imaging Nicotinic Receptors." Australian Journal of Chemistry 61, no. 6 (2008): 438. http://dx.doi.org/10.1071/ch08083.

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Within the class of (4-pyridinyl)vinylpyridines developed by Abbott laboratories as potent neuronal nicotinic acetylcholine receptor ligands, p-PVP-MEMA ({(R)-2-[6-chloro-5-((E)-2-pyridin-4-ylvinyl)pyridin-3-yloxy]-1-methylethyl}methylamine) is the lead compound of a novel series that do not display the traditional nicotinic-like pyrrole-ring but still possessing high subnanomolar affinity (Ki 0.077 nm—displacement of [3H](–)cytisine from whole rat brain synaptic membranes). In the present study, p-PVP-MEMA and its nor-derivative ({(R)-2-[6-chloro-5-((E)-2-pyridin-4-ylvinyl)pyridin-3-yloxy]-1-

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6

Al-Alawy, Iman Tarik, and Osamah Abdulameer Mzher. "Activity Measurement of Airborne Alpha and Beta Particles in Destroyed Radiochemical Laboratories, at Al-Tuwaitha-Iraq." Indian Journal of Public Health Research & Development 9, no. 12 (2018): 1222. http://dx.doi.org/10.5958/0976-5506.2018.02017.x.

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7

Uccelli, L., A. Boschi, M. Pasquali, A. Duatti, G. Di Domenico, G. Pupillo, J. Esposito, M. Giganti, A. Taibi, and M. Gambaccini. "Influence of the Generator in-Growth Time on the Final Radiochemical Purity and Stability of Radiopharmaceuticals." Science and Technology of Nuclear Installations 2013 (2013): 1–7. http://dx.doi.org/10.1155/2013/379283.

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At Legnaro laboratories of the Italian National Institute for Nuclear Physics (INFN), a feasibility study has started since 2011 related to accelerated-based direct production of by the100Mo(p,2n) reaction. Both theoretical investigations and some recent preliminary irradiation tests on100Mo-enriched samples have pointed out that both the / ratio and the specific activity will be basically different in the final accelerator-produced Tc with respect to generator-produced one, which might affect the radiopharmaceutical procedures. The aim of this work was to evaluate the possible impact of diffe

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Rassou, Somasoudrame, Clarisse Mariet, and Thomas Vercouter. "Analysis of radionuclides in microsystem: application to the selective recovery of 55Fe by solvent extraction." EPJ Nuclear Sciences & Technologies 6 (2020): 10. http://dx.doi.org/10.1051/epjn/2020002.

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The minimization of the sample quantities required by analytical laboratories, as well as the increase of the fastness of the analytical operations are emerging axes for improved radiochemical analyses related to D&D issues. Two microsystem-based protocols were developed for the selective recovery of 55Fe from radioactive samples by solvent extraction. Both protocols were tested on iron solutions in two different microchips. The yields of Fe extraction were compared with macroscale batch experiments. Better performances with more than 80% of iron extracted were obtained with the second pro

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Churakov, Sergey V., Wolfgang Hummel, and Maria Marques Fernandes. "Fundamental Research on Radiochemistry of Geological Nuclear Waste Disposal." CHIMIA International Journal for Chemistry 74, no. 12 (December 23, 2020): 1000–1009. http://dx.doi.org/10.2533/chimia.2020.1000.

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Currently, 5 · 1019 Bq of radioactive waste originating from the use of nuclear power for energy production, and medicine, industry and research, is maintained in Switzerland at intermediate storage facilities. Deep geological disposal of nuclear waste is considered as the most reliable and sustainable long-term solution worldwide. Alike the other European countries, the Swiss waste disposal concept embarks on the combination of engineered and geological barriers. The disposal cell is a complex geochemical system. The radionuclide mobility and consequently radiological impact depend not only o

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Lima, Marisa de Jesus de C., Fabio Luiz Navarro Marques, Miriam Roseli Yoshie Okamoto, Alexandre Tales Garcez, Marcelo Tatit Sapienza, and Carlos Alberto Buchpiguel. "Preparation and evaluation of modified composition for lyophilized kits of [Cu(MIBI)4]BF4 for [99mTc] technetium labeling." Brazilian Archives of Biology and Technology 48, spe2 (October 2005): 1–8. http://dx.doi.org/10.1590/s1516-89132005000700001.

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The [Cu(MIBI)4]BF4 complex was synthesized and different formulations for lyophilized kits that could be cost-effectively used with different routines in nuclear medicine laboratories were investigated. In one preparation the kit components were kept similar to the Cardiolite® , except that the SnCl2.2H2O concentration was increased to 0.150 mg. In a second formulation, component concentrations were reduced to 1/5 of the original value and the SnCl2.2H2O concentration was adjusted to 0.04 mg. These products were labeled with maximum activities of 55.5 GBq and 8.14 GBq, respectively, and have s

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Dissertations / Theses on the topic "Radiochemical laboratories"

1

Jia, Di. "A radon chamber and its role in a radon survey /." [Hong Kong : University of Hong Kong], 1992. http://sunzi.lib.hku.hk/hkuto/record.jsp?B13385379.

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2

Jia, Di, and 賈地. "A radon chamber and its role in a radon survey." Thesis, The University of Hong Kong (Pokfulam, Hong Kong), 1992. http://hub.hku.hk/bib/B31210818.

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

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This thesis reports on the modification of the "Safecode" computer-program to monitor the safety of radio-isotope laboratories, and its application to 24 compliance audits in NSW during the period 1999 to 2006. Additionally, an attempt was made to predict the level of risk to persons working within those laboratories. Based on the current NSW radiation control legislation and the relevant Australian Standards a comprehensive audit checklist was developed for this project. Each safety requirement in those documents was used to develop a question, resulting in 187 questions in the checklist.

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Books on the topic "Radiochemical laboratories"

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C, Humphreys Jimmy, and National Institute of Standards and Technology (U.S.)., eds. Criteria for characterization and performance of a high-dose radiation dosimetry calibration laboratory. Gaithersburg, MD: U.S. Department of Commerce, Technology Administration, National Institute of Standards and Technology, 1996.

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2

Cong Juli shi yan shi zou lai: Yang Chengzong kou shu zi zhuan = A Radiochemist from the Curie Laboratory : the Oral Autobiography of Yang Chengzong. Changsha Shi: Hunan jiao yu chu ban she, 2012.

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3

Radiological response: Assessing environmental and clinical laboratory capabilities : hearing before the Subcommittee on Investigations and Oversight of the Committee on Science and Technology, House of Representatives, One Hundred Tenth Congress, first session, October 25, 2007. Washington: U.S. G.P.O., 2008.

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4

U.S. Dept. of Energy. Medical isotopes production project: Molybdenum-99 and related isotopes : environmental impact statement. [Washington, D.C: The Office?, 1996.

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5

Los Alamos Historical Document Retrieval and Assessment Project. Draft final report of the Los Alamos Historical Document Retrieval and Assessment (LAHDRA) Project. Washington, D.C: Centers for Disease Control and Prevention?, 2009.

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6

Teknik Makmal Radioisotop. Malaysia: Dewan Bahasa dan Pustaka, Malaysia, 1993.

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7

RI bīmu fakutorī keikaku: RI beam factory. Saitama-ken Wakō-shi: Nishin Kasokuki Kenkyū Sentā, 2006.

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Book chapters on the topic "Radiochemical laboratories"

1

Landsberger, S., and D. Haas. "Research reactor support for nuclear forensics studies and the development of a companion graduate course." In Environmental Radiochemical Analysis VII, 117–24. Royal Society of Chemistry, 2023. http://dx.doi.org/10.1039/9781837670758-00117.

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The term nuclear forensics encompasses the detection and analysis of nuclear materials before they are used in a weapon, the analysis of radioactive debris following a nuclear event or the investigation of the pedigree of nuclear materials in non-proliferation. Nuclear forensics typically encompasses these three main broad areas: radiochemistry, chemical instrumentation and non-destructive techniques (typically gamma-ray spectrometry). Research reactors (10kW – 10MW) are a great resource to perform research and development in nuclear forensics as well as in the critical need of education. Research reactors' ability to produce isotopes in small or large amounts means that researchers have a unique source of material for nuclear forensics studies. A graduate course in nuclear forensics was developed as a companion to a research project with a grant through the US Department of Homeland Security. Besides the usual lectures on the basics of nuclear phenomena, a successful effort was made to include a significant amount of historical background. In addition, several guest lecturers from national laboratories and universities were added to the curriculum, resulting in a more meaningful and current course. Due to COVID-19 restrictions, all the laboratories were virtually delivered in both fully remote and hybrid modes across several semesters.

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Conference papers on the topic "Radiochemical laboratories"

1

Koroll, Grant W., Dennis M. Bilinsky, Randall S. Swartz, Jeff W. Harding, Michael J. Rhodes, and Randall W. Ridgway. "Decommissioning of AECL Whiteshell Laboratories." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16311.

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Whiteshell Laboratories (WL) is a Nuclear Research and Test Establishment near Winnipeg, Canada, operated by AECL since the early 1960s and now under decommissioning. WL occupies approximately 4400 hectares of land and employed more than 1000 staff up to the late-1990s, when the closure decision was made. Nuclear facilities at WL included a research reactor, hot cell facilities and radiochemical laboratories. Programs carried out at the WL site included high level nuclear fuel waste management research, reactor safety research, nuclear materials research, accelerator technology, biophysics, an

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2

Burgess, Peter. "The Level of Uncertainty in Materials Clearance." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16090.

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Measurement of surface levels is essential in waste assessment and in clearing materials from nuclear licensed sites. Radiation measurements in general are much less accurate than most forms of engineering measurement, even in relatively simple conditions, such as radiochemical laboratories. Waste assessment during clearance is far more difficult. The areas of uncertainty include: (1) The intrinsic limitations of the equipment employed. For surface activity measurement, the detector is often a large area alpha + beta scintillation probe connected to a ratemeter. Any detector has an effective e

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3

Darbyshire, Carol, and Pete Burgess. "Quantifying Tc-99 Contamination in a Fuel Fabrication Plant." In ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59024.

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The Springfields facility manufactures nuclear fuel products for the UK’s nuclear power stations and for international customers. Fuel manufacture is scheduled to continue into the future. In addition to fuel manufacture, Springfields is also undertaking decommissioning activities. Today it is run and operated by Springfields Fuels Limited, under the management of Westinghouse Electric UK Limited. The site has been operating since 1946 manufacturing nuclear fuel. As part of the decommissioning activities, there was a need was to quantify contamination in a large redundant building. This buildi

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Stephens, Michael E., Sheila M. Brooks, Joan M. Miller, and Robert A. Mason. "Lessons Learned in Planning the Canadian Nuclear Legacy Liabilities Program." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40270.

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In 2006, Atomic Energy of Canada Limited (AECL) and Natural Resources Canada (NRCan) began implementing a $7B CDN, 70-year Nuclear Legacy Liabilities Program (NLLP) to deal with legacy decommissioning and environmental issues at AECL nuclear sites. The objective of the NLLP is to safely and cost-effectively reduce the nuclear legacy liabilities and associated risks based on sound waste management and environmental principles in the best interest of Canadians. The liabilities include shutdown research and prototype power reactors, fuel handling facilities, radiochemical laboratories, support bu

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Mikheykin, S. V., P. P. Poluektov, S. L. Khrabrov, A. Yu Smirnov, and V. P. Simonov. "D&D Experience in VNIINM." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4769.

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Since the mid-1960s the VNIINM has been developing decontamination techniques for a variety of materials and contaminants for Russian nuclear engineering needs. 1. Early in the development, chemical decontamination was the most commonly used method. According to the nature of contaminants and contaminated material, mineral acids, alkali, mineral and organic oxidants and reductants were used. For best results, complex forming agents were sometimes added. However, in spite of widespread use of chemical decontamination at the USSR nuclear facilities, this technique has a drawback of producing a g

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