Relevant bibliographies by topics / Radiochemical laboratories

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

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"

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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 were compared with activation calculation result showing varying degree of comparability.
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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-methylethyl}methylamine) as precursor for labelling with the short-lived positron-emitter carbon-11 (T1/2 20.4 min) were synthesized in 10 chemical steps from 2-hydroxy-5-nitropyridine and Boc-d-alanine. N-Alkylation of nor-p-PVP-MEMA with [11C]methyl iodide afforded [11C]p-PVP-MEMA (>98% radiochemically pure, specific activity of 86.4 GBq μmol–1) in 2% (non-decay corrected and non-optimized) radiochemical yield, in 34 min (including HPLC purification and formulation). Preliminary positron emission tomography (PET) results obtained in a Papio hamadryas baboon showed that [11C]p-PVP-MEMA is not a suitable PET-radioligand.
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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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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 different / isomeric ratios on the preparation of different Tc-labeled pharmaceutical kits. A set of measurements with , eluted from a standard99Mo/ generator, was performed, and results on both radiochemical purity and stability studies (following the standard quality control procedures) are reported for a set of widely used pharmaceuticals (i.e., -Sestamibi, -ECD, -MAG3, -DTPA, -MDP, -HMDP, -nanocolloids, and -DMSA). These pharmaceuticals have been all reconstituted with either the first [O4]−eluate obtained from a99Mo/ generator (coming from two different companies) or eluates after 24, 36, 48, and 72 hours from last elution. Results show that the radiochemical purity and stability of these radiopharmaceuticals were not affected up to the value of 11.84 for the / ratio.
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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 protocol, which is based on a reactive transfer of the iron cation, and more suited to the use of microchannels and very low contact times. This study already demonstrate the high potential of microfluidic technology to improve analytical operations on D&D samples. This method will further be validated with radioactive samples.
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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 on their chemical speciation but also on the background concentration of other stable nuclides and their behaviour in the natural environment. The safety assessment of the repository is thus a complex multidisciplinary problem requiring knowledge in chemical thermodynamics, structural chemistry, fluid dynamics, geo- and radiochemistry. Broad aspects of radionuclide thermodynamics and geochemistry are investigated in state-of-the-art radiochemical laboratories at the Paul Scherrer Institute. The research conducted over the last 30 years has resulted in a fundamental understanding of the radionuclides release, retention and transport mechanism in the repository system.
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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 shown an average radiochemical purity of 95 %. Biodistribution of the products was assessed by dissection in mice and in rabbits, and did not show any statistical difference when compared to Cardiolite®. In the synthesis of [Cu(MIBI)4]BF4 a new procedure was introduced for the synthesis of N-(2-methyl-propenyl)-formamide, with the use of microwave radiation as heat source. This modification reduced the reaction time to 25 seconds, while maintaining a yield of 68%.
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Dissertations / Theses on the topic "Radiochemical laboratories"

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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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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. The questions were grouped into the following seven Topic Elements: Licensing and Registration; Radiation Safety Administration; Personal and Area Monitoring; Dose Limit Compliance; Documentation/Records; RSO/RSC Qualifications and Duties; and Facilities. A novel feature was the allocation of "weighting factors" to individual questions and Elements. The computer program facilitated analysis of data and provided output in spreadsheet and graphical form. .The on-site physical audits were conducted using the project check-list, and were supplemented by discussions with the client's representative. The results showed significant variation between sites with overall compliance scores ranging from 37% to 94%. The reasons for this large variation stem from differences in local management regime; the appointment of an RSO at one site; variation in the extent of adoption of relevant codes of practice; and legislative weaknesses. Further analysis of the data presented legal, advisory and combined scores for each Element for each site; and variations over time. The graphic displays of the results were appreciated by client management. The formula developed to predict risk, based on the physical parameters alone, showed little relationship to the total audit scores. Statistical analysis of the two data groups by correlation coefficient confirmed this general finding. Development of the formula however served to indicate deficiencies in the Question Set, and the importance of human factors in achieving a high degree of safety.
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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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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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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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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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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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Teknik Makmal Radioisotop. Malaysia: Dewan Bahasa dan Pustaka, Malaysia, 1993.

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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"

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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"

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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, and industrial radiation applications. In preparation for decommissioning, a comprehensive environmental assessment was successfully completed [1] and the Canadian Nuclear Safety Commission issued a six-year decommissioning licence for WL starting in 2003 — the first decommissioning licence issued for a Nuclear Research and Test Establishment in Canada. This paper describes the progress in this first six-year licence period. A significant development in 2006 was the establishment of the Nuclear Legacy Liabilities Program (NLLP), by the Government of Canada, to safely and cost effectively reduce, and eventually eliminate the nuclear legacy liabilities and associated risks, using sound waste management and environmental principles. The NLLP endorsed an accelerated approach to WL Decommissioning, which meant advancing the full decommissioning of buildings and facilities that had originally been planned to be decontaminated and prepared for storage-with-surveillance. As well the NLLP endorsed the construction of enabling facilities — facilities that employ modern waste handling and storage technology on a scale needed for full decommissioning of the large radiochemical laboratories and other nuclear facilities. The decommissioning work and the design and construction of enabling facilities are fully underway. Several redundant non-nuclear buildings have been removed and redundant nuclear facilities are being decontaminated and prepared for demolition. Along with decommissioning of redundant structures, site utilities are being decommissioned and reconfigured to reduce site operating costs. New waste handling and waste clearance facilities have been commissioned and a large shielded modular above ground storage (SMAGS) structure is in final design in preparation for construction in 2010. The eventual goal is full decommissioning of all facilities and infrastructure and removal of stored wastes from the site.
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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 energy threshold below which it fails to register an event. The detector response is rarely uniform over the window area. The detector is connected to a ratemeter. The design of a ratemeter and the way it is set up will have a large influence on how easy the user finds it to classify correctly materials close to the exempt limit. (2)Calibration of the equipment. There is only a limited set of surface contamination sources available. Prediction of the response to other nuclides can be complicated. (3)Determination of the fingerprint. For many practical situations, the potential contaminant is a mixture of nuclides emitting a mixture of alpha, beta, gamma and X radiation. Any detector will have a response which depends on the radiation type and energy. Frequently, the response to the fingerprint of the most operationally robust and convenient detectors will be dominated by only a small fraction of the total activity present. It is thus vital that that fraction is well established and any area zoned so that the fraction remains reasonably stable. (4)The influence of natural activity in materials and of gamma radiation from elsewhere. Many building materials have levels of natural activity in the Bq/g region. These often vary significantly from sample to sample and area to area, particularly where buildings and equipment have been extended or modified. (5)Surface condition. For short range emissions such as alpha particles and low energy betas, the range for detection in air is a few mm. Any material covering the activity, such as paint or grease, will reduce the emission rate.
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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 building had been used to process uranium derived from uranium ore concentrate but had also processed a limited quantity of recycled uranium. The major non-uranic contaminant was Tc-99. The aim was to be able to identify any areas where the bulk activity exceeded 0.4 Bq/g Tc-99 as this would preclude the demolition rubble being sent to the local disposal facility. The problems associated with this project were the presence of significant uranium contamination, the realisation that both the Tc-99 and the uranium had diffused into the brickwork to a significant depth and the relatively low beta energy of Tc-99. The uranium was accompanied by Pa-234m, an energetic beta emitter. The concentration/depth profile was determined for several areas on the plant for Tc-99 and for uranium. The radiochemical analysis was performed locally but the performance of the local laboratory was checked during the initial investigation by splitting samples three ways and having confirmation analyses performed by 2 other laboratories. The results showed surprisingly consistent concentration gradients for Tc-99 and for uranium across the samples. Using that information, the instrument response was calculated for Tc-99 using the observed diffusion gradient and averaged through the full 225 mm of brick wall, as agreed by the regulator. The Tc-99 and uranium contributions to the detector signal were separated using a simple absorber, which essentially eliminated the Tc-99 count rate and reduced the uranium contribution only marginally. The outcome of the project was that it was possible to demonstrate that the complete building met the criterion for acceptance at the local waste facility.
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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 buildings, radioactive waste storage facilities, and contaminated lands at several sites located across eastern Canada from Quebec to Manitoba. The largest site, Chalk River Laboratories (CRL) in Ontario, will continue as an operational nuclear site for the foreseeable future. Planning and delivery of the Program is managed by the Liability Management Unit (LMU), a group that was formed within AECL for the purpose. The composition and progress of the NLLP has been reported in recent conferences [1, 2]. The NLLP comprises a number of interlinked decommissioning, waste management and environmental restoration activities that are being executed at different sites, and by various technical groups as suppliers to the LMU. Many lessons about planning and executing such a large, diverse Program have been learned in planning the initial five-year “start-up” phase (which will conclude 2011 March), in planning the five-year second phase (which is currently being finalized), and in planning individual and interacting activities within the Program. The activities to be undertaken in the start-up phase were planned by a small group of AECL technical experts using the currently available information on the liabilities. Progress in executing the Program was slower than anticipated due to less than ideal alignment between some planned technical solutions and the actual requirements, as well as the limited available resources of the suppliers to execute the work. Several internal and external reviews of the Program during the start-up phase examined progress and identified several improvements to planning. These improvements included strengthening communications among the groups within the Program, conducting more detailed advance planning of the interlinked activities, and being cautious about making detailed commitments for activities for which major decisions had yet to be made. The second phase was planned using a dedicated core team, and involved much more involvement of the suppliers to ensure feasibility of the proposed program of work and more detailed specification of the required resources. Priorities for executing the diverse activities in the Program were originally set using criteria based on the risks that the liabilities presented to health and safety, to the environment and to AECL’s ability to meet its obligations as the owner-operator of licensed nuclear sites. The LMU later recognized that the decision criteria should also explicitly include the value gained in reducing the risks and liabilities for expended funds. Greater consideration should be given to mitigating risks to the execution of the Program that might materialize. In addition, licensing strategies and processes should be better-defined, and waste characterization methods and disposition pathways would have to be put in place, or clearly identified, to deal with the wastes the Program would generate before many of the planned activities could be initiated. The NLLP has developed several processes to assist in the detailed planning of the numerous projects and activities. These include developing a more formal procedure for setting priorities of the different parts of the Program, preparing an Integrated Waste Plan to identify the optimal suite of support facilities to be constructed, the creation of a series of “pre-project initiation” procedures and documents to guide the development of well-founded projects, and the use of staged decision-making to incorporate more flexibility to adjust Program strategy and the details of implementation at planned decision points. Several Case Studies are outlined to illustrate examples of the application of these planning techniques.
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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 great deal of secondary liquid radwaste. Since the early 1970s attention has focused on the reduction of radwaste. Currently, optimized electrochemical and strippable coating methods are showing the greatest promise. 2. A low-waste dry decontamination technique based on application of readily strippable polymeric (protecting, decontaminating, immobilizing) coats has been developed and tested in the laboratory and wide scale. A low-waste dry decontamination technique based on application of readily strippable polymeric (protecting, decontaminating, immobilizing) coats has been developed and tested in the laboratory and wide scale. 3. VNIINM has developed a few electrochemical decontamination procedures and equipment surface decontamination. 4. One of VNIINM’s laboratory rooms which had been put to prolonged storage after an incidental alpha-radioactivity release was chosen for tests and demonstration. At first, the radioactivity levels inside the room on all the surfaces were measured. On outer surfaces, the alpha-activity was 1–15 α-particles/min.cm2, the gammaactivity varied from 720 to 2880 mkrem/s. The room was equipped with instrumentation and apparatures located in three chains of gloveboxes and hot cells for handling Pu-bearing materials. Continuous checks of the airborne radioactivity and the personnel residence time inside the room were performed. 5. Old Pu extraction facility (U-5) was decontaminated and decommissioning in VNIINM in 1999–2000. This facility is a system of interconnected working areas housing process equipment located in 4 floor building and includes more than 20 laboratories rooms, 2 “hot cells”, few sealed contaminated rooms and two extraction shaft. Industrial separation technologies have been tested on the facility for 20 years since 1947. The first USSR Pu was obtained here. Practically all rooms were contaminated with Pu, Cs, Sr etc. The experimental equipment of two hot cells (63 m2 each cell) control and service rooms was decontaminated and certified. The dissolution equipment, the metering tank compartment was decommissioned and removed. 16 laboratory rooms with a total area of 300 m2 were rehabilitated and certified. The amount of waste removed exceeded 12 500 kg. All rooms rehabilitated were certified and accepted by sanitary control service for further use. 6. At the time old contaminated room contains a non standard radiochemical equipment includes glove boxes is under decommissioning procedure. This project started at 2002.
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