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Journal articles on the topic 'Radiochemical laboratories'

Author: Grafiati

Published: 4 June 2021

Last updated: 25 July 2024

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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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2

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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3

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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4

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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5

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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8

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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9

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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10

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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11

Otero-Pazos, Alberto, Alfonso Calleja-Garcia, Maria Fernandez-Ibanez, Benigno Rodriguez-Gomez, Andres Pinon-Pazos, and Jose Calvo-Rolle. "Determination of Sr-90 in milk samples from the study of statistical results." Nuclear Technology and Radiation Protection 32, no. 2 (2017): 185–91. http://dx.doi.org/10.2298/ntrp1702185o.

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The determination of 90Sr in milk samples is the main objective of radiation monitoring laboratories because of its environmental importance. In this paper the concentration of activity of 39 milk samples was obtained through radiochemical separation based on selective retention of Sr in a cationic resin (Dowex 50WX8, 50-100 mesh) and subsequent determination by a low-level proportional gas counter. The results were checked by performing the measurement of the Sr concentration by using the flame atomic absorption spectroscopy technique, to finally obtain the mass of 90Sr. From the data obtaine

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12

Vieth, Reinhold, Sarah E. Ledermann, Sang Whay Kooh, and J. Williamson Balfe. "Losses of Calcitriol to Peritoneal Dialysis Bags and Tubing." Peritoneal Dialysis International: Journal of the International Society for Peritoneal Dialysis 9, no. 4 (October 1989): 277–80. http://dx.doi.org/10.1177/089686088900900409.

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Peritoneal dialysis provides a convenient means of administering calcitriol. We investigated in vitro the efficiency with which this approach would deliver the drug to patients. We used an injectable preparation of calcitriol, Calcijex® (Abbott Laboratories, Montreal, Quebec, Canada), which we radiolabelled by adding radioactive 1,25 dihydroxyvitamin D3 to it. The preparation was injected into dialysis bags and drained through appropriate tubing to monitor delivery of the radiolabelled calcitriol. By 2 h after injecting calcitriol into dialysis bags, 50% of the dose was left in the fluid, by 2

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13

Kochnov, Oleg Yu, Valery I. Stepanov, Denis A. Pakholik, Valery V. Kolesov, and Evgeny V. Nikulin. "Experience in the production of 99Mo from low enriched uranium at the VVR-ts research nuclear facility." Nuclear Energy and Technology 10, no. 1 (March 26, 2024): 15–18. http://dx.doi.org/10.3897/nucet.10.122284.

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The key industrial method for producing 99Mo is production of the radionuclide as one of the 235U fission fragments. 235U is irradiated with neutrons in a nuclear reactor (both heterogeneous and homogeneous nuclear reactors can be used) and then processed in radiochemical laboratories, where 99Mo is chemically extracted from fission products. Both highly enriched uranium (HEU) and low enriched uranium (LEU) can be used to produce 99Mo by the fragmentation method. To date, almost all world producers, with the exception of Russia, are either in the final stages of transferring production from hi

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14

Camacho, Ximena, Agustina Banchero, Maria Fernanda García, Marcelo Fernández, Natalia Oddone, María Moreno, Cecilia Guillermo, Juan Pablo Gambini, Pablo Cabral, and Eloísa Riva. "99m. Tc-Rituximab as Radiotracer For Molecular Imaging In Non Hodgkin Lymphoma." Blood 122, no. 21 (November 15, 2013): 3026. http://dx.doi.org/10.1182/blood.v122.21.3026.3026.

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Abstract Introduction Non-Hodgkin lymphoma (NHL) is the most common hematologic malignancy and the fifth leading cause of cancer death in the world; over 90% are B cell lymphomas and express CD-20 surface antigen [1]. CD-20 antigen is a transmembrane protein of 33-37 kDa protein located on the surface of pre-B and mature lymphocytes B [2, 3]. It is expressed in 90% of B-cell NHL [4]. Anti-CD20 antibody (Rituximab®), a specific chimeric monoclonal antibody directed against CD20 on B lymphocytes and the first monoclonal antibody approved for the treatment of CD20+ NHL. The development of new age

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15

LaRosa, J. J., E. L. Cooper, A. Ghods-Esphahani, V. Jansta, M. Makarewicz, S. Shawky, and N. Vajda. "Radiochemical methods used by the IAEA's laboratories at Seibersdorf for the determination of 90Sr, 144Ce and Pu radionuclides in environmental samples collected for the International Chernobyl project." Journal of Environmental Radioactivity 17, no. 2-3 (January 1992): 183–209. http://dx.doi.org/10.1016/0265-931x(92)90025-o.

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16

Bennett, J., C. J. Webb, and S. Isch. "Preparing a laboratory for radioanalytical emergency response." Proceedings in Radiochemistry 1, no. 1 (September 1, 2011): 201–7. http://dx.doi.org/10.1524/rcpr.2011.0036.

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AbstractAs the state of the nation's ability to respond to a radiological event is examined, it has become apparent that both capacity and capability are lacking. Department of Homeland Security National Planning Scenario #11 is designed to address the planning activities for the response to an attack using radiological dispersal devices. The scenario details show that the cleanup activity will take several years, and that there will be between 360000 and 1000000 environmental samples in the first year. Based on existing capacity and capabilities it would take four to six years to analyze the

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17

Robinson, Sharon M., Dennis E. Benker, Emory D. Collins, Julie G. Ezold, Jon R. Garrison, and Susan L. Hogle. "Production of Cf-252 and other transplutonium isotopes at Oak Ridge National Laboratory." Radiochimica Acta 108, no. 9 (September 25, 2020): 737–46. http://dx.doi.org/10.1515/ract-2020-0008.

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AbstractIn 1957 Glenn T. Seaborg conceived and advocated for the construction of the High Flux Isotope Reactor (HFIR) and the Transuranium Processing Plant (since then renamed the Radiochemical Engineering Development Center, or REDC) at Oak Ridge National Laboratory. Heavily shielded hot cells, glove boxes, and laboratories allow recovery of transuranium elements produced in substantial quantities. Seaborg’s vision of HFIR and REDC producing milligram quantities of berkelium, californium, and einsteinium has been fulfilled beginning in 1966 through May 2019 with 78 production campaigns yieldi

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18

Pivovarov, A. A., E. A. Pivovarova, and V. E. Kurganov. "About development of control levels of specific total alpha-activity in water samples for a number of sources of the centralized economic and drinking water supply in the Republic of Khakassia." Radiatsionnaya Gygiena = Radiation Hygiene 12, no. 2(св) (September 23, 2019): 121–28. http://dx.doi.org/10.21514/1998-426x-2019-12-2s-121-128.

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The aim of the work is to develop control levels of specific total alpha-activity of water samples for a number of sources of centralized drinking water supply in the Republic of Khakassia on the basis of the results of long-term laboratory studies. Materials and methods. The analysis is carried out on the basis of the results of laboratory studies of water sources of centralized drinking water supply of the population of the Republic of Khakassia, performed by accredited testing laboratories of institutions of the state sanitary and epidemiological service of the Republic for the period from

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19

Riva, Eloísa, Victoria Calzada, Eugenia Gutiérrez, Marcelo Fernández, Natalia Oddone, María Moreno, Juan Benech, José A. Chabalgoity, Atanasio Pandiella, and Pablo Cabral. "Development of 99mTcHYNIC-Tocilizumab as Imaging Agent In Multiple Myeloma." Blood 116, no. 21 (November 19, 2010): 4081. http://dx.doi.org/10.1182/blood.v116.21.4081.4081.

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Abstract Abstract 4081 Introduction: Multiple myeloma (MM) accounts for 10% of hematological malignancies and 1% of cancer. It represents the second most common hematologic malignancy. The disease is characterised by plasma cell infiltration of the bone marrow, osteolytic bone lesions and the presence of a monoclonal paraprotein in the serum or urine. Interleukin-6 (IL-6) is a key molecule in the pathogenesis of MM. Its secretion occurs from the tumoral plasma cell as well as from the microenvironment. This results in myeloma cell proliferation. Tocilizumab, a humanized anti IL-6 receptor mono

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20

Smith, Gary L., and Steven C. Marschman. "Nuclear Waste Analytical Round Robins 1-6 Summary Report." MRS Proceedings 333 (1993). http://dx.doi.org/10.1557/proc-333-461.

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ABSTRACTThe Materials Characterization Center (MCC) at Pacific Northwest Laboratory(a) conducts Nuclear Waste Analytical Round Robins on simulated waste glasses with and without radionuclides. The analytical round robins are used to provide analytical laboratories with a forum for improving the accuracy and precision of analytical techniques that will be used for characterizing nuclear waste glasses. Chemical analysis data on glass waste forms produced by the nuclear waste community may need to withstand legal challenges for waste material storage qualification and for licensing repositories.

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21

Leskinen, Anumaija, Eric Dorval, Emilie Baudat, Celine Gautier, Solveig Stordal, and Susanna Salminen-Paatero. "Intercomparison exercise on difficult to measure radionuclides in spent ion exchange resin." Journal of Radioanalytical and Nuclear Chemistry, December 10, 2022. http://dx.doi.org/10.1007/s10967-022-08687-2.

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AbstractA need for method validation in radiochemical analyses of decommissioning waste is a challenging task due to lack of commercial reference materials. Participation in an intercomparison exercise is one way for a laboratory to assess their performance and validate their analysis results. A three-year project within the Nordic Nuclear Safety Research (NKS) community was initiated in order to carry out intercomparison exercises on difficult to measure (DTM) radionuclides in real decommissioning waste. Both Nordic and Non-Nordic laboratories participated. This paper reports the results from

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22

Infantino, Angelo, Richard William Harbron, Renaud Mouret, Philippe Bertreix, Ana-Paula Bernardes, Luca Bruno, Marco Calviani, et al. "Radiological characterization for the disposal of a decommissioned LHC external beam dump at CERN." European Physical Journal Plus 138, no. 8 (August 8, 2023). http://dx.doi.org/10.1140/epjp/s13360-023-04319-0.

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AbstractDuring the last Long Shutdown, a scheduled maintenance period between physics runs, the two Large Hadron Collider (LHC) beam dumps were replaced with upgraded spares modules. It was then decided to conduct an in-house autopsy and a post-irradiation examination of the removed dumps to extract information essential for the 3rd LHC physics run and to aid the design of new generations of beam dumps able to cope with future upgrades of the LHC. The need for a postmortem analysis of the dump cores opened the opportunity to combine the autopsy with processes required for the disposal of the d

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23

Woidy, Patrick, and Oliver Meisenberg. "Production of sealed rod sources made from epoxy resin for the Saint-Petersburg brick phantom for the calibration of whole-body counters." Radiation and Environmental Biophysics, July 14, 2022. http://dx.doi.org/10.1007/s00411-022-00987-1.

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AbstractRod sources are a common tool for the calibration of whole-body counters in combination with the Saint-Petersburg brick phantom. Here, a method for the production of such sources in ordinary radiochemical laboratories is presented. The rod sources consist of a tubular capsule of rigid polyvinyl chloride with a radioactive filling of epoxy resin. The method allows the production of rod sources at material costs of about 1 € per rod source and of ten rod sources by one person per day. Quality-assurance measurements were performed regarding the spatial distribution of the activity within

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