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Academic literature on the topic 'Radionuclide library'

Author: Grafiati
Published: 10 December 2022
Last updated: 29 January 2023

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Journal articles on the topic "Radionuclide library"

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Smith, L. E., J. E. Ellis, A. E. Valsan, C. E. Aalseth, and H. S. Miley. "A coincidence signature library for multicoincidence radionuclide analysis systems." IEEE Transactions on Nuclear Science 51, no. 3 (June 2004): 1044–48. http://dx.doi.org/10.1109/tns.2004.829435.

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Van Wyk, Bronwin P., Francis Hasford, Nozipho E. Nyakale, M. Mboyo-Di-Tamba Vangu, Bertus Oelofse, and Hector M. Leboea. "Critical Appraisal of Radionuclide Calibrators and Gamma Cameras Prior to Lutetium-177 Internal Dosimetry at Two South African Hospitals." World Journal of Nuclear Medicine 21, no. 01 (March 2022): 044–51. http://dx.doi.org/10.1055/s-0042-1746173.

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Abstract Introduction The functionality of radionuclide dose calibrator and nuclear medicine imaging systems hasa direct effect on the accuracy and preciseness of internal dosimetry evaluations. Our study, therefore, aimed to critically appraise the radionuclide calibrators and gamma cameras prior to Lutetium-177 (177Lu) internal dosimetry in a developing country. Materials and Methods Two radionuclide calibrators' and three gamma cameras at two South African hospitals were critically appraised in preparation for internal dosimetry of 177Lu. The radionuclide calibrators' accuracy, linearity, and sample volume abilities were appraised. For the three gamma cameras, the uniformity, energy resolution, center of rotation, and collimator sensitivity were appraised. These appraisals were performed between the years 2014 and 2019. Results The radionuclide calibrators' constancy, accuracy, linearity, and sample volume were within ± 5%. We also integrated a 177Lu calibration factor into one radionuclide calibrator's library. The three gamma cameras' uniformity was within 2 to 5%, energy resolution within 11%, center of rotation within 2 mm, and the sensitivity recorded for all low energy high resolution collimator. Conclusion Our radionuclide calibrators passed the critical appraisal and may be confidently used for assaying 177Lu. All three cameras also passed critical appraisal and may be used to assess organ absorbed dose.
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Hartati, Sri, and Naomi Heriputranti. "STUDI LITERATUR TEKNIK PEMERIKSAAN RADIOLOGI VESIKA URINARIA PADA PASIEN ANAK DENGAN KLINIS VESICOURETERAL RELFLUX (VUR)." JRI (Jurnal Radiografer Indonesia) 4, no. 1 (May 10, 2021): 35–40. http://dx.doi.org/10.55451/jri.v4i1.83.

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Background: VUR (Vesicoureteral Reflux) is a condition in which urine flows back from the bladder to one or both ureters or sometimes to the kidneys. Several types of modalities are used to support this clinical examination. The modalities that can be used to support this examination include: Voiding Cystourethrography, DRCG (Direct Radionuclide Cystourethrography), ceVUS (Contrast Enhancement Voiding Urosonography), and MRI (Magnetic Resonance Imaging) Methods: This research is a type of research that is library research, a method of collecting library data or research where the object of research is explored through a variety of library information (books, proceedings, articles and scientific journals). Results: Radiological examination of the clinical bladder with VUR can be performed with various radiological modalities including Voiding Cystourethrography, Direct Radionuclide Cystography (DRCG), Magnetic Resonance Imaging (MRI), and Contrast Enhancement Urosonography (ceVUS). Each examination uses a contrast material that is adjusted to the modality used. Conclusions: From the various modalities that can be used, it is assessed from the level of effectiveness and efficiency as well as the minimum radiation exposure dose. The ceVUS technique is the most appropriate technique to describe VUR because it does not use ionizing radiation but this technique will be difficult to perform in certain conditions such as the pathological condition of the patient.
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Cruickshank, Dana R., and Leonard G. Luyt. "The development of organometallic OBOC peptide libraries and sequencing of N-terminal rhenium(I) tricarbonyl-containing peptides utilizing MALDI tandem mass spectrometry." Canadian Journal of Chemistry 93, no. 2 (February 2015): 234–43. http://dx.doi.org/10.1139/cjc-2014-0259.

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The development of peptide-based imaging agents through screening of large peptide libraries is hindered by the additional requirement of a radionuclide−chelator complex that can negatively affect the binding properties of the peptide. Herein, we report N-terminal rhenium(I)tricarbonyl OBOC (one-bead, one-compound) peptide libraries for use in the direct screening of potential imaging agents. The rhenium(I) tricarbonyl is incorporated directly in the library as an imaging entity surrogate to account for the presence of a technetium-99m radionuclide chelate. The identification of unknown organometallic peptides on single beads is successfully accomplished through MALDI tandem mass spectrometry, preceded by a systematic investigation of the effects of a variety of N-terminal rhenium(I) tricarbonyl chelates on peptide fragmentation patterns.
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Lagari, Pola Lydia, Styliani Pantopoulou, Miltos Alamaniotis, and Lefteri H. Tsoukalas. "Development of a Gamma-Ray Radionuclide Library for the Identification of Gamma Spectra." Nuclear Technology 207, no. 8 (January 28, 2021): 1270–79. http://dx.doi.org/10.1080/00295450.2020.1816743.

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Breidokaite, Simona, and Gediminas Stankunas. "Activities in Divertor Reflector and Linear Plates Using WCLL and HCPB Breeding Blanket Concepts." Energies 14, no. 24 (December 9, 2021): 8305. http://dx.doi.org/10.3390/en14248305.

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In fusion devices, such as European Demonstration Fusion Power Reactor (EU DEMO), primary neutrons can cause material activation due to the interaction between the source particles and the targeting material. Subsequently, the reactor’s inner components become activated. For safety and safe performance purposes, it is necessary to evaluate neutron-induced activities. Activities results from divertor reflector and liner plates are presented in this work. The purpose of liner shielding plates is to protect the vacuum vessel and magnet coils from neutrons. As for reflector plates, the function is to shield the cooling components under plasma-facing components from alpha particles, thermal effects, and impurities. Plates are made of Eurofer with a 3 mm layer of tungsten, while the water is used for cooling purposes. The calculations were performed using two EU DEMO MCNP (Monte Carlo N-Particles) models with different breeding blanket configurations: helium-cooled pebble bed (HCPB) and water-cooled lithium lead (WCLL). The TENDL–2017 nuclear data library has been used for activation reactions cross-sections and nuclear reactions. Activation calculations were performed using the FISPACT-II code at the end of irradiation for cooling times of 0 s–1000 years. Radionuclide analysis of divertor liner and reflector plates is also presented in this paper. The main radionuclides, with at least 1% contribution to the total value of activation characteristics, were identified for the previously mentioned cooling times.
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Mitran, Bogdan, Vladimir Tolmachev, and Anna Orlova. "Radiolabeled GRPR Antagonists for Imaging of Disseminated Prostate Cancer - Influence of Labeling Chemistry on Targeting Properties." Current Medicinal Chemistry 27, no. 41 (December 8, 2020): 7090–111. http://dx.doi.org/10.2174/0929867327666200312114902.

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Background: Radionuclide molecular imaging of Gastrin-Releasing Peptide Receptor (GRPR) expression promises unparalleled opportunities for visualizing subtle prostate tumors, which due to small size, adjacent benign tissue, or a challenging location would otherwise remain undetected by conventional imaging. Achieving high imaging contrast is essential for this purpose and the molecular design of any probe for molecular imaging of prostate cancer should be aimed at obtaining as high tumor-to-organ ratios as possible. Objective: This short review summarizes the key imaging modalities currently used in prostate cancer, with a special focus on radionuclide molecular imaging. Emphasis is laid mainly on the issue of radiometals labeling chemistry and its influence on the targeting properties and biodistribution of radiolabeled GRPR antagonists for imaging of disseminated prostate cancer. Methods: A comprehensive literature search of the PubMed/MEDLINE, and Scopus library databases was conducted to find relevant articles. Results: The combination of radionuclide, chelator and required labeling chemistry was shown to have a significant influence on the stability, binding affinity and internalization rate, off-target interaction with normal tissues and blood proteins, interaction with enzymes, activity uptake and retention in excretory organs and activity uptake in tumors of radiolabeled bombesin antagonistic analogues. Conclusion: Labeling chemistry has a very strong impact on the biodistribution profile of GRPRtargeting peptide based imaging probes and needs to be considered when designing a targeting probe for high contrast molecular imaging. Taking into account the complexity of in vivo interactions, it is not currently possible to accurately predict the optimal labeling approach. Therefore, a detailed in vivo characterization and optimization is essential for the rational design of imaging agents.
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Hamid, Mohamad Amin Bin, Hoe Guan Beh, Yusuff Afeez Oluwatobi, Xiao Yan Chew, and Saba Ayub. "Generation of Proton- and Alpha-Induced Nuclear Cross-Section Data via Random Forest Algorithm: Production of Radionuclide 111In." Applied Sciences 11, no. 15 (July 29, 2021): 6969. http://dx.doi.org/10.3390/app11156969.

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We investigated the generation of proton- and alpha-induced nuclear cross-section data in the production of Indium-111 (111In) for application in nuclear medicine. Here, we are interested in three reaction channels, which are 109Ag (α, 2n), 111Cd (p, n) and 112Cd (p, 2n), in the production of 111In. A random forest algorithm was used to generate nuclear cross-section data by using an experimental nuclear cross-section from the Experimental Nuclear Reaction Data (EXFOR) database as input. Hence, reasonably accurate regression curves of nuclear cross-section data could be produced with the evaluated nuclear data library ENDF/B-VII.0 set as the benchmark.
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Zelchan, R. V., A. A. Medvedeva, O. D. Bragina, A. N. Ribina, A. I. Ryabova, V. I. Chernov, and E. L. Choynzonov. "Modern methods for radionuclide diagnosis of tumors and non-tumor pathologies of the brain." Bulletin of Siberian Medicine 20, no. 4 (January 3, 2022): 131–42. http://dx.doi.org/10.20538/1682-0363-2021-4-131-142.

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The review analyzes the global experience in the application of nuclear medicine techniques for diagnosis of tumors and non-tumor pathologies of the brain. The main groups of radiopharmaceuticals currently used for imaging of malignant brain tumors and diagnosis of cognitive impairments and neurotransmitter system disturbances by means of single-photon emission computed tomography and positron emission tomography are described.Modern approaches to the application of methods for radionuclide diagnosis in neuro-oncology and neurology are compared, and the main trends in production of new, more specific radiopharmaceuticals for visualizing brain tumors of various degrees of malignancy and diagnosing non-tumor pathologies of the brain are described. The review discusses the advantages and disadvantages of currently used techniques and radiopharmaceuticals for imaging of central nervous system disorders, depending on the clinical situation and specific diagnostic tasks.In addition, the review presents consolidated recommendations of the leading scientific schools in neuro-oncology on the use of nuclear medicine techniques in patients with brain tumors at the stages of treatment and follow-up. The presented article examines the experience of domestic scientific schools in the development of radiopharmaceuticals for neuro-oncology. The features of the development and use of new radiopharmaceuticals in patients with brain tumors and neurodegenerative diseases are highlighted. The review is based on the analysis of literature included in the Scopus, Web of Science, MedLine, The Cochrane Library, EMBASE, Global Health, and RSCI databases.
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Liang, Steven H., and Neil Vasdev. "Total Radiosynthesis: Thinking Outside ‘the Box'." Australian Journal of Chemistry 68, no. 9 (2015): 1319. http://dx.doi.org/10.1071/ch15406.

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The logic of total synthesis transformed a stagnant state of chemistry when there was a paucity of methods and reagents to synthesize pharmaceuticals. Molecular imaging by positron emission tomography (PET) is now experiencing a renaissance in the way radiopharmaceuticals are synthesized; however, a paradigm shift is desperately needed in the radiotracer discovery pipeline to accelerate drug development. As with most drugs, most radiotracers also fail, therefore expeditious evaluation of tracers in preclinical models before optimization or derivatization of the lead molecules is necessary. Furthermore the exact position of the 11C and 18F radionuclide in tracers is often critical for metabolic considerations, and flexible methodologies to introduce radionuclides are needed. A challenge in PET radiochemistry is the limited choice of labelled building blocks available with carbon-11 (11C; half-life ~20 min) and fluorine-18 (18F; half-life ~2 h). In fact, most drugs cannot be labelled with 11C or 18F owing to a lack of efficient and diverse radiosynthetic methods. Routine radiopharmaceutical production generally relies on the incorporation of the isotope at the last or penultimate step of synthesis. Such reactions are conducted within the constraints of an automated synthesis unit (‘box’), which has further stifled the exploration of multistep reactions with short-lived radionuclides. Radiopharmaceutical synthesis can be transformed by considering logic of total synthesis to develop novel approaches for 11C- and 18F-radiolabelling complex molecules via retrosynthetic analysis and multistep reactions. As a result of such exploration, new methods, reagents, and radiopharmaceuticals for in vivo imaging studies are discovered and are critical to work towards our ultimate, albeit impossible goal – a concept we term as total radiosynthesis – to radiolabel virtually any molecule. In this account, we show how multistep radiochemical reactions have impacted our radiochemistry program, with prominent examples from others, focusing on impact towards human imaging studies. As the goal of total synthesis is to be concise, we strive to simplify the syntheses of radiopharmaceuticals. New clinically useful strategies, including [11C]CO2 fixation, which has enabled library radiosynthesis, as well as radiofluorination of non-activated arenes via iodonium ylides are highlighted. We also showcase state-of-the-art automation technologies, including microfluidic flow chemistry for radiopharmaceutical production.
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Book chapters on the topic "Radionuclide library"

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Chiroşca, Gianina, Maria-Emanuela Mihailov, Cornel Liviu Ţugulan, and Alecsandru Vladimir Chiroşca. "Radionuclides Assessment for the Romanian Black Sea Shelf." In Coastal Research Library, 221–32. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-57577-3_13.

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Pătraşcu, Vasile, Romul Mircea Mărgineanu, Ana-Maria Blebea-Apostu, Dănuţ I. Diaconeasa, and Mariana Claudia Gomoiu. "Gamma-Ray Radionuclides in Sediments from Mamaia Beach on the Romanian Black Sea Coast." In Coastal Research Library, 233–39. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-57577-3_14.

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Mirzoyeva, Natalya Yu, Viktor N. Egorov, and Sergey B. Gulin. "Radionuclides 137Cs and 90Sr in Components of the Black Sea Ecosystems: Contemporary Status and Prognosis." In Coastal Research Library, 275–94. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-57577-3_17.

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Ahmad Baba, Waseem, Pankaj Kumar, Jitendra Kumar Pattanaik, and Neloy Khare. "Dronning Maud Land (Antarctica) and Reconstruction of Its Glacial History with Cosmogenic Radionuclides." In Earth and Environmental Sciences Library, 73–95. Cham: Springer International Publishing, 2022. http://dx.doi.org/10.1007/978-3-030-87078-2_5.

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Conference papers on the topic "Radionuclide library"

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Smith, L. E., J. E. Ellis, A. E. Valsan, C. E. Aalseth, and H. S. Miley. "A coincidence signature library for multicoincidence radionuclide analysis systems." In 2003 IEEE Nuclear Science Symposium. Conference Record (IEEE Cat. No.03CH37515). IEEE, 2003. http://dx.doi.org/10.1109/nssmic.2003.1351805.

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Zhanyang, Liu, Shang-Guan Zhihong, Zhao Feng, and Zhang Qiming. "Radiation Evaluation System for Radiation Releasing Environment of Nuclear Power Plant Based on Domain-Driven Design." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67358.

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In order to meet the sustainable development demand for energy, developing nuclear power actively has become an important means for the country to improve energy supply pattern and change the energy structure. The normal operation of the nuclear power station brings enormous economic and social benefits, but also accompanied by airborne radioactive effluent and liquid radioactive effluent discharge. In order to estimate the effect of radioactive effluent release during the normal operation of nuclear power plant on radiation dose of the environment and the public, in this article, domain knowledge analysis and domain knowledge modeling will be carried out on the theoretical model of evaluation calculation. Then, combined with actual business logic, advanced software development techniques and mature design ideas will be adopted to realize the field component of radiation dose evaluation in nuclear power plant. Establish the corresponding domain component library, and thus to achieve the building of radiation dose evaluation software system. The main content of this paper will be divided into two parts to elaborate, First part is the domain knowledge analysis and modeling of radiation dose evaluation model of nuclear power plant radiation environment, the other part is based on radiation dose evaluation component library software system researching, designing and achieving. In the domain knowledge analysis of the radiation dose estimation model, due to the mutual independence of the airborne radioactive effluent and the liquid radioactive effluent in the evaluation mode, this paper will analyze and model the domain knowledge separately. The airborne radioactive effluent is divided into four parts: air immersion external exposure, ground deposition external irradiation, ingestion inhalation and inhalation in air. The main contents of the analysis include atmospheric diffusion suitable for environmental characteristics of nuclear power plant site, ground deposition factors, food chain data, and lifestyle habits around the site. In the field of knowledge analysis of liquid radioactive effluent, there are four ways: external marine activity irradiation, coastal deposit sediment irradiation, and irradiation of seafood. The analysis mainly includes dilution and diffusion conditions in the surrounding sea area of nuclear power plant, the radionuclide in the seawater of the receiving water body, the shore sedimentation factor and the transfer model of the radionuclide in the seafood. Based on the detailed analysis and research on the radiation dose evaluation of nuclear power plant, and the designing of the domain model by adopting mature software design idea and the advanced software development technology, the domain component of the radiation dose evaluation field is realized, and build the corresponding domain component library. This can provide a reliable and usable domain component library for the radiation dose evaluation of each nuclear power plant, improve the maintainability of the radiation dose evaluation system of the nuclear power plant, the comprehensibility of business logic, and the reusability of the evaluate module, so as to meet the calculation demands on radiation dose effects of public caused by radionuclide release in normal operation of the nuclear power plant.
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Breidokaitė, Simona, Andrius Tidikas, and Gediminas Stankūnas. "Evaluation of Decay Dose Rates for European DEMO Vacuum Vessel Structure." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16465.

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Abstract Four types of breeder blanket modules are in consideration for European DEMO pre-conceptual design phase specified by European Fusion Roadmap. In this study two designs (Helium Cooled Pebble Bed (HCPB) and Water-Cooled Lithium Lead (WCLL)) were investigated in terms of their influence on vacuum vessel (VV) nuclear decay dose rates. In both cases, the same vacuum vessel structure is examined. VV model consists of two shells, interspace and thermal shield. The inner shell and outer shell of vacuum vessel are made of Stainless Steel 316L(N)-IG. The interspace layer is made of water for cooling and shielding purposes. Stainless steel constitutes around 60% of all material in vacuum vessel and water makes up the rest. The model of fusion reactor has been developed in the frame of EUROfusion’s Power Plant Physics and Technology (PPPT) programme. This paper presents information about calculation results of the dose rates caused by the neutron irradiation for the vacuum vessel structural elements in DEMO fusion power reactor. In order to perform dose rate calculations, neutron energy spectra are required for different VV segments. Those calculations were performed with MCNP6 code and Joint Evaluated Fission and Fusion (JEFF) 3.2 nuclear data library. Dose rates were calculated with FISPACT-2010 and European Activation File (EAF) 2010 nuclear data library. The dose rates were calculated for European DEMO nuclear fusion reaction after its 20 calendar years lasting operation. Cooling period was considered spanning for up to 1000 years. In addition, radionuclides with contribution of at least 1% to the total value of dose rate were identified. Highest dose rates are attributed to 56Mn radionuclide immediately after the operation until around one day.60Co is the most dominant isotope during intermediate and long cooling periods. Differences in Interspace layer occur due to 16N isotope.
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Shimada, Taro, Soichiro Ohshima, and Takenori Sukegawa. "Development of Safety Assessment Code for Decommissioning of Nuclear Facilities (DecDose)." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75123.

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A safety assessment code, DecDose, for decommissioning of nuclear facilities has been developed, based on the experiences of the decommissioning project of Japan Power Demonstration Reactor (JPDR) at Japan Atomic Energy Research Institute (now Japan Atomic Energy Agency). DecDose evaluates the annual exposure dose of the public and workers according to the progress of decommissioning of the plant, and also evaluates the public dose at accidental situations including fire and explosion. The public dose at normal situations during decommissioning is evaluated from the amount of radionuclides discharged from the plant to the atmosphere and the ocean. The amounts of radionuclides discharged depend on which and how activated and/or contaminated components and structures are dismantled. The amount is predicted by using the radioactive inventory given by the plant. The filtration efficiency of the ventilation system and decontamination factors of the liquid waste treatment system of the plant are also considered. Both of the internal dose caused by inhalation and ingestion of agricultural crops and seafood, and the external dose by radioactive aerosols airborne and radioactive deposition at soil surfaces are calculated for all of possible pathways. Also included in the external dose are direct radiation and skyshine radiation from waste containers which are packed and temporarily stored in the in-site building. For external dose of workers, the radiation dose rate from dismantling contaminated components and structures is calculated using the dose rate library which was previously evaluated by a point kernel shielding code. In this condition, radiation sources are regarded to be consisted of two parts; one is a dismantling object of interest, and the other is the sum of surrounding objects. Difference in job type or position is taken into account; workers for cutting are situated closer to a dismantling component, other workers help them at some distance, and the supervisor watches their activities from away. For worker’s internal dose, the radionuclide concentrations in air for individual radionuclides are calculated from a dismantling condition, e.g. cutting speed, cutting length of the dismantling component and exhaust velocity. A calculation model for working time on dismantling was developed using more segmented WBS (work breakdown structure). DecDose was partially verified by comparison with measured the external dose of workers during JPDR Decommissioning Project. The DecDose is expected to contribute to utilities in formulating rational dismantling plans and to the safety authority in estimating conservativeness in safety assessment of licensing application or risk-based regulatory criteria.
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Pavelescu, Alexandru Octavian, Dan Gabriel Cepraga, Konstantina Voukelatou, and Renato Tinti. "Estimation of Clearance Potential Index and Hazard Factors of CANDU Fuel Bundle and Its Validation Based on the Measurements of Radioisotopes Inventories From Pickering Reactor Fuel." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7086.

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This paper is related to the clearance potential levels, ingestion and inhalation hazard factors of the spent nuclear fuel and radioactive wastes. This study required a complex activity that consisted of more steps such as: the acquisition, setting up, validation and application of procedures, codes and libraries. The paper reflects the validation stage of this study. Its objective was to compare the measured inventories of selected actinide and fission products radionuclides in an element from the Pickering CANDU reactor with the inventories predicted using a recent version of the SCALE 5\ORIGEN-ARP code coupled with the time dependent cross sections library for the CANDU 28 reactor (produced by the sequence SCALE4.4a\SAS2H and SCALE4.4a\ORIGEN-S). In this way, the procedures, the codes and the libraries for the characterization of radioactive material in terms of radioactive inventories, clearance, and biological hazard factors could be qualified and validated, in support of the safety management of the radioactive wastes.
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