Validation of an advanced analytical procedure applied to the measurement of environmental radioactivity.

Science.gov (United States)

Thanh, Tran Thien; Vuong, Le Quang; Ho, Phan Long; Chuong, Huynh Dinh; Nguyen, Vo Hoang; Tao, Chau Van

2018-04-01

In this work, an advanced analytical procedure was applied to calculate radioactivity in spiked water samples in a close geometry gamma spectroscopy. It included MCNP-CP code in order to calculate the coincidence summing correction factor (CSF). The CSF results were validated by a deterministic method using ETNA code for both p-type HPGe detectors. It showed that a good agreement for both codes. Finally, the validity of the developed procedure was confirmed by a proficiency test to calculate the activities of various radionuclides. The results of the radioactivity measurement with both detectors using the advanced analytical procedure were received the ''Accepted'' statuses following the proficiency test. Copyright © 2018 Elsevier Ltd. All rights reserved.

Radioactive and non-radioactive polychlorinated biphenyl (PCB) management at Hanford

International Nuclear Information System (INIS)

Leonard, W.W.; Gretzinger, R.F.; Cox, G.R.

1986-01-01

Conformance to all state and federal regulations is the goal of Rockwell in the management of both radioactive and non-radioactive PCB's at Hanford. A continuing effort is being made to locate, remove, and properly dispose of all PCB's. As improved methods of management are developed, consideration will be given to them for their adaptation into the Hanford Site PCB Management Plan

A literature review of methods of analysis of organic analytes in radioactive wastes with an emphasis on sources from the United Kingdom

International Nuclear Information System (INIS)

Clauss, S.A.; Bean, R.M.

1993-09-01

This report, compiled by Pacific Northwest Laboratory (PNL), examines literature originating through the United Kingdom (UK) nuclear industry relating to the analyses of organic constituents of radioactive waste. Additionally, secondary references from the UK and other counties, including the United States, have been reviewed. The purpose of this literature review was to find analytical methods that would apply to the mixed-waste matrices found at Hanford

Effects of non-radioactive material around radioactive material on PET image quality

International Nuclear Information System (INIS)

Toshimitsu, Shinya; Yamane, Azusa; Hirokawa, Yutaka; Kangai, Yoshiharu

2015-01-01

Subcutaneous fat is a non-radioactive material surrounding the radioactive material. We developed a phantom, and examined the effect of subcutaneous fat on PET image quality. We created a cylindrical non-radioactive mimic of subcutaneous fat, placed it around a cylindrical phantom in up to three layers with each layer having a thickness of 20 mm to reproduce the obesity caused by subcutaneous fat. In the cylindrical phantom, hot spheres and cold spheres were arranged. The radioactivity concentration ratio between the hot spheres and B.G. was 4:1. The radioactivity concentration of B.G. was changed as follows : 1.33, 2.65, 4.00, and 5.30 kBq/mL. 3D-PET image were collected during 10 minutes. When the thickness of the mimicked subcutaneous fat increased from 0 mm to 60 mm, noise equivalent count decreased by 58.9-60.9% at each radioactivity concentration. On the other hand, the percentage of background variability increased 2.2-5.2 times. Mimic subcutaneous fat did not decrease the percentage contrast of the hot spheres, and did not affect the cold spheres. Subcutaneous fat decreases the noise equivalent count and increases the percentage of background variability, which degrades PET image quality. (author)

Investigation of radioactive contamination at non-radioactive drains of the Tsuruga Nuclear Power Station

International Nuclear Information System (INIS)

Koide, Hiroaki; Imanaka, Tetsuji; Ebisawa, Toru; Kawano, Shinji; Kobayashi, Keiji.

1982-05-01

In April, 1981, it was disclosed that a drainage area at the Tsuruga Nuclear Power Station was so much contaminated with radioactivites. Although Ministry of International Trade and Industry (MITI) officially provided an explanation of a process that resulted in the contamination, many problems remain unsolved on account of insufficient and limited investigations. The authors collected mud samples from contaminated manholes and examined radioactivities in them through the measurement of #betta#- and #betta#-spectra. Chemical separation of the samples was carried out in order to obtain precise concentration of radioactive cesium. Results are as follows: i) the concentration of radioactivities does not show monotonous decrease along the stream line but an anomalous peak at downstream manholes, ii) at the manhole specified No. 6 located rather downstream, 137 Cs concentration is significantly high and the composition of radioactive nuclides is quite different from that in the other manholes, and iii) additional radioactive contamination was observed in other manholes of non-radioactive drains which would not be influenced by the accident explained by MITI. Our present work has provided much more data than by MITI and made it clear that the overall data cnnot be consistent with the simple MITI explanation; a single radioactive release accident caused the disclosed contamination. It is concluded that non-radioactive water drains at the Tsuruga Nuclear Power Station had been under continual contamination. (author)

Can the same principles be used for the management of radioactive and non-radioactive waste?

International Nuclear Information System (INIS)

Bengtsson, Gunnar.

1989-01-01

Non-radioactive waste has a much more complex composition than radioactive waste and appears in much larger quantities. The two types of waste have, however, some properties in common when it comes to their longterm impact on health and the environment. The occurrence in both of substances that may exist for generations and may cause cancer provides one example. Both types of waste also always occur together. It is therefore proposed that the same basic principles could be applied for the management of radioactive and non-radioactive waste. By doing so one may increase the efficiency of policy development, research and practical management. This is particurlarly importand for the very costly restoration of old disposal sites which have earlier been poorly managed. (author)

Revisit of analytical methods for the process and plant control analyses during reprocessing of fast reactor fuels

International Nuclear Information System (INIS)

Subba Rao, R.V.

2016-01-01

CORAL (COmpact facility for Reprocessing of Advanced fuels in Lead cell) is an experimental facility for demonstrating the reprocessing of irradiated fast reactor fuels discharged from the Fast Breeder Test Reactor (FBTR). The objective of the reprocessing plant is to achieve nuclear grade plutonium and uranium oxides with minimum process waste volumes. The process flow sheet for the reprocessing of spent Fast Reactor Fuel consists of Transport of spent fuel, Chopping, Dissolution, Feed conditioning, Solvent Extraction cycle, Partitioning Cycle and Re-conversion of Plutonium nitrate and uranium nitrate to respective oxides. The efficiency and performance of the plant to achieve desired objective depends on the analyses of various species in the different steps adopted during reprocessing of fuels. The analytical requirements in the plant can be broadly classified as 1. Process control Analyses (Analyses which effect the performance of the plant- PCA); 2. Plant control Analyses (Analyses which indicates efficiency of the plant-PLCA); 3. Nuclear Material Accounting samples (Analyses which has bearing on nuclear material accounting in the plant - NUMAC) and Quality control Analyses (Quality of the input bulk chemicals as well as products - QCA). The analytical methods selected are based on the duration of analyses, precision and accuracies required for each type analytical requirement classified earlier. The process and plant control analyses requires lower precision and accuracies as compared to NUMAC analyses, which requires very high precision accuracy. The time taken for analyses should be as lower as possible for process and plant control analyses as compared to NUMAC analyses. The analytical methods required for determining U and Pu in process and plant samples from FRFR will be different as compared to samples from TRFR (Thermal Reactor Fuel Reprocessing) due to higher Pu to U ratio in FRFR as compared TRFR and they should be such that they can be easily

Sensitive non-radioactive detection of HIV-1

DEFF Research Database (Denmark)

Teglbjærg, Lars Stubbe; Nielsen, C; Hansen, J E

1992-01-01

This report describes the use of the polymerase chain reaction (PCR) for the non-radioactive detection of HIV-1 proviral genomic sequences in HIV-1 infected cells. We have developed a sensitive assay, using three different sets of nested primers and our results show that this method is superior...... to standard PCR for the detection of HIV-1 DNA. The assay described features the use of a simple and inexpensive sample preparation technique and a non-radioactive hybridization procedure for confirmation of results. To test the suitability of the assay for clinical purposes, we tested cell samples from 76...

Separation of non-hazardous, non-radioactive components from ICPP calcine via chlorination

International Nuclear Information System (INIS)

Nelson, L.O.

1995-05-01

A pyrochemical treatment method for separating non-radioactive from radioactive components in solid granular waste accumulated at the Idaho Chemical Processing Plant was investigated. The goal of this study was to obtain kinetic and chemical separation data on the reaction products of the chlorination of the solid waste, known as calcine. Thermodynamic equilibrium calculations were completed to verify that a separation of radioactive and non-radioactive calcine components was possible. Bench-scale chlorination experiments were completed subsequently in a variety of reactor configurations including: a fixed-bed reactor (reactive gases flowed around and not through the particle bed), a packed/fluidized-bed reactor, and a packed-bed reactor (reactive gases flowed through the particle bed). Chemical analysis of the reaction products generated during the chlorination experiments verified the predictions made by the equilibrium calculations. An empirical first-order kinetic rate expression was developed for each of the reactor configurations. 20 refs., 16 figs., 21 tabs

Analytical quality control in environmental analysis - Recent results and future trends of the IAEA's analytical quality control programme

Energy Technology Data Exchange (ETDEWEB)

Suschny, O; Heinonen, J

1973-12-01

The significance of analytical results depends critically on the degree of their reliability, an assessment of this reliability is indispensable if the results are to have any meaning at all. Environmental radionuclide analysis is a relatively new analytical field in which new methods are continuously being developed and into which many new laboratories have entered during the last ten to fifteen years. The scarcity of routine methods and the lack of experience of the new laboratories have made the need for the assessment of the reliability of results particularly urgent in this field. The IAEA, since 1962, has provided assistance to its member states by making available to their laboratories analytical quality control services in the form of standard samples, reference materials and the organization of analytical intercomparisons. The scope of this programme has increased over the years and now includes, in addition to environmental radionuclides, non-radioactive environmental contaminants which may be analysed by nuclear methods, materials for forensic neutron activation analysis, bioassay materials and nuclear fuel. The results obtained in recent intercomparisons demonstrate the continued need for these services. (author)

Proposal of threshold levels for the definition of non-radioactive wastes

International Nuclear Information System (INIS)

Yoshida, Yoshikazu

1979-01-01

With increasing amounts of radioactive wastes along with the advances of nuclear power generation and radioactive material utilizations, the needs for management cost reduction and resource saving have arisen. Under the situation, the threshold levels for the definition of non-radioactive solid wastes are required. The problem has been studied by an ad hoc committee in Nuclear Safety Research Association, by the request of the Science and Technology Agency. The matters described are the procedures of deriving the threshold levels, the feasibility studies of the management of waste threshold-level with several enterprises, and future subjects of study. The threshold levels are grouped in two, i.e. the unconditional level and the conditional level. According to the unconditional threshold level, solid wastes are separated definitely into radioactive and non-radioactive ones. According to the conditional threshold level, under certain conditions, some radioactive solid wastes according to the unconditional level are regarded as non-radioactive ones. (J.P.N.)

Radioactive particles in the environment: sources, particle characterization and analytical techniques

International Nuclear Information System (INIS)

2011-08-01

Over the years, radioactive particles have been released to the environment from nuclear weapons testing and nuclear fuel cycle operations. However, measurements of environmental radioactivity and any associated assessments are often based on the average bulk mass or surface concentration, assuming that radionuclides are homogeneously distributed as simple ionic species. It has generally not been recognised that radioactive particles present in the environment often contain a significant fraction of the bulk sample activity, leading to sample heterogeneity problems and false and/or erratic measurement data. Moreover, the inherent differences in the transport and bioavailability of particle bound radionuclides compared with those existing as molecules or ions have largely been ignored in dose assessments. To date, most studies regarding radionuclide behaviour in the soil-plant system have dealt with soluble forms of radionuclides. When radionuclides are deposited in a less mobile form, or in case of a superposition of different physico-chemical forms, the behaviour of radionuclides becomes much more complicated and extra efforts are required to provide information about environmental status and behaviour of radioactive particles. There are currently no documents or international guides covering this aspect of environmental impact assessments. To fill this gap, between 2001 and 2008 the IAEA performed a Coordinated Research Programme (CRP- G4.10.03) on the 'Radiochemical, Chemical and Physical Characterization of Radioactive Particles in the Environment' with the objective of development, adoption and application of standardized analytical techniques for the comprehensive study of radioactive particles. The CRP was in line with the IAEA project intended to assist the Member States in building capacity for improving environmental assessments and for management of sites contaminated with radioactive particles. This IAEA-TECDOC presents the findings and achievements of

Recommendations for sampling for prevention of hazards in civil defense. On analytics of chemical, biological and radioactive contaminations. Brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling

International Nuclear Information System (INIS)

Bachmann, Udo; Biederbick, Walter; Derakshani, Nahid

2010-01-01

The recommendation for sampling for prevention of hazards in civil defense is describing the analytics of chemical, biological and radioactive contaminations and includes detail information on the sampling, protocol preparation and documentation procedures. The volume includes a separate brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling.

Analytical errors in measuring radioactivity in cell proteins and their effect on estimates of protein turnover in L cells

International Nuclear Information System (INIS)

Silverman, J.A.; Mehta, J.; Brocher, S.; Amenta, J.S.

1985-01-01

Previous studies on protein turnover in 3 H-labelled L-cell cultures have shown recovery of total 3 H at the end of a three-day experiment to be always significantly in excess of the 3 H recovered at the beginning of the experiment. A number of possible sources for this error in measuring radioactivity in cell proteins has been reviewed. 3 H-labelled proteins, when dissolved in NaOH and counted for radioactivity in a liquid-scintillation spectrometer, showed losses of 30-40% of the radioactivity; neither external or internal standardization compensated for this loss. Hydrolysis of these proteins with either Pronase or concentrated HCl significantly increased the measured radioactivity. In addition, 5-10% of the cell protein is left on the plastic culture dish when cells are recovered in phosphate-buffered saline. Furthermore, this surface-adherent protein, after pulse labelling, contains proteins of high radioactivity that turn over rapidly and make a major contribution to the accumulating radioactivity in the medium. These combined errors can account for up to 60% of the total radioactivity in the cell culture. Similar analytical errors have been found in studies of other cell cultures. The effect of these analytical errors on estimates of protein turnover in cell cultures is discussed. (author)

Pre-analytic phase in molecular biology: criticism and non-compliance management

Directory of Open Access Journals (Sweden)

Catia Sias

2010-06-01

Full Text Available Introduction: During workflow in Laboratories the most delicate and important step is pre-analytic sample treatment because it involves more than one operator of the same structure and often different health services. In fact, the biological materials used for the diagnosis should be collected, sent and properly treated before the analytic phase. Correct methods for collecting and handling biological materials, including guidelines to users of laboratory services, improve performance of Laboratory testing activity. In the pre-analytic phase the operators check sample integrity, and prepare the sample for the subsequent analytic phase: in all these steps monitoring and control of “non- compliance” is crucial. Methods: During 2007-2008 we created a “non- compliance” check-list, to monitor errors which occurred in different sectors of the preanalytic phase, particularly in the nucleic acid extraction step. These “non-compliances” are analysed to identify and to remove errors, adopting preventive and corrective proceedings. Since 2008 we have been using DNA/RNA internal controls synthesized in our Laboratory. They can be amplified by the same primers and recognized by different probes. Results: Examination of the “non compliance” check-list for molecular biology investigations shows that the percentage of urine repeat samples decreased from 17% to 2% and the percentage of stool repeat samples from 27% to 2%. Regarding use of internal controls, they allow the assessment of inhibitory factors that can prevent gene amplification. Conclusions: Monitoring “non-compliance” cases and dividing them by typology allow us identifying the most frequent causes of incorrect sample handling, as a non optimal procedure of pre-treatment, thus improving the pre-analytic phase. Therefore by monitoring the preanalytic phase we can prevent the introduction of confounding factors that may negatively influence the accuracy of results and their

Analysis of spatial distribution and inventory of radioactivity within the uranium mill tailings impoundment

Directory of Open Access Journals (Sweden)

D. O. Bugai

2015-10-01

Full Text Available Results are presented of the characterization of radioactivity inventory of Zapadnoe uranium mill tailings impoundment situated at Pridneprovsky Chemical Plant (PChP; Dneprodzerzhinsk, Ukraine. Analyses of radioactivity data set based on analytical studies of core material from 15 characterization boreholes allowed significantly refining waste volume and radioactivity inventory estimates. Geostatistical analyses using variogram function have established that radioactivity distribution in Zapadnoe tailings is characterized by regular spatial correlation patterns. Ordinary kriging method was applied to assess distribution of radioactivity in 3D. Results of statistical analyses suggest significant redistribution of uranium in the dissolved form in the residues (presumably due to water infiltration process. The developed structural model for radioactivity distribution is used for further risk assessment analyses. Derived radioactivity correlation scales can be used for optimization of sample collection when characterizing the PChP Site and similar contaminated sites elsewhere.

Efficient handling of high-level radioactive cell waste in a vitrification facility analytical laboratory

International Nuclear Information System (INIS)

Roberts, D.W.; Collins, K.J.

1998-01-01

The Savannah River Site''s (SRS) Defense Waste Processing Facility (DWPF) near Aiken, South Carolina, is the world''s largest and the United State''s first high level waste vitrification facility. For the past 1.5 years, DWPF has been vitrifying high level radioactive liquid waste left over from the Cold War. The vitrification process involves the stabilization of high level radioactive liquid waste into borosilicate glass. The glass is contained in stainless steel canisters. DWPF has filled more than 200 canisters 3.05 meters (10 feet) long and 0.61 meters (2 foot) diameter. Since operations began at DWPF in March of 1996, high level radioactive solid waste continues to be generated due to operating the facility''s analytical laboratory. The waste is referred to as cell waste and is routinely removed from the analytical laboratories. Through facility design, engineering controls, and administrative controls, DWPF has established efficient methods of handling the high level waste generated in its laboratory facility. These methods have resulted in the prevention of undue radiation exposure, wasted man-hours, expenses due to waste disposal, and the spread of contamination. This level of efficiency was not reached overnight, but it involved the collaboration of Radiological Control Operations and Laboratory personnel working together to devise methods that best benefited the facility. This paper discusses the methods that have been incorporated at DWPF for the handling of cell waste. The objective of this paper is to provide insight to good radiological and safety practices that were incorporated to handle high level radioactive waste in a laboratory setting

Analysis of a Single Hot Particle by a Combination of Non-Destructive Analytical Methods

Energy Technology Data Exchange (ETDEWEB)

Hrnecek, E.; Aldave de las Heras, L.; Bielewski, M.; Carlos, R. [EC JRC Institute for Transuranium Elements, Karlsruhe (Germany); Betti, M. [IAEA Environment Laboratories (Monaco)

2013-07-15

Radioactive substances are often released to the environment in the form of particles. The determination of their chemical composition is a key factor in the overall understanding of their environmental behaviour. The aim of this investigation was to identify the source of one single radioactive particle collected from the Irish Sea and to understand its fate in the environment and in human body fluids. As the particle was supposed to be analysed for its dissolution behaviour in humans after ingestion, it was necessary to gain as much information as possible beforehand on the chemical and isotopic composition by means of non-destructive analysis such as SEM, SIMS, {mu}-XRF and {mu}-XANES. In this paper, an overview of the different non-destructive methods applied for the analysis of this particle and the results obtained is given. Additionally, the dissolution behaviour in human digestive solutions is discussed. (author)

Evaluation and standardisation of fast analytical techniques for destructive radwaste control

International Nuclear Information System (INIS)

De Simone, A.; Troiani, F.

2001-01-01

The document describes the work programme carried out by the Laboratorio Nazionale per la 'Caratterizzazione dei Refit Radioattivi', in the frame of the European research project Destructive Radwaste Control. The main tasks of the research work were the evaluation of fast sample pre-treatment procedures and the development of chromatographic methods coupled to fast nuclide detection by Liquid Scintillation Counting. In order to test the High Performance Ion Chromatograph (HPIC) coupled to the Liquid Scintillation Counter (LSC) on high salt content solutions, synthetic cement solutions have been prepared and spiked with several β-emitters hard to be measured with non-destructive analyses, along with other radionuclides important for the determination of the radiological inventory in radwastes. As the validation tests for the new analytical methods involved the manipulation of radioactive solutions, a remote area for HPIC-LSC apparatus has been designed and performed, in order to operate in safe conditions. According to the research programme, fast analytical methods for the chemical separation and radionuclide detection of the radioactive elements of interest, have been developed and qualified. From the results of the work, some protocols of analysis have been defined: they contain all information about operative conditions for HPIC-LSC apparatus, field of applicability, chemical and radioactive detection limits [it

Proceedings of the NEA Workshop on the Management of Non-Nuclear Radioactive Waste

International Nuclear Information System (INIS)

Zafiropoulos, Demetre; Dilday, Daniel; Siemann, Michael; Ciambrella, Massimo; Lazo, Edward; Sartori, Enrico; ); Dionisi, Mario; Long, Juliet; Nicholson, David; Chambers, Douglas; Garcia Alves, Joao Henrique; McMahon, Ciara; Bruno, Gerard; Fan, Zhiwen; ); Ripani, Marco; Nielsen, Mette; Solente, Nicolas; Templeton, John; Paratore, Angelo; Feinhals, Joerg; Pandolfi, Dana; Sarchiapone, Lucia; Picentino, Bruno; Simms, Helen; Beer, Hans-Frieder; Deryabin, Sergey; Ulrici, Luisa; Bergamaschi, Carlo; Nottestad, Stacy; Anagnostakis, Marios

2017-05-01

All NEA member countries, whether or not they have nuclear power plants, are faced with appropriately managing non-nuclear radioactive waste produced through industrial, research and medical activities. Sources of such waste can include national laboratory and university research activities, used and lost industrial gauges and radiography sources, hospital nuclear medicine activities and in some circumstances, naturally occurring radioactive material (NORM) activities. Although many of these wastes are not long-lived, the shear variety of sources makes it difficult to generically assess their physical (e.g. volume, chemical form, mixed waste) or radiological (e.g. activity, half-life, concentration) characteristics. Additionally, the source-specific nature of these wastes poses questions and challenges to their regulatory and practical management at a national level. This had generated interest from both the radiological protection and radioactive waste management communities, and prompted the Committee on Radiological Protection and Public Health (CRPPH) to organise, in collaboration with the Radioactive Waste Management Committee (RWMC), a workshop tackling some of the key issues of this challenging topic. The key objectives of the NEA Workshop on the Management of Non-Nuclear Radioactive Waste were to address the particularities of managing non-nuclear waste in all its sources and forms and to share and exchange national experiences. Presentations and discussions addressed both technical aspects and national frameworks. Technical aspects included: - the range of non-nuclear waste sources, activities, volumes and other relevant characteristics; - waste storage and repository capacities and life cycles; - safety considerations for mixed wastes management; - human resources and knowledge management; - legal, regulatory and financial assurance, and liability issues. Taking into account the entire non-nuclear waste life-cycle, the workshop covered planning and

Non-radioactive waste management in a Nuclear Energy Research Institution

Energy Technology Data Exchange (ETDEWEB)

Furusawa, Helio A.; Martins, Elaine A.J.; Cotrim, Marycel E.B.; Pires, Maria A. F., E-mail: helioaf@ipen.br, E-mail: elaine@ipen.br, E-mail: mecotrim@ipen.br, E-mail: mapires@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEM-SP), Sao Paulo, SP (Brazil). Centro de Quimica e Meio Ambiente

2013-07-01

For more than 50 years, non-radioactive materials have been used in processes at IPEN to support the nuclear fuel development and all related activities. Reagents, raw materials, products and by-products have been stored. Many of these are hazardous highly toxic or reactants materials. Some years ago actions sent part of these non-radioactive waste materials to proper disposal (technical incineration) resulting in an Institutional Non-Radioactive Waste Management Program. In 2005, an internal set of procedures and information entitled - Guia de Procedimentos para Armazenamento, Tratamento e Descarte de Residuos de Laboratorio Quimico - (Guide of Procedures for Storage, Treatment, and Disposal of Chemistry Laboratory Wastes) - was published to be used at the IPEN's facilities. A data base managed by software was created in order to allow the Units to input data and information about the routinely generated wastes and those already existing. Even after disposing so huge amount of wastes, a latent demand still exists. Several goals were achieved notably a well-organized and roomy space; safer storage places; local, state, and nationwide laws enforcement (for radioactive and non-radioactive materials); and improvement in chemicals control as hazardous and aged materials are more frequently disposed. A special stress was conducted to know and follow laws, regulations, and technical norms as the entire process is very detailed and this is not a day-by-day routine for the IPEN's technical personnel. The immediate consequence is that the safer the workplace the safer the nuclear related activities are done. (author)

Non-radioactive waste management in a Nuclear Energy Research Institution

International Nuclear Information System (INIS)

Furusawa, Helio A.; Martins, Elaine A.J.; Cotrim, Marycel E.B.; Pires, Maria A. F.

2013-01-01

For more than 50 years, non-radioactive materials have been used in processes at IPEN to support the nuclear fuel development and all related activities. Reagents, raw materials, products and by-products have been stored. Many of these are hazardous highly toxic or reactants materials. Some years ago actions sent part of these non-radioactive waste materials to proper disposal (technical incineration) resulting in an Institutional Non-Radioactive Waste Management Program. In 2005, an internal set of procedures and information entitled - Guia de Procedimentos para Armazenamento, Tratamento e Descarte de Residuos de Laboratorio Quimico - (Guide of Procedures for Storage, Treatment, and Disposal of Chemistry Laboratory Wastes) - was published to be used at the IPEN's facilities. A data base managed by software was created in order to allow the Units to input data and information about the routinely generated wastes and those already existing. Even after disposing so huge amount of wastes, a latent demand still exists. Several goals were achieved notably a well-organized and roomy space; safer storage places; local, state, and nationwide laws enforcement (for radioactive and non-radioactive materials); and improvement in chemicals control as hazardous and aged materials are more frequently disposed. A special stress was conducted to know and follow laws, regulations, and technical norms as the entire process is very detailed and this is not a day-by-day routine for the IPEN's technical personnel. The immediate consequence is that the safer the workplace the safer the nuclear related activities are done. (author)

International conference on management of radioactive waste from non-power applications - Sharing the experience. Book of extended synopses

International Nuclear Information System (INIS)

2001-01-01

The primary objective of the conference is to provide an opportunity for experts in this field to meet and exchange information, and to discuss experience, specific practices and technical solutions used in the management of radioactive waste derived from different non-power applications. This includes waste from the operation of research reactors, and from the production and application of radioisotopes, labelled compounds and sealed radioactive sources in industry, medicine, agriculture, research and education. The discussion may also include management of specific waste types, such as waste from radiological accidents, waste from remediation activities connected with old, inadequate waste management facilities, etc. The conference may also address the issues of management of very low level radioactive waste (VLLRW) and of technologically enhanced naturally occurring radioactive materials (TENORMs) to identify the existing scale of the problems and to analyse current approaches of Member States to their solution. The conference is also intended to identify the most important and problematic components of the subject and to facilitate the sharing of experience in improving efficiency, safety and economy in the management of radioactive waste from non-power nuclear applications. This publication contains 89 extended synopses of the oral and poster presentations delivered at the conference. Each of them was indexed separately

IAEA coordinated research project (CRP) on 'Analytical and experimental benchmark analyses of accelerator driven systems'

International Nuclear Information System (INIS)

Abanades, Alberto; Aliberti, Gerardo; Gohar, Yousry; Talamo, Alberto; Bornos, Victor; Kiyavitskaya, Anna; Carta, Mario; Janczyszyn, Jerzy; Maiorino, Jose; Pyeon, Cheolho; Stanculescu, Alexander; Titarenko, Yury; Westmeier, Wolfram

2008-01-01

In December 2005, the International Atomic Energy Agency (IAEA) has started a Coordinated Research Project (CRP) on 'Analytical and Experimental Benchmark Analyses of Accelerator Driven Systems'. The overall objective of the CRP, performed within the framework of the Technical Working Group on Fast Reactors (TWGFR) of IAEA's Nuclear Energy Department, is to increase the capability of interested Member States in developing and applying advanced reactor technologies in the area of long-lived radioactive waste utilization and transmutation. The specific objective of the CRP is to improve the present understanding of the coupling of an external neutron source (e.g. spallation source) with a multiplicative sub-critical core. The participants are performing computational and experimental benchmark analyses using integrated calculation schemes and simulation methods. The CRP aims at integrating some of the planned experimental demonstration projects of the coupling between a sub-critical core and an external neutron source (e.g. YALINA Booster in Belarus, and Kyoto University's Critical Assembly (KUCA)). The objective of these experimental programs is to validate computational methods, obtain high energy nuclear data, characterize the performance of sub-critical assemblies driven by external sources, and to develop and improve techniques for sub-criticality monitoring. The paper summarizes preliminary results obtained to-date for some of the CRP benchmarks. (authors)

Defense Waste Processing Facility prototypic analytical laboratory

International Nuclear Information System (INIS)

Policke, T.A.; Bryant, M.F.; Spencer, R.B.

1991-01-01

The Defense Waste Processing Technology (DWPT) Analytical Laboratory is a relatively new laboratory facility at the Savannah River Site (SRS). It is a non-regulated, non-radioactive laboratory whose mission is to support research and development (R ampersand D) and waste treatment operations by providing analytical and experimental services in a way that is safe, efficient, and produces quality results in a timely manner so that R ampersand D personnel can provide quality technical data and operations personnel can efficiently operate waste treatment facilities. The modules are sample receiving, chromatography I, chromatography II, wet chemistry and carbon, sample preparation, and spectroscopy

ALTERNATIVE ANALYTICAL DIGESTION SCHEME FOR THE DEFENSE WASTE PROCESSING FACILITY (DWPF) SLURRY RECEIPT AND ADJUSTMENT TANK (SRAT) ANALYSES

International Nuclear Information System (INIS)

Click, D; Charles02 Coleman, C; Frank Pennebaker, F; Kristine Zeigler, K; Tommy Edwards, T

2007-01-01

-vial (∼12-16 hrs) prior to performing the PF. Therefore, a modified digestion scheme was tested using simulant sludge that takes advantage of both digestion methods (CC and PF). The experimental work involved (1) performing the CC method on simulant sludge containing both boehmite and gibbsite, (2) filtering the digestate to collect undissolved solids, (3) drying the filter and the solids collected (2 hr step versus ∼12-16 hr step for drying peanut vial full of sludge), (4) heating the solids and filter to 675 C (causing complete oxidation of the filter), and (5) performing a PF digestion of the solids. The solutions from each type of digestion were analyzed by Inductively Coupled Plasma Emission Spectroscopy (ICP-ES) and the results were combined. The measured Al concentration from the PF digestion on a dried solids basis was 10.7% with a relative standard deviation of 0.92% and 10.1% with a relative standard deviation of 0.43% from the CC+PF digestion. The Al concentration measured in the digestion solutions from the CC method before performing the PF was ∼8.8 wt% of the solubilized solids on a total dried solids basis. The Al hydroxide dissolution results are discussed in this report. Also discussed are the experimental results obtained for all elements DWPF measures and a statistical comparison of that data. The following conclusions and recommendations are based upon spectroscopic and statistical analysis of results from experimental digestion tests conducted with SB4 simulant sludge slurry: (1) The CC + PF digestion method will result in reduced DWPF Lab analytical turnaround time over the PF only digestion method. (2) The CC + PF digestion resulted in complete digestion of all forms of Al and the measured combined concentration of Al was nearly equal to that of the PF only method. (3) Pursue a side-by-side development and comparison of the combined digestion method (DWPF CC plus PF of undissolved solids) using radioactive sludge. (4) Perform periodic analyses

Survey on non-nuclear radioactive waste; Kartlaeggning av radioaktivt avfall fraan icke kaernteknisk verksamhet

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-11-01

On request from the Swedish Radiation Protection Authority, the Swedish government has in May 2002 set up a non-standing committee for non-nuclear radioactive waste. The objective was to elaborate proposals for a national system for the management of all types of non-nuclear radioactive wastes with special consideration of inter alia the polluter pays principle and the responsibility of the producers. The committee will deliver its proposals to the government 1 December 2003. SSI has assisted the committee to the necessary extent to fulfill the investigation. This report is a summery of SSI's background material concerning non-nuclear radioactive waste in Sweden.

Simplified analytical model to simulate radionuclide release from radioactive waste trenches

International Nuclear Information System (INIS)

Sa, Bernardete Lemes Vieira de

2001-01-01

In order to evaluate postclosure off-site doses from low-level radioactive waste disposal facilities, a computer code was developed to simulate the radionuclide released from waste form, transport through vadose zone and transport in the saturated zone. This paper describes the methodology used to model these process. The radionuclide released from the waste is calculated using a model based on first order kinetics and the transport through porous media was determined using semi-analytical solution of the mass transport equation, considering the limiting case of unidirectional convective transport with three-dimensional dispersion in an isotropic medium. The results obtained in this work were compared with other codes, showing good agreement. (author)

Evaluation of radioactive emissions of lignite-fired power plants in Turkey using the Analytic Hierarchy Process

International Nuclear Information System (INIS)

Bueke, Tayfun

2013-01-01

Radioactive emissions of 13 lignite-fired power plants in Turkey are of great concern to the public and to scientists alike. The purpose of this study is to evaluate these power plants, according to their radioactive emissions by using the Analytic Hierarchy Process. Control criteria are in particular 226 Ra, 232 Th, 40 K and 238 U emissions from the power plants. These control criteria are weighted according to the objective assessment. The calculations are repeated for three different objective assessments of control criteria namely the mortality risk coefficients for inhalation, ingestion, external exposure of 226 Ra, 232 Th, 40 K and 238 U. It has been calculated that the Can lignite-fired power plant is ranking first while the Soma-B plant is ranking last according to the radioactive emissions of the power plants when the average of three different objective control criteria are used in the calculations. (orig.)

The Influence of Judgment Calls on Meta-Analytic Findings.

Science.gov (United States)

Tarrahi, Farid; Eisend, Martin

2016-01-01

Previous research has suggested that judgment calls (i.e., methodological choices made in the process of conducting a meta-analysis) have a strong influence on meta-analytic findings and question their robustness. However, prior research applies case study comparison or reanalysis of a few meta-analyses with a focus on a few selected judgment calls. These studies neglect the fact that different judgment calls are related to each other and simultaneously influence the outcomes of a meta-analysis, and that meta-analytic findings can vary due to non-judgment call differences between meta-analyses (e.g., variations of effects over time). The current study analyzes the influence of 13 judgment calls in 176 meta-analyses in marketing research by applying a multivariate, multilevel meta-meta-analysis. The analysis considers simultaneous influences from different judgment calls on meta-analytic effect sizes and controls for alternative explanations based on non-judgment call differences between meta-analyses. The findings suggest that judgment calls have only a minor influence on meta-analytic findings, whereas non-judgment call differences between meta-analyses are more likely to explain differences in meta-analytic findings. The findings support the robustness of meta-analytic results and conclusions.

Electronic tongue - an array of non-specific chemical sensors - for analysis of radioactive solutions

International Nuclear Information System (INIS)

Legin, A.; Rudnitskaya, A.; Babain, V.

2006-01-01

Multisensor systems, combining chemical sensor arrays with multivariate data processing engines (electronic tongue) rapidly and successfully developing in the last years are capable of simultaneous quantitative analysis of several species, e.g. metals, in complex real solutions. The expansion of the metals (metal ions) and species to be detected in radioactive waste requires permanent enhancement of sensing materials and sensors, with seriously different properties from those known earlier. A prospective direction of R and D of novel sensing materials is exploitation of radiochemical extraction systems and application of extraction substances as active components of new sensors. The sensors based on bidentate phosphorous organic compounds and their combinations with chlorinated cobalt dicarbollide displayed high sensitivity and selectivity to rare-earth metal ions La 3+ , Pr 3+ , Nd 3+ , Eu 3+ . The results indicated good promise for the development of novel analytical tools for detection of multivalent metal cations in different media, particularly in corrosive solutions such as radioactive wastes and solutions derived from spent nuclear fuel. The sensors and sensor arrays made on their basis can play an important role in the development of 'electronic tongue' systems for rapid analytical determinations of different components in complex radioactive solutions

Technical support for GEIS: radioactive waste isoltaion in geologic formations. Volume 19. Thermal analyses

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/19, ''Thermal Analyses,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume discusses the thermal impacts of the isolated high level and spent-fuel wastes in geologic formations. A detailed account of the methodologies employed is given as well as selected results of the analyses

Evaluation of radioactive emissions of lignite-fired power plants in Turkey using the Analytic Hierarchy Process

Energy Technology Data Exchange (ETDEWEB)

Bueke, Tayfun [Mugla Sitki Kocman Univ., Mugla (Turkey). Dept. of Energy Systems Engineering

2013-11-15

Radioactive emissions of 13 lignite-fired power plants in Turkey are of great concern to the public and to scientists alike. The purpose of this study is to evaluate these power plants, according to their radioactive emissions by using the Analytic Hierarchy Process. Control criteria are in particular {sup 226}Ra, {sup 232}Th, {sup 40}K and {sup 238}U emissions from the power plants. These control criteria are weighted according to the objective assessment. The calculations are repeated for three different objective assessments of control criteria namely the mortality risk coefficients for inhalation, ingestion, external exposure of {sup 226}Ra, {sup 232}Th, {sup 40}K and {sup 238}U. It has been calculated that the Can lignite-fired power plant is ranking first while the Soma-B plant is ranking last according to the radioactive emissions of the power plants when the average of three different objective control criteria are used in the calculations. (orig.)

Thermal-mechanical aspects for radioactive waste storage into underground caverns

International Nuclear Information System (INIS)

Vieira, Alvaro.

1985-12-01

The thermal and mechanical behaviors of rock mass by analytical models, considering transient effects of the heat generation from radioactive wastes, are analysed. The models were applied to Brazilian gneissic type of rock, considering the usual design of vitrified waste cylinders individually installed into conveniently spaced holes. (M.C.K.) [pt

Management of radioactive waste from non-power applications in the Netherlands

International Nuclear Information System (INIS)

Codee, H.D.K.

2002-01-01

Radioactive waste results from the use of radioactive materials in hospitals, research establishments, industry and nuclear power plants. The Netherlands forms a good example of a country with a small and in the near future ending nuclear power programme. The radioactive waste from non-power applications therefore strongly influences the management choices. A dedicated waste management company COVRA, the Central Organisation for Radioactive Waste manages all radioactive waste produced in the Netherlands. For the small volume, but broad spectrum of radioactive waste, a management system was developed based on the principle to isolate, to control and to monitor the waste. Long-term storage is an important element in this management strategy. It is not seen as a 'wait and see' option but as a necessary step in the strategy that will ultimately result in final removal of the waste. Since the waste will remain retrievable for a long time new technologies and new disposal options can be applied when available and feasible. (author)

Analytical methodology for optimization of waste management scenarios in nuclear installation decommissioning process - 16148

International Nuclear Information System (INIS)

Zachar, Matej; Necas, Vladimir; Daniska, Vladimir; Rehak, Ivan; Vasko, Marek

2009-01-01

The nuclear installation decommissioning process is characterized by production of large amount of various radioactive and non-radioactive waste that has to be managed, taking into account its physical, chemical, toxic and radiological properties. Waste management is considered to be one of the key issues within the frame of the decommissioning process. During the decommissioning planning period, the scenarios covering possible routes of materials release into the environment and radioactive waste disposal, should be discussed and evaluated. Unconditional and conditional release to the environment, long-term storage at the nuclear site, near surface or deep geological disposal and relevant material management techniques for achieving the final status should be taken into account in the analysed scenarios. At the level of the final decommissioning plan, it is desirable to have the waste management scenario optimized for local specific facility conditions taking into account a national decommissioning background. The analytical methodology for the evaluation of decommissioning waste management scenarios, presented in the paper, is based on the materials and radioactivity flow modelling, which starts from waste generation activities like pre-dismantling decontamination, selected methods of dismantling, waste treatment and conditioning, up to materials release or conditioned radioactive waste disposal. The necessary input data for scenarios, e.g. nuclear installation inventory database (physical and radiological data), waste processing technologies parameters or material release and waste disposal limits, have to be considered. The analytical methodology principles are implemented into the standardised decommissioning parameters calculation code OMEGA, developed in the DECOM company. In the paper the examples of the methodology implementation for the scenarios optimization are presented and discussed. (authors)

Final report on the proficiency test of the Analytical Laboratories for the Measurement of Environmental Radioactivity (ALMERA) network

International Nuclear Information System (INIS)

Shakhashiro, A.; Radecki, Z.; Trinkl, A.; Sansone, U.; Benesch, T.

2005-08-01

This report presents the statistical evaluation of results from the analysis of 12 radionuclides in 8 samples within the frame of the First Proficiency Test of Analytical Laboratories for the Measurement Environmental RAdioactivity (ALMERA) organized in 2001-2002 by the Chemistry Unit, Agency's Laboratory in Seibersdorf. The results were evaluated by using appropriate statistical means to assess laboratory analytical performance and to estimate the overall performance for the determination of each radionuclide. Evaluation of the analytical data for gamma emitting radionuclides showed that 68% of data obtained a 'Passed' final score for both the trueness and precision criteria applied to this exercise. However, transuranic radionuclides obtained only 58% for the same criteria. (author)

Analytical Chemistry Division annual progress report for period ending December 31, 1984

International Nuclear Information System (INIS)

Lyon, W.S.

1985-04-01

Progress reports are presented for the following sections: analytical methodology; mass and emission spectroscopy; radioactive materials analysis; bio/organic analysis; and general and environmental analysis; quality assurance, safety, and tabulation analyses. In addition a list of publications and oral presentations and supplemental activities are included

Analytical Chemistry Division annual progress report for period ending December 31, 1984

Energy Technology Data Exchange (ETDEWEB)

Lyon, W.S. (ed.)

1985-04-01

Progress reports are presented for the following sections: analytical methodology; mass and emission spectroscopy; radioactive materials analysis; bio/organic analysis; and general and environmental analysis; quality assurance, safety, and tabulation analyses. In addition a list of publications and oral presentations and supplemental activities are included.

Concepts and examples of safety analyses for radioactive waste repositories in continental geological formations

International Nuclear Information System (INIS)

1983-01-01

This document is addressed to authorities and specialists responsible for or involved in planning, performing and/or reviewing safety assessments of underground radioactive waste repositories. It is a companion to a general introductory document on the subject ''Safety Assessment for the Underground Disposal of Radioactive Wastes'', IAEA Safety Series No. 56, 1981, and reference to this earlier document will facilitate the reader's understanding of the present report. Since examples of safety analyses are summarized here, it is hoped that this document will contribute to providing a basis for a common understanding among authorities and specialists concerned with the numerous studies involving a variety of scientific disciplines. While providing technical information, this document is also intended to stimulate further international discussion. The purposes of this report are: a) to identify the factors to be taken into account in radiological safety analyses of deep geological repositories, indicating as far as possible their relative importance during the various phases of system development; b) to show how these factors have been analysed in various safety assessment studies; and c) to comment on the merits of the selected and alternative approaches

Concepts and examples of safety analyses for radioactive waste repositories in continental geological formations

Energy Technology Data Exchange (ETDEWEB)

1983-01-01

This document is addressed to authorities and specialists responsible for or involved in planning, performing and/or reviewing safety assessments of underground radioactive waste repositories. It is a companion to a general introductory document on the subject ''Safety Assessment for the Underground Disposal of Radioactive Wastes'', IAEA Safety Series No. 56, 1981, and reference to this earlier document will facilitate the reader's understanding of the present report. Since examples of safety analyses are summarized here, it is hoped that this document will contribute to providing a basis for a common understanding among authorities and specialists concerned with the numerous studies involving a variety of scientific disciplines. While providing technical information, this document is also intended to stimulate further international discussion. The purposes of this report are: a) to identify the factors to be taken into account in radiological safety analyses of deep geological repositories, indicating as far as possible their relative importance during the various phases of system development; b) to show how these factors have been analysed in various safety assessment studies; and c) to comment on the merits of the selected and alternative approaches.

Analytics of Radioactive Materials Released in the Fukushima Daiichi Nuclear Accident

Energy Technology Data Exchange (ETDEWEB)

Egarievwe, Stephen U. [Nuclear Engineering and Radiological Science Center, Alabama A and M University, Huntsville, AL (United States); Nuclear Engineering Department, University of Tennessee, Knoxville, TN (United States); Coble, Jamie B.; Miller, Laurence F. [Nuclear Engineering Department, University of Tennessee, Knoxville, TN (United States)

2015-07-01

The 2011 Fukushima Daiichi nuclear accident in Japan resulted in the release of radioactive materials into the atmosphere, the nearby sea, and the surrounding land. Following the accident, several meteorological models were used to predict the transport of the radioactive materials to other continents such as North America and Europe. Also of high importance is the dispersion of radioactive materials locally and within Japan. Based on the International Atomic Energy Agency (IAEA) Convention on Early Notification of a nuclear accident, several radiological data sets were collected on the accident by the Japanese authorities. Among the radioactive materials monitored, are I-131 and Cs-137 which form the major contributions to the contamination of drinking water. The radiation dose in the atmosphere was also measured. It is impractical to measure contamination and radiation dose in every place of interest. Therefore, modeling helps to predict contamination and radiation dose. Some modeling studies that have been reported in the literature include the simulation of transport and deposition of I-131 and Cs-137 from the accident, Cs-137 deposition and contamination of Japanese soils, and preliminary estimates of I-131 and Cs-137 discharged from the plant into the atmosphere. In this paper, we present statistical analytics of I-131 and Cs-137 with the goal of predicting gamma dose from the Fukushima Daiichi nuclear accident. The data sets used in our study were collected from the IAEA Fukushima Monitoring Database. As part of this study, we investigated several regression models to find the best algorithm for modeling the gamma dose. The modeling techniques used in our study include linear regression, principal component regression (PCR), partial least square (PLS) regression, and ridge regression. Our preliminary results on the first set of data showed that the linear regression model with one variable was the best with a root mean square error of 0.0133 μSv/h, compared

Analytics of Radioactive Materials Released in the Fukushima Daiichi Nuclear Accident

International Nuclear Information System (INIS)

Egarievwe, Stephen U.; Coble, Jamie B.; Miller, Laurence F.

2015-01-01

The 2011 Fukushima Daiichi nuclear accident in Japan resulted in the release of radioactive materials into the atmosphere, the nearby sea, and the surrounding land. Following the accident, several meteorological models were used to predict the transport of the radioactive materials to other continents such as North America and Europe. Also of high importance is the dispersion of radioactive materials locally and within Japan. Based on the International Atomic Energy Agency (IAEA) Convention on Early Notification of a nuclear accident, several radiological data sets were collected on the accident by the Japanese authorities. Among the radioactive materials monitored, are I-131 and Cs-137 which form the major contributions to the contamination of drinking water. The radiation dose in the atmosphere was also measured. It is impractical to measure contamination and radiation dose in every place of interest. Therefore, modeling helps to predict contamination and radiation dose. Some modeling studies that have been reported in the literature include the simulation of transport and deposition of I-131 and Cs-137 from the accident, Cs-137 deposition and contamination of Japanese soils, and preliminary estimates of I-131 and Cs-137 discharged from the plant into the atmosphere. In this paper, we present statistical analytics of I-131 and Cs-137 with the goal of predicting gamma dose from the Fukushima Daiichi nuclear accident. The data sets used in our study were collected from the IAEA Fukushima Monitoring Database. As part of this study, we investigated several regression models to find the best algorithm for modeling the gamma dose. The modeling techniques used in our study include linear regression, principal component regression (PCR), partial least square (PLS) regression, and ridge regression. Our preliminary results on the first set of data showed that the linear regression model with one variable was the best with a root mean square error of 0.0133 μSv/h, compared

Shielded analytical laboratory activities supporting waste isolation programs

International Nuclear Information System (INIS)

McCown, J.J.

1985-08-01

The Shielded Analytical Laboratory (SAL) is a six cell manipulator-equipped facility which was built in 1962 as an addition to the 325 Radiochemistry Bldg. in the 300 Area at Hanford. The facility provides the capability for handling a wide variety of radioactive materials and performing chemical dissolutions, separations and analyses on nuclear fuels, components, waste forms and materials from R and D programs

National policy for control of radioactive sources and radioactive waste from non-power applications in Lithuania

International Nuclear Information System (INIS)

Klevinskas, G.; Mastauskas, A.

2001-01-01

According to the Law on Radiation Protection of the Republic of Lithuania (passed in 1999), the Radiation Protection Centre of the Ministry of Health is the regulatory authority responsible for the radiation protection of public and of workers using sources of ionizing radiation in Lithuania. One of its responsibilities is the control of radioactive sources from the beginning of their 'life cycle', when they are imported in, used, transported and placed as spent into the radioactive waste storage facilities. For the effective control of sources there is national authorization system (notification- registration-licensing) based on the international requirements and recommendations introduced, which also includes keeping and maintaining the Register of Sources, controlling and investigating events while illegally carrying on or in possession of radioactive material, decision making and performing the state radiation protection supervision and control of users of radioactive sources, controlling, within the limits of competence, the radioactive waste management activities in nuclear and non-nuclear power applications. According to the requirements set out in the Law on Radiation Protection and the Government Resolution 'On Establishment of the State Register of the Sources of Ionizing Radiation and Exposure of Workers' (1999) and supplementary legal acts, all licence-holders conducting their activities with sources of ionizing radiation have to present all necessary data to the State Register after annual inventory of sources, after installation of new sources, after decommissioning of sources, after disposal of spent sources, after finishing the activities with the generators of ionizing radiation. The information to the Radiation Protection Centre has to be presented every week from the Customs Department of the Ministry of Finance about all sources of ionizing radiation imported to or exported from Lithuania and the information about the companies performed these

Non radioactive precursor import into chloroplasts

International Nuclear Information System (INIS)

Lombardo, V.A.; Ottado, J.

2003-01-01

Full text: Eukaryotic cells have a subcellular organization based on organelles. Protein transport to these organelles is quantitatively important because the majority of cellular proteins are codified in nuclear genes and then delivered to their final destination. Most of the chloroplast proteins are translated on cytoplasmic ribosomes as larger precursors with an amino terminal transit peptide that is necessary and sufficient to direct the precursor to the chloroplast. Once inside the organelle the transit peptide is cleaved and the mature protein adopts its folded form. In this work we developed a system for the expression and purification of the pea ferredoxin-NADP + reductase precursor (preFNR) for its import into chloroplasts in non radioactive conditions. We constructed a preFNR fused in its carboxy terminus to a 6 histidines peptide (preFNR-6xHis) that allows its identification using a commercial specific antibody. The construction was expressed, purified, processed and precipitated, rendering a soluble and active preFNR-6xHis that was used in binding and import into chloroplasts experiments. The reisolated chloroplasts were analyzed by SDS-PAGE, electro-blotting and revealed by immuno-detection using either colorimetric or chemiluminescent reactive. We performed also import experiments labeling preFNR and preFNR-6xHis with radioactive methionine as controls. We conclude that preFNR-6xHis is bound and imported into chloroplasts as the wild type preFNR and that both colorimetric or chemiluminescent detection methods are useful to avoid the manipulation of radioactive material. (author)

How Big of a Problem is Analytic Error in Secondary Analyses of Survey Data?

Directory of Open Access Journals (Sweden)

Brady T West

Full Text Available Secondary analyses of survey data collected from large probability samples of persons or establishments further scientific progress in many fields. The complex design features of these samples improve data collection efficiency, but also require analysts to account for these features when conducting analysis. Unfortunately, many secondary analysts from fields outside of statistics, biostatistics, and survey methodology do not have adequate training in this area, and as a result may apply incorrect statistical methods when analyzing these survey data sets. This in turn could lead to the publication of incorrect inferences based on the survey data that effectively negate the resources dedicated to these surveys. In this article, we build on the results of a preliminary meta-analysis of 100 peer-reviewed journal articles presenting analyses of data from a variety of national health surveys, which suggested that analytic errors may be extremely prevalent in these types of investigations. We first perform a meta-analysis of a stratified random sample of 145 additional research products analyzing survey data from the Scientists and Engineers Statistical Data System (SESTAT, which describes features of the U.S. Science and Engineering workforce, and examine trends in the prevalence of analytic error across the decades used to stratify the sample. We once again find that analytic errors appear to be quite prevalent in these studies. Next, we present several example analyses of real SESTAT data, and demonstrate that a failure to perform these analyses correctly can result in substantially biased estimates with standard errors that do not adequately reflect complex sample design features. Collectively, the results of this investigation suggest that reviewers of this type of research need to pay much closer attention to the analytic methods employed by researchers attempting to publish or present secondary analyses of survey data.

How Big of a Problem is Analytic Error in Secondary Analyses of Survey Data?

Science.gov (United States)

West, Brady T.; Sakshaug, Joseph W.; Aurelien, Guy Alain S.

2016-01-01

Secondary analyses of survey data collected from large probability samples of persons or establishments further scientific progress in many fields. The complex design features of these samples improve data collection efficiency, but also require analysts to account for these features when conducting analysis. Unfortunately, many secondary analysts from fields outside of statistics, biostatistics, and survey methodology do not have adequate training in this area, and as a result may apply incorrect statistical methods when analyzing these survey data sets. This in turn could lead to the publication of incorrect inferences based on the survey data that effectively negate the resources dedicated to these surveys. In this article, we build on the results of a preliminary meta-analysis of 100 peer-reviewed journal articles presenting analyses of data from a variety of national health surveys, which suggested that analytic errors may be extremely prevalent in these types of investigations. We first perform a meta-analysis of a stratified random sample of 145 additional research products analyzing survey data from the Scientists and Engineers Statistical Data System (SESTAT), which describes features of the U.S. Science and Engineering workforce, and examine trends in the prevalence of analytic error across the decades used to stratify the sample. We once again find that analytic errors appear to be quite prevalent in these studies. Next, we present several example analyses of real SESTAT data, and demonstrate that a failure to perform these analyses correctly can result in substantially biased estimates with standard errors that do not adequately reflect complex sample design features. Collectively, the results of this investigation suggest that reviewers of this type of research need to pay much closer attention to the analytic methods employed by researchers attempting to publish or present secondary analyses of survey data. PMID:27355817

Analytical vs. Simulation Solution Techniques for Pulse Problems in Non-linear Stochastic Dynamics

DEFF Research Database (Denmark)

Iwankiewicz, R.; Nielsen, Søren R. K.

Advantages and disadvantages of available analytical and simulation techniques for pulse problems in non-linear stochastic dynamics are discussed. First, random pulse problems, both those which do and do not lead to Markov theory, are presented. Next, the analytical and analytically-numerical tec......Advantages and disadvantages of available analytical and simulation techniques for pulse problems in non-linear stochastic dynamics are discussed. First, random pulse problems, both those which do and do not lead to Markov theory, are presented. Next, the analytical and analytically...

Nuclear techniques in analytical chemistry

CERN Document Server

Moses, Alfred J; Gordon, L

1964-01-01

Nuclear Techniques in Analytical Chemistry discusses highly sensitive nuclear techniques that determine the micro- and macro-amounts or trace elements of materials. With the increasingly frequent demand for the chemical determination of trace amounts of elements in materials, the analytical chemist had to search for more sensitive methods of analysis. This book accustoms analytical chemists with nuclear techniques that possess the desired sensitivity and applicability at trace levels. The topics covered include safe handling of radioactivity; measurement of natural radioactivity; and neutron a

Radioactive air emissions from non-uranium mining operations

International Nuclear Information System (INIS)

Silhanek, J.S.; Andrews, V.E.

1981-01-01

Section 122 of the Clean Air Act Amendments of 1977, Public Law 9595, directed the Administrator of the Environmental Protection Agency to review all relevant information and determine whether emissions of radioactive pollutants into ambient air will cause or contribute to air pollution which may reasonably be anticipated to endanger public health. A section of this document presented a theoretical analysis of the radioactive airborne emissions from several non-uranium mines including iron, copper, zinc, clay, limestone, fluorspar, and phosphate. Since 1978 EPA's Las Vegas Laboratory has been gathering field data on actual radionuclide emissions from these mines to support the earlier theoretical analysis. The purpose of this paper is to present the results of those field measurements in comparison with the assumed values for the theoretical analysis

IAEA coordinated research project (CRP) on 'Analytical and experimental benchmark analyses of accelerator driven systems'

Energy Technology Data Exchange (ETDEWEB)

Abanades, Alberto [Universidad Politecnica de Madrid (Spain); Aliberti, Gerardo; Gohar, Yousry; Talamo, Alberto [ANL, Argonne (United States); Bornos, Victor; Kiyavitskaya, Anna [Joint Institute of Power Eng. and Nucl. Research ' Sosny' , Minsk (Belarus); Carta, Mario [ENEA, Casaccia (Italy); Janczyszyn, Jerzy [AGH-University of Science and Technology, Krakow (Poland); Maiorino, Jose [IPEN, Sao Paulo (Brazil); Pyeon, Cheolho [Kyoto University (Japan); Stanculescu, Alexander [IAEA, Vienna (Austria); Titarenko, Yury [ITEP, Moscow (Russian Federation); Westmeier, Wolfram [Wolfram Westmeier GmbH, Ebsdorfergrund (Germany)

2008-07-01

In December 2005, the International Atomic Energy Agency (IAEA) has started a Coordinated Research Project (CRP) on 'Analytical and Experimental Benchmark Analyses of Accelerator Driven Systems'. The overall objective of the CRP, performed within the framework of the Technical Working Group on Fast Reactors (TWGFR) of IAEA's Nuclear Energy Department, is to increase the capability of interested Member States in developing and applying advanced reactor technologies in the area of long-lived radioactive waste utilization and transmutation. The specific objective of the CRP is to improve the present understanding of the coupling of an external neutron source (e.g. spallation source) with a multiplicative sub-critical core. The participants are performing computational and experimental benchmark analyses using integrated calculation schemes and simulation methods. The CRP aims at integrating some of the planned experimental demonstration projects of the coupling between a sub-critical core and an external neutron source (e.g. YALINA Booster in Belarus, and Kyoto University's Critical Assembly (KUCA)). The objective of these experimental programs is to validate computational methods, obtain high energy nuclear data, characterize the performance of sub-critical assemblies driven by external sources, and to develop and improve techniques for sub-criticality monitoring. The paper summarizes preliminary results obtained to-date for some of the CRP benchmarks. (authors)

Kinetic corrections from analytic non-Maxwellian distribution functions in magnetized plasmas

Energy Technology Data Exchange (ETDEWEB)

Izacard, Olivier, E-mail: izacard@llnl.gov [Lawrence Livermore National Laboratory, 7000 East Avenue, L-637, Livermore, California 94550 (United States)

2016-08-15

In magnetized plasma physics, almost all developed analytic theories assume a Maxwellian distribution function (MDF) and in some cases small deviations are described using the perturbation theory. The deviations with respect to the Maxwellian equilibrium, called kinetic effects, are required to be taken into account especially for fusion reactor plasmas. Generally, because the perturbation theory is not consistent with observed steady-state non-Maxwellians, these kinetic effects are numerically evaluated by very central processing unit (CPU)-expensive codes, avoiding the analytic complexity of velocity phase space integrals. We develop here a new method based on analytic non-Maxwellian distribution functions constructed from non-orthogonal basis sets in order to (i) use as few parameters as possible, (ii) increase the efficiency to model numerical and experimental non-Maxwellians, (iii) help to understand unsolved problems such as diagnostics discrepancies from the physical interpretation of the parameters, and (iv) obtain analytic corrections due to kinetic effects given by a small number of terms and removing the numerical error of the evaluation of velocity phase space integrals. This work does not attempt to derive new physical effects even if it could be possible to discover one from the better understandings of some unsolved problems, but here we focus on the analytic prediction of kinetic corrections from analytic non-Maxwellians. As applications, examples of analytic kinetic corrections are shown for the secondary electron emission, the Langmuir probe characteristic curve, and the entropy. This is done by using three analytic representations of the distribution function: the Kappa distribution function, the bi-modal or a new interpreted non-Maxwellian distribution function (INMDF). The existence of INMDFs is proved by new understandings of the experimental discrepancy of the measured electron temperature between two diagnostics in JET. As main results, it

Statistical Data Analyses of Trace Chemical, Biochemical, and Physical Analytical Signatures

Energy Technology Data Exchange (ETDEWEB)

Udey, Ruth Norma [Michigan State Univ., East Lansing, MI (United States)

2013-01-01

Analytical and bioanalytical chemistry measurement results are most meaningful when interpreted using rigorous statistical treatments of the data. The same data set may provide many dimensions of information depending on the questions asked through the applied statistical methods. Three principal projects illustrated the wealth of information gained through the application of statistical data analyses to diverse problems.

Non-linear analytic and coanalytic problems (Lp-theory, Clifford analysis, examples)

International Nuclear Information System (INIS)

Dubinskii, Yu A; Osipenko, A S

2000-01-01

Two kinds of new mathematical model of variational type are put forward: non-linear analytic and coanalytic problems. The formulation of these non-linear boundary-value problems is based on a decomposition of the complete scale of Sobolev spaces into the 'orthogonal' sum of analytic and coanalytic subspaces. A similar decomposition is considered in the framework of Clifford analysis. Explicit examples are presented

Radioactive substances monitoring programme. Report for 1995

International Nuclear Information System (INIS)

1995-01-01

The Radioactive Substances Act 1993 provides for controls to be exercised over the use and keeping of radioactive materials and the accumulation and disposal of radioactive wastes. The Environment Agency (the Agency) has been responsible for administration and enforcement of the Act in England and Wales since its formation on 1 April 1996. Prior to this date the work was undertaken by Her Majesty's Inspectorate of Pollution (HMIP). In support of its regulatory functions HMIP commissioned independent monitoring. This report presents the results from monitoring undertaken in 1995. The 1995 HMIP programme required operators of certain sites to provide samples of their liquid effluents for independent radiochemical analysis. The results provide checks on site operators' returns and insights into their quality assurance (QA) procedures and analytical techniques. The analyses were undertaken by the Laboratory of the Government Chemist (LGC) at its laboratories in Teddington, Middlesex. The programme also included checks on solid low level radioactive waste destined for land disposal at the site operated by British Nuclear Fuels plc (BNFL) at Drigg in Cumbria. (author)

Sample diagnosis using indicator elements and non-analyte signals for inductively coupled plasma mass spectrometry

International Nuclear Information System (INIS)

Antler, Margaret; Ying Hai; Burns, David H.; Salin, Eric D.

2003-01-01

A sample diagnosis procedure that uses both non-analyte and analyte signals to estimate matrix effects in inductively coupled plasma-mass spectrometry is presented. Non-analyte signals are those of background species in the plasma (e.g. N + , ArO + ), and changes in these signals can indicate changes in plasma conditions. Matrix effects of Al, Ba, Cs, K and Na on 19 non-analyte signals and 15 element signals were monitored. Multiple linear regression was used to build the prediction models, using a genetic algorithm for objective feature selection. Non-analyte elemental signals and non-analyte signals were compared for diagnosing matrix effects, and both were found to be suitable for estimating matrix effects. Individual analyte matrix effect estimation was compared with the overall matrix effect prediction, and models used to diagnose overall matrix effects were more accurate than individual analyte models. In previous work [Spectrochim. Acta Part B 57 (2002) 277], we tested models for analytical decision making. The current models were tested in the same way, and were able to successfully diagnose matrix effects with at least an 80% success rate

Background Radioactivity in River and Reservoir Sediments near Los Alamos, New Mexico

Energy Technology Data Exchange (ETDEWEB)

S.G.McLin; D.W. Lyons

2002-05-05

As part of its continuing Environmental Surveillance Program, regional river and lake-bottom sediments have been collected annually by Los Alamos National Laboratory (the Laboratory) since 1974 and 1979, respectively. These background samples are collected from three drainage basins at ten different river stations and five reservoirs located throughout northern New Mexico and southern Colorado. Radiochemical analyses for these sediments include tritium, strontium-90, cesium-137, total uranium, plutonium-238, plutonium-239,-240, americium-241, gross alpha, gross beta, and gross gamma radioactivity. Detection-limit radioactivity originates as worldwide fallout from aboveground nuclear weapons testing and satellite reentry into Earth's atmosphere. Spatial and temporal variations in individual analyte levels originate from atmospheric point-source introductions and natural rate differences in airborne deposition and soil erosion. Background radioactivity values on sediments reflect this variability, and grouped river and reservoir sediment samples show a range of statistical distributions that appear to be analyte dependent. Traditionally, both river and reservoir analyte data were blended together to establish background levels. In this report, however, we group background sediment data according to two criteria. These include sediment source (either river or reservoir sediments) and station location relative to the Laboratory (either upstream or downstream). These grouped data are statistically evaluated through 1997, and background radioactivity values are established for individual analytes in upstream river and reservoir sediments. This information may be used to establish the existence and areal extent of trace-level environmental contamination resulting from historical Laboratory research activities since the early 1940s.

The Belgian approach and status on the radiological surveillance of radioactive substances in metal scrap and non-radioactive waste and the financing of orphan sources

International Nuclear Information System (INIS)

Braeckeveldt, Marnix; Preter, Peter De; Michiels, Jan; Pepin, Stephane; Schrauben, Manfred; Wertelaers, An

2007-01-01

Numerous facilities in the non-nuclear sector in Belgium (e.g. in the non-radioactive waste processing and management sector and in the metal recycling sector) have been equipped with measuring ports for detecting radioactive substances. These measuring ports prevent radioactive sources or radioactive contamination from ending up in the material fluxes treated by the sectors concerned. They thus play an important part in the protection of the workers and the people living in the neighbourhood of the facilities, as well as in the protection of the population and the environment in general. In 2006, Belgium's federal nuclear control agency (FANC/AFCN) drew up guidelines for the operators of non-nuclear facilities with a measuring port for detecting radioactive substances. These guidelines describe the steps to be followed by the operators when the port's alarm goes off. Following the publication of the European guideline 2003/122/EURATOM of 22 December 2003 on the control of high-activity sealed radioactive sources and orphan sources, a procedure has been drawn up by FANC/AFCN and ONDRAF/NIRAS, the Belgian National Agency for Radioactive Waste and Enriched Fissile Materials, to identify the responsible to cover the costs relating to the further management of detected sealed sources and if not found to declare the sealed source as an orphan source. In this latter case and from mid-2006 the insolvency fund managed by ONDRAF/NIRAS covers the cost of radioactive waste management. At the request of the Belgian government, a financing proposal for the management of unsealed orphan sources as radioactive waste was also established by FANC/AFCN and ONDRAF/NIRAS. This proposal applies the same approach as for sealed sources and thus the financing of unsealed orphan sources will also be covered by the insolvency fund. (authors)

EPA's criteria development for radioactive waste that is Below Regulatory Concern

International Nuclear Information System (INIS)

Holcomb, W.F.; Gruhlke, J.M.

1987-01-01

The EPA's program for developing environmental standards for land disposal of low-level radioactive wastes, including a criterion for determining wastes with sufficiently low levels of radioactivity to be considered Below Regulatory Concern (BRC) has completed its risk assessment and cost-effectiveness analyses. The analyses for the BRC criterion included evaluation of general population health risks, maximum annual exposures to critical population groups, and costs of risk reduction. These risk assessments include analyses of 18 surrogate radioactive waste streams, representing both fuel cycle and non-fuel cycle facilities. Less restrictive disposal alternatives typical of those used for municipal garbage disposal, such as sanitary landfills, and situated in diverse demographic settings were used in the analyses. A number of waste types which contribute only small doses or fractions of a health effect over 10,000 years from unregulated disposal were identified. Disposal of such wastes without consideration of their very low radioactivity content results in significant cost savings. 3 references, 1 figure, 4 tables

Wipe sampling for characterization of noncompactable radioactive waste

International Nuclear Information System (INIS)

Barbieri, Aline E.O.; Ferreira, Robson J.; Vicente, Roberto

2009-01-01

Wipe sampling is a method of monitoring radioactive surface contamination on working area and on radioactive, non-compactable wastes, constituted of large pieces of replaced parts of equipment in nuclear and radioactive installations. In this method, sampling is executed by rubbing a disc of filter paper on the contaminated surface in such a way as to collect entirely or partially the deposited material. The target radioisotopes are subsequently measured directly on the wipe or extracted by appropriate radio analytical methods and then qualitatively and quantitatively determined. The collection factor, or the efficiency with which the material is removed from the surface and deposited on the smear, is the main source of error in quantitative measurements. The determination of the collection efficiency is the object of this communication. (author)

Management of radioactive wastes from non-power applications. The Cuban experience

International Nuclear Information System (INIS)

Benitez, J.C.; Salgado, M.; Jova, L.

2001-01-01

Full text: Origin of Radioactive Wastes. The wastes arisen from the applications of radioisotopes in medicine are mainly liquids and solid materials contaminated with short lived radionuclides and sealed sources used in radiotherapy and for sterilization of medical materials. Radioactive wastes from industrial applications are generally disused sealed sources used in level detection, quality control, smoke detection and non-destructive testing. The principal forms of wastes generated by research institutes are miscellaneous liquids, trash, biological wastes, and scintillation vials, sealed sources and targets. Solid radioactive wastes are mainly produced during research works, cleaning and decontamination activities and they consist of rags, paper, cellulose, plastics, gloves, clothing, overshoes, etc. Laboratory materials such as cans, polyethylene bags and glass bottles also contribute to the solid waste inventory. Small quantities of non-compactable wastes are also collected and received for treatment. They include wood pieces, metal scrap, defective components and tools. Radioactive Waste Management Policy and Infrastructure. Since 1994 the Cuban integral policy of nuclear development is entrusted to the Nuclear Energy Agency of the Ministry of Science, Technology and Environment (CITMA). The National Center for Nuclear Safety (CNSN) is responsible for the licensing and supervision of radioactive and nuclear installations. The CPHR is in charge of waste management policy and therefore is responsible for centralized collection, transportation, treatment, conditioning, long term storage, and disposal of radioactive waste, as well as for developing new waste conditioning and containment methods. Radioactive Waste Management Facilities. Waste Treatment and Conditioning Plant (WTCP). The present facility is a building that includes a technological area of 100 m 2 and a laboratory area with a surface of around 30 m 2 . Other areas to be distinguished inside the

ICP/AES radioactive sample analyses at Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Matsuzaki, C.L.; Hara, F.T.

1986-03-01

Inductively coupled argon plasma atomic emission spectroscopy (ICP/AES) analyses of radioactive materials at Pacific Northwest Laboratory (PNL) began about three years ago upon completion of the installation of a modified Applied Research Laboratory (ARL) 3560. Funding for the purchase and installation of the ICP/AES was provided by the Nuclear Waste Materials Characterization Center (MCC) established at PNL by the Department of Energy in 1979. MCC's objective is to ensure that qualified materials data are available on waste materials. This paper is divided into the following topics: (1) Instrument selection considerations; (2) initial installation of the simultaneous system with the source stand enclosed in a 1/2'' lead-shielded glove box; (3) retrofit installation of the sequential spectrometer; and (4) a brief discussion on several types of samples analyzed. 1 ref., 7 figs., 1 tab

Radioactive waste from non-power applications in Sweden

International Nuclear Information System (INIS)

Haegg, Ann-Christin; Lindbom, Gunilla; Persson, Monica

2001-01-01

regulations enable the free release of small amounts of radioactive waste either to the municipal sewage system or for delivering to a municipal dumpsite. Identified issues. It is not possible for the SSI to conduct more than a limited number of inspections. SSI relies on the licensee to inform the SSI when the source is no longer in use. An incitement for this is the annual fee mentioned above. Sources with activity below 500 megaBq from facilities with a summary licence are not accounted for separately and can therefore be difficult to control. The only radioactive waste facility (recognised waste facility) with the capacity and the authorisation for taking care of disused radioactive sources and other forms of radioactive waste from Non-Power applications is Studsvik AB. The future costs for final disposal of this waste is unclear because of the lack of final repository. Studsvik has to make sure that future costs are covered by the fee they charges for taking care of radioactive waste. As the only recognised waste facility Studsvik can freely set the fee for taking care of radioactive waste. If the fee is set too high there's a risk that waste from some unserious license-holder will be lost' or kept in storage. Studsvik has no formal responsibility for taking care of used radioactive sources. It's not unrealistic that Studsvik in the future decides not to accept a specific waste-form. Commercial products: Approximately there are 10 millions fireguards containing about 40 kBq Am-241 in Sweden. The average lifetime of the fireguards is 10 years and implicates that about one million fireguards are disposed of each year. SSI has issued regulations stating that private persons are allowed to occasionally throw a fireguard on municipal dump-sites. Companies are allowed to throw up to five fireguards each month. Identified issues: An assumption for the regulations was that the fireguards were not disposed at the same time nor at the same place. A dilution was anticipated

Estimation of contaminant transport in groundwater beneath radioactive waste disposal facilities

International Nuclear Information System (INIS)

Wang, J.C.; Tauxe, J.D.; Lee, D.W.

1995-01-01

Performance assessments are required for low-level radioactive waste disposal facilities to demonstrate compliance with the performance objectives contained in either 10 CFR 61, open-quotes Licensing Requirements for Land Disposal of Radioactive Waste,close quotes or U.S. Department of Energy Order 5820.2A, open-quotes Radioactive Waste Management.close quotes The purpose of a performance assessment is to provide detailed, site-specific analyses of all credible pathways by which radionuclides could escape from the disposal facility into the environment. Among these, the groundwater pathway analysis usually involves complex numerical simulations. This paper demonstrates that the use of simpler analytical models avoids the complexity and opacity of the numerical simulations while capturing the essential physical behavior of a site

Treatment and storage of radioactive wastes at Institute for Energy Technology, Kjeller, Norway and a short survey of non-radioactive hazardous wastes in Norway

International Nuclear Information System (INIS)

Lundby, J.E.

1988-08-01

The treatment and storage of low-level and intermediate-level radioactive wastes in Norway is described. A survey of non-radioactive hazardous wastes and planned processing methods for their treatment in Norway is given. It seems that processing methods developed for radioactive wastes to a greater extent could be adopted to hazardous wastes, and that an increased interdisciplinary waste cooperation could be a positive contribution to the solution of the hazardous waste problems

Background radioactivity in sediments near Los Alamos, New Mexico

International Nuclear Information System (INIS)

McLin, Stephen G.

2004-01-01

River and reservoir sediments have been collected annually by Los Alamos National Laboratory since 1974 and 1979, respectively. These background samples are collected from five river stations and four reservoirs located throughout northern New Mexico and southern Colorado. Analyses include 3 H, 90 Sr, 137 Cs, total U, 238 Pu, 239,240 Pu, 241 Am, gross alpha, gross beta, and gross gamma radioactivity. Surprisingly, there are no federal or state regulatory standards in the USA that specify how to compute background radioactivity values on sediments. Hence, the sample median (or 0.50 quantile) is proposed for this background because it reflects central data tendency and is distribution-free. Estimates for the upper limit of background radioactivity on river and reservoir sediments are made for sampled analytes using the 0.95 quantile (two-tail). These analyses also show that seven of ten analytes from reservoir sediments are normally distributed, or are normally distributed after a logarithmic or square root transformation. However, only three of ten analytes from river sediments are similarly distributed. In addition, isotope ratios for 137 Cs/ 238 Pu, 137 Cs/ 239,240 Pu, and 239,240 Pu/ 238 Pu from reservoir sediments are independent of clay content, total organic carbon/specific surface area (TOC/SSA) and cation exchange capacity/specific surface area (CEC/SSA) ratios. These TOC/SSA and CEC/SSA ratios reflect sediment organic carbon and surface charge densities that are associated with radionuclide absorption, adsorption, and ion exchange reactions on clay mineral structures. These latter ratio values greatly exceed the availability of background radionuclides in the environment, and insure that measured background levels are a maximum. Since finer-grained reservoir sediments contain larger clay-sized fractions compared to coarser river sediments, they show higher background levels for most analytes. Furthermore, radioactivity values on reservoir sediments have

Analytical exact solution of the non-linear Schroedinger equation

International Nuclear Information System (INIS)

Martins, Alisson Xavier; Rocha Filho, Tarcisio Marciano da

2011-01-01

Full text: In this work we present how to classify and obtain analytical solutions of the Schroedinger equation with a generic non-linearity in 1+1 dimensions. Our approach is based on the determination of Lie symmetry transformation mapping solutions into solutions, and non-classical symmetry transformations, mapping a given solution into itself. From these symmetries it is then possible to reduce the equation to a system of ordinary differential equations which can then be solved using standard methods. The generic non-linearity is handled by considering it as an additional unknown in the determining equations for the symmetry transformations. This results in an over-determined system of non-linear partial differential equations. Its solution can then be determined in some cases by reducing it to the so called involutive (triangular) form, and then solved. This reduction is very tedious and can only performed using a computer algebra system. Once the determining system is solved, we obtain the explicit form for the non-linearity admitting a Lie or non-classical symmetry. The analytical solutions are then derived by solving the reduced ordinary differential equations. The non-linear determining system for the non-classical symmetry transformations and Lie symmetry generators are obtaining using the computer algebra package SADE (symmetry analysis of differential equations), developed at our group. (author)

Environmental radioactive intercomparison program and radioactive standards program

Energy Technology Data Exchange (ETDEWEB)

Dilbeck, G. [Environmental Monitoring Systems Laboratory, Las Vegas, NV (United States)

1993-12-31

The Environmental Radioactivity Intercomparison Program described herein provides quality assurance support for laboratories involved in analyzing public drinking water under the Safe Drinking Water Act (SDWA) Regulations, and to the environmental radiation monitoring activities of various agencies. More than 300 federal and state nuclear facilities and private laboratories participate in some phase of the program. This presentation describes the Intercomparison Program studies and matrices involved, summarizes the precision and accuracy requirements of various radioactive analytes, and describes the traceability determinations involved with radioactive calibration standards distributed to the participants. A summary of program participants, sample and report distributions, and additional responsibilities of this program are discussed.

Non-linear analytic and coanalytic problems ( L_p-theory, Clifford analysis, examples)

Science.gov (United States)

Dubinskii, Yu A.; Osipenko, A. S.

2000-02-01

Two kinds of new mathematical model of variational type are put forward: non-linear analytic and coanalytic problems. The formulation of these non-linear boundary-value problems is based on a decomposition of the complete scale of Sobolev spaces into the "orthogonal" sum of analytic and coanalytic subspaces. A similar decomposition is considered in the framework of Clifford analysis. Explicit examples are presented.

The distribution of radioiodine administrated to pregnant mice and the effect of non radioactive iodide

International Nuclear Information System (INIS)

Okui, Toyo; Kobayashi, Satoshi

1987-01-01

Radioiodine, 131 I, which has a high fission yield in the nuclear reactor, is easily taken into the human body, accumilating in the thyroid gland, when released to the environment. 131 I was administrated orally to pregnant mice, and its transportation to the tissues, particularly the fetus, was examined closely. And further, the non-radioactive iodide, i.e., KI, was administrated to see its radiation protection effect. The transportation of 131 I to the fetus is the second highest, following the thyroid gland in the mother mouse. This transportation to the fetus becomes the higher, the larger the gestation period at which the 131 I administration is made. The administration of the non-radioactive iodide has large radiation protection effect in the thyroid gland of the mother mouse and of the fetus. But, depending on its concentration, the non-radioactive iodide may conversely increase overall exposure of the fetus. (Mori, K.)

Local properties of analytic functions and non-standard analysis

International Nuclear Information System (INIS)

O'Brian, N.R.

1976-01-01

This is an expository account which shows how the methods of non-standard analysis can be applied to prove the Nullstellensatz for germs of analytic functions. This method of proof was discovered originally by Abraham Robinson. The necessary concepts from model theory are described in some detail and the Nullstellensatz is proved by investigating the relation between the set of infinitesimal elements in the complex n-plane and the spectrum of the ring of germs of analytic functions. (author)

Non-Destructive Testing for Control of Radioactive Waste Package

Science.gov (United States)

Plumeri, S.; Carrel, F.

2015-10-01

Characterization and control of radioactive waste packages are important issues in the management of a radioactive waste repository. Therefore, Andra performs quality control inspection on radwaste package before disposal to ensure the compliance of the radwast characteristics with Andra waste disposal specifications and to check the consistency between Andra measurements results and producer declared properties. Objectives of this quality control are: assessment and improvement of producer radwaste packages quality mastery, guarantee of the radwaste disposal safety, maintain of the public confidence. To control radiological characteristics of radwaste package, non-destructive passive methods (gamma spectrometry and neutrons counting) are commonly used. These passive methods may not be sufficient, for instance to control the mass of fissile material contained inside radwaste package. This is particularly true for large concrete hull of heterogeneous radwaste containing several actinides mixed with fission products like 137Cs. Non-destructive active methods, like measurement of photofission delayed neutrons, allow to quantify the global mass of actinides and is a promising method to quantify mass of fissile material. Andra has performed different non-destructive measurements on concrete intermediate-level short lived nuclear waste (ILW-SL) package to control its nuclear material content. These tests have allowed Andra to have a first evaluation of the performance of photofission delayed neutron measurement and to identify development needed to have a reliable method, especially for fissile material mass control in intermediate-level long lived waste package.

Sensitivity and uncertainty analyses applied to one-dimensional radionuclide transport in a layered fractured rock: MULTFRAC --Analytic solutions and local sensitivities

International Nuclear Information System (INIS)

Gureghian, A.B.; Wu, Y.T.; Sagar, B.

1992-12-01

Exact analytical solutions based on the Laplace transforms are derived for describing the one-dimensional space-time-dependent, advective transport of a decaying species in a layered, saturated rock system intersected by a planar fracture of varying aperture. These solutions, which account for advection in fracture, molecular diffusion into the rock matrix, adsorption in both fracture and matrix, and radioactive decay, predict the concentrations in both fracture and rock matrix and the cumulative mass in the fracture. The solute migration domain in both fracture and rock is assumed to be semi-infinite with non-zero initial conditions. The concentration of each nuclide at the source is allowed to decay either continuously or according to some periodical fluctuations where both are subjected to either a step or band release mode. Two numerical examples related to the transport of Np-237 and Cm-245 in a five-layered system of fractured rock were used to verify these solutions with several well established evaluation methods of Laplace inversion integrals in the real and complex domain. In addition, with respect to the model parameters, a comparison of the analytically derived local sensitivities for the concentration and cumulative mass of Np-237 in the fracture with the ones obtained through a finite-difference method of approximation is also reported

Radioactive kryptonates in the analysis of environmental samples

International Nuclear Information System (INIS)

Tolgyessy, J.

1986-01-01

The term ''radioactive Kryptonates'' is used for substances into which atoms or ions of the radioactive nuclide 85 Kr are incorporated. The basis of the use of radioactive Kryptonates in analytical chemistry is that during a chemical reaction the crystalline lattice of the kryptonated carrier is destroyed, the carrier consumed, and the radioactive krypton released (radio-release method). Analysis can be made with a calibration curve or by comparison with a standard. Radio-release methods with the aid of radioactive Kryptonates as analytical reagents are very useful for the analysis of environmental samples, e.g. for the determination of air pollutants (ozone, sulphur dioxide, fluorine, hydrogen fluoride, mercury); and water pollutants (oxygen, dichromate, vanadium, hydrochloric acid, sulphur dioxide). (author)

Non-unique factorizations algebraic, combinatorial and analytic theory

CERN Document Server

Geroldinger, Alfred

2006-01-01

From its origins in algebraic number theory, the theory of non-unique factorizations has emerged as an independent branch of algebra and number theory. Focused efforts over the past few decades have wrought a great number and variety of results. However, these remain dispersed throughout the vast literature. For the first time, Non-Unique Factorizations: Algebraic, Combinatorial, and Analytic Theory offers a look at the present state of the theory in a single, unified resource.Taking a broad look at the algebraic, combinatorial, and analytic fundamentals, this book derives factorization results and applies them in concrete arithmetical situations using appropriate transfer principles. It begins with a basic introduction that can be understood with knowledge of standard basic algebra. The authors then move to the algebraic theory of monoids, arithmetic theory of monoids, the structure of sets of lengths, additive group theory, arithmetical invariants, and the arithmetic of Krull monoids. They also provide a s...

Recent advances in nuclear techniques for environmental radioactivity monitoring

International Nuclear Information System (INIS)

Kumar, Ajay; Tripathi, R.M.

2016-01-01

The environmental radioactivity monitoring was first started in the late 1950s following the global fallout from testing of nuclear weapons in the atmosphere. Nuclear analytical techniques are generally classified into two categories: destructive and non-destructive. Destructive techniques are carried out through several analytical methods such as α-spectrometry, liquid Scintillation counting system, solid state nuclear track detector, spectrophotometry, fluorimetry, atomic absorption spectrometry (AAS), inductively coupled plasma mass spectrometry (ICP-MS), inductively coupled plasma optical emission spectrometry (ICP-OES), chromatography techniques, electro-analytical techniques etc. However, nondestructive methods include gamma spectrometry, X-Ray fluorescence (XRF) spectrometry, neutron activation analysis (NAA) etc. The development of radiochemical methods and measurement techniques using alpha and gamma spectrometry have been described in brief

Analytical approach to the evaluation of nuclide transmutations

International Nuclear Information System (INIS)

Vukadin, Z.; Osmokrovic, P.

1995-01-01

Analytical approach to the evaluation of nuclide concentrations in a transmutation chain is presented. Non singular Bateman coefficients and depletion functions are used to overcome numerical difficulties when applying well-known Bateman solution of a simple radioactive decay. Method enables evaluation of complete decay chains without elimination of short lived radionuclides. It is efficient and accurate. Practical application of the method is demonstrated by computing the neptunium series inventory in used Candu TM fuel. (author)

Analysis of high-level radioactive slurries as a method to reduce DWPF turnaround times

International Nuclear Information System (INIS)

Coleman, C.J.; Bibler, N.E.; Ferrara, D.M.; Hay, M.S.

1996-01-01

Analysis of Defense Waste Processing Facility (DWPF) samples as slurries rather than as dried or vitrified samples is an effective way to reduce sample turnaround times. Slurries can be dissolved with a mixture of concentrated acids to yield solutions for elemental analysis by inductively coupled plasma-atomic emission spectroscopy (ICP-AES). Slurry analyses can be performed in eight hours, whereas analyses of vitrified samples require up to 40 hours to complete. Analyses of melter feed samples consisting of the DWPF borosilicate frit and either simulated or actual DWPF radioactive sludge were typically within a range of 3--5% of the predicted value based on the relative amounts of sludge and frit added to the slurry. The results indicate that the slurry analysis approach yields analytical accuracy and precision competitive with those obtained from analyses of vitrified samples. Slurry analyses offer a viable alternative to analyses of solid samples as a simple way to reduce analytical turnaround times

Radioactivity in the pelagic fish. II. Group separation of radioactive elements in fish tissues

Energy Technology Data Exchange (ETDEWEB)

Yamada, K; Tozawa, H; Amano, K; Takase, A

1955-01-01

Analytical group separation was performed with various ashed tissues of some fishes exposed to radioactive ash. The radioactivity was particularly large with elements belonging to the 3rd group, both A and B subgroups. The 2nd group showed considerable activity in pyloric ceca and kidney of Skipjacks. The radioactivity of the 1st and 4th groups was detected in some tissues; the 5th group showed slight activity.

Radioactive waste from non-licensed activities - identification of waste, compilation of principles and guidance, and proposed system for final management

International Nuclear Information System (INIS)

Jones, C.; Pers, K.

2001-07-01

Presently national guidelines for the handling of radioactive waste from non-licensed activities are lacking in Sweden. Results and information presented in this report are intended to form a part of the basis for decisions on further work within the Swedish Radiation Protection Institute on regulations or other guidelines on final management and final disposal of this type of waste. An inventory of radioactive waste from non-licensed activities is presented in the report. In addition, existing rules and principles used in Sweden - and internationally - on the handling of radioactive and toxic waste and non-radioactive material are summarized. Based on these rules and principles a system is suggested for the final management of radioactive material from non-licensed activities. A model is shown for the estimation of dose as a consequence of leaching of radio-nuclides from different deposits. The model is applied on different types of waste, e.g. peat ashes, light concrete and low-level waste from a nuclear installation

Evaluation of non-radioactive endpoints of ex vivo local lymph node assay-BrdU to investigate select contact sensitizers.

Science.gov (United States)

Ulker, Ozge Cemiloglu; Ates, Ilker; Atak, Aysegul; Karakaya, Asuman

2013-01-01

The present study sought to verify the utility of the non-radioactive endpoints LLNA BrdU (5-bromo-2'-deoxyuridine) ex vivo incorporation and cytokine release using auricular lymph node cells isolated from BALB/c mice topically treated with a strong (formaldehyde or p-phenylene-diamine [PPD]), moderate sensitizer (cinnamal), or weak sensitizer (eugenol). Stimulation index (SI) and EC₃ values were calculated for each agent. Based on the results of ex vivo LLNA-BrdU assays, EC₃ values were calculated to be 0.29, 0.09, 1.91, and 16.60% for formaldehyde, PPD, cinnamal, and eugenol, respectively. These results were in good agreement with data from previous standard radioactive LLNA. Cytokine analyses indicated T(H)1 and T(H)2 cytokine involvement in the regulation of murine contact allergy and these could be utilized as endpoints in assessments of contact allergy in mice. In conclusion, the current study provided evidence that the non-radioactive endpoint LLNA BrdU ex vivo incorporation could be of use as a viable alternative approach to assess the skin sensitization potential of test compound with respect to improving animal welfare. This is of particular importance in the case of any laboratory where it might be difficult to handle and/or readily employ radioisotopes. Further studies will be required to confirm--across test agents--the reproducibility as well as the limits of utility of this new ex vivo BrdU method.

Radioactive cesium content in selected food products. Pt. 2. Radioactive cesium in daily food rations of selected population groups

International Nuclear Information System (INIS)

Skibniewska, K.; Smoczynski, S.S.; Wisniewska, I.

1993-01-01

The content of radioactive cesium isotopes emitting beta radiation was studied in daily food rations analysed in diets of working-class and non-working-class families from food products from the regions of Olsztyn, Poznan, Lublin, Warsaw and Wroclaw in 1987 and 1988. In 1987 the highest level of radioactive cesium was found in the food rations in Olsztyn, and lowest in the rations in Poznan (3.32 and 0.65 Bq/kg respectively). In 1988 higher radiocesium content was found in rations composed according to the data on the diet consumed daily in non-working-class families. In that case the highest content was in the daily food rations composed in Warsaw - 2.35 Bq/kg and lowest in Poznan - 1.19 Bq/kg in the daily food rations of working-class families about one half of that value was found. The calculated means values of both analysed rations were: 1.35 for Olsztyn, 0.89 for Poznan, and 1.86 Bq/kg for Warsaw. The calculated mean value of the contamination with radioactive cesium was in 1988 0.93 Bq/kg for the rations in working-class families (in 1987 it was 1.80 Bq/kg). (author). 15 refs, 1 tab

Analytical Chemistry Division annual progress report for period ending December 31, 1985

International Nuclear Information System (INIS)

Shultz, W.D.

1986-05-01

Progress reports are presented for the four major sections of the division: analytical spectroscopy, radioactive materials laboratories, inorganic chemistry, and organic chemistry. A brief discussion of the division's role in the Laboratory's Environmental Restoration and Facilities Upgrade is given. Information about quality assurance and safety programs is presented, along with a tabulation of analyses rendered. Publications, oral presentations, professional activities, educational programs, and seminars are cited

Analytical method for solving radioactive transformations

International Nuclear Information System (INIS)

Vukadin, Z.

1999-01-01

The exact method of solving radioactive transformations is presented. Nonsingular Bateman coefficients, which can be computed using recurrence formulas, greatly reduce computational time and eliminate singularities that often arise in problems involving nuclide transmutations. Depletion function power series expansion enables high accuracy of the performed calculations, specially in a case of a decay constants with closely spaced values. Generality and simplicity of the method make the method useful for many practical applications. (author)

Treating radioactive effluent

International Nuclear Information System (INIS)

Kirkham, I.A.

1981-01-01

In the treatment of radioactive effluent it is known to produce a floc being a suspension of precipitates carrying radioactive species in a mother liquor containing dissolved non-radioactive salts. It is also known and accepted practice to encapsulate the floc in a solid matrix by treatment with bitumen, cement and the like. In the present invention the floc is washed with water prior to encapsulation in the solid matrix whereby to displace the mother liquor containing the dissolved non-radioactive salts. This serves to reduce the final amount of solidified radioactive waste with consequent advantages in the storage and disposal thereof. (author)

Study by X-ray diffraction of the crystalline structure versus time of a radioactive implanted coral and of a non radioactive implanted coral

International Nuclear Information System (INIS)

Irigaray, J.L.; Oudadesse, H.; Sauvage, T.; El Fadl, H.

1993-01-01

The corals used as biomaterials in bone surgery consist of 98% calcium carbonate in the form of aragonite and have orthorhombic crystalline structure. This structure changes progressively into a bone structure in an hexagonal form when the coral is implanted in cortical or spongy surroundings. For this experiment, a radioactive and a non radioactive coral have been implanted in the metaphysics of the ovine femur. The transformation of the orthorhombic structure into the hexagonal bone structure has been studied for the two types of implant. This makes it possible to verify if radioactivity modifies the process of transformation of the implanted biocoral. (K.A.) 3 refs.; 7 figs

Study by X-ray diffraction of the crystalline structure versus time of a radioactive implanted coral and of a non radioactive implanted coral

Energy Technology Data Exchange (ETDEWEB)

Irigaray, J.L.; Oudadesse, H.; Sauvage, T.; El Fadl, H. [Clermont-Ferrand-2 Univ., 63 - Aubiere (France). Lab. de Physique Corpusculaire; Lefevre, J.; Barlet, J.P. [Institut National de Recherches Agronomiques, 63 -Saint-Genes-Champanelle (France)

1993-12-31

The corals used as biomaterials in bone surgery consist of 98% calcium carbonate in the form of aragonite and have orthorhombic crystalline structure. This structure changes progressively into a bone structure in an hexagonal form when the coral is implanted in cortical or spongy surroundings. For this experiment, a radioactive and a non radioactive coral have been implanted in the metaphysics of the ovine femur. The transformation of the orthorhombic structure into the hexagonal bone structure has been studied for the two types of implant. This makes it possible to verify if radioactivity modifies the process of transformation of the implanted biocoral. (K.A.) 3 refs.; 7 figs.

Manual of selected physico-chemical analytical methods. IV

International Nuclear Information System (INIS)

Beran, M.; Klosova, E.; Krtil, J.; Sus, F.; Kuvik, V.; Vrbova, L.; Hamplova, M.; Lengyel, J.; Kelnar, L.; Zakouril, K.

1990-11-01

The Central Testing Laboratory of the Nuclear Research Institute at Rez has for a decade been participating in the development of analytical procedures and has been providing analyses of samples of different types and origin. The analytical procedures developed have been published in special journals and a number of them in the Manuals of analytical methods, in three parts. The 4th part of the Manual contains selected physico-chemical methods developed or modified by the Laboratory in the years 1986-1990 within the project ''Development of physico-chemical analytical methods''. In most cases, techniques are involved for non-nuclear applications. Some can find wider applications, especially in analyses of environmental samples. Others have been developed for specific cases of sample analyses or require special instrumentation (mass spectrometer), which partly restricts their applicability by other institutions. (author)

Application of digital radiography for the non-destructive characterization of radioactive waste packages

International Nuclear Information System (INIS)

Lierse, C.; Goebel, H.; Kaciniel, E.; Buecherl, T.; Krebs, K.

1995-01-01

Digital radiography (DR) using gamma-rays is a powerful tool for the non-destructive determination of various parameters which are relevant within the quality control procedure of radioactive waste packages prior to an interim storage or a final disposal. DR provides information about the waste form and the extent of filling in a typical container. It can identify internal structures and defects, gives their geometric dimensions and helps to detect non-declared inner containers, shielding materials etc. From a digital radiographic image the waste matrix homogeneity may be determined and mean attenuation coefficients as well as density values for selected regions of interest can be calculated. This data provides the basis for an appropriate attenuation correction of gamma emission measurements (gamma scanning) and makes a reliable quantification of gamma emitters in waste containers possible. Information from DR measurements are also used for the selection of interesting height positions of the object which are subsequently inspected in more detail by other non-destructive methods, e. g. by transmission computerized tomography (TCT). The present paper gives important technical specifications of an integrated tomography system (ITS) which is used to perform digital radiography as well as transmission/emission computerized tomography (TCT/ECT) on radioactive waste packages. It describes the DR mode and some of its main applications and shows typical examples of radiographs of real radioactive waste drums

Validation of radioactivity measurements under the Safe Drinking Water Act

International Nuclear Information System (INIS)

Goldin, Abraham S.

1978-01-01

Radioactivity measurements are made under the Safe Drinking Water Act to obtain information on the potential radiological hazard of water and to institute regulatory action when water quality does not meet requirements. Measurements must be both precise and accurate if these goals are to be met. Regulations issued under the act require that analyses be performed by approved (certified) laboratories, which must carry out quality assurance programs. This paper briefly describes the certification requirements and discusses the components of an effective quality assurance program. The Environmental Protection Agency has established procedures for the certification of laboratories making radioactivity measurements of drinking water. These procedures recommend minimum laboratory qualifications for personnel, facilities, equipment, and procedures; proficiency testing by analysis of samples provided by the Agency; and operation of a quality assurance program. A major function of a quality assurance program is to provide the Laboratory Director an ongoing flow of information on laboratory analytical performance. A properly designed and conducted program provides this information in a timely manner, indicates areas where discrepancies exist, and often suggests ways of correcting the discrepancies. Pertinent aspects of radioactivity measurements for drinking water are discussed, including how analyses of blanks, blind duplicates, and reference samples contribute needed information, and evaluations by control charts and statistical analyses. Examples of the usefulness of quality control in correcting both procedural and background problems are given. (author)

Destructive and non-destructive tests for radioactive waste packages Task 3 Characterization of radioactive waste forms. A series of final reports (1985-89) No 43

International Nuclear Information System (INIS)

Odoj, R.

1991-01-01

On the basis of preliminary waste acceptance requirements quality control of radioactive waste has to be performed prior to interim storage or final disposal. The quality control can either be achieved by random tests on conditioned radioactive waste packages or by process qualification of the conditioning processes. One of the most important criteria is the activity of the radioactive waste product or packages. To get some first information on the waste package γ-spectrometric measurement is performed as non-destructive test. Besides the γ-emitting nuclides the α and β-emitting nuclides can be estimated by calculation if the waste was generated in nuclear power plants and the nuclide relations are known. If the non-destructive determination of nuclides is not sufficient or the non-radioactive content of the waste packages has to be identified sampling from the waste packages has to be performed. This can best be done by core drilling. To avoid the need of water for cooling the drill head, air cooled core drilling is investigated. As mixed wastes is not allowed for final disposal the determination of possible organic toxic materials like PCB, dioxin and furane-compounds in cemented wastes is conducted by GC-MS-investigations. For getting more knowledge in the field of process qualification concerning super compaction, instrumentation of the super compaction process is investigated and tested

The non-agricultural areas of Canada and radioactivity

International Nuclear Information System (INIS)

Meyerhof, Dorothy; Marshall, Heather

1990-01-01

Approximately 90% of the Canadian land mass is non-agricultural. It is a source of food to native peoples and sport hunters. Although agricultural areas have been extensively monitored for the transfer of radionuclides through the food chain, very little work has been done on radionuclides in the natural environment in Canada. The exceptions are specific problems such as radiocesium in the lichen-caribou food chain in the Arctic and natural radioactivity in the vicinity of uranium mines. A systematic study of natural food chains is being initiated. This paper presents the results of the study so far and proposed future directions. (author)

Analytical Chemistry Division annual progress report for period ending December 31, 1985

Energy Technology Data Exchange (ETDEWEB)

Shultz, W.D.

1986-05-01

Progress reports are presented for the four major sections of the division: analytical spectroscopy, radioactive materials laboratories, inorganic chemistry, and organic chemistry. A brief discussion of the division's role in the Laboratory's Environmental Restoration and Facilities Upgrade is given. Information about quality assurance and safety programs is presented, along with a tabulation of analyses rendered. Publications, oral presentations, professional activities, educational programs, and seminars are cited.

A National system for the Management of Non-nuclear Radioactive Waste in Sweden

International Nuclear Information System (INIS)

Lindhe, J. C.

2004-01-01

The Swedish government in May 2002 set up a non-standing committee for non-nuclear radioactive waste. The objective was to suggest a national system for the management of all types of non-nuclear radioactive waste with special consideration to the principle of polluter pays and the responsibility of the producers. The committee delivered its recommendations to the government at the end of last year. Funding for future costs for nuclear waste management and final storage is collected in a state governed funding system. For non-nuclear waste, however, there are no means today to secure the funding. If a company goes bankrupt and leaves radioactive waste behind it might be up to the taxpayers to pay for its safe management. This is due to the fact that the cost for the waste is paid at the time one wants to dispose of it and it is usually the last owner of a product etc. that has to pay. Sometimes the price comes as a surprise and the owner might not have the money available. Thus the waste might be kept longer than otherwise and might even end up as orphan waste. To solve this dilemma the committee recommends a funding system in parallel with the system for the nuclear waste. The cost for the waste should be paid up front before the waste has been created. E.g. when a customer buys a product the cost for the future waste management would be included in the price and he will not have to pay for this the day he disposes the product by returning it to the producer or leaves it to a waste-collecting organisation. It should be the responsibility of the producer (manufacturer, importer or re-seller) to guarantee the funding for the waste management. In summary the non-nuclear radioactive waste is divided into three main groups: waste from products, waste from practices and other waste. Waste from products includes household products as well as products used in research, industry and hospitals etc. For this category it is easy to identify a producer who imports or

LA-ICP-MS for Trace Analysis of Long-Lived Radionuclides in Solid Non-conducting Radioactive Waste Samples

International Nuclear Information System (INIS)

Becker, J.S.; Gastel, M.; Tenzler, D.; Dietze, H.J.

1999-01-01

The characterization of radioactive waste materials from nuclear reactors for recycling and final storage requires fast, sensitive and precise analytical methods, which are able to determine long-lived radionuclidic ultra traces in a short time. For the determination of long-lived α and β ray-emitting nuclides besides the classical radiochemical methods which are mostly include time-consuming radiochemical separation procedures, to an increasing extent inductively coupled plasma mass spectrometry (ICP-MS) has been used successfully as a powerful trace, ultra trace and isotopic analytical method for the determination of long-lived radionuclides in aqueous solutions [1-3

Analytical results for non-Hermitian parity–time-symmetric and ...

Indian Academy of Sciences (India)

Abstract. We investigate both the non-Hermitian parity–time-(PT-)symmetric and Hermitian asymmetric volcano potentials, and present the analytical solution in terms of the confluent Heun function. Under certain special conditions, the confluent Heun function can be terminated as a polynomial, thereby leading to certain ...

Recommendations for sampling for prevention of hazards in civil defense. On analytics of chemical, biological and radioactive contaminations. Brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling; Empfehlungen fuer die Probenahme zur Gefahrenabwehr im Bevoelkerungsschutz. Zur Analytik von chemischen, biologischen und radioaktiven Kontaminationen. Kurzanleitung fuer die CBRN-Probenahme

Energy Technology Data Exchange (ETDEWEB)

Bachmann, Udo; Biederbick, Walter; Derakshani, Nahid (and others)

2010-07-01

The recommendation for sampling for prevention of hazards in civil defense is describing the analytics of chemical, biological and radioactive contaminations and includes detail information on the sampling, protocol preparation and documentation procedures. The volume includes a separate brief instruction for the CBRN (chemical, biological, radioactive, nuclear) sampling.

Characterization and source term assessments of radioactive particles from Marshall Islands using non-destructive analytical techniques

Science.gov (United States)

Jernström, J.; Eriksson, M.; Simon, R.; Tamborini, G.; Bildstein, O.; Marquez, R. Carlos; Kehl, S. R.; Hamilton, T. F.; Ranebo, Y.; Betti, M.

2006-08-01

Six plutonium-containing particles stemming from Runit Island soil (Marshall Islands) were characterized by non-destructive analytical and microanalytical methods. Composition and elemental distribution in the particles were studied with synchrotron radiation based micro X-ray fluorescence spectrometry. Scanning electron microscope equipped with energy dispersive X-ray detector and with wavelength dispersive system as well as a secondary ion mass spectrometer were used to examine particle surfaces. Based on the elemental composition the particles were divided into two groups: particles with pure Pu matrix, and particles where the plutonium is included in Si/O-rich matrix being more heterogenously distributed. All of the particles were identified as nuclear fuel fragments of exploded weapon components. As containing plutonium with low 240Pu/ 239Pu atomic ratio, less than 0.065, which corresponds to weapons-grade plutonium or a detonation with low fission yield, the particles were identified to originate from the safety test and low-yield tests conducted in the history of Runit Island. The Si/O-rich particles contained traces of 137Cs ( 239 + 240 Pu/ 137Cs activity ratio higher than 2500), which indicated that a minor fission process occurred during the explosion. The average 241Am/ 239Pu atomic ratio in the six particles was 3.7 × 10 - 3 ± 0.2 × 10 - 3 (February 2006), which indicated that plutonium in the different particles had similar age.

Radioactive waste and transport. Chapter 6

International Nuclear Information System (INIS)

1978-01-01

A brief definition of the nature of radioactive waste is followed by a more detailed discussion of high level waste, its composition the amounts involved, storage in liquid and in solid form and the storage of non-reprocessed spent fuel. The final disposal of high level waste in deep geological structures is then described, based on the Swedish KBS study. The effectiveness of the artificial and natural barriers in preventing the radioactive substances from reaching the biosphere is discussed. American and Swedish risk analyses are briefly discussed, and practical experience presented. Low and medium level wastes are thereafter treated in a similar, though briefer manner. Transport of radioactive materials, fresh fuel, spent fuel and waste is then dealt with. Regulations for the containers and their tests are briefly presented and the risk of accidents, theft and sabotage during transport are discussed. (JIW)

Thermo-Analytical and Physico-Chemical Characterization of Woody and Non-Woody Biomass from an Agro-ecological Zone in Nigeria

Directory of Open Access Journals (Sweden)

Ayokunle Oluwabusayo Balogun

2014-07-01

Full Text Available Woody (Albizia pedicellaris and Terminalia ivorensis and non-woody (guinea corn (Sorghum bicolor glume and stalk biomass resources from Nigeria were subjected to thermo-analytical and physico-chemical analyses to determine their suitability for thermochemical processing. They were found to have comparably high calorific values (between 16.4 and 20.1 MJ kg-1. The woody biomass had very low ash content (0.32%, while the non-woody biomass had relatively high ash content (7.54%. Thermogravimetric analysis (TGA of the test samples showed significant variation in the decomposition behavior of the individual biomasses. Gas chromatography/mass spectrometry (GC/MS of fatty acid methyl esters (FAMEs derivatives indicated the presence of fatty and resin acids in the dichloromethane (CH2Cl2 extracts. Analytical pyrolysis (Py-GC/MS of the samples revealed that the volatiles liberated consisted mostly of acids, alcohols, ketones, phenols, and sugar derivatives. These biomass types were deemed suitable for biofuel applications.

High-level radioactive waste disposal type and theoretical analyses

International Nuclear Information System (INIS)

Lu Yingfa; Wu Yanchun; Luo Xianqi; Cui Yujun

2006-01-01

Study of high-level radioactive waste disposal is necessary for the nuclear electrical development; the determination of nuclear waste depository type is one of importance safety. Based on the high-level radioactive disposal type, the relative research subjects are proposed, then the fundamental research characteristics of nuclear waste disposition, for instance: mechanical and hydraulic properties of rock mass, saturated and unsaturated seepage, chemical behaviors, behavior of special soil, and gas behavior, etc. are introduced, the relative coupling equations are suggested, and a one dimensional result is proposed. (authors)

Incident involving radioactive material at IAEA Safeguards Laboratory - No radioactivity released to environment

International Nuclear Information System (INIS)

2008-01-01

Full text: Pressure build-up in a small sealed sample bottle in a storage safe resulted in plutonium contamination of a storage room at about 02:30 today at the IAEA's Safeguards Analytical Laboratory in Seibersdorf. All indications are that there was no release of radioactivity to the environment. Further monitoring around the laboratory will be undertaken. No one was working in the laboratory at the time. The Laboratory's safety system detected plutonium contamination in the storage room where the safe was located and in two other rooms - subsequently confirmed by a team of IAEA radiation protection experts. The Laboratory is equipped with multiple safety systems, including an air-filtering system to prevent the release of radioactivity to the environment. There will be restricted access to the affected rooms until they are decontaminated. A full investigation of the incident will be conducted. The IAEA has informed the Austrian regulatory authority. The IAEA's Laboratory in Seibersdorf is located within the complex of the Austrian Research Centers Seibersdorf (ARC), about 35 km southeast of Vienna. The laboratory routinely analyses small samples of nuclear material (uranium or plutonium) as part of the IAEA's safeguards verification work. (IAEA)

Radioactivity monitoring of Irish dairy produce

International Nuclear Information System (INIS)

Kelleher, K.

2010-01-01

Full text: The RPII has been carrying out monitoring of milk and dairy produce since 1986. Milk samples are routinely analysed for radiocaesium and strontium-90 as part of the RPII's environmental monitoring programme to determine the doses received to the Irish population from milk consumption. The method the RPII utilises for determining the Sr-90 activity in milk is by measuring the Cerenkov radiation produced by its daughter 90 Y isolated from interfering nuclides such as uranium, thorium, radium and their decay products as well as isotopes of caesium, potassium and strontium by extraction with 10% di-(2-ethylhexyl)phosphate (HDEHP) in toluene. The chemical yield of 90 Y is determined by the acidmetric titration of yttrium nitrate carrier with titriplex III. The levels of Sr-90 and dose to the Irish population from milk consumption have been negligible when compared to other radioactive sources in the Irish environment. Other dairy products are analysed for radiocaesium on a routine basis for commercial customers to ensure the levels of radioactivity in the dairy products fall within EC regulations governing the export/import of dairy produce. The export of milk and milk produce from Ireland is a very important industry, 80% of dairy products produced in Ireland are exported and these exports are worth Euro 2.2 billion annually to the Irish economy. The dairy products are analysed by gamma spectroscopy and include full and skim milk powders, butter, casein, cheese, cream, whey and lactose. The levels of radiocaesium in these products are typically below 5 Bk/kg and fall well within the limit of 370 Bq/kg laid down by the European Community in Council Regulation 737/90. Although the levels of these radionuclides are relatively low the RPII recognises the importance of analysing these samples for radioactivity to inform the public, ensure consumer confidence and, more importantly, to maintain a level of expertise in the RPII in these analytical techniques so that

Radioactivity monitoring of Irish dairy produce

Energy Technology Data Exchange (ETDEWEB)

Kelleher, K. (Radiological Protection Institute of Ireland. Radiation Monitoring, Dublin (Ireland))

2010-03-15

Full text: The RPII has been carrying out monitoring of milk and dairy produce since 1986. Milk samples are routinely analysed for radiocaesium and strontium-90 as part of the RPII's environmental monitoring programme to determine the doses received to the Irish population from milk consumption. The method the RPII utilises for determining the Sr-90 activity in milk is by measuring the Cerenkov radiation produced by its daughter 90Y isolated from interfering nuclides such as uranium, thorium, radium and their decay products as well as isotopes of caesium, potassium and strontium by extraction with 10% di-(2-ethylhexyl)phosphate (HDEHP) in toluene. The chemical yield of 90Y is determined by the acidmetric titration of yttrium nitrate carrier with titriplex III. The levels of Sr-90 and dose to the Irish population from milk consumption have been negligible when compared to other radioactive sources in the Irish environment. Other dairy products are analysed for radiocaesium on a routine basis for commercial customers to ensure the levels of radioactivity in the dairy products fall within EC regulations governing the export/import of dairy produce. The export of milk and milk produce from Ireland is a very important industry, 80% of dairy products produced in Ireland are exported and these exports are worth Euro 2.2 billion annually to the Irish economy. The dairy products are analysed by gamma spectroscopy and include full and skim milk powders, butter, casein, cheese, cream, whey and lactose. The levels of radiocaesium in these products are typically below 5 Bk/kg and fall well within the limit of 370 Bq/kg laid down by the European Community in Council Regulation 737/90. Although the levels of these radionuclides are relatively low the RPII recognises the importance of analysing these samples for radioactivity to inform the public, ensure consumer confidence and, more importantly, to maintain a level of expertise in the RPII in these analytical techniques so

Characterization and source term assessments of radioactive particles from Marshall Islands using non-destructive analytical techniques

Energy Technology Data Exchange (ETDEWEB)

Jernstroem, J. [Laboratory of Radiochemistry, Department of Chemistry, P.O. Box 55, FI-00014 University of Helsinki (Finland)]. E-mail: jussi.jernstrom@helsinki.fi; Eriksson, M. [IAEA-MEL, International Atomic Energy Agency - Marine Environment Laboratory, 4 Quai Antoine 1er, MC 98000 Monaco (Monaco); Simon, R. [Institute for Synchrotron Radiation, Forschungszentrum Karlsruhe GmbH, D-76021 Karlsruhe (Germany); Tamborini, G. [European Commission, Joint Research Centre, Institute for Transuranium Elements, P.O. Box 2340, D-76125 Karlsruhe (Germany); Bildstein, O. [European Commission, Joint Research Centre, Institute for Transuranium Elements, P.O. Box 2340, D-76125 Karlsruhe (Germany); Marquez, R. Carlos [European Commission, Joint Research Centre, Institute for Transuranium Elements, P.O. Box 2340, D-76125 Karlsruhe (Germany); Kehl, S.R. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94551-0808 (United States); Hamilton, T.F. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94551-0808 (United States); Ranebo, Y. [European Commission, Joint Research Centre, Institute for Transuranium Elements, P.O. Box 2340, D-76125 Karlsruhe (Germany); Betti, M. [European Commission, Joint Research Centre, Institute for Transuranium Elements, P.O. Box 2340, D-76125 Karlsruhe (Germany)]. E-mail: maria.betti@ec.europa.eu

2006-08-15

Six plutonium-containing particles stemming from Runit Island soil (Marshall Islands) were characterized by non-destructive analytical and microanalytical methods. Composition and elemental distribution in the particles were studied with synchrotron radiation based micro X-ray fluorescence spectrometry. Scanning electron microscope equipped with energy dispersive X-ray detector and with wavelength dispersive system as well as a secondary ion mass spectrometer were used to examine particle surfaces. Based on the elemental composition the particles were divided into two groups: particles with pure Pu matrix, and particles where the plutonium is included in Si/O-rich matrix being more heterogenously distributed. All of the particles were identified as nuclear fuel fragments of exploded weapon components. As containing plutonium with low {sup 240}Pu/{sup 239}Pu atomic ratio, less than 0.065, which corresponds to weapons-grade plutonium or a detonation with low fission yield, the particles were identified to originate from the safety test and low-yield tests conducted in the history of Runit Island. The Si/O-rich particles contained traces of {sup 137}Cs ({sup 239+240}Pu/{sup 137}Cs activity ratio higher than 2500), which indicated that a minor fission process occurred during the explosion. The average {sup 241}Am/{sup 239}Pu atomic ratio in the six particles was 3.7 x 10{sup -3} {+-} 0.2 x 10{sup -3} (February 2006), which indicated that plutonium in the different particles had similar age.

Beyond low-level activity: On a 'non-radioactive' gas mantle

International Nuclear Information System (INIS)

Poljanc, Karin; Steinhauser, Georg; Sterba, Johannes H.; Buchtela, Karl; Bichler, Max

2007-01-01

Gas mantles for camping gas lanterns sometimes contain thorium compounds. During the last years, the use of thorium-free gas mantles has become more and more popular due to the avoidance of a radioactive heavy metal. We investigated a gas mantle type that is declared to be 'non-radioactive' and that can be bought in Austria at the moment. Methods used were Instrumental Neutron Activation Analysis (INAA), γ-spectroscopy, and Liquid Scintillation Counting (LSC). We found massive thorium contents of up to 259 mg per gas mantle. Leaching experiments showed that only 0.4% of the Th but approximately 90% of the decay products of 232 Th can be leached under conditions simulating sucking and chewing with human saliva. In this paper, the investigation of these gas mantles including the consideration of the environmental hazard caused by disposed mantles and the health hazard for unsuspecting consumers is presented and legal consequences are discussed for this fraud

Analytical solutions of time-fractional models for homogeneous Gardner equation and non-homogeneous differential equations

Directory of Open Access Journals (Sweden)

Olaniyi Samuel Iyiola

2014-09-01

Full Text Available In this paper, we obtain analytical solutions of homogeneous time-fractional Gardner equation and non-homogeneous time-fractional models (including Buck-master equation using q-Homotopy Analysis Method (q-HAM. Our work displays the elegant nature of the application of q-HAM not only to solve homogeneous non-linear fractional differential equations but also to solve the non-homogeneous fractional differential equations. The presence of the auxiliary parameter h helps in an effective way to obtain better approximation comparable to exact solutions. The fraction-factor in this method gives it an edge over other existing analytical methods for non-linear differential equations. Comparisons are made upon the existence of exact solutions to these models. The analysis shows that our analytical solutions converge very rapidly to the exact solutions.

The fundamentals of the Russian Federation National Policy in the non-nuclear fuel cycle radioactive waste management

International Nuclear Information System (INIS)

Latypov, E.M.; Rikunov, V.A.

1995-01-01

Extensive manufacture and use of sources of ionizing radiation result inevitably in the generation of a considerable amount of radioactive waste. The crucial objective within the context of the general problem of radioactive waste management involves the safe isolation of radioactive waste from the environment for the entire period of the existence of their potential hazardous impacts upon it. The complex nature of the problem requires substantial efforts to be placed for the establishment of an integrated radioactive waste management system providing a national control in medicine, industry and science. To this end, the fundamentals of the national policy for the safe management of radioactive waste from non-nuclear fuel cycle activities are being developed in the Russian Federation. The essential components of the national policy are: development of a scientifically sound concept of radioactive waste management; adoption of legislative documents such as standards and acts, relevant to this area; implementation and enforcement of state regulations and supervision of the relevant activities; development of a national programme on radioactive waste management; provision and maintaining of a national radioactive waste inventory; radiation monitoring

Assessments of the thermal evolution for a radioactive waste final repository using analytical methods

International Nuclear Information System (INIS)

Radut, A. C.; Roman, M. R.; Florea, S.; Ionescu, D. V.; Olteanu, G.; Valeca, S.

2016-01-01

In the designing process for a radioactive final repository concept, the temperature evolution over time is a significant issue for the stability and long-term safety of entire emplacement. In particular, the maximum value of temperature in the whole structure, during time, must not exceed a certain safety value which depends, beside other criteria, on the bulk material of the repository. A computer code TEMPROC, based on analytical model for the transient thermal heat conduction, described in this paper, was developed inside ''Fuel Performance''Department from ICN Pitesti, in order to evaluate the waste repository's temperature distribution. The program was developed under ''Microsoft FORTRAN Power Station''platform that provides IMSL subroutines library support for numeric algorithm. So the program is relative small, with a good calculus speed. The numerical results obtained with TEMPROC computer code, have been acceptably compared with similar existing data from scientific literature [1]. (authors)

Installation for analytic chemistry under irradiation

International Nuclear Information System (INIS)

Fradin, J.; Azoeuf, P.; Guillon, A.

1966-01-01

An installation has been set up for carrying out manipulations and chemical analyses on radioactive products. It is completely remote-controlled and is of linear shape, 15 metres long; it is made up of three zones: - an active zone containing the apparatus, - a rear zone giving access to the active zone, - a forward zone independent of the two others and completely protected from which the remote-control of the apparatus is effected. The whole assembly has been designed so that each apparatus corresponding to an analytical technique is set up in a sealed enclosure. The sealed enclosures are interconnected by a conveyor. After three years operation, a critical review is now made of the installation. (authors) [fr

Recommendations for sampling for prevention of hazards in civil defense. On analytics of chemical, biological and radioactive contaminations. 2. ed.; Empfehlungen fuer die Probenahme zur Gefahrenabwehr im Bevoelkerungsschutz. Zur Analytik von chemischen, biologischen und radioaktiven Kontaminationen

Energy Technology Data Exchange (ETDEWEB)

Bachmann, Udo; Derakshani, Nahid; Drobig, Matthias; Koenig, Mario; Mentfewitz, Joachim; Prast, Hartmut; Uelpenich, Gerhard; Vidmayer, Marc; Wilbert, Stefan; Wolf, Manfred

2016-07-01

The recommendations for sampling for prevention of hazards in civil defense (analytics of chemical, biological and radioactive contaminations) cover the following topics: Requirements for sampling, description of the materials (chemical, biological and radioactive contaminated materials), decontamination, sample transport and protocol documents.

Prompt-gamma neutron activation analysis for the non-destructive characterization of radioactive wastes; Prompt-Gamma-Neutronen-Aktivierungs-Analyse zur zerstoerungsfreien Charakterisierung radioaktiver Abfaelle

Energy Technology Data Exchange (ETDEWEB)

Kettler, John Paul Hermann

2010-07-01

In Germany, stringent official regulations govern the handling and final storage of radioactive waste. For this reason, the Federal Government has opted for final storage of radioactive waste with negligible heat generation in deep geological formations. At present the Konrad mine in Salzgitter will be rebuilt as a final disposal, the start of operation is scheduled for 2014. Radioactive waste with negligible heat generation originates from the operation and decommissioning of nuclear power plants, the medical sector or from research establishments. The requirements of the planning approval decision to build up the disposal Konrad, published on the 22{sup nd} of May 2002, obligate the waste producer to consider the limits for chemotoxic substances and to document the waste content. Before the radioactive waste can be stored in the final disposal, it is necessary to characterize the waste composition, relating to the concentration of water polluting substances. In particular for the wastes produced in the year before 1990, the so-called old wastes, there is a lack of documentation. The chemotoxicity of old wastes can mostly only characterized by time consuming and destructive methods. Furthermore these methods produce high costs, which depend on the arrangements to avoid contamination, to comply with the radiation protection and for the conditioning of the wastes. A prototype system, based on the Prompt-Gamma-Neutron-Activation-Analysis (PGNAA) with 14 MeV neutrons, has been developed in this work. This system allows the characterization of large samples, like 25 and 50 l drums. The signature of the element composition is in this processed by gamma-ray spectroscopy. This work was focused, in addition to the feasibility of the system, to the neutron and photon transport in large samples. Therefore the neutron and photon self-absorption in dependence of the sample composition were the main part of interest. Computer simulations (MCNP) and experiments were performed to

Preparation process of a stable non radioactive carrier intended for radiodiagnosis

International Nuclear Information System (INIS)

Molinski, V.J.; Wilczewski, J.A.

1976-01-01

The description is given of a stable non radioactive carrier with a pH of around 2 and around 4, for cardiological studies, exploring the blood in circulation and exploring the brain, after labelling with sup(99m)Tc. It includes human serum albumin (SAH) and stannous tartrate, the proportion in weight between the SAH and stannous tartrate being between around 50:1 and around 150:1 [fr

Activation analyses updating the ITER radioactive waste assessment

International Nuclear Information System (INIS)

Pampin, R.; Zheng, S.; Lilley, S.; Na, B.C.; Loughlin, M.J.; Taylor, N.P.

2012-01-01

Highlights: ► Comprehensive updated of ITER radwaste assessment. ► Latest coupled neutronics and activation methods. ► Type A waste at shutdown decays to TFA within 100 years. ► Most type B waste at shutdown is still type B after 100 years. - Abstract: A study is reported which computes the radiation transport and activation response throughout the ITER machine and updates the ITER radioactive waste assessment using modern 3D models and up-to-date methods. The latest information on component design, maintenance, replacement schedules and materials is adopted. The radwaste classification is revised for all the major components of ITER, as well as several representative port plugs. Results include categorisation snapshots at different decay times, time histories of radiological quantities throughout the machine, and guidelines on interim decay times for components. All plasma-facing materials except tungsten are found to classify as type B due to the transmutation of their main constituents. Major contributors to the IRAS index of all materials are reported. Elemental concentration limits for type A classification of first wall and divertor materials are obtained; for the steels, only a reduction in service lifetime can reduce the waste class. Comparison of total waste amounts with earlier assessments is limited by the fact that analyses of some components are still preliminary; the trend, however, indicates a potential reduction in the total amount of waste if component segregation is demonstrated.

Process analytical chemistry applied to actinide waste streams

International Nuclear Information System (INIS)

Day, R.S.

1994-01-01

The Department of Energy is being called upon to clean up it's legacy of waste from the nuclear complex generated during the cold war period. Los Alamos National Laboratory is actively involved in waste minimization and waste stream polishing activities associated with this clean up. The Advanced Testing Line for Actinide Separations (ATLAS) at Los Alamos serves as a developmental test bed for integrating flow sheet development of nitric acid waste streams with process analytical chemistry and process control techniques. The wastes require processing in glove boxes because of the radioactive components, thus adding to the difficulties of making analytical measurements. Process analytical chemistry methods provide real-time chemical analysis in support of existing waste stream operations and enhances the development of new waste stream polishing initiatives. The instrumentation and methods being developed on ATLAS are designed to supply near-real time analyses on virtually all of the chemical parameters found in nitric acid processing of actinide waste. These measurements supply information on important processing parameters including actinide oxidation states, free acid concentration, interfering anions and metal impurities

Semianalytical Solutions of Radioactive or Reactive Transport in Variably-Fractured Layered Media: 1. Solutes

International Nuclear Information System (INIS)

George J. Moridis

2001-01-01

In this paper, semianalytical solutions are developed for the problem of transport of radioactive or reactive solute tracers through a layered system of heterogeneous fractured media with misaligned fractures. The tracer transport equations in the non-flowing matrix account for (a) diffusion, (b) surface diffusion, (c) mass transfer between the mobile and immobile water fractions, (d) linear kinetic or equilibrium physical, chemical, or combined solute sorption or colloid filtration, and (e) radioactive decay or first-order chemical reactions. The tracer-transport equations in the fractures account for the same processes, in addition to advection and hydrodynamic dispersion. Any number of radioactive decay daughter products (or products of a linear, first-order reaction chain) can be tracked. The solutions, which are analytical in the Laplace space, are numerically inverted to provide the solution in time and can accommodate any number of fractured and/or porous layers. The solutions are verified using analytical solutions for limiting cases of solute and colloid transport through fractured and porous media. The effect of important parameters on the transport of 3 H, 237 Np and 239 Pu (and its daughters) is investigated in several test problems involving layered geological systems of varying complexity

Effect of Radioactivity of Technetium-99m on the Autosterilization Process of non-sterile Tetrofosmin Kits

Directory of Open Access Journals (Sweden)

Widyastuti Widyastuti

2017-03-01

Full Text Available Technetium-99m labeled radiopharmaceutical is commonly used in nuclear medicines as a diagnostic agent, by mixing the sterile kit with Tc-99m. Manufacturing of kits requires an aseptic facility which need to be well designed and maintained according to cGMP, since mostly kits can not be terminally sterilized. Radiopharmaceuticals as pharmaceuticals containing radionuclide is assumed to have an autosterilization property, but correlation between radioactivity and capability of killing microorganisms has to be studied so far. The aim of this study is to investigate the effect of radioactivity on the autosterilization process of radiopharmaceuticals. The study was carried out by adding Tc-99m of various radioactivity into non-sterile tetrofosmin kits, then the samples were tested for sterility. Sterile tetrofosmin kit and non-sterile kit with no Tc-99m added will be used as a negative control and positive control respectively. The sterility was tested using standard direct inoculation method, by inoculating samples in culture media for both bacteria and fungi and observing qualitatively within 14 days. The results showed that the samples with radioactivity of 1, 3 and 5 mCi changed the clarity of the media to turbid, conformed with the performance of positive controls but samples with radioactivity of 10 mCi and 20 mCi did not change the clarity of the media, conformed with the performance of negative control, indicating neither growth of bacteria nor fungi. It is concluded that Tc-99m behaves as an autosterilizing agent at certain radioactivity. Therefore the preparation of Tc-99m radiopharmaceutical can be considered as terminal sterilization rather than aseptic preparation.

Analytical chemistry equipment for radioactive products; Installation de chimie analytique pour produits radioactifs

Energy Technology Data Exchange (ETDEWEB)

Douis, M; Guillon, A; Laurent, H; Sauvagnac, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1959-07-01

The report deals with a shielded enclosure, hermetic, for analytical examination and handling of radioactive products. Remote handling for the following is provided: pipette absorption - weighing - centrifuging - desiccation - volumetric - pH measurement - potentiometric - colorimetric - polarographic. The above list is not restrictive: the enclosure is designed for the rapid installation of other equipment. Powerfully ventilated and screened to 400 m-curies long life fission product levels by 5 cm of lead, the enclosure is fully safe to the stated level. (author) [French] La presente communication decrit une enceinte etanche et blindee permettant un travail et un controle analytique sur des produits radioactifs. Les techniques suivantes sont adaptees pour une manipulation a distance: pipettage, pesees, centrifugation, dessiccation, volumetrie, mesure de pH, potentiometrie, colorimetrie, polarographie. Cette liste n'est pas limitative. La conception de l'installation permet la mise en place rapide d'autres appareils. Protegee par 5 cm de plomb et fortement ventilee, elle donne toute securite de manipulation jusqu'a un niveau d'activite 400 mcuries en produits de fission a vie longue. (auteur)

Radionuclides in analytical chemistry

International Nuclear Information System (INIS)

Tousset, J.

1984-01-01

Applications of radionuclides in analytical chemistry are reviewed in this article: tracers, radioactive sources and activation analysis. Examples are given in all these fields and it is concluded that these methods should be used more widely [fr

Non-fuel cycle radioactive waste policy in Turkey

International Nuclear Information System (INIS)

Demirel, H.

2003-01-01

Radioactive wastes generated in Turkey are mostly low level radioactive waste generated from the operation of one research reactor, research centers and universities, hospitals, and from radiological application of various industries. Disused sealed sources which potentially represent medium and high radiological risks in Turkey are mainly Am-241, Ra-226, Kr-85, Co-60, Ir-192 and Cs-137. All radioactive waste produced in Turkey is collected, segregated, conditioned and stored at CWPSF. Main components of the facility are listed below: Liquid waste is treated in chemical processing unit where precipitation is applied. Compactable solids are compressed in a compaction cell. Spent sources are embedded into cement mortar with their original shielding. If the source activities are in several millicuries, sometimes dismantling is applied and segregated sources are conditioned in shielded drums. Due to increasing number of radiation and nuclear related activities, the waste facility of CNAEM is now becoming insufficient to meet the storage demand of the country. TAEA is now in a position to establish a new radioactive waste management facility and studies are now being carried out on the selection of best place for the final storage of processed radioactive wastes. Research and development studies in TAEA should continue in radioactive waste management with the aim of improving data, models, and concepts related to long-term safety of disposal of long-lived waste

Proton radioactivity at non-collective prolate shape in high spin state of 94Ag

International Nuclear Information System (INIS)

Aggarwal, Mamta

2010-01-01

We predict proton radioactivity and structural transitions in high spin state of an excited exotic nucleus near proton drip line in a theoretical framework and investigate the nature and the consequences of the structural transitions on separation energy as a function of temperature and spin. It reveals that the rotation of the excited exotic nucleus 94 Ag at excitation energies around 6.7 MeV and angular momentum near 21h generates a rarely seen prolate non-collective shape and proton separation energy becomes negative which indicates proton radioactivity in agreement with the experimental results of Mukha et al. for 94 Ag.

Inductively coupled plasma mass spectrometer installation modifications in a radioactive contaminated laboratory for the analysis of DOE radioactive waste streams

International Nuclear Information System (INIS)

Giaquinto, J.M.; Keller, J.M.; Meeks, A.M.

1998-01-01

The operation and maintenance of a complex analytical instrument such as an inductively coupled plasma mass spectrometer in a radioactive contaminated environment presents unique problems and challenges that have to be considered in the purchasing and installation process. Considerations such as vendor experience, typical radiation levels, sample matrices encountered during sample analysis, instrument accessibility for maintenance, and upkeep must be incorporated into the decision process. The Radioactive Materials Analytical Laboratory (RMAL) at Oak Ridge National Laboratory (ORNL) recently purchased and installed an inductively coupled plasma mass spectrometer for the analysis of Department of Energy (DOE) radioactive waste streams. This presentation will outline the purchasing decision, installation of the instrument, and how the modifications needed to operate in a radioactive contaminated laboratory do not significantly impact the daily operation and maintenance requirements of the instrument. Also, a contamination survey of the system will be presented which demonstrates the contamination levels in the instrument from the sample introduction system to the detector. (author)

Inductively coupled plasma mass spectrometer installation modifications in a radioactive contaminated laboratory for the analysis of DOE radioactive waste streams

International Nuclear Information System (INIS)

Giaquinto, J.M.; Keller, J.M.; Meeks, A.M.

1997-04-01

The operation and maintenance of a complex analytical instrument such as an inductively coupled plasma mass spectrometer in a radioactive contaminated environment presents unique problems and challenges that have to be considered in the purchasing and installation process. Considerations such as vendor experience, typical radiation levels, sample matrices encountered during sample analysis, instrument accessibility for maintenance, and upkeep must be incorporated into the decision process. The Radioactive Materials Analytical Laboratory (RMAL) at Oak Ridge National Laboratory (ORNL) recently purchased and installed an inductively coupled plasma mass spectrometer for the analysis of Department of Energy (DOE) radioactive waste streams. This presentation will outline the purchasing decision, installation of the instrument, and how the modifications needed to operate in a radioactive contaminated laboratory do not significantly impact the daily operation and maintenance requirements of the instrument. Also, a contamination survey of the system will be presented which demonstrates the contamination levels in the instrument from the sample introduction system to the detector

Evaluating the reproducibility of environmental radioactivity monitoring data through replicate sample analysis

International Nuclear Information System (INIS)

Lindeken, C.L.; White, J.H.; Silver, W.J.

1978-01-01

At the Lawrence Livermore Laboratory, about 10% of the sampling effort in the environmental monitoring program represents replicate sample collection. Replication of field samples was initiated as part of the quality assurance program for environmental monitoring to determine the reproducibility of environmental measurements. In the laboratory these replicates are processed along with routine samples. As all components of variance are included in analysis of such field samples, comparison of the analytical data from replicate analyses provides a basis for estimating the overall reproducibility of the measurements. The replication study indicates that the reproducibility of environmental radioactivity monitoring data is subject to considerably more variability than is indicated by the accompanying counting errors. The data are also compared with analyses of duplicate aliquots from a well mixed sample or with duplicate aliquots of samples with known radionuclide content. These comparisons show that most of the variability is associated with the collection and preparation of the sample rather than with the analytical procedures

Investigation of potential analytical methods for redox control of the vitrification process

International Nuclear Information System (INIS)

Goldman, D.S.

1985-11-01

An investigation was conducted to evaluate several analytical techniques to measure ferrous/ferric ratios in simulated and radioactive nuclear waste glasses for eventual redox control of the vitrification process. Redox control will minimize the melt foaming that occurs under highly oxidizing conditions and the metal precipitation that occurs under highly reducing conditions. The analytical method selected must have a rapid response for production problems with minimal complexity and analyst involvement. The wet-chemistry, Moessbauer spectroscopy, glass color analysis, and ion chromatography techniques were explored, with particular emphasis being placed on the Moessbauer technique. In general, all of these methods can be used for nonradioactive samples. The Moessbauer method can readily analyze glasses containing uranium and thorium. A shielded container was designed and built to analyze fully radioactive glasses with the Moessbauer spectrometer in a hot cell environment. However, analyses conducted with radioactive waste glasses containing 90 Sr and 137 Cs were unsuccessful, presumably due to background radiation problems caused by the samples. The color of glass powder can be used to analyze the ferrous/ferric ratio for low chromium glasses, but this method may not be as precise as the others. Ion chromatography was only tested on nonradioactive glasses, but this technique appears to have the required precision due to its analysis of both Fe +2 and Fe +3 and its anticipated adaptability for radioactivity samples. This development would be similar to procedures already in use for shielded inductively coupled plasma emission (ICP) spectrometry. Development of the ion chromatography method is therefore recommended; conventional wet-chemistry is recommended as a backup procedure

Selection of optimal treatment procedures for non-standard radioactive waste arising from decommissioning of NPP after accident

Energy Technology Data Exchange (ETDEWEB)

Strážovec, Roman, E-mail: strazovec.roman@javys.sk [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia); JAVYS, a.s., Tomášikova 22, 821 02 Bratislava (Slovakia); Hrnčíř, Tomáš [DECOM, a.s., Sibírska 1, 917 01 Trnava (Slovakia); Lištjak, Martin [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia); VUJE, a.s., Okružná 5, 918 64 Trnava (Slovakia); Nečas, Vladimír [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia)

2016-05-15

The decommissioning of nuclear power plants is becoming a standard industrial activity where the optimization processes of partial activities are inevitable mainly for technical and economic reasons. In Slovakia, the decommissioning of A1 NPP is very specific case because A1 NPP is rare type of NPP (prototype) and furthermore its operation was affected by the accident. A large number of specific non-standard radioactive waste, such as long-time storage cases (hereinafter LSC), that is not usually present within the decommissioning projects of NPP with a regular termination of operation, represent one of the significant consequences of the accident and issues arisen from follow-up activities. The presented article describes the proposal of processing and conditioning of non-standard radioactive waste (such as LSC), together with description of methodology applied in the proposal for update of waste acceptance criteria for the processing and conditioning of radioactive waste (hereinafter RAW) within Bohunice Radioactive waste Treatment and Conditioning Centre (hereinafter RWTC). The results of performed detailed analysis are summarized into new waste acceptance criteria for technological lines keeping in mind safety principles and requirements for protection of operating personnel, the public and the environment.

Radioimmunoassay. A revolution in the analytic procedure

Energy Technology Data Exchange (ETDEWEB)

Strecker, H; Eckert, H G [Farbwerke Hoechst A.G., Frankfurt am Main (Germany, F.R.). Radiochemisches Lab.

1978-04-01

Radioimmunoassay is an analytic method which combines the sensitivity of radioactive measurement and the specificity of the antigen-antibody reaction Substances down to a concentration of some picograms per ml serum (or biological material) can be measured in the presence of a millionfold excess of otherwise interfering substances. The method is easy to carry out (test tube chemistry). The main field of application at the moment is in endocrinology; further possibilities of application are in pharmaceutical research, environmental protection, forensic medicine, and for general analytic purposes. Radioactive sources are used only in vitro in the nanocurie range, i.e. radiation exposure is negligible.

National inventory of radioactive wastes and valorizable materials. Synthesis report

International Nuclear Information System (INIS)

2004-01-01

This national inventory of radioactive wastes is a reference document for professionals and scientists of the nuclear domain and also for any citizen interested in the management of radioactive wastes. It contains: 1 - general introduction; 2 - the radioactive wastes: definition, classification, origin and management; 3 - methodology of the inventory: organization, accounting, prospective, production forecasting, recording of valorizable materials, exhaustiveness, verification tools; 4 - general results: radioactive waste stocks recorded until December 31, 2002, forecasts for the 2003-2020 era, post-2020 prospects: dismantling operations, recording of valorizable materials; 5 - inventory per producer or owner: front-end fuel cycle facilities, power generation nuclear centers, back-end fuel cycle facilities, waste processing or maintenance facilities, civil CEA research centers, non-CEA research centers, medical activities (diagnostics, therapeutics, analyses), various industrial activities (sources fabrication, control, particular devices), military research and experiment centers, storage and disposal facilities; 6 - elements about radioactive polluted sites; 7 - examples of foreign inventories; 8 - conclusion and appendixes. (J.S.)

Analytical study in 1D nuclear waste migration

International Nuclear Information System (INIS)

Perez Guerrero, Jesus S.; Heilbron Filho, Paulo L.; Romani, Zrinka V.

1999-01-01

The simulation of the nuclear waste migration phenomena are governed mainly by diffusive-convective equation that includes the effects of hydrodynamic dispersion (mechanical dispersion and molecular diffusion), radioactive decay and chemical interaction. For some special problems (depending on the boundary conditions and when the domain is considered infinite or semi-infinite) an analytical solution may be obtained using classical analytical methods such as Laplace Transform or variable separation. The hybrid Generalized Integral Transform Technique (GITT) is a powerful tool that can be applied to solve diffusive-convective linear problems to obtain formal analytical solutions. The aim of this work is to illustrate that the GITT may be used to obtain an analytical formal solution for the study of migration of radioactive waste in saturated flow porous media. A case test considering 241 Am radionuclide is presented. (author)

A simple method for the verification of clearance levels for non-radioactive solid waste

International Nuclear Information System (INIS)

Holland, B.

1997-01-01

ANSTO's radiopharmaceutical production laboratories generate 25 m 3 of solid waste per month. Most of this waste is not radioactive. Up until recently the non-radioactive waste was cleared from the controlled area and stored for 10 halflives prior to disposal as normal solid refuse. To eliminate the storage and ''double handling'' of the large quantities of non-radioactive waste a simple clearance method was devised to allow direct disposal. This paper describes how clearance levels were determined. Here the term ''clearance level'' is used as a general term for the release of material regardless of whether it was previously subject to regulatory control. This contrasts with the IAEA definition of a clearance level and highlights a potential problem with the implementation of exemption levels to keep material out of regulatory control and the use of clearance levels to allow removal of materials from regulatory control. Several common hand held contamination monitors were tested to determine their limits of detection and ability to meet these clearance levels. The clearance method includes waste segregation and size limitation features to ensure the waste is monitored in a consistent manner, compatible with the limits of detection. The clearance levels achieved were subsequently found to be compatible with some of the unconditional clearance levels in IAEA-TECDOC-855 and the measurement method also meets the required features of that document. The ANSTO non-radioactive waste clearance system has been in operation for more than 12 months and has proved simple and effective to operate. Approximately 12m 3 of the solid waste is now been treated directly as normal solid refuse. This paper describes the ANSTO clearance system, the contamination monitor tests and details practical problems associated with the direct monitoring of solid waste, including averaging of the activity in the package. The paper also briefly highlights the potential problem with the use of

Self-attenuation of gamma rays during radioactivity concentration analysis of environmental samples

International Nuclear Information System (INIS)

Watson, D.; Dharmasiri, J.; Akber, R.

2001-01-01

Gamma spectroscopy using HPGe detector systems is a readily used technique for routine analysis of radioactivity in environmental samples. The systems are generally calibrated using standards of known radioactivity and composition. Radioactivity in environmental samples is generally distributed in the bulk of the material. When a sample of finite thickness is analysed through gamma spectroscopy, a proportion of the gamma rays emitted from the sample is either stopped or scattered from the sample material itself. These processes of self-absorption and self-attenuation depend upon the physical and elemental composition of the sample and the energy of the gamma radiation. Since environmental samples vary in composition, instrument calibration using a fixed matrix composition may not be valid for a diversity of samples. We selected and analysed five sample matrices to investigate the influence of self-absorption and self-attenuation in environmental samples. Our selection consisted of bentonite and kaolin representing clay, quartz representing silica, ash representing prepared biota, and analytical grade MnO 2 representing a co-precipitant used for extractive radioactivity from aqueous samples. Our findings show that within 5% of uncertainty the silica based standards can be used to cover the environmental samples of varying clay (silica content). The detection efficiency for ash and MnO 2 could be different particularly in the 30 - 100 keV energy range. The differences in sample behaviour can be explained on the basis of atomic number, mass number and density

Radioactivity in the environment. A summary and radiological assessment of the Environment Ageny's monitoring programmes. Report for 1996

International Nuclear Information System (INIS)

1996-01-01

This report presents the results from the Environment Agency's monitoring of radioactivity in the environment during 1996. Monitoring programmes were carried out in support of the Agency's regulatory functions under the Radioactive Substances Act 1993 and as part of the UK Government's obligations under the Euratom Treaty. The programmes included: effluent monitoring; the quality checking of solid waste disposals; environmental monitoring; the monitoring of radioactivity in air and rainwater; the monitoring of radioactivity in drinking water sources. A total of 160 effluent samples were analysed for nearly 900 determinants, two consignments of solid radioactive waste destined for disposal at British Nuclear Fuels' site at Drigg were checked, direct instrumental monitoring was carried out at ISO locations within the vicinity of nuclear sites, and 532 environmental samples were analysed for over 2,000 determinants. Effluent monitoring: The Agency requires operators of certain sites to provide samples of their liquid effluents for independent analysis. The results are compared with reports submitted by site operators. The majority of results showed satisfactory agreement; operators' values were frequently higher than the Agency's measurements indicating that they were not under-reporting. However, some discrepancies were found and are being investigated. Quality checking of solid waste disposals: Consignments of solid low level radioactive waste are seized by inspectors for examination at the Agency's Waste Quality Checking Laboratory. Sophisticated non-destructive and destructive analytical techniques are used at the laboratory to check the radioactive content and description of the wastes. Consignments of waste from the Atomic Weapons Establishment at Aldermaston and Amersham International at Amersham were examined. In both cases the operators reported higher activity than the Agency's laboratory. The consignments also conformed with the operators' disposal

Non-fuel cycle radioactive waste policy in Turkey

International Nuclear Information System (INIS)

Izmir, A.I.; Uslu, I.

2001-01-01

Full text: Introduction. Radioactive wastes generated in Turkey are mostly low level radioactive waste generated from the operation of one research reactor, research centers and universities, hospitals, and from radiological application of various industries. It involves both short-lived and long lived radionuclides. In general, this includes radioactive materials, which are no longer useful and have their origin from practice or intervention both with unsealed and sealed sources. Radioactive Waste Management in Turkey. Utilisation of radioactive materials in Turkey requires special authorisations and falls under legal rules, in particular under the Radiation Safety Regulation of 24th March 2000 (Official Gazette number: 20983) outlining a general regulation for the protection of the population and workers against the danger of ionising radiation and subsequent amendments. There is also a requirement enforced by the Regulations for Radioactive Wastes Exempt from Regulatory Authority Control (published on 15 January 2000, Official Gazette number: 23934) that identifies the limits and other conditions for the discharges of radioactive substances to the environment. Radioactive waste is generally understood as material for which no further use is foreseen, and which has been managed in a system of reporting, authorisation and control as specified in International Atomic Energy Agency (IAEA) recommendations or national legislation. In this paper radioactive waste is considered in two categories: as originated from unsealed sources or from sealed sources. a) Management of Unsealed Sources. Unsealed radionuclides are utilised in human medicine for in vivo diagnosis, metabolic therapy and in vitro biological analysis. The most common types of radionuclides used in Turkey are C-14, Co-57, Cr-51, Fe-59, Ga-67, H-3, I-123, I-125, I-131, In-111, Mo-99, P-32, P-33, Re-186, S-35, Sr-89, Sr-90, Tc-99, Tl-201, Xe-133, Y-90 which are import of radiopharmaceuticals to Turkey in

U Y 105 standard use of non sealed radioactive sources in nuclear medicine: approve for Industry energy and Mining Ministry 28/6/2002 Resolution

International Nuclear Information System (INIS)

2002-01-01

Establish minimal requirements radiological safety for use non sealed radioactive sources in nuclear medicine.The present standard is used in operation or nuclear medicine practices using non sealed radioactive sources with diagnostic and therapeutic purposes in vivo and in vitro

Numerical Analyses of Subsoil-structure Interaction in Original Non-commercial Software based on FEM

Science.gov (United States)

Cajka, R.; Vaskova, J.; Vasek, J.

2018-04-01

For decades attention has been paid to interaction of foundation structures and subsoil and development of interaction models. Given that analytical solutions of subsoil-structure interaction could be deduced only for some simple shapes of load, analytical solutions are increasingly being replaced by numerical solutions (eg. FEM – Finite element method). Numerical analyses provides greater possibilities for taking into account the real factors involved in the subsoil-structure interaction and was also used in this article. This makes it possible to design the foundation structures more efficiently and still reliably and securely. Currently there are several software that, can deal with the interaction of foundations and subsoil. It has been demonstrated that non-commercial software called MKPINTER (created by Cajka) provides appropriately results close to actual measured values. In MKPINTER software stress-strain analysis of elastic half-space by means of Gauss numerical integration and Jacobean of transformation is done. Input data for numerical analysis were observed by experimental loading test of concrete slab. The loading was performed using unique experimental equipment which was constructed in the area Faculty of Civil Engineering, VŠB-TU Ostrava. The purpose of this paper is to compare resulting deformation of the slab with values observed during experimental loading test.

Application of geostatistical methods to long-term safety analyses for radioactive waste repositories

International Nuclear Information System (INIS)

Roehlig, K.J.

2001-01-01

Long-term safety analyses are an important part of the design and optimisation process as well as of the licensing procedure for final repositories for radioactive waste in deep geological formations. For selected scenarios describing possible evolutions of the repository system in the post-closure phase, quantitative consequence analyses are performed. Due to the complexity of the phenomena of concern and the large timeframes under consideration, several types of uncertainties have to be taken into account. The modelling work for the far-field (geosphere) surrounding or overlaying the repository is based on model calculations concerning the groundwater movement and the resulting migration of radionuclides which possibly will be released from the repository. In contrast to engineered systems, the geosphere shows a strong spatial variability of facies, materials and material properties. The paper presented here describes the first steps towards a quantitative approach for an uncertainty assessment taking into account this variability. Due to the availability of a large amount of data and information of several types, the Gorleben site (Germany) has been used for a case study in order to demonstrate the method. (orig.)

Regulation of naturally occurring radioactive materials in non-nuclear industries

International Nuclear Information System (INIS)

Scott, L.M.

1997-01-01

The volume and concentrations of naturally occurring radioactive material is large across a variety of industries commonly thought not to involve radioactive material. The regulation of naturally occurring radioactive material in the United States is in a state of flux. Inventory of naturally occurring radioactive materials is given, along with a range of concentrations. Current and proposed regulatory limits are presented. (author)

From basic survival analytic theory to a non-standard application

CERN Document Server

Zimmermann, Georg

2017-01-01

Georg Zimmermann provides a mathematically rigorous treatment of basic survival analytic methods. His emphasis is also placed on various questions and problems, especially with regard to life expectancy calculations arising from a particular real-life dataset on patients with epilepsy. The author shows both the step-by-step analyses of that dataset and the theory the analyses are based on. He demonstrates that one may face serious and sometimes unexpected problems, even when conducting very basic analyses. Moreover, the reader learns that a practically relevant research question may look rather simple at first sight. Nevertheless, compared to standard textbooks, a more detailed account of the theory underlying life expectancy calculations is needed in order to provide a mathematically rigorous framework. Contents Regression Models for Survival Data Model Checking Procedures Life Expectancy Target Groups Researchers, lecturers, and students in the fields of mathematics and statistics Academics and experts work...

Release process for non-real property containing residual radioactive material

International Nuclear Information System (INIS)

Ranek, N.L.; Chen, S.Y.; Kamboj, S.; Hensley, J.; Burns, D.; Fleming, R.; Warren, S.; Wallo, A.

1997-01-01

It is DOE's objective to operate its facilities and to conduct its activities so that radiation exposures to members of the public are maintained within acceptable limits and exposures to residual radioactive materials are controlled. To accomplish this, DOE has adopted Order DOE 5400.51 'Radiation Protection of the Public and the Environment', and will be promulgating IO CR Part 834 to codify and clarify the requirements of DOE 5400.5. Under both DOE 5400.5 and 10 CR Part 834, radioactively contaminated DOE property is prohibited from release unless specific actions have been completed prior to the release. This paper outlines a ten-step process that, if followed, will assist DOE Operations and contractor personnel in ensuring that the required actions established by Order DOE 5400.5 and 10 CR Part 834 have been appropriately completed prior to the release for reuse or recycle of non-real property (e.g., office furniture, computers, hand tools, machinery, vehicles and scrap metal). Following the process will assist in ensuring that radiological doses to the public from the released materials will meet applicable regulatory standards and be as low as reasonably achievable (ALARA)

Analysing task design and students' responses to context-based problems through different analytical frameworks

Science.gov (United States)

Broman, Karolina; Bernholt, Sascha; Parchmann, Ilka

2015-05-01

Background:Context-based learning approaches are used to enhance students' interest in, and knowledge about, science. According to different empirical studies, students' interest is improved by applying these more non-conventional approaches, while effects on learning outcomes are less coherent. Hence, further insights are needed into the structure of context-based problems in comparison to traditional problems, and into students' problem-solving strategies. Therefore, a suitable framework is necessary, both for the analysis of tasks and strategies. Purpose:The aim of this paper is to explore traditional and context-based tasks as well as students' responses to exemplary tasks to identify a suitable framework for future design and analyses of context-based problems. The paper discusses different established frameworks and applies the Higher-Order Cognitive Skills/Lower-Order Cognitive Skills (HOCS/LOCS) taxonomy and the Model of Hierarchical Complexity in Chemistry (MHC-C) to analyse traditional tasks and students' responses. Sample:Upper secondary students (n=236) at the Natural Science Programme, i.e. possible future scientists, are investigated to explore learning outcomes when they solve chemistry tasks, both more conventional as well as context-based chemistry problems. Design and methods:A typical chemistry examination test has been analysed, first the test items in themselves (n=36), and thereafter 236 students' responses to one representative context-based problem. Content analysis using HOCS/LOCS and MHC-C frameworks has been applied to analyse both quantitative and qualitative data, allowing us to describe different problem-solving strategies. Results:The empirical results show that both frameworks are suitable to identify students' strategies, mainly focusing on recall of memorized facts when solving chemistry test items. Almost all test items were also assessing lower order thinking. The combination of frameworks with the chemistry syllabus has been

Global marine radioactivity database (GLOMARD)

International Nuclear Information System (INIS)

2000-06-01

The GLOMARD stores all available data on marine radioactivity in seawater, suspended matter, sediments and biota. The database provides critical input to the evaluation of the environmental radionuclide levels in regional seas and the world's oceans. It can be used as a basis for the assessment of the radiation doses to local, regional and global human populations and to marine biota. It also provides information on temporal trends of radionuclide levels in the marine environment and identifies gaps in available information. The database contains information on the sources of the data; the laboratories performing radionuclide analysis; the type of samples (seawater, sediment, biota) and associated details (such as volume and weight); the sample treatment, analytical methods, and measuring instruments; and the analysed results (such as radionuclide concentrations, uncertainties, temperature, salinity, etc.). The current version of the GLOMARD allows the input, maintenance and extraction of data for the production of various kinds of maps using external computer programs. Extracted data are processed by these programs to produce contour maps representing radionuclide distributions in studied areas. To date, development work has concentrated on the Barents and Kara Seas in the Arctic and the Sea of Japan in the northwest Pacific Ocean, in connection with the investigation of radioactive waste dumping sites, as well as on marine radioactivity assessment of the Mururoa and Fangataufa nuclear weapons tests sites in French Polynesia. Further data inputs and evaluations are being carried out for the Black and Mediterranean Seas. In the framework of the project on Worldwide Marine Radioactivity Studies, background levels of 3 H, 90 Sr, 137 Cs and 239,240 Pu in water, sediment and biota of the world's oceans and seas will be established

On accuracy problems for semi-analytical sensitivity analyses

DEFF Research Database (Denmark)

Pedersen, P.; Cheng, G.; Rasmussen, John

1989-01-01

The semi-analytical method of sensitivity analysis combines ease of implementation with computational efficiency. A major drawback to this method, however, is that severe accuracy problems have recently been reported. A complete error analysis for a beam problem with changing length is carried ou...... pseudo loads in order to obtain general load equilibrium with rigid body motions. Such a method would be readily applicable for any element type, whether analytical expressions for the element stiffnesses are available or not. This topic is postponed for a future study....

Potential sources of analytical bias and error in selected trace element data-quality analyses

Science.gov (United States)

Paul, Angela P.; Garbarino, John R.; Olsen, Lisa D.; Rosen, Michael R.; Mebane, Christopher A.; Struzeski, Tedmund M.

2016-09-28

Potential sources of analytical bias and error associated with laboratory analyses for selected trace elements where concentrations were greater in filtered samples than in paired unfiltered samples were evaluated by U.S. Geological Survey (USGS) Water Quality Specialists in collaboration with the USGS National Water Quality Laboratory (NWQL) and the Branch of Quality Systems (BQS).Causes for trace-element concentrations in filtered samples to exceed those in associated unfiltered samples have been attributed to variability in analytical measurements, analytical bias, sample contamination either in the field or laboratory, and (or) sample-matrix chemistry. These issues have not only been attributed to data generated by the USGS NWQL but have been observed in data generated by other laboratories. This study continues the evaluation of potential analytical bias and error resulting from matrix chemistry and instrument variability by evaluating the performance of seven selected trace elements in paired filtered and unfiltered surface-water and groundwater samples collected from 23 sampling sites of varying chemistries from six States, matrix spike recoveries, and standard reference materials.Filtered and unfiltered samples have been routinely analyzed on separate inductively coupled plasma-mass spectrometry instruments. Unfiltered samples are treated with hydrochloric acid (HCl) during an in-bottle digestion procedure; filtered samples are not routinely treated with HCl as part of the laboratory analytical procedure. To evaluate the influence of HCl on different sample matrices, an aliquot of the filtered samples was treated with HCl. The addition of HCl did little to differentiate the analytical results between filtered samples treated with HCl from those samples left untreated; however, there was a small, but noticeable, decrease in the number of instances where a particular trace-element concentration was greater in a filtered sample than in the associated

Use of bremsstrahlung information for the nondestructive characterization of radioactive waste packages; Nutzung von Bremsstrahlungsinformation zur zerstoerungsfreien Charakterisierung radioaktiver Abfallgebinde

Energy Technology Data Exchange (ETDEWEB)

Rohrmoser, Benjamin Paul

2016-11-10

In order to minimize pseudo activity whilst storage of radioactive waste packages it is required to determine the nuclide inventory as precisely as possible. The in Gamma spectra contained parts of bremsstrahlung can be used to identify and quantify certain beta nuclides. For this an analytical method has been developed. This was mainly tested with beta-emitter Sr-90 and Tm-170, as well as commonly present gamma-emitters in laboratory scale and actual 200 liter waste packages. As a result, non-destructive determination of radioactive wastes can be conducted more precisely.

A study on the safety of radioactive waste incineration facilities

Energy Technology Data Exchange (ETDEWEB)

Seo, Y C [Yonsei Univ., Seoul (Korea, Republic of); Park, W J; Lee, B S; Lee, S H [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

1994-12-15

The main scope of the project is the selection of some considerable items in design criteria of radioactive waste incineration facilities not only for the protection of workers and residents during operation but also for the safe disposal of ashes after incineration. The technological and regulational status on incineration technologies in domestic and foreign is surveyed and analyzed for providing such basic items which must be contained in the guideline for safe and appropriate design, construction and operation of the facilities. The contents of the project are summarized as follows; surveying the status on incineration technologies for both radioactive and non-radioactive wastes in domestic and foreign, surveying and analysing same related technical standards and regulations in domestic and foreign, picking out main considerable items and proposing a direction of further research.

Analytical study plan: Shielded Cells batch 1 campaign; Revision 1

International Nuclear Information System (INIS)

Bibler, N.E.; Ha, B.C.; Hay, M.S.; Ferrara, D.M.; Andrews, M.K.

1993-01-01

Radioactive operations in the Defense Waste Processing Facility (DWPF) will require that the Savannah River Technology Center (SRTC) perform analyses and special studies with actual Savannah River Site (SRS) high-level waste sludge. SRS Tank 42 and Tank 51 will comprise the first batch of sludge to be processed in the DWPF. Approximately 25 liters of sludge from each of these tanks will be characterized and processed in the Shielded Cells of SRTC. During the campaign, processes will include sludge characterization, sludge washing, rheology determination, mixing, hydrogen evolution, feed preparation, and vitrification of the waste. To complete the campaign, the glass will be characterized to determine its durability and crystallinity. This document describes the types of samples that will be produced, the sampling schedule and analyses required, and the methods for sample and analytical control

Analytical performance, agreement and user-friendliness of six point-of-care testing urine analysers for urinary tract infection in general practice

NARCIS (Netherlands)

Schot, Marjolein J C; van Delft, Sanne; Kooijman-Buiting, Antoinette M J; de Wit, Niek J; Hopstaken, Rogier M

2015-01-01

OBJECTIVE: Various point-of-care testing (POCT) urine analysers are commercially available for routine urine analysis in general practice. The present study compares analytical performance, agreement and user-friendliness of six different POCT urine analysers for diagnosing urinary tract infection

On the Decay of Correlations in Non-Analytic SO(n)-Symmetric Models

Science.gov (United States)

Naddaf, Ali

We extend the method of complex translations which was originally employed by McBryan-Spencer [2] to obtain a decay rate for the two point function in two-dimensional SO(n)-symmetric models with non-analytic Hamiltonians for $.

Development of a database system for the management of non-treated radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Pinto, Antônio Juscelino; Freire, Carolina Braccini; Cuccia, Valeria; Santos, Paulo de Oliveira; Seles, Sandro Rogério Novaes; Haucz, Maria Judite Afonso, E-mail: ajp@cdtn.br, E-mail: cbf@cdtn.br, E-mail: vc@cdtn.br, E-mail: pos@cdtn.br, E-mail: seless@cdtn.br, E-mail: hauczmj@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

The radioactive waste produced by the research laboratories at CDTN/CNEN, Belo Horizonte, is stored in the Non-Treated Radwaste Storage (DRNT) until the treatment is performed. The information about the waste is registered and the data about the waste must to be easily retrievable and useful for all the staff involved. Nevertheless, it has been kept in an old Paradox database, which is now becoming outdated. Thus, to achieve this goal, a new Database System for the Non-treated Waste will be developed using Access® platform, improving the control and management of solid and liquid radioactive wastes stored in CDTN. The Database System consists of relational tables, forms and reports, preserving all available information. It must to ensure the control of the waste records and inventory. In addition, it will be possible to carry out queries and reports to facilitate the retrievement of the waste history and localization and the contents of the waste packages. The database will also be useful for grouping the waste with similar characteristics to identify the best type of treatment. The routine problems that may occur due to change of operators will be avoided. (author)

Development of a database system for the management of non-treated radioactive waste

International Nuclear Information System (INIS)

Pinto, Antônio Juscelino; Freire, Carolina Braccini; Cuccia, Valeria; Santos, Paulo de Oliveira; Seles, Sandro Rogério Novaes; Haucz, Maria Judite Afonso

2017-01-01

The radioactive waste produced by the research laboratories at CDTN/CNEN, Belo Horizonte, is stored in the Non-Treated Radwaste Storage (DRNT) until the treatment is performed. The information about the waste is registered and the data about the waste must to be easily retrievable and useful for all the staff involved. Nevertheless, it has been kept in an old Paradox database, which is now becoming outdated. Thus, to achieve this goal, a new Database System for the Non-treated Waste will be developed using Access® platform, improving the control and management of solid and liquid radioactive wastes stored in CDTN. The Database System consists of relational tables, forms and reports, preserving all available information. It must to ensure the control of the waste records and inventory. In addition, it will be possible to carry out queries and reports to facilitate the retrievement of the waste history and localization and the contents of the waste packages. The database will also be useful for grouping the waste with similar characteristics to identify the best type of treatment. The routine problems that may occur due to change of operators will be avoided. (author)

Leakage of radioactive materials from particle accelerator facilities by non-radiation disasters like fire and flooding and its environmental impacts

Science.gov (United States)

Lee, A.; Jung, N. S.; Mokhtari Oranj, L.; Lee, H. S.

2018-06-01

The leakage of radioactive materials generated at particle accelerator facilities is one of the important issues in the view of radiation safety. In this study, fire and flooding at particle accelerator facilities were considered as the non-radiation disasters which result in the leakage of radioactive materials. To analyse the expected effects at each disaster, the case study on fired and flooded particle accelerator facilities was carried out with the property investigation of interesting materials presented in the accelerator tunnel and the activity estimation. Five major materials in the tunnel were investigated: dust, insulators, concrete, metals and paints. The activation levels on the concerned materials were calculated using several Monte Carlo codes (MCNPX 2.7+SP-FISPACT 2007, FLUKA 2011.4c and PHITS 2.64+DCHAIN-SP 2001). The impact weight to environment was estimated for the different beam particles (electron, proton, carbon and uranium) and the different beam energies (100, 430, 600 and 1000 MeV/nucleon). With the consideration of the leakage path of radioactive materials due to fire and flooding, the activation level of selected materials, and the impacts to the environment were evaluated. In the case of flooding, dust, concrete and metal were found as a considerable object. In the case of fire event, dust, insulator and paint were the major concerns. As expected, the influence of normal fire and flooding at electron accelerator facilities would be relatively low for both cases.

Evaluation and standardisation of fast analytical techniques for destructive radwaste control

Energy Technology Data Exchange (ETDEWEB)

De Simone, A.; Troiani, F. [ENEA, Unita' Rifiuti Radioattivi e Disattivazione Impianti, Centro Ricerche Saluggia, Vercelli (Italy)

2001-07-01

The document describes the work programme carried out by the Laboratorio Nazionale per la 'Caratterizzazione dei Rifiuti Radioattivi', in the frame of the European research project Destructive Radwaste Control. The main tasks of the research work were the evaluation of fast sample pre-treatment procedures and the development of chromatographic methods coupled to fast nuclide detection by Liquid Scintillation Counting. In order to test the High Performance Ion Chromatograph (HPIC) coupled to the Liquid Scintillation Counter (LSC) on high salt content solutions, synthetic cement solutions have been prepared and spiked with several {beta}-emitters hard to be measured with non-destructive analyses, along with other radionuclides important for the determination of the radiological inventory in radwastes. As the validation tests for the new analytical methods involved the manipulation of radioactive solutions, a remote area for HPIC-LSC apparatus has been designed and performed, in order to operate in safe conditions. According to the research programme, fast analytical methods for the chemical separation and radionuclide detection of the radioactive elements of interest, have been developed and qualified. From the results of the work, some protocols of analysis have been defined: they contain all information about operative conditions for HPIC-LSC apparatus, field of applicability, chemical and radioactive detection limits. [Italian] Questo documento riporta il lavoro realizzato dal Laboratorio Nazionale per la Caratterizzazione dei Rifiuti Radioattivi, nell'ambito del progetto di ricerca Europeo sulle tecniche di misura distruttive per rifiuti radioattivi. Il lavoro era finalizzato sia alla valutazione di nuove procedure veloci per la preparazione dei campioni da analizzare sia allo sviluppo di metodi Cromatografici accoppiati alla rivelazione di radionuclidi mediante Conteggio a Scintillazione Liquida. La sperimentazione della Cromatografia Ionica ad

Influence of the conditional release of the materials with very low level of radioactivity on the environment - 59132

International Nuclear Information System (INIS)

Prvakova, Slavka; Mrskova, Adela; Pritrsky, Jozef

2012-01-01

Significant amount of solid materials (metals, non-metals, building structures) that could be contaminated or activated is produced during operation and especially decommissioning of nuclear power plants. Considerable fraction of these materials has level of radioactivity close to the radiological limits allowing its safe release into the environment thereby could be potentially recycled within the special constructions, as for example tunnels, roads or bridges. If the requirements of legislation on the radiological limits for handling such material and long-term safety of the constructions are met, contaminated material can be incorporated in the form of recycled concrete, remelted steel, etc. The paper presents implementation of the IAEA and EC recommendations into the form of detailed analytical approaches with the aim to develop integrated scenarios and to analyse long-term influence of the conditional release of the material with very low level of radioactivity on the environment. Further, an estimation of the key input parameters characteristic for the specific conditions of Slovak case in order to fulfil the radiological limits according to the Slovak legislation is included. Analysed integrated scenarios represent surface or underground civil construction with radionuclides released directly into the geosphere and transported by a groundwater flow to the biosphere. The migration of radionuclides is modelled in the near-surface conditions with the advection as a dominant transport mechanism. Computer code GoldSim is used to evaluate the long-term safety assessment of the conditionally released material on the environment. (authors)

On the Analytical Solution of Non-Orthogonal Stagnation Point Flow towards a Stretching Sheet

DEFF Research Database (Denmark)

Kimiaeifar, Amin; Bagheri, G. H.; Barari, Amin

2011-01-01

An analytical solution for non-orthogonal stagnation point for the steady flow of a viscous and incompressible fluid is presented. The governing nonlinear partial differential equations for the flow field are reduced to ordinary differential equations by using similarity transformations existed...... in the literature and are solved analytically by means of the Homotopy Analysis Method (HAM). The comparison of results from this paper and those published in the literature confirms the precise accuracy of the HAM. The resulting analytical equation from HAM is valid for entire physical domain and effective...

Argentina's radioactive waste disposal policy

International Nuclear Information System (INIS)

Palacios, E.

1986-01-01

The Argentina policy for radioactive waste disposal from nuclear facilities is presented. The radioactive wastes are treated and disposed in confinement systems which ensure the isolation of the radionucles for an appropriate period. The safety criteria adopted by Argentina Authorities in case of the release of radioactive materials under normal conditions and in case of accidents are analysed. (M.C.K.) [pt

Optimization of the radioactive waste storage

International Nuclear Information System (INIS)

Dellamano, Jose Claudio

2005-01-01

Radioactive waste storage is the practice adopted in countries where the production of small quantities of radioactive waste does not justify the immediate investment in the construction of a repository. Accordingly, at IPEN, treated radioactive wastes, mainly solid compacted, have been stored for more than 20 years, in 200 dm 3 drums. The storage facility is almost complete and must be extended. Taking into account that a fraction of these wastes has decayed to a very low level due to the short half - life of some radionuclides and considering that 'retrieval for disposal as very low level radioactive waste' is one of the actions suggested to radioactive waste managers, the Laboratory of Waste Management of IPEN started a project to apply the concepts of clearance levels and exemption limits to optimize the radioactive waste storage capacity . This study has been carried out by determining the doses and costs related to two main options: either to maintain the present situation or to open the packages and segregate the wastes that may be subject to clearance, using the national, two international clearance levels and the annual public limit. Doses and costs were evaluated as well as the collective dose and the detriment cost. The analytical solution among the evaluated options was determined by using the technique to aid decision making known as cost-benefit analysis. At last, it was carried out the sensitivity analysis considering all criteria and parameters in order to assess the robustness of the analytical solution. This study can be used as base to other institutions or other countries with similar nuclear programs. (author)

Beyond low-level activity: On a 'non-radioactive' gas mantle

Energy Technology Data Exchange (ETDEWEB)

Poljanc, Karin [Atominstitut der Osterreichischen Universitaeten, Vienna University of Technology, Stadionallee 2, 1020 Vienna (Austria); Steinhauser, Georg [Atominstitut der Osterreichischen Universitaeten, Vienna University of Technology, Stadionallee 2, 1020 Vienna (Austria)]. E-mail: georg.steinhauser@ati.ac.at; Sterba, Johannes H. [Atominstitut der Osterreichischen Universitaeten, Vienna University of Technology, Stadionallee 2, 1020 Vienna (Austria); Buchtela, Karl [Atominstitut der Osterreichischen Universitaeten, Vienna University of Technology, Stadionallee 2, 1020 Vienna (Austria); Bichler, Max [Atominstitut der Osterreichischen Universitaeten, Vienna University of Technology, Stadionallee 2, 1020 Vienna (Austria)

2007-03-01

Gas mantles for camping gas lanterns sometimes contain thorium compounds. During the last years, the use of thorium-free gas mantles has become more and more popular due to the avoidance of a radioactive heavy metal. We investigated a gas mantle type that is declared to be 'non-radioactive' and that can be bought in Austria at the moment. Methods used were Instrumental Neutron Activation Analysis (INAA), {gamma}-spectroscopy, and Liquid Scintillation Counting (LSC). We found massive thorium contents of up to 259 mg per gas mantle. Leaching experiments showed that only 0.4% of the Th but approximately 90% of the decay products of {sup 232}Th can be leached under conditions simulating sucking and chewing with human saliva. In this paper, the investigation of these gas mantles including the consideration of the environmental hazard caused by disposed mantles and the health hazard for unsuspecting consumers is presented and legal consequences are discussed for this fraud.

Proton radioactivity at non-collective prolate shape in high spin state of {sup 94}Ag

Energy Technology Data Exchange (ETDEWEB)

Aggarwal, Mamta, E-mail: mamta.a4@gmail.co [UM-DAE Centre for Excellence in Basic Sciences, University of Mumbai, Kalina Campus, Mumbai 400 098 (India)

2010-10-11

We predict proton radioactivity and structural transitions in high spin state of an excited exotic nucleus near proton drip line in a theoretical framework and investigate the nature and the consequences of the structural transitions on separation energy as a function of temperature and spin. It reveals that the rotation of the excited exotic nucleus {sup 94}Ag at excitation energies around 6.7 MeV and angular momentum near 21h generates a rarely seen prolate non-collective shape and proton separation energy becomes negative which indicates proton radioactivity in agreement with the experimental results of Mukha et al. for {sup 94}Ag.

Radiant-heat spray-calcination process for the solid fixation of radioactive waste. Part 1, Non-radioactive pilot unit

Energy Technology Data Exchange (ETDEWEB)

Allemann, R.T.; Johnson, B.M. Jr.

1960-11-14

The fixation of radioactive waste in a stable solid media by means of calcination of these aqueous solutions has been the subject of considerable-effort throughout the U. S. Atomic Energy Commission and by atomic energy organizations in other countries. Several methods of doing this on a continuous or semi-continuous basis have been devised, and a fev have been demonstrated to be feasible for the handling of non-radioactive, or low-activity, simulated wastes. Notable among methods currently under development are: (a) batch-operated pot calcination of waste generated from reprocessing stainless steel clad fuel elements (Darex process) and Purex waste, (b) combination rotary kiln and ball mill calcination of aluminum nitrate (TBP-25 and Redox process), and (c) fluidized bed calcination of TBP-25 and Purex wastes. Although a considerable amount of engineering experience has been obtained on the calcination of dissolved salts in a fluidized bed, and the other methods have been the subjects of a great deal of study, none of them have been developed to-the extent which would rule out the desirability of further investigation of other possible methods of calcination.

The influence of non-radiation factors on the kinetics of radioactive iodine metabolism in thyroid

International Nuclear Information System (INIS)

Kalistratova, V.S.; Filatov, V.V.; Shavrina, E.A.

1985-01-01

Estimation of the role non-radiation factors which may influence the dose formation in the most of all irradiated organs is considered very important for the normalization of radioactive isotopes of iodine. The significance of this problem was noted in some recent publications of NCARE. Since a human population which is being irradiated can be affected by the environmental temperature (43-45 deg and 4-6 deg C) and light (complete darkness and darkness for 21 hours) as well as vaccines (dysentery and typhoid) and alcohol (ethanol solutions of 0,02; 0,2; 2,0; and 20,0% concentration) were used as modifying factors. Iodine-125 administrated per os (0,8-1,3 MBq/rat) was used as a model for studying metabolism kinetics of radioactive iodine isotopes. Vaccination of animals results in a change of iodine-125 accumulation level in the thyroid depending on the time interval between an injection of the vaccine and administration of the radionuclide: one day after vaccination the levels of accumulation and the tissue doses formed by radionuclide in the thyroid were decreased by 1,5-2,0 times;14 days after vaccination they were increased by 1,5 times. Accumulation of iodine-125 in other endocrinal organs (pituitary and adrenal glands) was increased. The effect is independent of the type of injected vaccine. A single administration of 2,0-20,0% ethanol caused an increase of iodine-125 content in the thyroid. Chronical exposure to ethanol resulted in a decrease of iodine accumulation in the critical organ by 30% and the tissue doses accumulated by the thyroid, accordingly. Administration 0,02-0,2% ethanol did not affect metabolism kinetics of iodine-125. A single and chronical exposure to higher temperatures (43-45 deg C) decreased accumulation levels and absorbed doses of iodine-125 in the thyroid (by 30-50%) and delayed an elimination of the radionuclide from this organ. Lower temperatures of the environment (4-6 deg C), shorter light day and complete darkness did not affect

Dispersion of radioactive materials in air and water

International Nuclear Information System (INIS)

Tolksdorf, P.; Meurin, G.

1976-01-01

A review of current analytical methods for treating the dispersion of radioactive material in air and water is given. It is shown that suitable calculational models, based on experiments, exist for the dispersion in air. By contrast, the analysis of the dispersion of radioactive material in water still depends on the evaluation of experiments with site-specific models. (orig.) [de

Polarized secondary radioactive beams

International Nuclear Information System (INIS)

Zaika, N.I.

1992-01-01

Three methods of polarized radioactive nuclei beam production: a) a method nuclear interaction of the non-polarized or polarized charged projectiles with target nuclei; b) a method of polarization of stopped reaction radioactive products in a special polarized ion source with than following acceleration; c) a polarization of radioactive nuclei circulating in a storage ring are considered. Possible life times of the radioactive ions for these methods are determined. General schemes of the polarization method realizations and depolarization problems are discussed

Lessons learnt from participation in international inter-comparison exercise for environmental radioactivity measurement

International Nuclear Information System (INIS)

Jha, S.K.; Pulhani, Vandana; Sartandel, Sangeeta

2016-06-01

Environmental Radioactivity Measurement Section of Health Physics Division is regularly carrying out surveillance of the radioactivity concentration in the environment. The laboratory participates in the inter-comparison exercises conducted by various international agencies for quality assurance and quality control of analytical estimations. This report summarizes the results of the analysis of radioactivity in environmental matrices of the inter-comparison exercises. The participation in inter-comparison exercises has demonstrated competence in radionuclide identification and estimations, equivalence with the results of other participating laboratories, validated adopted analytical methods, introduced traceability to measurement etc. at national and international level. (author)

Incineration of European non-nuclear radioactive waste in the USA

International Nuclear Information System (INIS)

Moloney, B. P.; Ferguson, D.; Stephenson, B.

2013-01-01

Incineration of dry low level radioactive waste from nuclear stations is a well established process achieving high volume reduction factors to minimise disposal costs and to stabilise residues for disposal. Incineration has also been applied successfully in many European Union member countries to wastes arising from use of radionuclides in medicine, nonnuclear research and industry. However, some nations have preferred to accumulate wastes over many years in decay stores to reduce the radioactive burden at point of processing. After decay and sorting the waste, they then require a safe, industrial scale and affordable processing solution for the large volumes accumulated. This paper reports the regulatory, logistical and technical issues encountered in a programme delivered for Eckert and Ziegler Nuclitec to incinerate safely 100 te of waste collected originally from German research, hospital and industrial centres, applying for the first time a 'burn and return' process model for European waste in the US. The EnergySolutions incinerators at Bear Creek, Oak Ridge, Tennessee, USA routinely incinerate waste arising from the non-nuclear user community. To address the requirement from Germany, EnergySolutions had to run a dedicated campaign to reduce cross-contamination with non-German radionuclides to the practical minimum. The waste itself had to be sampled in a carefully controlled programme to ensure the exacting standards of Bear Creek's license and US emissions laws were maintained. Innovation was required in packaging of the waste to minimise transportation costs, including sea freight. The incineration was inspected on behalf of the German regulator (the BfS) to ensure suitability for return to Germany and disposal. This first 'burn and return' programme has safely completed the incineration phase in February and the arising ash will be returned to Germany presently. The paper reports the main findings and lessons learned on this first

Advantages and disadvantages of relational and non-relational (NoSQL) databases for analytical tasks

OpenAIRE

Klapač, Milan

2015-01-01

This work focuses on NoSQL databases, their use for analytical tasks and on comparison of NoSQL databases with relational and OLAP databases. The aim is to analyse the benefits of NoSQL databases and their use for analytical purposes. The first part presents the basic principles of Business Intelligence, Data Warehousing, and Big Data. The second part deals with the key features of relational and NoSQL databases. The last part of the thesis describes the properties of four basic types of NoSQ...

Ambient radioactivity levels and radiation doses. Annual report 2009

International Nuclear Information System (INIS)

Bernhard-Stroel, Claudia; Hachenburger, Claudia; Trugenberger-Schnabel, Angela; Peter, Josef

2010-12-01

The annual report on environmental radioactivity and radiation exposure 2009 consists of two parts. Part A: General information: natural environmental radioactivity, artificial radioactivity in the environment, occupational radiation exposure, radiation exposures from medical applications, the handling of radioactive materials and sources of ionizing radiation, non-ionizing radiation. Part B includes current data and their evaluation for natural environmental radioactivity, artificial radioactivity in the environment, occupational radiation exposure, radiation exposures from medical applications, the handling of radioactive materials and sources of ionizing radiation, non-ionizing radiation.

Mixed radioactive and chemotoxic wastes (RMW)

International Nuclear Information System (INIS)

Dejonghe, I.P.

1991-01-01

During the first decades of development of nuclear energy, organizations involved in the management of nuclear wastes had their attention focused essentially on radioactive components. The impression may have prevailed that, considering the severe restrictions on radioactive materials, the protection measured applied for radioactive components of wastes would be more than adequate to cope with potential hazards from non radioactive components associated with radioactive wastes. More recently it was acknowledged that such interpretation is not necessarily justified in all cases since certain radioactive wastes also contain non-negligible amounts of heavy metals or hazardous organic components which, either, do not decay, or are subject to completely different decay (decomposition) mechanisms. The main purposes of the present study are to analyze whether mixed radioactive wastes are likely to occur in Europe and in what form, whether one needs a basis for integration for evaluating various forms of toxicity and by which practical interventions possible problems can be avoided or at least reduced. (au)

Solid and liquid radioactive wastes

International Nuclear Information System (INIS)

Cluchet, J.; Desroches, J.

1977-01-01

The problems raised by the solid and liquid radioactive wastes from the CEA nuclear centres are briefly exposed. The processing methods developed at the Saclay centre are described together with the methods for the wastes from nuclear power plants and reprocessing plants. The different storage techniques used at the La Hague centre are presented. The production of radioactive wastes by laboratories, hospitals and private industry is studied for the sealed sources and the various radioactive substances used in these plants. The cost of the radioactive wastes is analysed: processing, transport, long term storage [fr

Results of the Interlaboratory Exercise CNS/CIEMAT-04 Among Environmental Radioactivity Laboratories (Aqueous Solution)

International Nuclear Information System (INIS)

Romero Gonzalez, M. L.; Barrera Izquierdo, M.

2004-01-01

The document describes the outcome of the CSN/CIEMAT-04 interlaboratory test comparison among environmental radioactivity laboratories. The exercise was organised according to the ISO-43 and the ISO/IUPAC/AOAC Harmonised Protocol for the proficiency testing of analytical laboratories. Following the issue of the European Community Drinking Water Directive 98/83/EC concerning the quality of water for human consumption, the last inter-comparison exercise was organised by using a water sample, in an attempt to evaluate the performance of the laboratories analysing the required radioactivity parameters (H-3, gross alpha and beta activity and residual beta). The sample (a synthetic drinking water), was prepared at the National Laboratory for Ionising Radiation's Standards (CIEMAT), and contained the following radionuclides ''241 Am, ''239+240 Pu, ''90Sr, ''137 Cs, ''3 H y ''40 K. The results of the exercise were computed for 38 participating laboratories, and their analytical performance was assessed using the z-score approach. Robust statistics of the participant's results was applied to obtain the median and standard deviation, including suspected outliers. The exercise has revealed and homogeneous behaviour of laboratories, being statistical parameters from the results close to the reference values. A raised percentage os satisfactory laboratory performance has been obtained for gross alpha, gross beta and residual beta: 85, 97 and 87% respectively. The study has shown that participant laboratories perform radioactive determinations in drinking water samples with satisfactory quality levels. (Author) 16 refs

Self-consistent spectral function for non-degenerate Coulomb systems and analytic scaling behaviour

International Nuclear Information System (INIS)

Fortmann, Carsten

2008-01-01

Novel results for the self-consistent single-particle spectral function and self-energy are presented for non-degenerate one-component Coulomb systems at various densities and temperatures. The GW (0) -method for the dynamical self-energy is used to include many-particle correlations beyond the quasi-particle approximation. The self-energy is analysed over a broad range of densities and temperatures (n = 10 17 cm -3 -10 27 cm -3 , T = 10 2 eV/k B -10 4 eV/k B ). The spectral function shows a systematic behaviour, which is determined by collective plasma modes at small wavenumbers and converges towards a quasi-particle resonance at higher wavenumbers. In the low density limit, the numerical results comply with an analytic scaling law that is presented for the first time. It predicts a power-law behaviour of the imaginary part of the self-energy, ImΣ ∼ -n 1/4 . This resolves a long time problem of the quasi-particle approximation which yields a finite self-energy at vanishing density

Advanced techniques for analytic liquid wastes management in the Rokkasho reprocessing plant

International Nuclear Information System (INIS)

Madic, C.; Moulin, J.P.; Runge, S.; Schott, R.; Kashiwai, T.; Hayashi, M.

1991-01-01

The JNFS Rokkasho reprocessing plant is a large scale commercial reprocessing plant. Liquid waste treatment relies on concentration by evaporation. The management of liquid wastes is rather sophisticated and implies, beside the organic wastes, sorting out between process and non-process, acidic and salt-bearing, tritiated and low tritiated streams and also according to their level of activity. A particular attention had to be paid to the analytical wastes, as their particularity is to contain not only a significant amount of radioactivity but also some fissile material and exotic chemicals which are useful for analytical purpose but unwanted in the main process mainly because of their corrosive and chelating properties. The analytical wastes are sorted out according to their activity level and fissile material content. On the one hand, a specific process has been developed to recover the bulk of plutonium from the analytical wastes. On the other hand, the foreseeable amount of unwanted chemicals (such as chloride ions) has been drastically reduced by carefully selecting all the analytical methods either by modification of already known methods or in some cases by working out new methods

Learning Analytics: Readiness and Rewards / L’analyse de l’apprentissage : état de préparation et récompenses

Directory of Open Access Journals (Sweden)

Norm Friesen

2013-12-01

Full Text Available This paper introduces the relatively new field of learning analytics, first by considering the relevant meanings of both “learning” and “analytics,” and then by looking at two main levels at which learning analytics can be or has been implemented in educational organizations. Although turnkey systems or modules are not yet available for review, specific technologies for analyzing online student activities have been implemented and piloted. As a result, this paper recommends an incremental approach to institutional preparedness. Ce rapport présente le domaine relativement nouveau de l’analyse de l’apprentissage en considérant d’abord la pertinence des deux termes “apprentissage” et “analyse”, puis en examinant les deux principaux niveaux auxquels l’analyse de l’apprentissage peut être ou a été mise en œuvre dans les organisations éducatives. Bien que des systèmes ou des modules « clés en main » intégrés ne puissent pas encore être examinés, des technologies spécifiques pour analyser les activités en ligne des étudiants ont été mises en place et testées. En conséquence, cet essai conseille en conclusion une approche progressive de préparation institutionnelle.

Analytical solutions for recession analyses of sloping aquifers - applicability on relict rock glaciers in alpine catchments

Science.gov (United States)

Pauritsch, Marcus; Birk, Steffen; Hergarten, Stefan; Kellerer-Pirklbauer, Andreas; Winkler, Gerfried

2014-05-01

Rock glaciers as aquifer systems in alpine catchments may strongly influence the hydrological characteristics of these catchments. Thus, they have a high impact on the ecosystem and potential natural hazards such as for example debris flow. Therefore, knowledge of the hydrodynamic processes, internal structure and properties of these aquifers is important for resource management and risk assessment. The investigation of such aquifers often turns out to be expensive and technically complicated because of their strongly limited accessibility. Analytical solutions of discharge recession provide a quick and easy way to estimate aquifer parameters. However, due to simplifying assumptions the validity of the interpretation is often questionable. In this study we compared results of an analytical solution of discharge recessions with results based on a numerical model. This was done in order to analyse the range of uncertainties and the applicability of the analytical method in alpine catchment areas. The research area is a 0.76 km² large catchment in the Seckauer Tauern Range, Austria. The dominant aquifer in this catchment is a rock glacier, namely the Schöneben Rock Glacier. This relict rock glacier (i.e. containing no permafrost at present) covers an area of 0.11 km² and is drained by one spring at the rock glacier front. The rock glacier consists predominantly of gneissic sediments (mainly coarse-grained, blocky at the surface) and extends from 1720 to 1905 m a.s.l.. Discharge of the rock glacier spring is automatically measured since 2002. Electric conductivity and water temperature is monitored since 2008. An automatic weather station was installed in 2011 in the central part of the catchment. Additionally data of geophysical surveys (refraction seismic and ground penetrating radar) have been used to analyse the base slope and inner structure of the rock glacier. The measured data are incorporated into a numerical model implemented in MODFLOW. The numerical

32-Week Holding-Time Study of SUMMA Polished Canisters and Triple Sorbent Traps Used To Sample Organic Constituents in Radioactive Waste Tank Vapor Headspace

International Nuclear Information System (INIS)

Evans, John C.; Huckaby, James L.; Mitroshkov, Alexandre V.; Julya, Janet L.; Hayes, James C.; Edwards, Jeffrey A.; Sasaki, Leela M.

1997-01-01

Two sampling methods[SUMMA polished canisters and triple sorbent traps (TSTs)] were compared for long-term storage of trace organic vapor samples collected from the headspaces of high-level radioactive waste tanks at the U.S. Department of Energy's Hanford Site in Washington State. Because safety, quality assurance, radiological controls, the long-term stability of the sampling media during storage needed to be addressed. Samples were analyzed with a gas chromatograph/mass spectrometer (GC/MS) using cryogenic reconcentration or thermal desorption sample introduction techniques. SUMMA canister samples were also analyzed for total non-methane organic compounds (TNMOC) by GC/flame ionization detector (FID) using EPA Compendium Method TO-12 . To verify the long-term stability of the sampling media, multiple samples were collected in parallel from a typical passively ventilated radioactive waste tank known to contain moderately high concentrations of both polar and nonpolar organic compounds. Analyses for organic analytes and TNMOC were conducted at increasing intervals over a 32-week period to determine whether any systematic degradation of sample integrity occurred. Analytes collected in the SUMMA polished canisters generally showed good stability over the full 32 weeks with recoveries at the 80% level or better for all compounds studied. The TST data showed some loss (50-80% recovery) for a few high-volatility compounds even in the refrigerated samples; losses for unrefrigerated samples were far more pronounced with recoveries as low as 20% observed in a few cases

Non-linear degradation model of cement barriers in a borehole repository for disused radioactive sources

International Nuclear Information System (INIS)

Gharbieh, Heidar K.; Cota, Stela

2015-01-01

Narrow diameter borehole facilities (a few tens of centimeters), like the BOSS concept developed by the IAEA, provide a safe and cost effective disposal option for radioactive waste and particularly disused sources. The BOSS concept (borehole disposal of sealed radioactive sources) comprises a multi-barrier system of cement grout and stainless steel components. In order to predict the long-time performance of the cement barriers as an input of a future safety assessment under the specific hydrochemical and hydrological conditions, a non-linear degradation model was developed in this work. With the assistance of the program 'PHREEQC' it describes the change of the porosity and the hydraulic conductivity with time, which also let to conclusions concerning the change of the sorption capacity of the cement grout. This work includes the theoretical approach and illustrates the non-liner degradation by means of an exemplary water composition found in the saturated zone and the dimensions of the backfill made of cement grout representing a barrier of the BOSS borehole facility. (author)

Analyses for some transuranic and natural radionuclides in the environmental samples

International Nuclear Information System (INIS)

Harley, J.H.

1978-01-01

There is considerable present and expected future interest in the contamination of the environment with transuranic elements, particularly plutonium and americium. In addition, the alpha-emitting natural radionuclides are the usual standard of comparison for such transuranic element contamination. The present paper reviews the quality of data available for evaluating the distribution of transuranic elements and some natural radioactive elements in the environment. The overall quality cannot be documented for most programs and the data that are available indicate that the quality is poor. The fact that a few programs maintain high quality analyses indicates that the cause is poor analytical work rather than poor methods of analysis. (author)

An improved analytical method for iodine-129 determination in low-level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Hsieh, Yi-Kong; Wang, TsingHai; Jian, Li-Wei; Chen, Wei-Han; Wang, Chu-Fang [National Tsing Hua Univ., Hsinchu, Taiwan (China). Dept. of Biomedical Engineering and Environmental Sciences; Tsai, Tsuey-Lin [Atomic Energy Council, Taiwan (China). Chemical Analysis Div.

2014-07-01

In this study, an alkaline-digestion pretreatment and a subsequent ICP-MS measurement were conducted for iodine-129 (I-129) determination in low-level radioactive waste. A TMAH + H{sub 2}O{sub 2} + Triton X-100 mixed alkaline digestion was the most effective mixture for I-129 determination. Using this alkaline reagent, a high level of I-129 recovery (101 ± 6%) was achieved for the analysis of the I-129-spiked standard reference materials NIST 2709 and 2711. Importantly, the I-129 concentrations determined for ten real samples provided by the Lan-Yu radioactive waste temporary storage site were found to be below the detection limit (0.011 mg/kg). This value was only approximately 30-70% of the values determined using the I-129/Cs-137 scaling factor. This means that using the I-129/Cs-137 scaling factor severely overestimates the I-129 concentration in these low-level radioactive wastes. We therefore suggest that a detailed re-inspection of the I-129/Cs-137 scaling factor should be performed to appropriately categorize these low-level radioactive wastes.

Calculational framework for safety analyses of non-reactor nuclear facilities

International Nuclear Information System (INIS)

Coleman, J.R.

1994-01-01

A calculational framework for the consequences analysis of non-reactor nuclear facilities is presented. The analysis framework starts with accident scenarios which are developed through a traditional hazard analysis and continues with a probabilistic framework for the consequences analysis. The framework encourages the use of response continua derived from engineering judgment and traditional deterministic engineering analyses. The general approach consists of dividing the overall problem into a series of interrelated analysis cells and then devising Markov chain like probability transition matrices for each of the cells. An advantage of this division of the problem is that intermediate output (as probability state vectors) are generated at each calculational interface. The series of analyses when combined yield risk analysis output. The analysis approach is illustrated through application to two non-reactor nuclear analyses: the Ulysses Space Mission, and a hydrogen burn in the Hanford waste storage tanks

Follow-up and control of analytical results from environmental monitoring program of the Radioactive Waste Disposal Facility - Abadia de Goias

International Nuclear Information System (INIS)

Peixoto, Claudia Marques; Jacomino, Vanusa Maria Feliciano

2000-01-01

The analytical results for the 12 month period (August/1997 to July/1998) of the Environmental Monitoring Program operational phase of the radioactive waste disposal facility 'Abadia de Goias' (DIGOI), located in the District of Goiania, are summarized in this report. A statistical treatment of the data using control graphs is also presented. The use of these graphs allows the arrangement of the data in a way that facilitates process control and visualization of data trends and periodicity organized according to temporal variation. A comparison is made of these results vs. those obtained during the pre-operational phase. Moreover, the effective equivalent dose received by the public individuals for different critical pathways is estimated. (author)

Analytical prediction model for non-symmetric fatigue crack growth in Fibre Metal Laminates

NARCIS (Netherlands)

Wang, W.; Rans, C.D.; Benedictus, R.

2017-01-01

This paper proposes an analytical model for predicting the non-symmetric crack growth and accompanying delamination growth in FMLs. The general approach of this model applies Linear Elastic Fracture Mechanics, the principle of superposition, and displacement compatibility based on the

Emerging concepts and requirements for the long-term management of non-radioactive hazardous wastes - would geological disposal be an appropriate solution for some of these wastes

International Nuclear Information System (INIS)

Rein, K. von

1994-01-01

This work deals with the emerging concepts and requirements for the long-term management of non-radioactive hazardous wastes. After some generalities on the pollution of natural environment and the legislations taken by the swedish government the author tries to answer to the question : would geological disposal be an appropriate solution for the non-radioactive hazardous wastes? Then is given the general discussion of the last three articles concerning the background to current environmental policies and their implementation and more particularly the evolution and current thoughts about environmental policies, the managing hazardous activities and substances and the emerging concepts and requirements for the long-term management of non-radioactive hazardous wastes. Comments and questions concerning the similarity or otherwise between the present position of radioactive waste disposal and the background to current environmental policies are indicated. (O.L.)

Materials characterization of radioactive waste forms using a multi-element detection method based on the instrumental neutron activation analysis. MEDINA; Stoffliche Charakterisierung radioaktiver Abfallprodukte durch ein Multi-Element-Analyseverfahren basierend auf der instrumentellen Neutronen-Aktivierungs-Analyse. MEDINA

Energy Technology Data Exchange (ETDEWEB)

Havenith, Andreas Wilhelm

2015-07-01

Radioactive waste has to meet the specifications and acceptance criteria defined by national regulatory and management authorities for its intermediate and final storage. In Germany the Federal Office for Radiation Protection (Bundesamt fuer Strahlenschutz - BfS) has established waste acceptance requirements for the Konrad repository. Konrad is the disposal for radioactive waste with negligible heat generation and is located near the city of Salzgitter and is currently under construction. It will start operation not before the year 2021. The waste-acceptance-requirements are derived from a site-specific safety assessment. They include specific requirements on waste forms, packaging as well as limitations to activities of individual radionuclides and limitations to masses of non-radioactive harmful substances. The amount of chemically toxic elements in the waste is limited in order to avoid pollution of underground water reserves. To comply with these requirements every waste package has to be characterised in its radiological and chemical composition. This characterisation can be performed on the basis of existing documentation or, if the documentation is insufficient, on further analytical analysis. Segmented or integral gamma-scanning as well as active or passive neutron counting are used worldwide as the standard measurement methods for the radiological characterisation and quality checking of radioactive waste. These techniques determine the isotope specific activity of waste packages, but they do not allow the detection of non-radioactive hazardous substances inside the waste packages. Against this background the Institute of Nuclear Engineering and Technology Transfer (NET) at RWTH Aachen University and the Institute of Safety Research and Reactor Technology at Forschungszentrum Juelich jointly develop an innovative non-destructive analytical technique called MEDINA - ''Multi-Element Detection based on Instrumental Neutron Activation'' for

Full and semi-analytic analyses of two-pump parametric amplification with pump depletion

DEFF Research Database (Denmark)

Steffensen, Henrik; Ott, Johan Raunkjær; Rottwitt, Karsten

2011-01-01

This paper solves the four coupled equations describing non-degenerate four-wave mixing, with the focus on amplifying a signal in a fiber optical parametric amplifier (FOPA). Based on the full analytic solution, a simple approximate solution describing the gain is developed. The advantage...... of this new approximation is that it includes the depletion of the pumps, which is lacking in the usual quasi-linearized approximation. With the proposed model it is thus simple to predict the gain of a FOPA, which we demonstrate with a highly nonlinear fiber to show that an undepleted FOPA can produce a flat...

System for disposing of radioactive waste

International Nuclear Information System (INIS)

Gablin, K.A.; Hansen, L.J.

1979-01-01

A system is described for disposing of radioactive waste material from nuclear reactors by solidifying the liquid components to produce an encapsulated mass adapted for disposal by burial. The method contemplates mixing of radioactive waste materials, with or without contained solids, with a setting agent capable of solidifying the waste liquids into a free standing hardened mass, placing the resulting liquid mixture in a container with a proportionate amount of a curing agent to effect solidification under controlled conditions, and thereafter burying the container and contained solidified mixture. The setting agent is a water-extendable polymer consisting of a suspension of partially polymerized particles of urea formaldehyde in water, and the curing agent is sodium bisulfate. Methods are disclosed for dewatering slurry-like mixtures of liquid and particulate radioactive waste materials, such as spent ion exchange resin beads, and for effecting desired distribution of non-liquid radioactive materials in the central area of the container prior to solidification, so that the surrounding mass of lower specific radioactivity acts as a partial shield against higher radioactivity of the non-liquid radioactive materials. The methods also provide for addition of non-radioactive filler materials to dilute the mixture and lower the overall radioactivity of the hardened mixture to desired Lowest Specific Activity counts. An inhibiting agent is added to the liquid mixture to adjust the solidification time, and provision is made for adding additional amounts of setting agent and curing agent to take up any free water and further encapsulate the hardened material within the container. 30 claims

System for disposing of radioactive waste

International Nuclear Information System (INIS)

Gablin, K.A.; Hansen, L.J.

1977-01-01

A system is described for disposing of radioactive waste material from nuclear reactors by solidifying the liquid components to produce an encapsulated mass adapted for disposal by burial. The method contemplates mixing of radioactive waste materials, with or without contained solids, with a setting agent capable of solidifying the waste liquids into a free standing hardened mass, placing the resulting liquid mixture in a container with a proportionate amount of a curing agent to effect solidification under controlled conditions, and thereafter burying the container and contained solidified mixture. The setting agent is a water-extendable polymer consisting of a suspension of partially polymerized particles of urea formaldehyde in water, and the curing agent is sodium bisulfate. Methods are disclosed for dewatering slurry-like mixtures of liquid and particulate radioactive waste materials, such as spent ion exchange resin beads, and for effecting desired distribution of non-liquid radioactive materials in the central area of the container prior to solidification, so that the surrounding mass of lower specific radioactivity acts as a partial shield against higher radioactivity of the non-liquid radioactive materials. The methods also provide for addition of non-radioactive filler materials to dilute the mixture and lower the overall radioactivity of the hardened mixture to desired Lowest Specific Activity counts. An inhibiting agent is added to the liquid mixture to adjust the solidification time, and provision is made for adding additional amounts of setting agent and curing agent to take up any free water and further encapsulate the hardened material within the container

Analytical Chemistry Division annual progress report for period ending December 31, 1982

International Nuclear Information System (INIS)

Lyon, W.S.

1983-05-01

The Analytical Chemistry Dvision of Oak Ridge National laboratory (ORNL) serves a multitude of functions for a clientele that exists both in and outside ORNL. These functions fall into the following general categories: (1) analytical research, development, and implementation; (2) programmatic research, development, and utilization; and (3) technical support. The Division is organized into five major sections, each of which may carry out any type of work falling in the three categories mentioned above. Chapters 1 through 5 of this report highlight progress within the five sections (analytical methodology, mass and emission spectrometry, radioactive materials, bio/organic analysis, and general and environmental analysis) during the period January 1, 1982 to December 31, 1982. A short summary introduces each chapter to indicate work scope. Information about quality assurance and safety programs is presented in Chapter 6, along with a tabulation of analyses rendered. Publications, oral presentations, professional activities, educational programs, and seminars are cited in Chapters 7 and 8. Approximately 61 articles, 32 proceedings publications and 37 reports have been published, and 107 oral presentations were given during this reporting period

Regulatory inspection practices for radioactive and non-radioactive waste management facilities

International Nuclear Information System (INIS)

Roy, Amitava

2017-01-01

Management of nuclear waste plays an important role in the nuclear energy programme of the country. India has adopted the Closed Fuel Cycle option, where the spent nuclear fuel is treated as a material of resource and the nuclear waste is wealth. Closed fuel cycle aims at recovery and recycle of valuable nuclear materials in to reactors as fuel and also separation of useful radio isotopes for the use in health care, agriculture and industry. India has taken a lead role in the waste management activities and has reached a level of maturity over a period of more than forty decades. The nuclear waste management primarily comprises of waste characterization, segregation, conditioning, treatment, immobilization of radionuclides in stable and solid matrices and interim retrievable storage of conditioned solid waste under surveillance. The waste generated in a nuclear facility is in the form of liquid and solid, and it's classification depends on the content of radioactivity. The liquid waste is characterized as Low level (LLW), Intermediate level (ILW) and High Level (HLW). The LLW is relatively large in volume and much lesser radioactive. The LLW is subjected to chemical precipitation using various chemicals based on the radionuclides present, followed by filtration, settling, ion exchange and cement fixation. The conditioning and treatment processes of ILW uses ion exchange, alkali hydrolysis for spent solvent, phase separation and immobilization in cement matrix. The High Level Waste (HLW), generated during spent fuel reprocessing and containing more than 99 percent of the total radioactivity is first subjected to volume reduction/concentration by evaporation and then vitrified in a meIter using borosilicate glass. Presently, Joule Heated Ceramic Meter is used in India for Vitrification process. Vitrified waste products (VWP) are stored for interim period in a multibarrier, air cooled facility under surveillance

A simplified system for doing ICP analysis on radioactive samples

International Nuclear Information System (INIS)

McCown, J.J.

1985-11-01

Methods for setting up equipment to perform analyses on radioactive materials vary considerably from one site to another. Factors include the interests of the group involved, i.e., research vs service work; the type of building containing the lab; the arrangement of the lab for contamination control; previous experiences in operating similar equipment; the local interpretation of safety regulations; and the time and money available for the task. The Chemistry and Analysis group of the Westinghouse Hanford Company performs analytical chemistry in support of many Hanford programs. Samples analyzed cover a wide variety of materials with more than 50% involving radioactivity of one type or another. All of the laboratories in the building are connected to a common exhaust system with ductwork leading to the basement. Double HEPA filtration is provided with the first stage in the basement and the final stage done in the exhaust fan and filter building northwest of the main building. In addition, glove boxes are equipped with small HEPA filters on their outlet providing another stage of filtration. 6 figs

Lessons to be learned from radioactive waste disposal practices for non-radioactive hazardous waste management

International Nuclear Information System (INIS)

Merz, E.R.

1991-01-01

The criteria to be set up for any kind of hazardous waste disposal must always be put in perspective: 1. what are the waste characteristics? 2. what time period for safe isolation is of interest? 3. which geological disposal alternatives exist? Different approaches may be used in the short- and long-term perspective. In either case, a general procedure is recommended which involves concentrating, containing and isolating the source of toxicity, both radioactive and chemotoxic substances, as far as practicable. Waste characterization of either chemotoxic or radioactive wastes should be performed applying comparable scientifically based principles. The important question which arises is whether their hazard potential can be quantified on the basis of dose comparison regarding the morbidity effects of radiation and of chemical pollutants. Good control over the consequences of hazardous waste disposal requires threat detailed criteria for tolerable contamination of radioactive as well as chemical pollutants should be established, and that compliance with these criteria can be demonstrated. As yet, there are no well developed principles for assessing the detriment from most types of genotoxic waste other than radioactive material. The time horizon discussed for both categories of waste for their proof of safe isolation differs by a factor of about one hundred. (au)

H Canyon Processing In Correlation With FH Analytical Labs

International Nuclear Information System (INIS)

Weinheimer, E.

2012-01-01

Management of radioactive chemical waste can be a complicated business. H Canyon and F/H Analytical Labs are two facilities present at the Savannah River Site in Aiken, SC that are at the forefront. In fact H Canyon is the only large-scale radiochemical processing facility in the United States and this processing is only enhanced by the aid given from F/H Analytical Labs. As H Canyon processes incoming materials, F/H Labs provide support through a variety of chemical analyses. Necessary checks of the chemical makeup, processing, and accountability of the samples taken from H Canyon process tanks are performed at the labs along with further checks on waste leaving the canyon after processing. Used nuclear material taken in by the canyon is actually not waste. Only a small portion of the radioactive material itself is actually consumed in nuclear reactors. As a result various radioactive elements such as Uranium, Plutonium and Neptunium are commonly found in waste and may be useful to recover. Specific processing is needed to allow for separation of these products from the waste. This is H Canyon's specialty. Furthermore, H Canyon has the capacity to initiate the process for weapons-grade nuclear material to be converted into nuclear fuel. This is one of the main campaigns being set up for the fall of 2012. Once usable material is separated and purified of impurities such as fission products, it can be converted to an oxide and ultimately turned into commercial fuel. The processing of weapons-grade material for commercial fuel is important in the necessary disposition of plutonium. Another processing campaign to start in the fall in H Canyon involves the reprocessing of used nuclear fuel for disposal in improved containment units. The importance of this campaign involves the proper disposal of nuclear waste in order to ensure the safety and well-being of future generations and the environment. As processing proceeds in the fall, H Canyon will have a substantial

Fusion reactor radioactive waste management

International Nuclear Information System (INIS)

Kaser, J.D.; Postma, A.K.; Bradley, D.J.

1976-01-01

Quantities and compositions of non-tritium radioactive waste are estimated for some current conceptual fusion reactor designs, and disposal of large amounts of radioactive waste appears necessary. Although the initial radioactivity of fusion reactor and fission reactor wastes are comparable, the radionuclides in fusion reactor wastes are less hazardous and have shorter half-lives. Areas requiring further research are discussed

Reactor Section standard analytical methods. Part 1

Energy Technology Data Exchange (ETDEWEB)

Sowden, D.

1954-07-01

the Standard Analytical Methods manual was prepared for the purpose of consolidating and standardizing all current analytical methods and procedures used in the Reactor Section for routine chemical analyses. All procedures are established in accordance with accepted practice and the general analytical methods specified by the Engineering Department. These procedures are specifically adapted to the requirements of the water treatment process and related operations. The methods included in this manual are organized alphabetically within the following five sections which correspond to the various phases of the analytical control program in which these analyses are to be used: water analyses, essential material analyses, cotton plug analyses boiler water analyses, and miscellaneous control analyses.

Proceedings of the 4. National Meeting on Analytical Chemistry - Abstracts

International Nuclear Information System (INIS)

1987-01-01

The 4. National Meeting on Analytical Chemistry includes analysis of nuclear interest elements with nuclear and non nuclear methods and the elements not interest of nuclear energy with nuclear methods. The materials analysed are rocks, ores, metals alloys, waters, plants and biological materials. (C.G.C.)

General Atomic's radioactive gas recovery system

International Nuclear Information System (INIS)

Mahn, J.A.; Perry, C.A.

1975-01-01

General Atomic Company has developed a Radioactive Gas Recovery System for the HTGR which separates, for purposes of retention, the radioactive components from the non-radioactive reactor plant waste gases. This provides the capability for reducing to an insignificant level the amount of radioactivity released from the gas waste system to the atmosphere--a most significant improvement in reducing total activity release to the environment. (U.S.)

Automated Sample Preparation for Radiogenic and Non-Traditional Metal Isotopes: Removing an Analytical Barrier for High Sample Throughput

Science.gov (United States)

Field, M. Paul; Romaniello, Stephen; Gordon, Gwyneth W.; Anbar, Ariel D.; Herrmann, Achim; Martinez-Boti, Miguel A.; Anagnostou, Eleni; Foster, Gavin L.

2014-05-01

MC-ICP-MS has dramatically improved the analytical throughput for high-precision radiogenic and non-traditional isotope ratio measurements, compared to TIMS. The generation of large data sets, however, remains hampered by tedious manual drip chromatography required for sample purification. A new, automated chromatography system reduces the laboratory bottle neck and expands the utility of high-precision isotope analyses in applications where large data sets are required: geochemistry, forensic anthropology, nuclear forensics, medical research and food authentication. We have developed protocols to automate ion exchange purification for several isotopic systems (B, Ca, Fe, Cu, Zn, Sr, Cd, Pb and U) using the new prepFAST-MC™ (ESI, Nebraska, Omaha). The system is not only inert (all-flouropolymer flow paths), but is also very flexible and can easily facilitate different resins, samples, and reagent types. When programmed, precise and accurate user defined volumes and flow rates are implemented to automatically load samples, wash the column, condition the column and elute fractions. Unattended, the automated, low-pressure ion exchange chromatography system can process up to 60 samples overnight. Excellent reproducibility, reliability, recovery, with low blank and carry over for samples in a variety of different matrices, have been demonstrated to give accurate and precise isotopic ratios within analytical error for several isotopic systems (B, Ca, Fe, Cu, Zn, Sr, Cd, Pb and U). This illustrates the potential of the new prepFAST-MC™ (ESI, Nebraska, Omaha) as a powerful tool in radiogenic and non-traditional isotope research.

8. All Polish Conference on Analytical Chemistry: Analytical Chemistry for the Community of the 21. Century

International Nuclear Information System (INIS)

Koscielniak, P.; Wieczorek, M.; Kozak, J.

2010-01-01

Book of Abstracts contains short descriptions of lectures, communications and posters presented during 8 th All Polish Conference on Analytical Chemistry (Cracow, 4-9.07.2010). Scientific programme consisted of: basic analytical problems, preparation of the samples, chemometry and metrology, miniaturization of the analytical procedures, environmental analysis, medicinal analyses, industrial analyses, food analyses, biochemical analyses, analysis of relicts of the past. Several posters were devoted to the radiochemical separations, radiochemical analysis, environmental behaviour of the elements important for the nuclear science and the professional tests.

Unified analytical threshold voltage model for non-uniformly doped dual metal gate fully depleted silicon-on-insulator MOSFETs

Science.gov (United States)

Rao, Rathnamala; Katti, Guruprasad; Havaldar, Dnyanesh S.; DasGupta, Nandita; DasGupta, Amitava

2009-03-01

The paper describes the unified analytical threshold voltage model for non-uniformly doped, dual metal gate (DMG) fully depleted silicon-on-insulator (FDSOI) MOSFETs based on the solution of 2D Poisson's equation. 2D Poisson's equation is solved analytically for appropriate boundary conditions using separation of variables technique. The solution is then extended to obtain the threshold voltage of the FDSOI MOSFET. The model is able to handle any kind of non-uniform doping, viz. vertical, lateral as well as laterally asymetric channel (LAC) profile in the SOI film in addition to the DMG structure. The analytical results are validated with the numerical simulations using the device simulator MEDICI.

Relativistic quantum mechanic calculation of photoionization cross-section of hydrogenic and non-hydrogenic states using analytical potentials

International Nuclear Information System (INIS)

Rodriguez, R.; Gil, J.M.; Rubiano, J.G.; Florido, R.; Martel, P.; Minguez, E.

2005-01-01

Photoionization process is a subject of special importance in many areas of physics. Numerical methods must be used in order to obtain photoionization cross-sections for non-hydrogenic levels. The atomic data required to calculate them is huge so self-consistent calculations increase computing time considerably. Analytical potentials are a useful alternative because they avoid the iterative procedures typical in self-consistent models. In this work, we present a relativistic quantum calculation of photoionization cross-sections for isolated ions based on an analytical potential to obtain the required atomic data, which is valid both for hydrogenic and non-hydrogenic ions. Comparisons between our results and others obtained using either widely used analytical expressions for the cross-sections or more sophisticated calculations are done

Labelling of olive oil with radioactive iodine and radioactive technetium

International Nuclear Information System (INIS)

Al-Dayel, O.A.F.

1988-03-01

Investigates labelling of olive oil with 125 iodine and with the radioactive 99mTC. A radio analytical study for 99Mo-99mTC generator is also presented. Iodine monochloride and chlormine-T methods are used for labelling olive oil and oleic acid with radioactive iodine. Diethyl ether, benzene and n-heptane have been used as solvents, with diethyl ether giving best results using iodine monochloride method. Infrared spectroscopic studies show that labelling took place at the double bond. Use of milked 99mTc gave very low yield only. A fairly higher labelling yield was achieved when 20 mg of tin chloride has been added in acetone medium than diethyl ether medium. Thin layer chromatography and paper chromatography technique were used as quality control systems. The labelled oil can be used for diagnostic and study purposes. 140 Ref

Incineration of Non-radioactive Simulated Waste

International Nuclear Information System (INIS)

Ahmed, A.Z.; Abdelrazek, I.D.

1999-01-01

An advanced controlled air incinerator has been investigated, developed and put into successful operation for both non radioactive simulated and other combustible solid wastes. Engineering efforts concentrated on providing an incinerator which emitted a clean, easily treatable off-gas and which produced minimum amounts of secondary waste. Feed material is fed by gravity into the gas reactor without shredding or other pretreatment. The temperature of the waste is gradually increased in a reduced oxygen atmosphere as the resulting products are introduced into the combustion chamber. Steady burning is thus accomplished under easily controlled excess air conditions with the off-gas then passing through a simple dry cleaning-up system. Experimental studies showed that, at lower temperature, CO 2 , and CH 4 contents in gas reactor effluent increase by the increase of glowing bed temperature, while H 2 O, H 2 and CO decrease . It was proved that, a burn-out efficiency (for ash residues) and a volume reduction factor appeared to be better than 95.5% and 98% respectively. Moreover, high temperature permits increased volumes of incinerated material and results in increased gasification products. It was also found that 8% by weight of ashes are separated by flue gas cleaning system as it has chemical and size uniformity. This high incineration efficiency has been obtained through automated control and optimization of process variables like temperature of the glowing bed and the oxygen feed rate to the gas reactor

Mental Models of Radioactivity and Attitudes towards Radioactive Waste

International Nuclear Information System (INIS)

Zeleznik, N.

2010-01-01

Siting of a radioactive waste repository presents a great problem in almost every country that produces such waste. The main problem is not a technical one, but socio-psychological, namely the acceptability of this kind of repository. Previous research on people's perception of the LILW repository construction, their attitudes towards radioactive waste, their willingness to accept it, indicated significant differences in answers of experts and lay persons, mainly regarding evaluation of the consequences of repository construction. Based on the findings of pilot investigations a mental model approach to the radioactivity, radioactive waste and repository was used as a method for development better risk communication strategies with local communities. The mental models were obtained by adjustment of the method developed by Morgan and co-workers where expert model of radioactivity is compared with mental model of lay people obtained through individual opened interviews. Additional information on trust, risk perception, role of main actors in the site selection process and their credibility was gained with the overall questionnaire on the representative sample of Slovenian population. Results of the survey confirm some already known findings, in addition we gained new cognitions and with analyses obtained the relationships and ratios between different factors, which are characteristics both for the general public and for the public, which is involved in the site selection process for a longer period and has been living beside a nuclear power plant for one generation. People have in general negative associations regarding the repository, the perceived risk for nuclear facilities is high, and trust in representatives of governmental institutions is low. Mental models of radioactivity, radioactive waste and the LILW repository are mostly irregular and differ from the experts' models. This is particularly valid for the models of radioactivity and the influences of

Explicit solutions for exit-only radioactive decay chains

International Nuclear Information System (INIS)

Yuan, Ding; Kernan, Warnick

2007-01-01

In this study, we extended Bateman's [Proc. Cambridge Philos. Soc. 15, 423 (1910)] original work for solving radioactive decay chains and explicitly derived analytic solutions for generic exit-only radioactive decay problems under given initial conditions. Instead of using the conventional Laplace transform for solving Bateman's equations, we used a much simpler algebraic approach. Finally, we discuss methods of breaking down certain classes of large decay chains into collections of simpler chains for easy handling

Analytical, Numerical, and Experimental Investigation on a Non-Contact Method for the Measurements of Creep Properties of Ultra-High-Temperature Materials

Science.gov (United States)

Lee, Jonghyun; Hyers, Robert W.; Rogers, Jan R.; Rathz, Thomas J.; Choo, Hahn; Liaw, Peter

2006-01-01

Responsive access to space requires re-use of components such as rocket nozzles that operate at extremely high temperatures. For such applications, new ultra-hightemperature materials that can operate over 2,000 C are required. At the temperatures higher than the fifty percent of the melting temperature, the characterization of creep properties is indispensable. Since conventional methods for the measurement of creep is limited below 1,700 C, a new technique that can be applied at higher temperatures is strongly demanded. This research develops a non-contact method for the measurement of creep at the temperatures over 2,300 C. Using the electrostatic levitator in NASA MSFC, a spherical sample was rotated to cause creep deformation by centrifugal acceleration. The deforming sample was captured with a digital camera and analyzed to measure creep deformation. Numerical and analytical analyses have also been conducted to compare the experimental results. Analytical, numerical, and experimental results showed a good agreement with one another.

Reflection on anthropogenic radionuclide concentrations in the French environment, corresponding doses and adaptation of analysing tools to monitoring needs; Reflexion sur l'evolution des concentrations en radionucleides artificiels dans l'environnement francais, les doses associees et l'adaptation des techniques d'analyse aux besoins de la surveillance

Energy Technology Data Exchange (ETDEWEB)

Renaud, Ph. [CEA Cadarache, Institut de Radioprotection et de Surete Nucleaire, Dir. de l' Environnement et de l' Intervention, Service d' Etude et de Surveillance de la Radioprotection dans l' Environnement, Lab. d' Etude et Recherches en Milieux Continental et Marin, 13 - Saint Paul lez-Durance (France); Gurriaran, R. [CEA Cadarache, Service de Traitement des Echantillons et de Metrologie pour l' Environnement, Lab. de Mesure de la Radioactivite dans l' Environnement, 13 - Saint Paul lez Durance (France)

2009-04-15

Anthropogenic radioactivity of the French environment and analytical tools, have both significantly evolved during the last 50 years. During the 60 s and the 70 s, the I.R.S.N. monitoring allowed knowing activity levels of the most plentiful radionuclides and which provided the main contribution to doses. Since the 80 s, the main radionuclides in term of activity and dose are {sup 3}H, {sup 14}C, {sup 85}Kr and {sup 133}Xe. However, these nuclides are poorly analysed. The relationship between radioactive backgrounds, potentially added activities linked to nuclear releases, corresponding doses, and detection limits using best analytical tools available, provides factors to the radiological monitoring stakes thought. Except for {sup 3}H and {sup 14}C, lowest activities of radionuclides in the environment are still at the level or below detection limits. {sup 3}H and {sup 14}C are the only ones that can be currently measured and which can label the various environmental compartments around nuclear facilities. (author)

Using meta-analytic path analysis to test theoretical predictions in health behavior: An illustration based on meta-analyses of the theory of planned behavior.

Science.gov (United States)

Hagger, Martin S; Chan, Derwin K C; Protogerou, Cleo; Chatzisarantis, Nikos L D

2016-08-01

Synthesizing research on social cognitive theories applied to health behavior is an important step in the development of an evidence base of psychological factors as targets for effective behavioral interventions. However, few meta-analyses of research on social cognitive theories in health contexts have conducted simultaneous tests of theoretically-stipulated pattern effects using path analysis. We argue that conducting path analyses of meta-analytic effects among constructs from social cognitive theories is important to test nomological validity, account for mediation effects, and evaluate unique effects of theory constructs independent of past behavior. We illustrate our points by conducting new analyses of two meta-analyses of a popular theory applied to health behaviors, the theory of planned behavior. We conducted meta-analytic path analyses of the theory in two behavioral contexts (alcohol and dietary behaviors) using data from the primary studies included in the original meta-analyses augmented to include intercorrelations among constructs and relations with past behavior missing from the original analysis. Findings supported the nomological validity of the theory and its hypotheses for both behaviors, confirmed important model processes through mediation analysis, demonstrated the attenuating effect of past behavior on theory relations, and provided estimates of the unique effects of theory constructs independent of past behavior. Our analysis illustrates the importance of conducting a simultaneous test of theory-stipulated effects in meta-analyses of social cognitive theories applied to health behavior. We recommend researchers adopt this analytic procedure when synthesizing evidence across primary tests of social cognitive theories in health. Copyright © 2016 Elsevier Inc. All rights reserved.

Analytic description of Raman-induced frequency shift in the case of non-soliton ultrashort pulses

Energy Technology Data Exchange (ETDEWEB)

Bugay, Aleksandr N., E-mail: bugay_aleksandr@mail.ru [Joint Institute for Nuclear Research, Joliot-Curie 6, 141980, Dubna, Moscow Region (Russian Federation); Khalyapin, Vyacheslav A., E-mail: slavasxi@gmail.com [Immanuel Kant Baltic Federal University, Kaliningrad, 236041 (Russian Federation); Kaliningrad State Technical University, Kaliningrad, 236000 (Russian Federation)

2017-01-30

Raman-induced frequency shift of ultrashort pulses have been studied extensively for the soliton propagation regime. Here we derive explicit analytic expressions for the evolution of Raman-induced frequency shift in much less studied case of non-soliton ultrashort pulses. Pulse spectra may belong to any region of group velocity dispersion including zero group dispersion point. The analysis is based on the moment method. Obtained expressions fit well to the numerical solution of the nonlinear wave equation. - Highlights: • Explicit analytic formulas for the evolution of Raman-induced frequency shift are derived in the case of non-soliton pulses. • Dynamics of non-soliton ultrashort pulses in the cases of positive and zero group dispersion is considered. • The deceleration and the saturation of Raman-induced frequency shift are analyzed. • The calculation relies on the moment method and fit well to the numerical solution of the nonlinear wave equation.

Analytic description of Raman-induced frequency shift in the case of non-soliton ultrashort pulses

International Nuclear Information System (INIS)

Bugay, Aleksandr N.; Khalyapin, Vyacheslav A.

2017-01-01

Raman-induced frequency shift of ultrashort pulses have been studied extensively for the soliton propagation regime. Here we derive explicit analytic expressions for the evolution of Raman-induced frequency shift in much less studied case of non-soliton ultrashort pulses. Pulse spectra may belong to any region of group velocity dispersion including zero group dispersion point. The analysis is based on the moment method. Obtained expressions fit well to the numerical solution of the nonlinear wave equation. - Highlights: • Explicit analytic formulas for the evolution of Raman-induced frequency shift are derived in the case of non-soliton pulses. • Dynamics of non-soliton ultrashort pulses in the cases of positive and zero group dispersion is considered. • The deceleration and the saturation of Raman-induced frequency shift are analyzed. • The calculation relies on the moment method and fit well to the numerical solution of the nonlinear wave equation.

Analytic formulas for the topological degree of non-smooth mappings: The odd-dimensional case

OpenAIRE

Goffeng, Magnus

2012-01-01

The notion of topological degree is studied for mappings from the boundary of a relatively compact strictly pseudo-convex domain in a Stein manifold into a manifold in terms of index theory of Toeplitz operators on the Hardy space. The index formalism of non-commutative geometry is used to derive analytic integral formulas for the index of a Toeplitz operator with H\\"older continuous symbol. The index formula gives an analytic formula for the degree of a H\\"older continuous mapping from the b...

Simplified analytical solutions for free drops during NCT for radioactive material packagings

International Nuclear Information System (INIS)

Gupta, N.K.

1997-01-01

To ensure structural integrity during normal conditions of transport (NCT), Federal regulations in 10CFR71.71 require that the nuclear material package designs be evaluated for the effects of free drops. The vessel stress acceptance criteria for these drops are given in Regulatory Guide 7.6 and ASME Section III Code. During initial phases of the package design, the effects of the NCT free drops can be evaluated by simplified analytical solutions which will ensure that the safety margins specified in R. G. 7.6 are met. These safety margins can be verified during the final stages of the package design with dynamic analyses using finite element methods. This paper calculates the maximum impact open-quotes gclose quotes loading on the vessels using single degree of freedom models for different drop orientations. Only end, bottom, and corner drops are analyzed for cylindrical packages or packages with cylindrical ends

Letter report: Pre-conceptual design study for a pilot-scale Non-Radioactive Low-Level Waste Vitrification Facility

International Nuclear Information System (INIS)

Thompson, R.A.; Morrissey, M.F.

1996-03-01

This report presents a pre-conceptual design study for a Non-Radioactive Low-Level Waste, Pilot-Scale Vitrification System. This pilot plant would support the development of a full-scale LLW Vitrification Facility and would ensure that the full-scale facility can meet its programmatic objectives. Use of the pilot facility will allow verification of process flowsheets, provide data for ensuring product quality, assist in scaling to full scale, and support full-scale start-up. The facility will vitrify simulated non-radioactive LLW in a manner functionally prototypic to the full-scale facility. This pre-conceptual design study does not fully define the LLW Pilot-Scale Vitrification System; rather, it estimates the funding required to build such a facility. This study includes identifying all equipment necessary. to prepare feed, deliver it into the melter, convert the feed to glass, prepare emissions for atmospheric release, and discharge and handle the glass. The conceived pilot facility includes support services and a structure to contain process equipment

Role of the unsaturated zone in radioactive and hazardous waste disposal

International Nuclear Information System (INIS)

Mercer, J.W.; Marine, I.W.; Rao, P.S.C.

1983-01-01

The problems of hazardous and low-level radioactive waste disposal caused by the physical and chemical processes active in the unsaturated zone are explored in this book. The focus is on the use of laboratory analyses, field observations, and numerical and analytical calculations to create a clear picture of both problems and potential solutions. Topics include policy modeling, statistical techniques, liners, and field applications. Contents include: Modeling of Moisture Movement through Layered Trench Covers; Role of Partially Saturated Soil in Liner Design for Hazardous Waste Disposal Sites; Field Experiments to Determine Saturated Hydraulic Conductivity in the Vadose Zone; Role of Desaturation on Transport through Fractured Rock; Nuclear Waste Isolation in the Unsaturated Zone of Arid Regions

Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the NTS

Energy Technology Data Exchange (ETDEWEB)

Vefa Yucel

2007-01-03

U.S. Department of Energy (DOE) Manual M 435.1-1 requires that performance assessments (PAs) and composite analyses (CAs) for low-level waste (LLW) disposal facilities be maintained by the field offices. This plan describes the activities performed to maintain the PA and the CA for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS). This plan supersedes the Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (DOE/NV/11718--491-REV 1, dated September 2002). The plan is based on U.S. Department of Energy (DOE) Order 435.1 (DOE, 1999a), DOE Manual M 435.1-1 (DOE, 1999b), the DOE M 435.1-1 Implementation Guide DOE G 435.1-1 (DOE, 1999c), and the Maintenance Guide for PAs and CAs (DOE, 1999d). The plan includes a current update on PA/CA documentation, a revised schedule, and a section on Quality Assurance.

7 CFR 94.103 - Analytical methods.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Analytical methods. 94.103 Section 94.103 Agriculture... POULTRY AND EGG PRODUCTS Voluntary Analyses of Egg Products § 94.103 Analytical methods. The analytical methods used by the Science and Technology Division laboratories to perform voluntary analyses for egg...

Radioactive wastes. Management

International Nuclear Information System (INIS)

Guillaumont, R.

2001-01-01

Many documents (journal articles, book chapters, non-conventional documents..) deal with radioactive wastes but very often this topic is covered in a partial way and sometimes the data presented are contradictory. The aim of this article is to precise the definition of radioactive wastes and the proper terms to describe this topic. It describes the main guidelines of the management of radioactive wastes, in particular in France, and presents the problems raised by this activity: 1 - goal and stakes of the management; 2 - definition of a radioactive waste; 3 - radionuclides encountered; 4 - radio-toxicity and radiation risks; 5 - French actors of waste production and management; 6 - French classification and management principles; 7 - wastes origin and characteristics; 8 - status of radioactive wastes in France per categories; 9 - management practices; 10 - packages conditioning and fabrication; 11 - storage of wastes; 12 - the French law from December 30, 1991 and the opportunities of new ways of management; 13 - international situation. (J.S.)

Low-level Radioactivity Measurements

International Nuclear Information System (INIS)

Churtgen, C.

2007-01-01

The low-level radioactivity measurements service performs measurements of alpha or beta emitters on various types of low-radioactivity samples (biological and environmental) from internal and external clients. to maintain and develop techniques concerning the measurement of low-level radioactivity of alpha and beta emitting radionuclides in environmental or biological samples; to measure these samples by means of low-background counters (liquid scintillators, proportional counters, ZnS counters and alpha-spectrometers); to support and advise the nuclear and non-nuclear industry on problems of radioactive contamination or low level radioactivity measurements; to maintain the quality assurance system according to the ISO17025 standard for which we obtained the Beltest accreditation in 1998; to assess the internal dose from occupational intakes of radionuclides for workers of the nuclear industry;

Role of the IAEA's ALMERA network in harmonization of analytical procedures applicable worldwide for radiological emergencies

International Nuclear Information System (INIS)

Pitois, A.; Osvath, I.; Tarjan, S.; Groening, M.; Osborn, D.; )

2016-01-01

The International Atomic Energy Agency (IAEA) coordinates and provides analytical support to the worldwide network of Analytical Laboratories for the Measurement of Environmental Radioactivity (ALMERA), consisting at the end of 2015 of 154 laboratories in 85 countries. This network, established by the IAEA in 1995, has for aim to provide timely and reliable measurement results of environmental radioactivity in routine monitoring and emergency situations. The IAEA supports the ALMERA laboratories in their routine and emergency response environmental monitoring activities by organizing proficiency tests and inter-laboratory comparison exercises, developing validated analytical procedures for environmental radioactivity measurement, and organizing training courses and workshops. The network also acts as a forum for sharing knowledge and expertise. The aim of this paper is to describe the current status of ALMERA analytical method development activities for radiological emergencies and the plans for further development in the field

7 CFR 94.4 - Analytical methods.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Analytical methods. 94.4 Section 94.4 Agriculture... POULTRY AND EGG PRODUCTS Mandatory Analyses of Egg Products § 94.4 Analytical methods. The majority of analytical methods used by the USDA laboratories to perform mandatory analyses for egg products are listed as...

IAEA coordinated research project on 'analytical and experimental benchmark analyses of accelerator driven systems'

International Nuclear Information System (INIS)

Ait-Abderrahim, H.; Stanculescu, A.

2006-01-01

This paper provides the general background and the main specifications of the benchmark exercises performed within the framework of the IAEA Coordinated Research Project (CRP) on Analytical and Experimental Benchmark Analyses of Accelerator Driven Systems. The overall objective of the CRP, performed within the framework of the Technical Working Group on Fast Reactors (TWG-FR) of IAEA's Nuclear Energy Dept., is to contribute to the generic R and D efforts in various fields common to innovative fast neutron system development, i.e. heavy liquid metal thermal hydraulics, dedicated transmutation fuels and associated core designs, theoretical nuclear reaction models, measurement and evaluation of nuclear data for transmutation, and development and validation of calculational methods and codes. (authors)

Scanning electron microscopic analyses of Ferrocyanide tank wastes for the Ferrocyanide safety program

International Nuclear Information System (INIS)

Callaway, W.S.

1995-09-01

This is Fiscal Year 1995 Annual Report on the progress of activities relating to the application of scanning electron microscopy in addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. The status of the FY 1995 activities directed towards establishing facilities capable of providing SEM based micro-characterization of ferrocyanide tank wastes is described. A summary of key events in the SEM task over FY 1995 and target activities in FY 1996 are presented. A brief overview of the potential applications of computer controlled SEM analytical data in light of analyses of ferrocyanide simulants performed by an independent contractor is also presented

National inventory of radioactive wastes

International Nuclear Information System (INIS)

1997-01-01

There are in France 1064 sites corresponding to radioactive waste holders that appear in this radioactive waste inventory. We find the eighteen sites of E.D.F. nuclear power plants, The Cogema mine sites, the Cogema reprocessing plants, The Cea storages, the different factories and enterprises of nuclear industry, the sites of non nuclear industry, the Andra centers, decommissioned installations, disposals with low level radioactive wastes, sealed sources distributors, national defence. (N.C.)

Protection of environmental contamination by radioactive materials and remediation of environment

International Nuclear Information System (INIS)

2003-05-01

This report consisted of the environmental contamination of radioactive and non-radioactive materials. 38 important accident examples of environmental contamination of radioactive materials in the world from 1944 to 2001 are stated. Heavily polluted areas by accidents are explained, for example, Chernobyl, atomic reactor accidents, development of nuclear weapon in USA and USSR, radioactive waste in the sea. The environmental contamination ability caused by using radioactive materials, medical use, operating reactor, disposal, transferring, crashing of airplane and artificial satellite, release are reported. It contains measurements and monitor technologies, remediation technologies of environmental contamination and separation and transmutation of radioactive materials. On the environmental contamination by non-radioactive materials, transformation of the soil contamination in Japan and its control technologies are explained. Protection and countermeasure of environmental contamination of radioactive and non-radioactive materials in Japan and the international organs are presented. There are summary and proposal in the seventh chapter. (S.Y.)

A simple and feasible method of effectiveness evaluation on radioactive decontamination action

International Nuclear Information System (INIS)

Chen Lin; Geng Xiaobing; Sun Jian; Wang Jihong; Guo Lijun

2012-01-01

Radioactive decontamination is a vital task in nuclear emergency response. The assessment of decontamination effectiveness is of great importance to decision-making. An index system for effectiveness evaluation of radioactive decontamination action in nuclear emergency response is produced. A method of decontamination effectiveness evaluation based on analytic hierarchy process and fuzzy comprehensive evaluation is presented. Index weights are determined through analytic hierarchy process. And scores of objects in each hierarchy are judged by fuzzy comprehensive evaluation. Then comprehensive effectiveness of the top object can be obtained, which can offer a basis for decision-making of decontamination action. (authors)

Pre-waste-emplacement ground-water travel time sensitivity and uncertainty analyses for Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Kaplan, P.G.

1993-01-01

Yucca Mountain, Nevada is a potential site for a high-level radioactive-waste repository. Uncertainty and sensitivity analyses were performed to estimate critical factors in the performance of the site with respect to a criterion in terms of pre-waste-emplacement ground-water travel time. The degree of failure in the analytical model to meet the criterion is sensitive to the estimate of fracture porosity in the upper welded unit of the problem domain. Fracture porosity is derived from a number of more fundamental measurements including fracture frequency, fracture orientation, and the moisture-retention characteristic inferred for the fracture domain

Analytical solutions for evaluating the thermal performances of wet air cooling coils under both unit and non-unit Lewis Factors

International Nuclear Information System (INIS)

Xia Liang; Chan, M.Y.; Deng, S.M.; Xu, X.G.

2010-01-01

Analytical solutions for evaluating the thermal performances of both chilled water wet cooling coils and direct expansion (DX) wet cooling coils, respectively, under both unit and non-unit Lewis Factors are developed and reported in this paper. The analytical solution was validated by comparing its predictions with those from numerically solving the fundamental governing equations of heat and mass transfer taking place in a wet cooling coil. With the analytical solutions, the distributions of air temperature and humidity ratio along air flow direction in a wet cooling coil can be predicted, and the differences in the thermal performances of the cooling coils under both unit and non-unit Lewis Factors can be identified. The analytical solutions, on one hand, can be a low-cost replacement to numerically solving the fundamental heat and mass transfer governing equations, and on the other hand, is able to deal with evaluating thermal performance for wet air cooling coils operated under both unit and non-unit Lewis Factors.

Ambient radioactivity levels and radiation doses. Annual report 2011

International Nuclear Information System (INIS)

Bernhard-Stroel, Claudia; Hachenburger, Claudia; Trugenberger-Schnabel, Angela; Peter, Josef

2013-07-01

The annual report 2011 on ambient radioactivity levels and radiation doses covers the following issues: Part A: Natural environmental radioactivity, artificial radioactivity in the environment, occupational radiation exposure, radiation exposure from medical applications, the handling of radioactive materials and sources of ionizing radiation, non-ionizing radiation. Part B; Current data and their evaluation: Natural environmental radioactivity, artificial radioactivity in the environment, occupational radiation exposure, radiation exposure from medical applications, the handling of radioactive materials and sources of ionizing radiation, non-ionizing radiation. The Appendix includes Explanations of terms, radiation doses and related units, external and internal radiation exposure, stochastic and deterministic radiation effects, genetic radiation effects, induction of malignant neoplasm, risk assessment, physical units and glossary, laws, ordinances, guidelines, recommendations and other regulations concerning radiation protection, list of selected radionuclides.

Ultrastructural localisation of intramuscular expression of BDNF mRNA by silver-gold intensified non-radioactive in situ hybridisation

NARCIS (Netherlands)

Liem, RSB; Brouwer, N; Copray, JCVM

2001-01-01

A non-radioactive in situ hybridisation method is described for the detection of low intramuscular levels of brain-derived neurotrophic factor (BDNF) mRNA at the electron microscope level. Application of high-grade silver-gold intensification of the diaminobenzidine end product of in situ

Design criteria burial containers for non-transuranic solid radioactive waste

International Nuclear Information System (INIS)

Hammond, J.E.

1976-01-01

The criteria, replace HW-83959 and apply to containers constructed specifically for the containment of beta-gamma radioactively contaminated waste removed from an area controlled by radiation work procedures, transported across an uncontrolled area where there is risk of a radiation release to the environs, and buried in an approved radioactive waste burial ground

Coal combustion ashes: A radioactive Waste?

International Nuclear Information System (INIS)

Michetti, F.P.; Tocci, M.

1992-01-01

The radioactive substances naturally hold in fossil fuels, such as Uranium and Thorium, after the combustion, are subjected to an increase of concentration in the residual combustion products as flying ashes or as firebox ashes. A significant percentage of the waste should be classified as radioactive waste, while the political strategies seems to be setted to declassify it as non-radioactive waste. (Author)

Sampling methods and non-destructive examination techniques for large radioactive waste packages

International Nuclear Information System (INIS)

Green, T.H.; Smith, D.L.; Burgoyne, K.E.; Maxwell, D.J.; Norris, G.H.; Billington, D.M.; Pipe, R.G.; Smith, J.E.; Inman, C.M.

1992-01-01

Progress is reported on work undertaken to evaluate quality checking methods for radioactive wastes. A sampling rig was designed, fabricated and used to develop techniques for the destructive sampling of cemented simulant waste using remotely operated equipment. An engineered system for the containment of cooling water was designed and manufactured and successfully demonstrated with the drum and coring equipment mounted in both vertical and horizontal orientations. The preferred in-cell orientation was found to be with the drum and coring machinery mounted in a horizontal position. Small powdered samples can be taken from cemented homogeneous waste cores using a hollow drill/vacuum section technique with the preferred subsampling technique being to discard the outer 10 mm layer to obtain a representative sample of the cement core. Cement blends can be dissolved using fusion techniques and the resulting solutions are stable to gelling for periods in excess of one year. Although hydrochloric acid and nitric acid are promising solvents for dissolution of cement blends, the resultant solutions tend to form silicic acid gels. An estimate of the beta-emitter content of cemented waste packages can be obtained by a combination of non-destructive and destructive techniques. The errors will probably be in excess of +/-60 % at the 95 % confidence level. Real-time X-ray video-imaging techniques have been used to analyse drums of uncompressed, hand-compressed, in-drum compacted and high-force compacted (i.e. supercompacted) simulant waste. The results have confirmed the applicability of this technique for NDT of low-level waste. 8 refs., 12 figs., 3 tabs

Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

International Nuclear Information System (INIS)

Bierschbach, M.C.; Haffner, D.R.; Schneider, K.J.; Short, S.M.

2002-01-01

that contaminated components either be: (1) decontaminated to restricted or unrestricted release levels or (2) packaged and shipped to an authorized disposal site. This study considers unrestricted release only. The new decommissioning criteria of July 1997 are too recent for this study to include a cost analysis of the restricted release option, which is now allowed under these new criteria. The costs of decommissioning facility components are generally estimated to be in the range of $140 to $27,000, depending on the type of component, the type and amount of radioactive contamination, the remediation options chosen, and the quantity of radioactive waste generated from decommissioning operations. Estimated costs for decommissioning the example laboratories range from $130,000 to $205,000, assuming aggressive low-level waste (LLW) volume reduction. If only minimal LLW volume reduction is employed, decommissioning costs range from $150,000 to $270,000 for these laboratories. On the basis of estimated decommissioning costs for facility components, the costs of decommissioning typical non-fuel-cycle laboratory facilities are estimated to range from about $25,000 for the decommissioning of a small room containing one or two fume hoods to more than $1 million for the decommissioning of an industrial plant containing several laboratories in which radiochemicals and sealed radioactive sources are prepared. For the reference sites of this study, the basic decommissioning alternatives are: (1) site stabilization followed by long-term care and (2) removal of the waste or contaminated soil to an authorized disposal site. Cost estimates made for decommissioning three reference sites range from about $130,000 for the removal of a contaminated drain line and hold-up tank to more than $23 million for the removal of a tailings pile that contains radioactive residue from ore-processing operations in which tin slag is processed for the recovery of rare metals. Total occupational

Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

Energy Technology Data Exchange (ETDEWEB)

MC Bierschbach; DR Haffner; KJ Schneider; SM Short

2002-12-01

facility, DECON requires that contaminated components either be: (1) decontaminated to restricted or unrestricted release levels or (2) packaged and shipped to an authorized disposal site. This study considers unrestricted release only. The new decommissioning criteria of July 1997 are too recent for this study to include a cost analysis of the restricted release option, which is now allowed under these new criteria. The costs of decommissioning facility components are generally estimated to be in the range of $140 to $27,000, depending on the type of component, the type and amount of radioactive contamination, the remediation options chosen, and the quantity of radioactive waste generated from decommissioning operations. Estimated costs for decommissioning the example laboratories range from $130,000 to $205,000, assuming aggressive low-level waste (LLW) volume reduction. If only minimal LLW volume reduction is employed, decommissioning costs range from $150,000 to $270,000 for these laboratories. On the basis of estimated decommissioning costs for facility components, the costs of decommissioning typical non-fuel-cycle laboratory facilities are estimated to range from about $25,000 for the decommissioning of a small room containing one or two fume hoods to more than $1 million for the decommissioning of an industrial plant containing several laboratories in which radiochemicals and sealed radioactive sources are prepared. For the reference sites of this study, the basic decommissioning alternatives are: (1) site stabilization followed by long-term care and (2) removal of the waste or contaminated soil to an authorized disposal site. Cost estimates made for decommissioning three reference sites range from about $130,000 for the removal of a contaminated drain line and hold-up tank to more than $23 million for the removal of a tailings pile that contains radioactive residue from ore-processing operations in which tin slag is processed for the recovery of rare metals. Total

Handbook of radioactivity analysis. Second edition

International Nuclear Information System (INIS)

L'Annunziata, M.

2003-07-01

This updated and much expanded Second Edition is an authoritative handbook providing the principles, practical techniques, and procedures for the accurate measurement of radioactivity from the very low levels encountered in the environment to higher levels measured in radioisotope research, clinical laboratories, biological sciences, radionuclide standardization, nuclear medicine, nuclear power, fuel cycle facilities, and in the implementation of nuclear safeguards. The book describes the preparation of samples from a wide variety of matrices, assists the investigator or technician in the selection and use of appropriate radiation detectors, and presents state-of-the-art methods of analysis. Fundamentals of radioactivity properties, radionuclide decay, the calculations involved, and methods of detection provide the basis for a thorough understanding of the analytical procedures. The Handbook of Radioactivity Analysis, Second Edition is suitable as a teaching text for university and professional training courses

Process for recovering xenon from radioactive gaseous wastes

International Nuclear Information System (INIS)

Kishimoto, Tsuneo.

1980-01-01

Purpose: To recover pure xenon economically and efficiently by amply removing radioactive krypton mixed in xenon without changing the rectifying capacity of an xenon rectifying system itself. Method: Xe containing radioactive Kr(Kr-85) is rectified to reduce the concentration of radioactive Kr. Thereafter, non-radioactive Kr or Ar is added to Xe and further the rectification is carried out. The raw material Xe from the Xe adsorption system of, for example, a radioactive gaseous waste disposal system is cooled to about 100 0 C by a heat-exchanger and thereafter supplied to a rectifying tower to carry out normal rectification of Xe thereby to reduce the concentration of Kr contained in Xe at the tower bottom to the rectification limit concentration. Then, non-radioactive Kr is supplied via a precooler to the tower bottom to continue the rectification, thus the Xe fractions at the tower bottom, in which the concentration of radioactive Kr is reduced, being compressed and recovered. (Kamimura, M.)

Nuclear techniques and the disposal of non-radioactive solid wastes

International Nuclear Information System (INIS)

Landsberger, S.; Buchholz, B.

1993-01-01

One of the most vital and persistent public health challenges facing local, state, and national governments is the disposal of solid waste produced from industrial, utility, and municipal sources. There is a growing interest in the monitoring, control, and safe disposal of the chemical constituents arising from these sources. For instance, it is now well known that the release of by products from coal-fired power plants - namely airborne particulates, bottom ash, and fly ash - can have adverse effects on air and water quality. It is therefore important that reliable chemical analytical techniques are readily available to assess the impact of widespread disposal practices of organic and inorganic chemicals. The use of nuclear and nuclear-related analytical techniques - such as neutron activation analysis, energy dispersive x-ray fluorescence and particle induced X-ray emission - have become widespread in major areas of science and technology. These methods and techniques have important applications in such work since they can be used for both the determination of specific individual pollutants (e.g. toxic heavy metals) and multi-elemental analyses for source identification and apportionment purposes. Other nuclear techniques, such as isotope tracers, have also had wide acceptance in characterizing diffusion patterns for metals in soil and aqueous environments and water pollution flows. 1 graph., 1 tab

Development of an immobilisation technique by cementation for non-radioactive simulated liquid waste, from Mo-99 production process

International Nuclear Information System (INIS)

Arva, E A; Marabini, S G; Varani, J L

2012-01-01

The Argentine Atomic Energy Commission (CNEA) is the responsible for developing a management nuclear waste disposal programme. This programme contemplates the strictly environmental safe and efficient management of the radioactive waste from different sources. Since 1985, CNEA has been producing commercially Mo-99 for medical use. In this process two types of liquid waste are produced. One of them has high alkaline (NaOH 3,5M) and aluminate contents. Since Mo-99 production started, such liquid waste was stored in specially designed containers during production, and after a decay period in smaller containers in interim storage conditions. As this waste is still a liquid, development of an immobilisation technique is required. Immobilisation of radioactive liquid waste by cementation is a frequently used technique, and will be studied in the present work using Mo-99 non-radioactive simulated liquid waste. In this second stage, a full scale (200 liters drum) cementation test using simulated non radioactive waste was carried out. Such test included: using the BEBA 201 mixing machine - the same that will be used with real waste in the future for 'tuning up' the process, construction of a specially designed temperature sensor for measuring the maximum temperature value (five different positions, four inside the drum and one outside) and the time elapsed after all components mixing. Finally, standard specimens (IRAM 1622) were made for mechanical resistance tests after cement setting at 28 days. The results show values of temperature not above 40 o C with the maximum at 12 hours before component mixing and compression strength of 14 MPa. Such values are compatible for a waste immobilisation process by cementation (author)

RADTRAN3, Risk of Radioactive Material Transport

International Nuclear Information System (INIS)

Madsen, M.M.; Taylor, J.M.; Ostmeyer, R.M.; Reardon, P.C.

2001-01-01

1 - Description of program or function: RADTRAN3 is a flexible analytical tool for calculating both the incident-free and accident impacts of transporting radioactive materials. The consequences from incident-free shipments are apportioned among eight population sub- groups and can be calculated for several transport modes. The radiological accident risk (probability times consequence summed over all postulated accidents) is calculated in terms of early fatalities, early morbidities, latent cancer fatalities, genetic effects, and economic impacts. Ground-shine, ingestion, inhalation, direct exposure, resuspension, and cloud-shine dose pathways are modeled to calculate the radiological health risks from accidents. Economic impacts are evaluated based on costs for emergency response, cleanup, evacuation, income loss, and land use. RADTRAN3 can be applied to specific scenario evaluations (individual transport modes or specified combinations), to compare alternative modes or to evaluate generic radioactive material shipments. Unit-risk factors can easily be evaluated to aid in performing generic analyses when several options must be compared with the amount of travel as the only variable. RADTRAN4 offers advances in the handling of route-related data and in the treatment of multiple-isotope materials. 2 - Method of solution: There are several modes used in the transporting of radioactive material such as trucks, passenger vans, passenger airplanes, rail and others. With these modes of transport come several shipment scenarios. The RADTRAN4 methodology uses material, transportation, population distribution, and health effects models to treat the incident-free case. To handle the vehicle accident impacts, accident severity and package release, meteorological dispersion, and economic models are also employed. 3 - Restrictions on the complexity of the problem: There are no apparent limitations due to programming dimensions

Risk methodology for geologic disposal of radioactive waste: interim report

International Nuclear Information System (INIS)

Campbell, J.E.; Dillon, R.T.; Tierney, M.S.; Davis, H.T.; McGrath, P.E.; Pearson, F.J. Jr.; Shaw, H.R.; Helton, J.C.; Donath, F.A.

1978-10-01

The Fuel Cycle Risk Analysis Division of Sandia Laboratories is funded by the Nuclear Regulatory Commission (NRC) to develop a methodology for assessment of the long-term risks from radioactive waste disposal in deep, geologic media. The first phase of this work, which is documented in this report, involves the following: (1) development of analytical models to represent the processes by which radioactive waste might leave the waste repository, enter the surface environment and eventually reach humans and (2) definition of a hypothetical ''reference system'' to provide a realistic setting for exercise of the models in a risk or safety assessment. The second phase of this work, which will be documented in a later report, will involve use of the analytical models in a demonstration risk or safety assessment of the reference system. The analytical methods and data developed in this study are expected to form the basis for a portion of the NRC repository licensing methodology

Developing semi-analytical solution for multiple-zone transient storage model with spatially non-uniform storage

Science.gov (United States)

Deng, Baoqing; Si, Yinbing; Wang, Jia

2017-12-01

Transient storages may vary along the stream due to stream hydraulic conditions and the characteristics of storage. Analytical solutions of transient storage models in literature didn't cover the spatially non-uniform storage. A novel integral transform strategy is presented that simultaneously performs integral transforms to the concentrations in the stream and in storage zones by using the single set of eigenfunctions derived from the advection-diffusion equation of the stream. The semi-analytical solution of the multiple-zone transient storage model with the spatially non-uniform storage is obtained by applying the generalized integral transform technique to all partial differential equations in the multiple-zone transient storage model. The derived semi-analytical solution is validated against the field data in literature. Good agreement between the computed data and the field data is obtained. Some illustrative examples are formulated to demonstrate the applications of the present solution. It is shown that solute transport can be greatly affected by the variation of mass exchange coefficient and the ratio of cross-sectional areas. When the ratio of cross-sectional areas is big or the mass exchange coefficient is small, more reaches are recommended to calibrate the parameter.

Method of solidifying radioactive waste by plastics

International Nuclear Information System (INIS)

Yasumura, Keijiro; Tomita, Toshihide.

1976-01-01

Purpose: To prevent leakage of radioactivity by providing corrosion-resistant layer on the inner surface of a waste container for radioactive waste. Constitution: The inner periphery and bottom of a drum can is lined with an non-flammable cloth of such material as asbestos. This drum is filled with a radioactive waste in the form of powder or pellets. Then, a mixture of a liquid plastic monomer and a polymerization starting agent is poured at a normal temperature, and the surface is covered with a non-flammable cloth. The plastic monomer and radioactive waste are permitted to impregnate the non-flammable cloth and are solidified there. Thus, even if the drum can is corroded at the sea bottom after disposal it in the ocean, it is possible to prevent the waste from permeating into the outer sea water because of the presence of the plastic layer on the inside. Styrene is used as the monomer. (Aizawa, K.)

Gross alpha/beta analyses in water by liquid scintillation counting

International Nuclear Information System (INIS)

Wong, C.T.; Lawrence Livermore National Laboratory, CA; Soliman, V.M.; Perera, S.K.

2005-01-01

The standard procedure for analyzing gross alpha and gross beta in water is evaporation of the sample and radioactivity determination of the resultant solids by proportional counting. This technique lacks precision, and lacks sensitivity for samples with high total dissolved solids. Additionally, the analytical results are dependent on the choice of radionuclide calibration standard and the sample matrix. Direct analysis by liquid scintillation counting has the advantages of high counting efficiencies and minimal sample preparation time. However, due to the small sample aliquants used for analysis, long count times are necessary to reach required detection limits. The procedure proposed consists of evaporating a sample aliquant to dryness, dissolving the resultant solids in a small volume of dilute acid, followed by liquid scintillation counting to determine radioactivity. This procedure can handle sample aliquants containing up to 500 mg of dissolved solids. Various acids, scintillation cocktail mixtures, instrument discriminator settings, and regions of interest (ROI) were evaluated to determine optimum counting conditions. Precision is improved and matrix effects are reduced as compared to proportional counting. Tests indicate that this is a viable alternative to proportional counting for gross alpha and gross beta analyses of water samples. (author)

Radioactive legacies from medicine and industry

International Nuclear Information System (INIS)

Linder, R.; Rodriguez, J.

2005-01-01

Due to the unintended disposal of radioactive legacies (waste from medicine, industry or private persons) radioactive material occasionally enters the disposal ways of conventional waste. The Swiss Federal Office of Public Health (SFOPH) and the Swiss accident Insurance Fund (Swiss) are the licensing authorities and regulatory agencies of the handling with radioactive materials for non-nuclear use. The aim is to avoid such incidents with concrete measures and so to preserve men and environment from the negative effect of not correctly disposed radioactive waste. (orig.)

Analyses of soils at commercial radioactive-waste-disposal sites

International Nuclear Information System (INIS)

Piciulo, P.L.; Shea, C.E.; Barletta, R.E.

1982-01-01

Brookhaven National Laboratory, in order to provide technical assistance to the NRC, has measured a number of physical and chemical characteristics of soils from two currently operating commercial radioactive waste disposal sites; one at Barnwell, SC, and the other near Richland, WA. Soil samples believed to be representative of the soil that will contact the buried waste were collected and analyzed. Earth resistivities (field measurements), from both sites, supply information to identify variations in subsurface material. Barnwell soil resistivities (laboratory measurements) range from 3.6 x 10 5 ohm-cm to 8.9 x 10 4 ohm-cm. Soil resistivities of the Hanford sample vary from 3.0 x 10 5 ohm-cm to 6.6 x 10 3 ohm-cm. The Barnwell and Hanford soil pH ranges from 4.8 to 5.4 and from 4.0 to 7.2 respectively. The pH of a 1:2 mixture of soil to 0.01 M CaCl 2 resulted in a pH for the Barnwell samples of 3.9 +- 0.1 and for the Hanford samples of 7.4 +- 0.2. These values are comparable to the pH measurements of the water extract of the soils used for the analyses of soluble ion content of the soils. The exchange acidity of the soils was found to be approximately 7 mg-eq per 100 g of dry soil for clay material from Barnwell, whereas the Hanford soils showed an alkaline reaction. Aqueous extracts of saturated pastes were used to determine the concentrations of the following ions: Ca 2+ , Mg 2+ , K + , Na + , HCO 3 - , SO 4 /sup =/, and Cl - . The sulfide content of each of the soils was measured in a 1:2.5 mixture of soil to an antioxidant buffer solution. The concentrations of soluble ions found in the soils from both sites are consistent with the high resistivities

Radioactive wastes management in a radiochemistry laboratory

International Nuclear Information System (INIS)

Silva, Ana C.A.; Pereira, Wagner de S; Py Junior, Delcy de A.; Antunes, Ivan M.; Kelecom, Alphonse

2009-01-01

The Laboratorio de Monitoracao Ambiental (AMB) of the Unidade de Tratamento de Minerio (UTM) belonging to the Industrias Nucleares do Brasil is a chemical, radiochemical and radiometric laboratory, that analyses the natural radionuclides present in samples coming from the various installation of Industrias Nucleares do Brasil (INB). To minimize the radiological environmental impact, that laboratory has adopted a washing system of the chapel exhausting, that recirculate the washing water. These water can accumulate the radionuclides coming from the samples, that are liberated together the exhaustion gases from the chapels. Also, the water coming from the analyses and the sample releases (environmental and of the process) represent the liquid effluents of the AMB. The release of this effluent must pass by chemical and radiological criteria. From the radiological viewpoint, that release must be based on the Brazilian Nuclear Energy Commission (CNEN) regulations. This work try to establish the monitoring frequency, the radionuclides to be analysed, the form of liberation of those effluents, and the analytical techniques to be used. The radionuclides to be analysed will be U-nat, Ra-226 and Pb-210, of the uranium series, and the Th-232 and Ra-228, of the thorium series. The effluents must be monitored either before the release or, at least, twice a year. The effluents considered radioactive wastes, will be send to waste dam by the radioprotection service, or to the effluent treatment for controlled liberation for the environment

Radioactive aerosols. [In Russian

Energy Technology Data Exchange (ETDEWEB)

Natanson, G L

1956-01-01

Tabulations are given presenting various published data on safe atmospheric concentrations of various radioactive and non-radioactive aerosols. Methods of determination of active aerosol concentrations and dispersion as well as the technical applications of labeled aerosols are discussed. The effect of atomic explosions are analyzed considering the nominal atomic bomb based on /sup 235/U and /sup 232/Pu equivalent to 20,000 tons of TNT.

Proceedings of the 8. Brazilian meeting on analytical chemistry. Abstracts

International Nuclear Information System (INIS)

1995-01-01

Abstracts from theoretical and experimental works on qualitative and quantitative analytical chemistry are presented. Several nuclear and non nuclear techniques have been used, such as neutron activation analysis, absorption spectroscopy, x-ray fluorescence analysis and others. The materials analysed were rocks, rare earths, environmental materials (soil, water, air), complexes and so on. Synthesis, kinetics and radiochemistry were also discussed

Development of a micro total analytic system based on isotachophoresis for the separation and characterization of lanthanides

International Nuclear Information System (INIS)

Vio, L.

2010-01-01

The accurate and reproducible characterization of radioactive solutions in isotope composition and concentration is an essential topic for analytical laboratories in the nuclear field. In order to reduce manipulation time in glove box and production of contaminated wastes, it is necessary to propose innovative and efficient solutions for these analyses. Since few years, microchips are a major field of development in analytical chemistry and those devices could provide a solution which fits the needs of nuclear industry. The aim of this work is to design a disposable analytical micro-device devoted to lanthanide separation from spent nuclear fuel before their analysis in mass spectrometry. Designed to be used in place of a separation process by liquid chromatography which is involved in a three step protocol, the new protocol based on isotachophoresis (ITP) keeps compatible with the other two steps. The complete separation of lanthanides by ITP was obtained by the use of only one chelating compound rigorously selected: the 2-hydroxy 2-methyl butyric acid (HMBA). The main parameters involved in solute resolution were defined from the theoretical models of ITP and experimental studies of the influence of these parameters allowed to optimize the geometry of the system and to improve its performances. To suppress cleaning of the system and, consequently, to strongly reduce both liquid waste volume and handling radioactive material, the ITP protocol was transferred in a polymeric (COC) disposable microchip especially developed for this purpose. (author) [fr

Analytical solutions for non-linear conversion of a porous solid particle in a gas–II. Non-isothermal conversion and numerical verification

NARCIS (Netherlands)

Brem, Gerrit; Brouwers, J.J.H.

1990-01-01

In Part I, analytical solutions were given for the non-linear isothermal heterogeneous conversion of a porous solid particle. Account was taken of a reaction rate of general order with respect to the gas reactant, intrinsic reaction surface area and effective pore diffusion, which change with solid

Analytical solutions for non-linear conversion of a porous solid particle in a gas : II. non-isothermal conversion and numerical verification

NARCIS (Netherlands)

Brem, G.; Brouwers, J.J.H.

1990-01-01

In Part I, analytical solutions were given for the non-linear isothermal heterogeneous conversion of a porous solid particle. Account was taken of a reaction rate of general order with respect to the gas reactant, intrinsic reaction surface area and effective pore diffusion, which change with solid

Non-perturbative analytical solutions of the space- and time-fractional Burgers equations

International Nuclear Information System (INIS)

Momani, Shaher

2006-01-01

Non-perturbative analytical solutions for the generalized Burgers equation with time- and space-fractional derivatives of order α and β, 0 < α, β ≤ 1, are derived using Adomian decomposition method. The fractional derivatives are considered in the Caputo sense. The solutions are given in the form of series with easily computable terms. Numerical solutions are calculated for the fractional Burgers equation to show the nature of solution as the fractional derivative parameter is changed

Radioactive waste disposal on a non-industrial scale

International Nuclear Information System (INIS)

1990-01-01

A 13 minute videotape deals with the following points: 1) Exposure pathways for solid, liquid and gaseous effleunt; 2) Critical pathways; 3) Critical groups; 4) Controlling authorities; 5) Principles of disposal, including a) concentrate and contain or b) delay and decay or c) dilute and disperse and 6) record keeping. The possible effects on Man and the Environment, of the release of radioactive wastes are discussed, and the principles underlying safe disposal of such wastes are explained. There are illustrations of procedures used in Imperial College for dealing with both high and low activity waste, and methods suitable for disposal of solid, liquid and gaseous forms are described. The programme gives a useful introduction to an important aspect of work with radioactive materials, but is only intended as a supplement to practical training. (author)

Analytical procedures for the determination of strontium radionuclides in environmental materials

International Nuclear Information System (INIS)

Harvey, B.R.; Ibbett, R.D.; Lovett, M.B.; Williams, K.J.

1989-01-01

As part of its statutory role in the authorisation, monitoring and research relating to radioactive wastes discharged into the aquatic environment, the Aquatic Environment Protection Division of the Directorate of Fisheries Research (DFR), Lowestoft routinely carries out analyses for a substantial number of radionuclides in a wide range of environmental materials. The Ministry of a Agriculture, Fisheries and Food has for many years required information about the concentrations of strontium radionuclides in waters, sediments and biological materials. There are not absolute standard methods for such radiochemical analysis; indeed none are required because methodology is continually developing. A very considerable amount of expertise has been developed in the analysis of radiostrontium at the Laboratory since the late 1950s, when detailed analysis first commenced, and the procedures described in this report have been developed and tested over a long period of time with a view to achieving the highest analytical quality. Full details of the practical, analytical and computational procedures, as currently used, are given in the Appendix. (author)

Radioactive Demonstration Of Final Mineralized Waste Forms For Hanford Waste Treatment Plant Secondary Waste By Fluidized Bed Steam Reforming Using The Bench Scale Reformer Platform

International Nuclear Information System (INIS)

Crawford, C.; Burket, P.; Cozzi, A.; Daniel, W.; Jantzen, C.; Missimer, D.

2012-01-01

. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage, but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the SRNL to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. BSR testing with WTP SW waste surrogates and associated analytical analyses and tests of granular products (GP) and monoliths began in the Fall of 2009, and then was continued from the Fall of 2010 through the Spring of 2011. Radioactive testing commenced in 2010 with a demonstration of Hanford's WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of 125/129 I and 99 Tc to chemically resemble WTP-SW. Prior to these radioactive feed tests, non-radioactive simulants were also processed. Ninety six grams of radioactive granular product were made for testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing.

A performance assessment methodology for low-level radioactive waste disposal

International Nuclear Information System (INIS)

Deering, L.R.; Kozak, M.W.

1990-01-01

To demonstrate compliance with the performance objectives governing protection of the general population in 10 CFR 61.41, applicants for land disposal of low-level radioactive waste are required to conduct a pathways analysis, or quantitative evaluation of radionuclide release, transport through environmental media, and dose to man. The Nuclear Regulatory Commission staff defined a strategy and initiated a project at Sandia National Laboratories to develop a methodology for independently evaluating an applicant's analysis of postclosure performance. This performance assessment methodology was developed in five stages: (1) identification of environmental pathways, (2) ranking, the significance of the pathways, (3) identification and integration of models for pathway analyses, (4) identification and selection of computer codes and techniques for the methodology, and (5) implementation of the codes and documentation of the methodology. The final methodology implements analytical and simple numerical solutions for source term, ground-water flow and transport, surface water transport, air transport, food chain, and dosimetry analyses, as well as more complex numerical solutions for multidimensional or transient analyses when more detailed assessments are needed. The capability to perform both simple and complex analyses is accomplished through modular modeling, which permits substitution of various models and codes to analyze system components

Analytical methods under emergency conditions

International Nuclear Information System (INIS)

Sedlet, J.

1983-01-01

This lecture discusses methods for the radiochemical determination of internal contamination of the body under emergency conditions, here defined as a situation in which results on internal radioactive contamination are needed quickly. The purpose of speed is to determine the necessity for medical treatment to increase the natural elimination rate. Analytical methods discussed include whole-body counting, organ counting, wound monitoring, and excreta analysis. 12 references

Treatment and conditioning of radioactive organic liquids

International Nuclear Information System (INIS)

1992-07-01

Liquid organic radioactive wastes are generated from the use of radioisotopes in nuclear research centres and in medical and industrial applications. The volume of these wastes is small by comparison with aqueous radioactive wastes, for example; nevertheless, a strategy for the effective management of these wastes is necessary in order to ensure their safe handling, processing, storage and disposal. A aqueous radioactive wastes may be discharged to the environment after the radioactivity has decayed or been removed. By contrast, organic radioactive wastes require management steps that not only take account of their radioactivity, but also of their chemical content. This is because both the radioactivity and the organic chemical nature can have detrimental effects on health and the environment. Liquid radioactive wastes from these applications typically include vacuum pump oil, lubricating oil and hydraulic fluids, scintillation cocktails from analytical laboratories, solvents from solvent extraction research and uranium refining, and miscellaneous organic solvents. The report describes the factors which should be considered in the development of appropriate strategies for managing this class of wastes from generation to final disposal. Waste sources and characterization, treatment and conditioning processes, packaging, interim storage and the required quality assurance are all discussed. The report is intended to provide guidance to developing Member States which do not have nuclear power generation. A range of processes and procedures is presented, though emphasis is given to simple, easy-to-operate processes requiring less sophisticated and relatively inexpensive equipment. 31 refs, 16 figs, 3 tabs

Application of radioactive sources in analytical instruments for planetary exploration

International Nuclear Information System (INIS)

Economou, T.E.

2008-01-01

Full text: In the past 50 years or so, many types of radioactive sources have been used in space exploration. 238 Pu is often used in space missions in Radioactive Heater Units (RHU) and Radioisotope Thermoelectric Generators (RTG) for heat and power generation, respectively. In 1960's, 2 ' 42 Cm alpha radioactive sources have been used for the first time in space applications on 3 Surveyor spacecrafts to obtain the chemical composition of the lunar surface with an instrument based on the Rutherford backscatterring of the alpha particles from nuclei in the analyzed sample. 242 Cm is an alpha emitter of 6.1 MeV alpha particles. Its half-life time, 163 days, is short enough to allow sources to be prepared with the necessary high intensity per unit area ( up to 470 mCi and FWHM of about 1.5% in the lunar instruments) that results in narrow energy distribution, yet long enough that the sources have adequate lifetimes for short duration missions. 242 Cm is readily prepared in curie quantities by irradiation of 241 Am by neutrons in nuclear reactors, followed by chemical separation of the curium from the americium and fission products. For long duration missions, like for example missions to Mars, comets, and asteroids, the isotope 244 Cm (T 1/2 =18.1 y, E α =5.8 MeV) is a better source because of its much longer half-life time. Both of these isotopes are also excellent x-ray excitation sources and have been used for that purpose on several planetary missions. For the light elements the excitation is caused mainly by the alpha particles, while for the heavier elements (> Ca) the excitation is mainly due to the x-rays from the Pu L-lines (E x =14-18 keV). 244 Cm has been used in several variations of the Alpha Proton Xray Spectrometer (APXS): PHOBOS 1 and 2 Pathfinder, Russian Mars-96 mission, Mars Exploration Rover (MER) and Rosetta. Other sources used in X-ray fluorescence instruments in space are 55 Fe and 109 Cd (Viking1,2, Beagle 2) and 57 Co is used in Moessbauer

Method of solidifying radioactive wastes

International Nuclear Information System (INIS)

Maeda, Masahiko; Kira, Satoshi; Watanabe, Naotoshi; Nagaoka, Takeshi; Akane, Junta.

1982-01-01

Purpose: To obtain solidification products of radioactive wastes having sufficient monoaxial compression strength and excellent in water durability upon ocean disposal of the wastes. Method: Solidification products having sufficient strength and filled with a great amount of radioactive wastes are obtained by filling and solidifying 100 parts by weight of chlorinated polyethylene resin and 100 - 500 parts by weight of particular or powderous spent ion exchange resin as radioactive wastes. The chlorinated polyethylene resin preferably used herein is prepared by chlorinating powderous or particulate polyethylene resin in an aqueous suspending medium or by chlorinating polyethylene resin dissolved in an organic solvent capable of dissolving the polyethylene resin, and it is crystalline or non-crystalline chlorinated polyethylene resin comprising 20 - 50% by weight of chlorine, non-crystalline resin with 25 - 40% by weight of chlorine being particularly preferred. (Horiuchi, T.)

Development of quantitative analytical methods for the control of actinides in a pyrochemical partitioning process

International Nuclear Information System (INIS)

Abousahl, S.; Belle, P. van; Eberle, H.; Ottmar, H.; Lynch, B.; Vallet, P.; Mayer, K.; Ougier, M.

2005-01-01

Advanced nuclear fuel cycles are being developed in order to reduce the long-term radiotoxicity of highly radioactive waste. Pyrochemical partitioning techniques appear particularly attractive for advanced fuel cycles in which the minor actinides are recycled. The electrochemical processes of practical importance are the electrorefining process and the liquid-liquid extraction of transuranic (TRU) elements from fission products using either non-miscible molten metal or molten salt-metal phases. Analytical methods for the accurate assay of actinide elements in these matrices needed to be developed. A quantitative assay is required in order to establish a material balance for process development and - at a later stage - for accountancy and control purposes. To this end radiometric techniques such as energy-dispersive X-ray fluorescence analysis (XRF), neutron coincidence counting (NCC) and high-resolution gamma spectrometry (HRGS) were extensively employed for the quantitative determination of actinides (U, Np, Pu, Am, Cm) in process samples. Comparative analyses were performed using inductively coupled plasma mass spectrometry (ICP-MS). The respective samples were available in small quantities (≅ 100 mg) either in the form of eutectic salt or in metallic form with Cd, Zr or Bi as major metallic matrix constituents. (orig.)

Maintenance Plan for the Performance Assessments and Composite Analyses of the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site

International Nuclear Information System (INIS)

Vefa Yucel

2007-01-01

U.S. Department of Energy (DOE) Manual M 435.1-1 requires that performance assessments (PAs) and composite analyses (CAs) for low-level waste (LLW) disposal facilities be maintained by the field offices. This plan describes the activities performed to maintain the PA and the CA for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS). This plan supersedes the Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (DOE/NV/11718--491-REV 1, dated September 2002). The plan is based on U.S. Department of Energy (DOE) Order 435.1 (DOE, 1999a), DOE Manual M 435.1-1 (DOE, 1999b), the DOE M 435.1-1 Implementation Guide DOE G 435.1-1 (DOE, 1999c), and the Maintenance Guide for PAs and CAs (DOE, 1999d). The plan includes a current update on PA/CA documentation, a revised schedule, and a section on Quality Assurance

Radioactivity in the Marine Environment 1999

Energy Technology Data Exchange (ETDEWEB)

Rudjord, A.L.; Foeyn, L.; Brungot, A.L.; Kolstad, A.K.; Helldal, H.E.; Brown, J.; Iosjpe, M.; Christensen, G.

2001-07-01

in the present report. Several institutions have collected samples and analysed results for the coordinated monitoring programme. They are, the Norwegian Radiation Protection Authority (including the environmental unit in Tromsoe), the Institute of Marine Research, Institute for Energy Technology, the Directorate of Fisheries (including the local office in Tromsoe) and the Norwegian Food Control Authority (local office in Salten). The main sections of the report are (1) Sources of radionuclides in the marine environment, (2) Collection of samples, (3) Environmental radioactivity from Norwegian sources, (4) Radioactivity in sea water and sediments, (5) Radioactivity in fish and other biota, (6) Development of assessment tools. Appendix 1 gives general information about radionuclide analysis and provides details of analytical methods employed by each institution.

Radioactivity in the Marine Environment 1999

International Nuclear Information System (INIS)

Rudjord, A.L.; Foeyn, L.; Brungot, A.L.; Kolstad, A.K.; Helldal, H.E.; Brown, J.; Iosjpe, M.; Christensen, G.

2001-01-01

in the present report. Several institutions have collected samples and analysed results for the coordinated monitoring programme. They are, the Norwegian Radiation Protection Authority (including the environmental unit in Tromsoe), the Institute of Marine Research, Institute for Energy Technology, the Directorate of Fisheries (including the local office in Tromsoe) and the Norwegian Food Control Authority (local office in Salten). The main sections of the report are (1) Sources of radionuclides in the marine environment, (2) Collection of samples, (3) Environmental radioactivity from Norwegian sources, (4) Radioactivity in sea water and sediments, (5) Radioactivity in fish and other biota, (6) Development of assessment tools. Appendix 1 gives general information about radionuclide analysis and provides details of analytical methods employed by each institution

Survey monitoring of environmental radioactivity in Daegu area

Energy Technology Data Exchange (ETDEWEB)

Kang, H. D.; Lee, S. Y. [Kyungpook National Univ., Daegu (Korea, Republic of)

1998-01-15

The objectives of the project are to monitor an abnormal radiation level in Taegu and Kyungpook region, and to enhance our ability to prepare for the radiological emergency situation by establishing the radioactivity monitoring system in Taegu and Kyungpook region. Gross beta activities were measured and gamma radionuclides were analysed for the environmental samples of air-borned dust. precipitation. fallout and drinking water collected in Taegu radioactivity monitoring center. and gamma exposure rates were also measured. To establish the basic data base on the environmental radioactivity, gamma radionuclide analyses were carried out for the samples of soil, drinking water, grain, vegetable, milk, and fish which were obtained from 31 different areas, and the spatial gamma exposure rates from 61 different points were also measured in Taegu and Kyungpook region. In conclusion, it didn't appear any evidence for newly pollution of artificial radioactivity in Taegu and Kyungpook region.

Development and application of RP-HPLC methods for the analysis of transition metals and their radioactive isotops in radioactive waste

International Nuclear Information System (INIS)

Seekamp, S.

1999-07-01

A major criterion in the final disposal of nuclear waste is to keep possible changes in the geosphere due to the introduction of radioactive waste as small as possible and to prevent any escape into the biosphere in the long term. The Federal Office for Radiation Protection (BfS) has therefore established limit values for a number of nuclides. Verifying these limits has to date involved laborious wet chemical analysis. In order to accelerate quantification there is a need to develop rapid multielement methods. HPLC methods represent a starting point for this development. Chemical separation is necessary to quantify β-emitters via their radioactive radiation since they are characterized by a continuous energy spectrum. A method for quantifying transition metals and their radioactive isotopes from radioactive waste has been created by using a chelating agent to select the analytes and RP-HPLC to separate the complexes formed. In addition to separating the matrix, complexation on a precolumn has the advantage of enriching the analytes. The subject of this thesis is the development and application of the method including studies of the mobile and stationary phase, as well as the optimization of all parameters, such as pH value, sample volume etc., which influence separation, enrichment or detection. The method developed was successfully tested using cement samples. It was also used for investigations of ion exchange resins and for trace analysis in calcium fluoride. Furthermore, the transferability of the method to actinides was examined by using a different complexing agent. (orig.) [de

Sampling and characterization of radioactive liquid wastes

International Nuclear Information System (INIS)

Zepeda R, C.; Monroy G, F.; Reyes A, T.; Lizcano, D.; Cruz C, A. C.

2017-09-01

To define the management of radioactive liquid wastes stored in 200 L drums, its isotope and physicochemical characterization is essential. An adequate sampling, that is, representative and homogeneous, is fundamental to obtain reliable analytical results, therefore, in this work, the use of a sampling mechanism that allows collecting homogenous aliquots, in a safe way and minimizing the generation of secondary waste is proposed. With this mechanism, 56 drums of radioactive liquid wastes were sampled, which were characterized by gamma spectrometry, liquid scintillation, and determined the following physicochemical properties: ph, conductivity, viscosity, density and chemical composition by gas chromatography. 67.86% of the radioactive liquid wastes contains H-3 and of these, 47.36% can be released unconditionally, since it presents activities lower than 100 Bq/g. 94% of the wastes are acidic and 48% have viscosities <50 MPa s. (Author)

Non-radioactive verification test of ZRF25 radioactive combustible solid waste incinerator

International Nuclear Information System (INIS)

Wang Peiyi; Li Xiaohai; Yang Liguo

2013-01-01

This paper mainly introduces the construction and test run of ZRF25 radioactive combustible solid waste incinerator, by a series of simulating waste tests, such as 24 h test, 72 h test, 168 h test, making a conclusion that the incinerator runs reliably. In addition, all of the indexes (such as treatment capacity, volume reduction coefficient, clinker ignition loss of incineration ash) meet the requirements of contract and pollution discharging standards. (authors)

NPDES permits and water analyses

International Nuclear Information System (INIS)

Pojasek, R.B.

1975-01-01

Provisions of the Federal Water Pollution Control Act, as amended by P. L. 92-500, including an explanation of the National Pollutant Discharge Elimination System (NPDES), and EPA's criteria for the analysis of pollutants are discussed. The need for a revision of current restrictive variance procedures is pointed out. References for the comparison of analytical methods for water pollutants under permits, including radioactive parameters, are tabulated. (U.S.)

Natural radioactivity in environmental samples from an island of volcanic origin (Milos, Aegean Sea)

International Nuclear Information System (INIS)

Florou, H.; Kritidis, P.

1991-01-01

Enhanced concentrations of natural radionuclides occur in volcanic islands such as Milos in the Aegean Sea. The natural gamma radiation status of the entire environment in Milos were studied using gamma radiometry. Gamma spectrometry was used to analyse ore samples, sediments and marine biota. While non-living materials showed enhanced levels of natural radioactivity, most of the marine organisms examined did not seem to reflect this radiological status. (UK)

Performance of analytical methods for tomographic gamma scanning

International Nuclear Information System (INIS)

Prettyman, T.H.; Mercer, D.J.

1997-01-01

The use of gamma-ray computerized tomography for nondestructive assay of radioactive materials has led to the development of specialized analytical methods. Over the past few years, Los Alamos has developed and implemented a computer code, called ARC-TGS, for the analysis of data obtained by tomographic gamma scanning (TGS). ARC-TGS reduces TGS transmission and emission tomographic data, providing the user with images of the sample contents, the activity or mass of selected radionuclides, and an estimate of the uncertainty in the measured quantities. The results provided by ARC-TGS can be corrected for self-attenuation when the isotope of interest emits more than one gamma-ray. In addition, ARC-TGS provides information needed to estimate TGS quantification limits and to estimate the scan time needed to screen for small amounts of radioactivity. In this report, an overview of the analytical methods used by ARC-TGS is presented along with an assessment of the performance of these methods for TGS

Radioactive waste material testing capabilities in Romania

International Nuclear Information System (INIS)

Vieru, G.

1999-01-01

Radioactive material including wastes, generated by Romanian nuclear facilities are packaged in accordance with national and IAEA's Regulation for a safe transport to the disposal center. The evaluation and certification of packages is accomplished by subjecting these packages to normal and simulated test conditions in order to prove the package to technical performances. The standards provide to package designers the possibility to use analysis, testing or a combination of these. The paper describes the experimental and simulating qualification tests for type A packages used for transport and storage of radioactive wastes (low level). Testing are used to substantiate assumptions used in analytical models and to demonstrate package structural response. There are also presented testing capabilities which are used to perform and simulate the required qualification tests. By direct comparison of analysis and experimental results, the degree of reliability of analytical methods and admissibility of assumptions taken in package designing and in demonstrating its safety under conditions of INR - Pitesti, within the contract between the INR - Pitesti and IAEA - Vienna, were determined. (author)

Optimised Pre-Analytical Methods Improve KRAS Mutation Detection in Circulating Tumour DNA (ctDNA) from Patients with Non-Small Cell Lung Cancer (NSCLC)

Science.gov (United States)

Sherwood, James L.; Corcoran, Claire; Brown, Helen; Sharpe, Alan D.; Musilova, Milena; Kohlmann, Alexander

2016-01-01

Introduction Non-invasive mutation testing using circulating tumour DNA (ctDNA) is an attractive premise. This could enable patients without available tumour sample to access more treatment options. Materials & Methods Peripheral blood and matched tumours were analysed from 45 NSCLC patients. We investigated the impact of pre-analytical variables on DNA yield and/or KRAS mutation detection: sample collection tube type, incubation time, centrifugation steps, plasma input volume and DNA extraction kits. Results 2 hr incubation time and double plasma centrifugation (2000 x g) reduced overall DNA yield resulting in lowered levels of contaminating genomic DNA (gDNA). Reduced “contamination” and increased KRAS mutation detection was observed using cell-free DNA Blood Collection Tubes (cfDNA BCT) (Streck), after 72 hrs following blood draw compared to EDTA tubes. Plasma input volume and use of different DNA extraction kits impacted DNA yield. Conclusion This study demonstrated that successful ctDNA recovery for mutation detection in NSCLC is dependent on pre-analytical steps. Development of standardised methods for the detection of KRAS mutations from ctDNA specimens is recommended to minimise the impact of pre-analytical steps on mutation detection rates. Where rapid sample processing is not possible the use of cfDNA BCT tubes would be advantageous. PMID:26918901

Optimised Pre-Analytical Methods Improve KRAS Mutation Detection in Circulating Tumour DNA (ctDNA from Patients with Non-Small Cell Lung Cancer (NSCLC.

Directory of Open Access Journals (Sweden)

James L Sherwood

Full Text Available Non-invasive mutation testing using circulating tumour DNA (ctDNA is an attractive premise. This could enable patients without available tumour sample to access more treatment options.Peripheral blood and matched tumours were analysed from 45 NSCLC patients. We investigated the impact of pre-analytical variables on DNA yield and/or KRAS mutation detection: sample collection tube type, incubation time, centrifugation steps, plasma input volume and DNA extraction kits.2 hr incubation time and double plasma centrifugation (2000 x g reduced overall DNA yield resulting in lowered levels of contaminating genomic DNA (gDNA. Reduced "contamination" and increased KRAS mutation detection was observed using cell-free DNA Blood Collection Tubes (cfDNA BCT (Streck, after 72 hrs following blood draw compared to EDTA tubes. Plasma input volume and use of different DNA extraction kits impacted DNA yield.This study demonstrated that successful ctDNA recovery for mutation detection in NSCLC is dependent on pre-analytical steps. Development of standardised methods for the detection of KRAS mutations from ctDNA specimens is recommended to minimise the impact of pre-analytical steps on mutation detection rates. Where rapid sample processing is not possible the use of cfDNA BCT tubes would be advantageous.

Road Transportable Analytical Laboratory (RTAL) system

International Nuclear Information System (INIS)

Finger, S.M.

1995-01-01

U.S. Department of Energy (DOE) facilities around the country have, over the years, become contaminated with radionuclides and a range of organic and inorganic wastes. Many of the DOE sites encompass large land areas and were originally sited in relatively unpopulated regions of the country to minimize risk to surrounding populations. In addition, wastes were sometimes stored underground at the sites in 55-gallon drums, wood boxes or other containers until final disposal methods could be determined. Over the years, these containers have deteriorated, releasing contaminants into the surrounding environment. This contamination has spread, in some cases polluting extensive areas. The DOE would benefit greatly if it had reliable, road transportable, fully independent laboratory systems that could perform on-site the full range of analyses required. The goal of the Road Transportable Analytical Laboratory (RTAL) project is the development and demonstration of a system to meet the unique needs of the DOE for rapid, accurate analysis of a wide variety of hazardous and radioactive contaminants in soils, ground water and surface waters. This document describes the requirements for such a laboratory

Monitoring of low-level radioactive liquid effluent in Tokai reprocessing plant

International Nuclear Information System (INIS)

Mizutani, Tomoko; Koarashi, Jun; Takeishi, Minoru

2009-01-01

The Tokai reprocessing plant (TRP), the first reprocessing plant in Japan, has discharged low-level liquid wastes to the Pacific Ocean since the start of its operation in 1977. We have performed liquid effluent monitoring to realize an appropriate radioactive discharge control. Comparing simple and rapid analytical methods with labor-intensive radiochemical analyses demonstrated that the gross-alpha and gross-beta activities agreed well with the total activities of plutonium isotopes ( 238 Pu and 239+240 Pu) and major beta emitters (e.g., 90 Sr and 137 Cs), respectively. The records of the radioactive liquid discharge from the TRP showed that the normalized discharges of all nuclides, except for 3 H, were three or four orders of magnitude lower than those from the Sellafield and La Hague reprocessing plants. This was probably due to the installation of multistage evaporators in the liquid waste treatment process in 1980. The annual public doses for a hypothetical person were estimated to be less than 0.2 μSv y -1 from the aquatic pathway. Plutonium radioactivity ratios ( 238 Pu/ 239+240 Pu) of liquid effluents were determined to be 1.3-3.7, while those of the seabed sediment samples collected around the discharge point were 0.003-0.059, indicating no remarkable accumulation of plutonium in the regional aquatic environment. Thus, we concluded that there were no significant radiological effects on the public and the aquatic environment during the past 30-year operation of the TRP. (author)

Road Transportable Analytical Laboratory (RTAL) system

International Nuclear Information System (INIS)

1993-01-01

The goal of this contractual effort is the development and demonstration of a Road Transportable Analytical Laboratory (RTAL) system to meet the unique needs of the Department of Energy (DOE) for rapid, accurate analysis of a wide variety of hazardous and radioactive contaminants in soil, groundwater, and surface waters. This laboratory system will be designed to provide the field and laboratory analytical equipment necessary to detect and quantify radionuclides, organics, heavy metals and other inorganics, and explosive materials. The planned laboratory system will consist of a set of individual laboratory modules deployable independently or as an interconnected group to meet each DOE site's specific needs

thermal characteristics of a simulated non-radioactive agricultural waste

International Nuclear Information System (INIS)

Ahmed, A.Z.; Soliman, H.M.; Abdelmoniem, M.

2004-01-01

characterization of thermal degradation of a mixture of a simulated non radioactive contaminated almond shell and cotton straw is important to check possibility of its safe treatment by pyrolysis. thermal analysis of the mixture was carried out using thermal gravimetric analysis (TGA) under inert atmosphere. thermal degradation of almond shell and cotton straw mixture takes place in two stages namely, volatilization stage and decarbonization stage. kinetics of the thermal degradation was studied to determine the reaction rate, activation energy, entropy change, enthalpy change and free energy for both stages. during pyrolysis, 5.8% water Vapor, 46.4% condensed gases, 29.2% condensed gases, and 18.6% pyrolysis coke residue by weight were obtained . analysis of pyrolysis condensed gases showed that it contained 24.2% N 2 ,7.1% CO, 14% H 2 and 17.3 CO 2 by weight. in addition, results revealed that the heavy elements are concentrated in the coke residue. it was found that the rate constant of the reacion increases by the increase in the temperature for both sages. more above, results revealed that the activation energy for volatilization stage is higher than decarbonization stage

Low-level Radioactivity Measurements

International Nuclear Information System (INIS)

Hurtgen, C.

2002-01-01

The objectives of the research performed in the area of low-level radioactivity measurements are (1) to maintain and develop techniques for the measurement of low-level environmental and biological samples, (2) to measure these samples by means of low-background counters (liquid scintillators, proportional counters, ZnS counters, alpha spectrometry), (3) to support and advise the nuclear and non-nuclear industry on problems of radioactive contamination and low-level radioactivity measurements; (4) to maintain and improve the quality assurance system according to the ISO17025 standard; and (5) to assess the internal dose from occupational intakes of radionuclides of workers of the nuclear industry. Progress and achievements in these areas in 2001 are reported

Low-level Radioactivity Measurements

International Nuclear Information System (INIS)

Hurtgen, C.

2001-01-01

The objectives of the research performed in the area of low-level radioactivity measurements are (1) to maintain and develop techniques for the measurement of low-level environmental and biological samples, (2) to measure these samples by means of low-background counters (liquid scintillators, proportional counters, ZnS counters, alpha spectrometry), (3) to support and advice the nuclear and non-nuclear industry in matters concerning radioactive contamination and/or low-level radioactivity measurements; (4) to maintain the quality assurance system according to the EN45001/ISO17025 standard; and (5) to assess the internal dose from occupational intakes of radionuclides of workers of the nuclear industry. Progress and achievements in these areas in 2000 are reported

Measurement and analysis of radioactive substances

International Nuclear Information System (INIS)

2001-01-01

Here are gathered the abstracts presented to the 3. summer university of the year 2001 whose main themes were the destructive (5 conferences) and nondestructive (8 conferences) analyses applied to nuclear industry. The points of view of different organisms (as DSIN: Directorate for the Safety of Nuclear Installations, IPSN: Institute of Nuclear Protection and Safety, OPRI: Office of Protection against Ionizing Radiations, TUI: Institute for Transuranium Elements, COGEMA, EDF: Electric Utilities, ANDRA: French National Agency for Radioactive Waste Management, CRLC Val d'Aurelle, France) concerning the needs involved in nuclear facilities control, the methods of radionuclide speciation in use internationally, the measurements and analyses of radioactive substances are given too as well as some general concepts concerning 1)the laser-matter interaction 2)the ions production 3)the quality applied to the measurements and analyses 4)the standard in activity metrology. (O.M.)

Distribution-analytical techniques in the study of AD/HD: Delta plot analyses reveal deficits in response inhibition that are eliminated by methylphenidate treatment

NARCIS (Netherlands)

Ridderinkhof, K.R.; Scheres, A.; Oosterlaan, J.; Sergeant, J.A.

2005-01-01

The authors highlight the utility of distribution-analytical techniques in the study of individual differences and clinical disorders. Cognitive deficits associated with attention-deficit/hyperactivity disorder (AD/HD) were examined by using delta-plot analyses of performance data (reaction time and

Airborne concentrations of radioactive materials in severe accidents

International Nuclear Information System (INIS)

Ross, D.F. Jr.; Denning, R.S.

1989-01-01

Radioactive materials would be released to the containment building of a commercial nuclear reactor during each of the stages of a severe accident. Results of analyses of two accident sequences are used to illustrate the magnitudes of these sources of radioactive materials, the resulting airborne mass concentrations, the characteristics of the airborne aerosols, the potential for vapor forms of radioactive materials, the effectiveness of engineered safety features in reducing airborne concentrations, and the release of radioactive materials to the environment. Ability to predict transport and deposition of radioactive materials is important to assessing the performance of containment safety features in severe accidents and in the development of accident management procedures to reduce the consequences of severe accidents

Simplified analytical model to simulate radionuclide release from radioactive waste trenches; Modelo simplificado para simulacao da liberacao de radionuclideos de repositorios de rejeitos radioativos

Energy Technology Data Exchange (ETDEWEB)

Sa, Bernardete Lemes Vieira de

2001-07-01

In order to evaluate postclosure off-site doses from low-level radioactive waste disposal facilities, a computer code was developed to simulate the radionuclide released from waste form, transport through vadose zone and transport in the saturated zone. This paper describes the methodology used to model these process. The radionuclide released from the waste is calculated using a model based on first order kinetics and the transport through porous media was determined using semi-analytical solution of the mass transport equation, considering the limiting case of unidirectional convective transport with three-dimensional dispersion in an isotropic medium. The results obtained in this work were compared with other codes, showing good agreement. (author)

Radioactive cloud dose calculations

International Nuclear Information System (INIS)

Healy, J.W.

1984-01-01

Radiological dosage principles, as well as methods for calculating external and internal dose rates, following dispersion and deposition of radioactive materials in the atmosphere are described. Emphasis has been placed on analytical solutions that are appropriate for hand calculations. In addition, the methods for calculating dose rates from ingestion are discussed. A brief description of several computer programs are included for information on radionuclides. There has been no attempt to be comprehensive, and only a sampling of programs has been selected to illustrate the variety available

Analytical Chemistry Division annual progress report: For period ending December 31, 1987

International Nuclear Information System (INIS)

1988-05-01

This report is divided into analytical spectroscopy; radioactive materials analysis; inorganic chemistry; organic chemistry; ORNL environmental programs; quality assurance, safety, and training; supplementary activities; and presentation of research results

Analytical Chemistry Division annual progress report: For period ending December 31, 1987

Energy Technology Data Exchange (ETDEWEB)

1988-05-01

This report is divided into analytical spectroscopy; radioactive materials analysis; inorganic chemistry; organic chemistry; ORNL environmental programs; quality assurance, safety, and training; supplementary activities; and presentation of research results.

RADIOACTIVE DEMONSTRATION OF FINAL MINERALIZED WASTE FORMS FOR HANFORD WASTE TREATMENT PLANT SECONDARY WASTE BY FLUIDIZED BED STEAM REFORMING USING THE BENCH SCALE REFORMER PLATFORM

Energy Technology Data Exchange (ETDEWEB)

Crawford, C.; Burket, P.; Cozzi, A.; Daniel, W.; Jantzen, C.; Missimer, D.

2012-02-02

ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage, but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the SRNL to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. BSR testing with WTP SW waste surrogates and associated analytical analyses and tests of granular products (GP) and monoliths began in the Fall of 2009, and then was continued from the Fall of 2010 through the Spring of 2011. Radioactive testing commenced in 2010 with a demonstration of Hanford's WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of {sup 125/129}I and {sup 99}Tc to chemically resemble WTP-SW. Prior to these radioactive feed tests, non-radioactive simulants were also processed. Ninety six grams of radioactive granular product were made for testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing.

Melting method for radioactive solid wastes and device therefor

Energy Technology Data Exchange (ETDEWEB)

Komatsu, Masahiko; Abe, Takashi; Nakayama, Junpei; Kusamichi, Tatsuhiko; Sakamoto, Koichi

1998-11-17

Upon melting radioactive solid wastes mixed with radioactive metal wastes and non metal materials such as concrete by cold crucible high frequency induction heating, induction coils are wound around the outer circumference of a copper crucible having a water cooling structure to which radioactive solid wastes are charged. A heating sleeve formed by a material which generates heat by an induction heating function of graphite is disposed to the inside of the crucible at a height not in contact with molten metals in the crucible vertically movably. Radioactive solid wastes are melted collectively by the induction heat of the induction coils and thermal radiation and heat conduction of the heating sleeve heated by the induction heat. With such procedures, non metal materials such as concrete and radioactive metal wastes in a mixed state can be melt collectively continuously highly economically. (T.M.)

Summary of industrial impacts from recycled radioactive scrap metals

International Nuclear Information System (INIS)

Dehmel, J.-C.; Harrop, J.; MacKinney, J.A.

1995-01-01

During operation, decontamination, and dismantlement, nuclear facilities are generating significant quantities of radioactive scrap metal (RSM). Future decommissioning will generate even more RSM. The petroleum industry also generates RSM in the form of equipment contaminated with naturally occurring radioactivity. Finally, the accidental melting of radioactive sources in steel mills has generated smaller amounts of contaminated metals. Steel mills, smelters, and foundries could recycle these materials, which might then appear in finished products or as feedstocks used by other industries. If introduced in this manner, residual radioactivity can adversely affect the performance of certain products. Such products include computers and other devices that rely on integrated circuits. The most important effect of residual radioactivity on integrated circuits is a phenomenon known as 'single event upsets or soft errors.' Radioactivity can also adversely affect the performance of products such as photographic film and components designed to measure the presence of radioactivity. Radioactivity that raises background count-rates to higher levels could affect the performance of radiation monitoring systems and analytical equipment. Higher background count-rates would lead to reduced sensitivity and lower resolution in spectroscopic systems. The computer, photographic, and radiation measurement industries have taken steps to minimize the impact of residual radioactivity on their products. These steps include monitoring manufacturing processes, specifying material acceptance standards, and screening suppliers. As RSM is recycled, these steps may become more important and more costly. This paper characterizes potentially impacted industries and vulnerability and effects due to the presence of residual radioactivity. Finally, the paper describes practices used to limit the impact of residual radioactivity. (J.P.N.)

Trace elements and naturally occurring radioactive materials in 'Non-traditional fertilizers' used in Ghana

International Nuclear Information System (INIS)

Assibey, E. O.

2013-07-01

Fertilizers have been implicated for being contaminated with toxic trace elements and naturally occurring radioactive materials (NORMs) even though they are an indispensable component of our agriculture. This phenomenon of contamination has been investigated and established world-wide in various forms of fertilizers (i.e., granular or 'traditional' type and liquid/powder or 'non-traditional type'). In Ghana, the crop sub-sector has seen a gradual rise in the importation and use of 'non-traditional fertilizers' which are applied to both the foliar parts and roots of plants. This notwithstanding, research on fertilizers has been largely skewed towards the 'traditional' types, focusing principally on the subjects of yield, effects of application and their quality. This study was, therefore, undertaken to bridge the knowledge gap by investigating the levels of trace elements and NORMs found in the 'non-traditional' fertilizers used in Ghana. The principal objective of the study was to investigate the suitability of the 'non-traditional fertilizers' for agricultural purposes with respect to trace elements and NORMs contamination. Atomic Absorption Spectrometry and instrumental Neutron Activation Analysis were employed to determine the trace elements (Cu, Zn, Fe, Na, Al, Br, Ni, Cd, As, Hg, Co, Pb, La, Mn, Si, Ca, Cl, S, K, Ba and V) and NORMs ( 238 U, 232 Th and 40 K) concentrations in thirty-nine (39) fertilizer samples taken from two major agro-input hubs in the country (Kumasi-Kejetia and Accra). Multivariate statistical analyses (cluster analysis, principal component analysis and pearson's correlation) were applied to the data obtained in order to identify possible sources of contamination, investigate sample/ parameter affinities and groupings and for fingerprinting. The toxic trace element concentrations determined in all samples were found to be in the order Fe>Cu>Co>Cd>Cr >Ni>Pb>As>Hg. The study found most of the trace elements determined to be within limits set

Economic analysis of radioactive waste storage and disposal projects

International Nuclear Information System (INIS)

Kleinen, P.J.; Starnes, R.B.

1995-01-01

Radioactive waste storage and disposal efforts present challenging issues for cost and economic analyses. In particular, legal requirements for states and compact areas to develop radioactive waste disposal sites, combined with closure of some sites, have placed urgency on planning, locating, and constructing storage and disposal sites. Cost analyses of potential projects are important to the decision processes. Principal objectives for cost analyses for projects are to identify all activities, covering the entire project life cycle, and to develop costs for those activities using methods that allow direct comparisons between competing project alternatives. For radioactive waste projects, long project lives ranging from tens of years to 100 or more years must be considered. Alternative, and competing, technologies, designs, and operating plans must be evaluated. Thorough base cost estimates must be made for all project phases: planning, development, licensing/permitting, construction, operations, and maintenance, closure, and post-closure/institutional care. Economic analysis procedures need to accommodate the specific features of each project alternative and facilitate cost comparisons between differing alternatives. Economic analysis assumptions must be developed to address the unusually long project lives involved in radioactive waste projects

Simple quasi-analytical holonomic homogenization model for the non-linear analysis of in-plane loaded masonry panels: Part 1, meso-scale

Science.gov (United States)

Milani, G.; Bertolesi, E.

2017-07-01

A simple quasi analytical holonomic homogenization approach for the non-linear analysis of masonry walls in-plane loaded is presented. The elementary cell (REV) is discretized with 24 triangular elastic constant stress elements (bricks) and non-linear interfaces (mortar). A holonomic behavior with softening is assumed for mortar. It is shown how the mechanical problem in the unit cell is characterized by very few displacement variables and how homogenized stress-strain behavior can be evaluated semi-analytically.

Road Transportable Analytical Laboratory (RTAL) system

International Nuclear Information System (INIS)

Finger, S.M.

1995-01-01

U.S. Department of Energy (DOE) facilities around the country have, over the years, become contaminated with radionuclides and a range of organic and inorganic wastes. Many of the DOE sites encompass large land areas and were originally sited in relatively unpopulated regions of the country to minimize risk to surrounding populations. In addition, wastes were sometimes stored underground at the sites in 55-gallon drums, wood boxes or other containers until final disposal methods could be determined. Over the years, these containers have deteriorated, releasing contaminants into the surrounding environment. This contamination has spread, in some cases polluting extensive areas. Remediation of these sites requires extensive sampling to determine the extent of the contamination, to monitor clean-up and remediation progress, and for post-closure monitoring of facilities. The DOE would benefit greatly if it had reliable, road transportable, fully independent laboratory systems that could perform on-site the full range of analyses required. Such systems would accelerate and thereby reduce the cost of clean-up and remediation efforts by (1) providing critical analytical data more rapidly, and (2) eliminating the handling, shipping and manpower associated with sample shipments. The goal of the Road Transportable Analytical Laboratory (RTAL) Project is the development and demonstration of a system to meet the unique needs of the DOE for rapid, accurate analysis of a wide variety of hazardous and radioactive contaminants in soil, groundwater, and surface waters. This laboratory system has been designed to provide the field and laboratory analytical equipment necessary to detect and quantify radionuclides, organics, heavy metals and other inorganic compounds. The laboratory system consists of a set of individual laboratory modules deployable independently or as an interconnected group to meet each DOE site's specific needs

Recent Advances in Analytical Pyrolysis to Investigate Organic Materials in Heritage Science.

Science.gov (United States)

Degano, Ilaria; Modugno, Francesca; Bonaduce, Ilaria; Ribechini, Erika; Colombini, Maria Perla

2018-06-18

The molecular characterization of organic materials in samples from artworks and historical objects traditionally entailed qualitative and quantitative analyses by HPLC and GC. Today innovative approaches based on analytical pyrolysis enable samples to be analysed without any chemical pre-treatment. Pyrolysis, which is often considered as a screening technique, shows previously unexplored potential thanks to recent instrumental developments. Organic materials that are macromolecular in nature, or undergo polymerization upon curing and ageing can now be better investigated. Most constituents of paint layers and archaeological organic substances contain major insoluble and chemically non-hydrolysable fractions that are inaccessible to GC or HPLC. To date, molecular scientific investigations of the organic constituents of artworks and historical objects have mostly focused on the minor constituents of the sample. This review presents recent advances in the qualitative and semi-quantitative analyses of organic materials in heritage objects based on analytical pyrolysis coupled with mass spectrometry. © 2018 Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

Nuclide separation modeling through reverse osmosis membranes in radioactive liquid waste

OpenAIRE

Lee, Byung-Sik

2015-01-01

The aim of this work is to investigate the transport mechanism of radioactive nuclides through the reverse osmosis (RO) membrane and to estimate its effectiveness for nuclide separation from radioactive liquid waste. An analytical model is developed to simulate the RO separation, and a series of experiments are set up to confirm its estimated separation behavior. The model is based on the extended Nernst–Plank equation, which handles the convective flux, diffusive flux, and electromigration f...

Role of shell corrections in the phenomenon of cluster radioactivity

Science.gov (United States)

Kaur, Mandeep; Singh, Bir Bikram; Sharma, Manoj K.

2018-05-01

The detailed investigation has been carried out to explore the role of shell corrections in the decay of various radioactive parent nuclei in trans-lead region, specifically, which lead to doubly magic 208Pb daughter nucleus through emission of clusters such as 14C, 18,20O, 22,24,26Ne, 28,30 Mg and 34S i. The fragmentation potential comprises of binding energies (BE), Coulomb potential (Vc) and nuclear or proximity potential (VP) of the decaying fragments (or clusters). It is relevant to mention here that the contributions of VLDM (T=0) and δU (T=0) in the BE have been analysed within the Strutinsky renormanlization procedure. In the framework of quantum mechanical fragmentation theory (QMFT), we have investigated the above mentioned cluster decays with and without inclusion of shell corrections in the fragmentation potential for spherical as well as non-compact oriented nuclei. We find that the experimentally observed clusters 14C, 18,20O, 22,24,26 Ne, 28,30 Mg and 34Si having doubly magic 208 Pb daughter nucleus are not strongly minimized, they do so only after the inclusion of shell corrections in the fragmentation potential. The nuclear structure information carried by the shell corrections have been explored via these calculations, within the collective clusterisation process of QMFT, in the study of ground state decay of radioactive nuclei. The role of different parts of fragmentation potentials such as VLDM, δU, Vc and Vp is dually analysed for better understanding of radioactive cluster decay.

Radioactivity in food crops

International Nuclear Information System (INIS)

Drury, J.S.; Baldauf, M.F.; Daniel, E.W.; Fore, C.S.; Uziel, M.S.

1983-05-01

Published levels of radioactivity in food crops from 21 countries and 4 island chains of Oceania are listed. The tabulation includes more than 3000 examples of 100 different crops. Data are arranged alphabetically by food crop and geographical origin. The sampling date, nuclide measured, mean radioactivity, range of radioactivities, sample basis, number of samples analyzed, and bibliographic citation are given for each entry, when available. Analyses were reported most frequently for 137 Cs, 40 K, 90 Sr, 226 Ra, 228 Ra, plutonium, uranium, total alpha, and total beta, but a few authors also reported data for 241 Am, 7 Be, 60 Co, 55 Fe, 3 H, 131 I, 54 Mn, 95 Nb, 210 Pb, 210 Po, 106 Ru, 125 Sb, 228 Th, 232 Th, and 95 Zr. Based on the reported data it appears that radioactivity from alpha emitters in food crops is usually low, on the order of 0.1 Bq.g -1 (wet weight) or less. Reported values of beta radiation in a given crop generally appear to be several orders of magnitude greater than those of alpha emitters. The most striking aspect of the data is the great range of radioactivity reported for a given nuclide in similar food crops with different geographical origins

Determination of radioactive emission origins based on analyses of isotopic composition

International Nuclear Information System (INIS)

Devell, L.

1987-01-01

The nature of radioactivity emissions can be determined through gamma spectroscopy of air samples with good precision, which means that the type of source of the emission may be found, e.g. nuclear weapons test, of nuclear power plant accident. Combined with information on wind trajectories it is normally possible to recognize time and area for the emission. In this preliminary study, the knowledge of and preparedness for such measurements are described. (L.E.)

Generation projection of solid and liquid radioactive wastes and spent radioactive sources in Mexico

International Nuclear Information System (INIS)

Garcia A, E.; Hernandez F, I. Y.; Fernandez R, E.; Monroy G, F.; Lizcano C, D.

2014-10-01

This work is focused to project the volumes of radioactive aqueous liquid wastes and spent radioactive sources that will be generated in our country in next 15 years, solids compaction and radioactive organic liquids in 10 years starting from the 2014; with the purpose of knowing the technological needs that will be required for their administration. The methodology involves six aspects to develop: the definition of general objectives, to specify the temporary horizon of projection, data collection, selection of the prospecting model and the model application. This approach was applied to the inventory of aqueous liquid wastes, as well as radioactive compaction organic and solids generated in Mexico by non energy applications from the 2001 to 2014, and of the year 1997 at 2014 for spent sources. The applied projection models were: Double exponential smoothing associating the tendency, Simple Smoothing and Lineal Regression. For this study was elected the first forecast model and its application suggests that: the volume of the compaction solid wastes, aqueous liquids and spent radioactive sources will increase respectively in 152%, 49.8% and 55.7%, while the radioactive organic liquid wastes will diminish in 13.15%. (Author)

Characterization of the solid radioactive waste from Cernavoda NPP

International Nuclear Information System (INIS)

Iordache, M.; Lautaru, V.; Bujoreanu, D.

2005-01-01

During the operation of a nuclear plant significant quantities of radioactive waste result that have a very large diversity. At Cernavoda NPP large amounts of wastes are either non-radioactive wastes or radioactive wastes, each of these being managed completely different from each other. For a CANDU type reactor, the occurrence of radioactive wastes is due to contamination with the following types of radioactive substances: - fission products resulting from nuclear fuel burning; - activated products from materials composing the technological systems; - activated products in process fluids. Radioactive wastes can be in solid, liquid or gas form. At Cernavoda NPP the solid wastes represent about 70% of the waste volume which is produced during plant operation and as a consequence of maintenance and decontamination operations. The most important types of solid wastes that are obtained and then handled, processed (if necessary) and temporarily stored are: solid low-level radioactive wastes (classified as compactible and non-compactible), solid medium radioactive wastes, spent resins, used filters and filter cartridges. The liquid radioactive waste class includes organic liquids (used oil, scintillator liquids and used solvents) and aqueous wastes resulting from process system operating, from decontamination and maintenance operations. Radioactive gas wastes occur subsequently to the fission process inside the fuel elements as well as due to the neutron activation of process fluids in the reactor systems. As result of plant operation, iodine, noble gases, tritium and radioactive particles occur and are passed toward the ventilation stack in a controlled manner so that environmental release of radioactive materials with concentrations exceeding the maximum permissible level could not occur. (authors)

Using meta-analytic path analysis to test theoretical predictions in health behavior: An illustration based on meta-analyses of the theory of planned behavior

OpenAIRE

Hagger, Martin; Chan, Dervin K. C.; Protogerou, Cleo; Chatzisarantis, Nikos L. D.

2016-01-01

Objective Synthesizing research on social cognitive theories applied to health behavior is an important step in the development of an evidence base of psychological factors as targets for effective behavioral interventions. However, few meta-analyses of research on social cognitive theories in health contexts have conducted simultaneous tests of theoretically-stipulated pattern effects using path analysis. We argue that conducting path analyses of meta-analytic effects among constructs fr...

Sponsored research on radioactive waste management

International Nuclear Information System (INIS)

1983-01-01

The report is in chapters entitled: introduction (background, responsibilities, options, structure of the programme); strategy development; disposal of accumulations; disposal of radioactive waste arisings; quality assurance for waste conditioning quality assurance related to radioactive waste disposal (effectiveness of different rock types as natural barriers to the movement of radioactivity, and non-site specific factors in the design of repositories; radiological assessment; environmental studies; research and development to meet requirements specific to UKAEA wastes; long term research (processes for the solidification of highly active liquid wastes); plutonium contamination waste minimisation. (U.K.)

Comparison of selected DOE and non-DOE requirements, standards, and practices for Low-Level Radioactive Waste Disposal

International Nuclear Information System (INIS)

Cole, L.; Kudera, D.; Newberry, W.

1995-12-01

This document results from the Secretary of Energy's response to Defense Nuclear Facilities Safety Board Recommendation 94--2. The Secretary stated that the US Department of Energy (DOE) would ''address such issues as...the need for additional requirements, standards, and guidance on low-level radioactive waste management. '' The authors gathered information and compared DOE requirements and standards for the safety aspects Of low-level disposal with similar requirements and standards of non-DOE entities

Environmental radioactivity networks in Italy, 1994-1997

International Nuclear Information System (INIS)

Belli, M.; Notaro, M.; Rosamilia, S.; Sansone, U.

1999-01-01

This report contains the environmental radioactivity data collected in Italy from 1994 to 1997 by the National Environmental Radioactivity Networks of Italy. The National Environmental Protection Agency (ANPA) is law-fully responsible for publishing the environmental and dietary contamination data, provided by the organisations participating to the National Environmental Radioactivity Networks. The complete list of the participants is reported at the end of the present document. The National Environmental Radioactivity Networks of Italy are aimed at survey of the pattern of environmental and dietary contamination in order to assess the radiation doses which the Italian population may receive. The sampling networks have been designed on regional basis, to provide information on the average extent of environmental and dietary contamination. The sampling programmes are planned to obtain representative samples able to reveal the average situation both in time and space. To guarantee that the laboratories of the organisations participating to the National Environmental Radioactivity Networks, perform measurements with a certain degree of accuracy and maintain the quality of their systems, the National Environmental Protection Agency organises yearly an intercalibration programme of the analytical methods used for measuring radioactivity in food and environmental samples. The calibration programme is performed with the collaboration of the National Institute of Ionising Radiation Metrology (ENEA). Routine tests with transfer standards are used for accurate calibration, so that the results can be traceable to a common reference point [it

Control System Radioactive Contamination in Food Samples in Poland

International Nuclear Information System (INIS)

Grabowski, D.; Kurowski, W.; Muszynski, W.; Rubel, B.; Smagala, G.; Swietochowska, J.

2001-01-01

Full text: The analyses of the level of radioactive contamination in food samples are carried out by the Service for Measurements of Radioactive Contamination (SMRC) in Poland. The Service was brought into existence in 1961. The Service comprises of a network of measurement stations and the Centre of Radioactive Contamination Measurements (CRCM). The duty of the Centre is being executed by the Central Laboratory for Radiological Protection (CLRP). The uniform methods of sampling are used in measurement stations. All important foodstuff: milk, meat, vegetables, fruit, cereals are controlled in the Service stations. The radiochemical and spectrometric methods are used to determine the activity of radioactive isotopes. The standard equipment of the measurement station is the measurement system type SAPOS-90 and multichannel analyser with scintillation or germanium detector. The structure of the Service, kinds of samples tested by each station, program of sampling in normal and during accident situation are presented in this paper. (author)

Radioactivity control after Fukushima accident

International Nuclear Information System (INIS)

Vukovic, D.; Mitrovic, R.; Vicentijevic, M.; Pantelic, G.

2011-01-01

Fukushima nuclear accident has influence on more attention when radioactivity of fish were controlled. Sea fish, freshwater fish, fish products and fish flour were analysed ( 95 samples). All products were safe for use with radiation-hygienic aspects. [sr

Geochemistry and mineralogy of the radioactive minerals associated with some pegmatite veins of the Ukma-Nawahatu Hursi sector, Purulia district, W.B., in the Precambrian Chhotanagpur Gneissic complex

International Nuclear Information System (INIS)

Baidya, Tapan Kumar

2014-01-01

Some barite-bearing pegmatites in the Ukma-Nawahatu-Hursi sector (23° 25 min - 26 sec N, 86° 02 min - 04 sec E) in Purulia dist., West Bengal, have association of radioactive minerals in the form of coarse-grained pitchblack lumps and irregular patches. The present author and his associates first reported the occurrence of this radioactive belt along a ENE-WSW shearzone during their fieldwork in November, 1978. Groundborne radiometric survey and isorad mapping has established a radioactive high zone of about 15 km length running through Ukma, Nawahatu and Hursi areas. Mineralogical studies of the radioactive minerals have revealed the occurrence of Chevkinite, Aeschynite, Brannerite, Allanite, Uraninite, Tyuyamunite, Davidite, Euxenite, Samarskite, Thorutite, Autunite, Cerianite, in association with quartz, barite, microcline as the principal minerals and various minor minerals like biotite, vermiculite, hornblende, augite, orthoclase, celsian, muscovite, calcite, epidote, zoisite, ilmenite, sphene, rutile, hematite, magnetite, anatase, galena and sodic plagioclase. The barite-bearing pegmatites occur as lenses or lenticular veins hosted by garnetiferous sillimanite-biotite-quartz-schist or occasionally by migmatite. Near Nawahatu the radioactive barite-pegmatite vein occurs at or near the junction between the footwall amphibolite and hangingwall garnetiferous schist. The pegmatite veins have followed mainly schistosity of the host rock and dip at 70°-80° towards south. Chemical analyses of individual radioactive minerals by SEM-EDX and also of the bulk radioactive lumps by ICP-MS have shown significant concentration of U, Tb and Rare earths. Minor and trace element analyses also record notable contents of Zr, Ga, Sc, Pb, Zn, Nb, Cu, Ni, V, Cr, As, W, Pd, Ag and TI. Details of chemical analytical data are presented here. Chemically active fluids generated during metamorphism, metasomatism and granitic activity appear to have played a significant role in the

Finite element code FENIA verification and application for 3D modelling of thermal state of radioactive waste deep geological repository

Science.gov (United States)

Butov, R. A.; Drobyshevsky, N. I.; Moiseenko, E. V.; Tokarev, U. N.

2017-11-01

The verification of the FENIA finite element code on some problems and an example of its application are presented in the paper. The code is being developing for 3D modelling of thermal, mechanical and hydrodynamical (THM) problems related to the functioning of deep geological repositories. Verification of the code for two analytical problems has been performed. The first one is point heat source with exponential heat decrease, the second one - linear heat source with similar behavior. Analytical solutions have been obtained by the authors. The problems have been chosen because they reflect the processes influencing the thermal state of deep geological repository of radioactive waste. Verification was performed for several meshes with different resolution. Good convergence between analytical and numerical solutions was achieved. The application of the FENIA code is illustrated by 3D modelling of thermal state of a prototypic deep geological repository of radioactive waste. The repository is designed for disposal of radioactive waste in a rock at depth of several hundred meters with no intention of later retrieval. Vitrified radioactive waste is placed in the containers, which are placed in vertical boreholes. The residual decay heat of radioactive waste leads to containers, engineered safety barriers and host rock heating. Maximum temperatures and corresponding times of their establishment have been determined.

Environmental radioactivity in Canada 1973-1976

International Nuclear Information System (INIS)

1979-03-01

The radiological surveillance program of the Department of National Health and Welfare is conducted for the purpose of determining levels of environmental radioactivity in Canada and assessing the resulting population exposures. This report summarizes the results obtained during 1973-1976 from the analyses of air, precipitation, water vapour, drinking water, milk, biota and bone for critical radionuclides. During this period, all radioactivity levels were below the maximum permissible limits recommended by the International Commission on Radiological Protection. (Auth)

Releases of radioactivity at the Savannah River Plant, 1954--1985

International Nuclear Information System (INIS)

Zeigler, C.C.; Lawrimore, I.B.

1988-07-01

Radioactive releases from Savannah River Plant (SRP) facilities to air, water and earthen seepage basins have been monitored and tabulated throughout the history of the site. The purpose of this report is to provide a source of data on routine releases of radioactivity to air, water and seepage basins that can be used for analyses of trends, environmental impact, etc. As used in this report, routine radioactive releases means radioactive materials that are released through established effluents from process facilities. This report provides a summary of radioactive releases that inflects the release values contained m records and documents from startup through 1985

Safe management of smoke detectors containing radioactive sources

International Nuclear Information System (INIS)

Salgado, M.; Benitez, J.C.; Castillo, R.A.; Berdellans, A.; Hernandez, J.M.; Pirez, C.J.; Soto, P.G.

2013-01-01

Ionic smoke detectors contain radioactive sources that could be Am-241, Pu-238, Pu-239, Kr-85, etc. According to Cuban regulations (Resolution 96 /2003 of the Minister of Science Technology and Environment), smoke detectors, once become disused, should be managed as radioactive waste. For this reason, disused smoke detectors should be transferred to the Centre for Radiation Protection and Hygiene, the organization responsible for radioactive waste management in the country. More than 20 000 smoke detectors have been collected by the CPHR and stored at the Centralized Waste Management Facility. There are 28 different models of smoke detectors of different origin. They contain between 18 - 37 kBq of Am-241 or between 0.37 - 37 MBq of Plutonium or around 37 MBq of Kr-85. The safe management of ionic smoke detectors consists in dismantling the devices, recovering the radioactive sources and conditioning them for long term storage and disposal. The rest of non-radioactive materials should be segregated (plastic, metal and electronic components) for recycling. A technical manual was developed with specific instructions for dismantling each model of smoke detector and recovering the radioactive sources. Instructions for segregation of non-radioactive components are also included in the manual. Most of smoke detectors contain long lived radioactive sources (Am-241, Pu-238, Pu-239), so especial attention was given to the management of these sources. A methodology was developed for conditioning of radioactive sources, consisting in encapsulating them for long term storage. The retrievability of the sources (sealed capsules with radioactive sources) for future disposal was also considered. A documented procedure was elaborated for these operations. (author)

Ambient radioactivity levels and radiation doses. Annual report 2014; Umweltradioaktivitaet und Strahlenbelastung. Jahresbericht 2014

Energy Technology Data Exchange (ETDEWEB)

Trugenberger-Schnabel, Angela; Loebke-Reinl, Angelika; Peter, Josef (comps.) [Bundesamt fuer Strahlenschutz, Salzgitter (Germany)

2016-08-15

The annual report 2014 on ambient radioactivity levels and radiation doses covers the following topics: (1) Actual data and their evaluation: natural environmental radioactivity, artificial environmental radioactivity, occupational radiation exposure, radiation exposures from medical applications, handling of radioactive materials and sources of ionizing radiation, non-ionizing radiation. (2) Fundamentals and general information: legal basis and explanations, basic information on natural environmental radioactivity, basic information on artificial radioactivity in the environment, basic information on occupational radiation exposure, basic information on radiation exposures from medical applications, basic information on the handling of radioactive materials and sources of ionizing radiation, basic information on non-ionizing radiation. (3) Tables.

Development of system for management of radioactive waste from non-nuclear application in Russia

International Nuclear Information System (INIS)

Barinov, A.

2000-01-01

The 'Radon' system serves for collecting, transporting, conditioning and disposal of radioactive waste with low and intermediate level activity and spent ionizing sources. The technical policy in this field is embodied most completely in the 'Concept of RF Minatom on radioactive waste management', which outlines the activities till 2025. The main organizational and technical measures in enhancing safety in the process of radioactive waste management as well as the organization of radiation control are described. The main statements of the quality assurance programme for the radioactive waste management are presented

Development of system for management of radioactive waste from non-nuclear application in Russia

Energy Technology Data Exchange (ETDEWEB)

Barinov, A [SIA ' Radon' , Moskow (Russian Federation)

2000-07-01

The 'Radon' system serves for collecting, transporting, conditioning and disposal of radioactive waste with low and intermediate level activity and spent ionizing sources. The technical policy in this field is embodied most completely in the 'Concept of RF Minatom on radioactive waste management', which outlines the activities till 2025. The main organizational and technical measures in enhancing safety in the process of radioactive waste management as well as the organization of radiation control are described. The main statements of the quality assurance programme for the radioactive waste management are presented.

Ionization profile of beta radiation from radioactive cloud

International Nuclear Information System (INIS)

Vujovic, M.; Vojvodic, V.

1978-01-01

A method for calculation of the ionization profile induced by beta radiation from a radioactive cloud is given. The procedure can be applied for high altitudes of the could (H 75 km) as well as for lower ones, when the thickness of the cloud must be taken into account. The final result is given in the analytical form. (author)

IAEA-MEL's AQCS programme for marine radioactivity measurements

International Nuclear Information System (INIS)

Povinec, P.P.; Gastaud, J.; Pham, M.K.

1999-01-01

The main objectives of the IAEA-MEL's Analytical Quality Control Services (AQCS) for marine radioactivity measurements are discussed and future plans for the organization of intercomparison exercises and the production of certified reference materials are presented. The new developments should also include implementation of quality assurance programmes in Member States' laboratories, training in quality management and accreditation programmes. (author)

Virtual cascade impactors for the collection of radioactive atmospheric aerosols

International Nuclear Information System (INIS)

Berner, A.

1988-01-01

Starting from impaction theory, the properties of virtual impaction stages are discussed and compared to classical impactors. Virtual impaction stages offer the benefit of sampling coarse particles without bouncing and reentrainment, but turbulent mixing affects the performance of virtual stages. Future research should concentrate on special configurations for reducing the effects of turbulent mixing. Virtual impaction stages for sampling radioactive aerosols are to be designed in regard of the analytical requirements, the purpose of the measurements, and the aerosol. Therefore, the aerosol components expected in radioactive aerosols are discussed on the background of the multimodal model, which relates the size distribution to the genesis and the history of the aerosol. Reference is made to recent data of the radioactive atmospheric aerosol

A quantification method for peroxyacetyl nitrate (PAN) using gas chromatography (GC) with a non-radioactive pulsed discharge detector (PDD)

Science.gov (United States)

Zhang, Lei; Jaffe, Daniel A.; Gao, Xin; McClure, Crystal D.

2018-04-01

In this study, we developed a method for continuous PAN measurements by gas chromatography (GC) with a non-radioactive pulsed discharge detector (PDD). Operational parameters were optimized based on the ratio of peak height over baseline noise (P/N ratio). The GC/PDD system was compared with a traditional radioactive electron-capture detector (ECD). In the lab, the method detection limit (MDL) of the new GC/PDD method (9 pptv) was lower than the radioactive GC/ECD method (15 pptv), demonstrating its excellent potential. The MDL of GC/PDD in the field campaign at the Mt. Bachelor Observatory (MBO) was 23 pptv, higher than in the lab. This was caused in part by the decreased slope of the calibration curve resulting from the low air pressure level at MBO. However, the MDL level of GC/PDD at MBO is still low enough for accurate PAN measurements, although special attention should be paid to its application at high-elevation sites. Observations of PAN were conducted at MBO in the summer of 2016 with the GC/PDD system, and provided more evidence of the performance of the system. PAN was found to be highly correlated with CO. The promising performance of GC/PDD which does not require a radioactive source makes it a useful approach for accurate PAN measurements in the field.

Radioactive fallout over South Africa during 1974-1983

International Nuclear Information System (INIS)

Brits, R.J.N.; Van der Bank, D.J.; Moolman, E.W.; Bain, C.A.R.; Van As, D.; Van derwesthuizen, G.S.H.

1985-05-01

NUCOR is routinely monitoring air and rainwater for radioactive fallout from atmospheric sources. Air humidity is continuously collected and analysed for tritium. Milk samples are obtained from a number of places throughout the country. These samples are analysed to detect timeously any build-up of radionuclides in soil and plants. Only a few atmosperic nuclear tests have been conducted (by China) since the previous report period of 1965 to 1973. The fallout from these sources over South Africa is extremely small and it is mainly cosmogenic radioactivity, viz 3 H and 7 Be, that is detected

Low-level radioactive waste management options

International Nuclear Information System (INIS)

Schmalz, R.F.

1989-01-01

This paper discusses the non-technical problems associated with the social and political obstacles to the secure disposal of low level radioactive waste. The author reviews thirty years' experience managing non-military wastes. The merits of available options are considered

Screening calculations for radioactive waste releases from non-nuclear facilities

International Nuclear Information System (INIS)

Xu, Shulan; Soederman, Ann-Louis

2009-02-01

A series of screening calculations have been performed to assess the potential radiological consequences of discharges of radioactive substances to the environment arising from waste from non-nuclear practices. Solid waste, as well as liquids that are not poured to the sewer, are incinerated and ashes from incineration and sludge from waste water treatment plants are disposed or reused at municipal disposal facilities. Airborne discharges refer to releases from an incineration facility and liquid discharges refer both to releases from hospitals and laboratories to the sewage system, as well as leakage from waste disposal facilities. The external exposure of workers is estimated both in the waste water treatment plant and at the disposal facility. The calculations follow the philosophy of the IAEA's safety guidance starting with a simple assessment based on very conservative assumptions which may be iteratively refined using progressively more complex models, with more realistic assumptions, as necessary. In the assessments of these types of disposal, with cautious assumptions, carried out in this report we conclude that the radiological impacts on representative individuals in the public are negligible in that they are small with respect to the target dose of 10 μSv/a. A Gaussian plume model was used to estimate the doses from airborne discharges from the incinerator and left a significant safety margin in the results considering the conservative assumptions in the calculations. For the sewage plant workers the realistic approach included a reduction in working hours and the shorter exposure time resulted in maximum doses around 10 μSv/a. The calculations for the waste disposal facility show that the doses are higher or in the range of the target dose. The excess for public exposure is mainly caused by H-3 and C-14. The assumption used in the calculation is that all of the radioactive substances sent to the incineration facility and waste water treatment plant

Screening calculations for radioactive waste releases from non-nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Shulan Xu; Soederman, Ann-Louis

2009-02-15

A series of screening calculations have been performed to assess the potential radiological consequences of discharges of radioactive substances to the environment arising from waste from non-nuclear practices. Solid waste, as well as liquids that are not poured to the sewer, are incinerated and ashes from incineration and sludge from waste water treatment plants are disposed or reused at municipal disposal facilities. Airborne discharges refer to releases from an incineration facility and liquid discharges refer both to releases from hospitals and laboratories to the sewage system, as well as leakage from waste disposal facilities. The external exposure of workers is estimated both in the waste water treatment plant and at the disposal facility. The calculations follow the philosophy of the IAEA's safety guidance starting with a simple assessment based on very conservative assumptions which may be iteratively refined using progressively more complex models, with more realistic assumptions, as necessary. In the assessments of these types of disposal, with cautious assumptions, carried out in this report we conclude that the radiological impacts on representative individuals in the public are negligible in that they are small with respect to the target dose of 10 muSv/a. A Gaussian plume model was used to estimate the doses from airborne discharges from the incinerator and left a significant safety margin in the results considering the conservative assumptions in the calculations. For the sewage plant workers the realistic approach included a reduction in working hours and the shorter exposure time resulted in maximum doses around 10 muSv/a. The calculations for the waste disposal facility show that the doses are higher or in the range of the target dose. The excess for public exposure is mainly caused by H-3 and C-14. The assumption used in the calculation is that all of the radioactive substances sent to the incineration facility and waste water treatment

Environmental radioactivity in Canada 1986

International Nuclear Information System (INIS)

1987-01-01

The radiological surveillance program of the Department of National Health and Welfare is conducted for the purpose of determining levels of environmental radioactivity in Canada and assessing the resulting population exposures. During 1986 the program was strongly influenced by radioactive fallout on Canada resulting from the Chernobyl nuclear reactor accident on April 26, 1986 in the Soviet Ukraine. The Environmental Radiation Hazards Division (ERHD) increased its frequency of analyses of environmental samples immediately following the accident. Interim screening limits for foodstuffs were developed. A measurement program for radioactivity in domestic and imported foods was implemented. The ERHD measurement program was supplemented by additional measurements conducted by many other private and government laboratories. Radiation doses to Canadian from Chernobyl fallout were extremely low with no group in the population receiving more than 10 microsieverts

Characterization of the solid radioactive waste From Cernavoda NPP

International Nuclear Information System (INIS)

Iordache, M.; Laotaru, V.

2005-01-01

Full text: During the operation of a nuclear plant significant quantities of radioactive waste result that have a very large diversity. At Cernavoda NPP large amounts of wastes are either non-radioactive wastes or radioactive wastes, each of these being managed completely different from which other. For a CANDU type reactor, the appearance of radioactive wastes is due to contamination with the following types of radioactive substances: - fission products resulting from nuclear fuel burning; - activated products from materials composing the technological systems; - activated products in process fluids. Radioactive wastes can be in solid, liquid or gas form. At Cernavoda NPP the solid wastes represent about 70% of the waste volume which is produced during plant operation and as a consequence of maintenance and decontamination operations. The most important types of solid wastes that are obtained and then handled, processed (if necessary) and temporarily stored are: solid low-level radioactive wastes (classified as compactible and non-compactible), solid medium radioactive wastes, spent resins, used filters and filter cartridges. The liquid radioactive waste class includes organic liquids (used oil, scintillator liquids and used solvents) and aqueous wastes resulting from process system operating, from decontamination and maintenance operations. Radioactive gas wastes occur subsequently to the fission process inside the fuel elements as well as due to the neutron activation of process fluids in the reactor systems. As result of plant operation, iodine, noble gases, tritium and radioactive particles occur and are passed toward the ventilation stack in a controlled manner so that environmental release of radioactive materials with concentrations exceeding the maximum permissible level could not occur. (authors)

Proposed goals for radioactive waste management

International Nuclear Information System (INIS)

Bishop, W.P.; Frazier, D.H.; Hoos, I.R.; McGrath, P.E.; Metlay, D.S.; Stoneman, W.C.; Watson, R.A.

1977-04-01

Goals are proposed for the national radioactive waste management program to establish a policy basis for the guidance and coordination of the activities of government, business, and academic organizations whose responsibility it will be to manage radioactive wastes. The report is based on findings, interpretations, and analyses of selected primary literature and interviews of personnel concerned with waste management. Public concerns are identified, their relevance assessed, and a conceptual framework is developed that facilitates understanding of the dimensions and demands of the radioactive waste management problem. The nature and scope of the study are described along with the approach used to arrive at a set of goals appropriately focused on waste management

Computerized Analytical Data Management System and Automated Analytical Sample Transfer System at the COGEMA Reprocessing Plants in La Hague

International Nuclear Information System (INIS)

Flament, T.; Goasmat, F.; Poilane, F.

2002-01-01

Managing the operation of large commercial spent nuclear fuel reprocessing plants, such as UP3 and UP2-800 in La Hague, France, requires an extensive analytical program and the shortest possible analysis response times. COGEMA, together with its engineering subsidiary SGN, decided to build high-performance laboratories to support operations in its plants. These laboratories feature automated equipment, safe environments for operators, and short response times, all in centralized installations. Implementation of a computerized analytical data management system and a fully automated pneumatic system for the transfer of radioactive samples was a key factor contributing to the successful operation of the laboratories and plants

Use of Eichornia crassipes for treatment of low level liquid radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Hafez, N.; Ramadan, Y.S.; Hassanin, R.A.; Gafez, M.B. (Atomic Energy Authority, Hot Lab. Center, Cairo (Egypt))

1993-01-01

Radioactive and non-radioactive isotopes of cobalt, cerium and cesium were found to be accumulated inside Eichornia crassipes (the water hyacinth). The rate and extent of accumulation were dependent upon environmental parameters such as pH, temperature and interference by certain anions and cations. The accumulation rate of radioactive isotopes inside Eichornia crassipes, were more rapid than non-active ions. The results showed that accumulation of such metals inside the plant could be used successfully in the treatment of low-level liquid radioactive wastes. (author) 4 figs., 2 tabs., 15 refs.

Use of Eichornia crassipes for treatment of low level liquid radioactive waste

International Nuclear Information System (INIS)

Hafez, N.; Ramadan, Y.S.; Hassanin, R.A.; Gafez, M.B.

1993-01-01

Radioactive and non-radioactive isotopes of cobalt, cerium and cesium were found to be accumulated inside Eichornia crassipes (the water hyacinth). The rate and extent of accumulation were dependent upon environmental parameters such as pH, temperature and interference by certain anions and cations. The accumulation rate of radioactive isotopes inside Eichornia crassipes, were more rapid than non-active ions. The results showed that accumulation of such metals inside the plant could be used successfully in the treatment of low-level liquid radioactive wastes. (author) 4 figs., 2 tabs., 15 refs

Methods for Characterisation of unknown Suspect Radioactive Samples

International Nuclear Information System (INIS)

Sahagia, M.; Grigorescu, E.L.; Luca, A.; Razdolescu, A.C.; Ivan, C.

2001-01-01

Full text: The paper presents various identification and measurement methods, used for the expertise of a wide variety of suspect radioactive materials, whose circulation was not legally stated. The main types of examined samples were: radioactive sources, illegally trafficked; suspect radioactive materials or radioactively contaminated devices; uranium tablets; fire detectors containing 241 Am sources; osmium samples containing radioactive 185 Os or enriched 187 Os. The types of analyses and determination methods were as follows: the chemical composition was determined by using identification reagents or by neutron activation analysis; the radionuclide composition was determined by using gamma-ray spectrometry; the activity and particle emission rates were determined by using calibrated radiometric equipment; the absorbed dose rate at the wall of all types of containers and samples was determined by using calibrated dose ratemeters. The radiation exposure risk for population, due to these radioactive materials, was evaluated for every case. (author)

Smartphone Analytics: Mobilizing the Lab into the Cloud for Omic-Scale Analyses.

Science.gov (United States)

Montenegro-Burke, J Rafael; Phommavongsay, Thiery; Aisporna, Aries E; Huan, Tao; Rinehart, Duane; Forsberg, Erica; Poole, Farris L; Thorgersen, Michael P; Adams, Michael W W; Krantz, Gregory; Fields, Matthew W; Northen, Trent R; Robbins, Paul D; Niedernhofer, Laura J; Lairson, Luke; Benton, H Paul; Siuzdak, Gary

2016-10-04

Active data screening is an integral part of many scientific activities, and mobile technologies have greatly facilitated this process by minimizing the reliance on large hardware instrumentation. In order to meet with the increasingly growing field of metabolomics and heavy workload of data processing, we designed the first remote metabolomic data screening platform for mobile devices. Two mobile applications (apps), XCMS Mobile and METLIN Mobile, facilitate access to XCMS and METLIN, which are the most important components in the computer-based XCMS Online platforms. These mobile apps allow for the visualization and analysis of metabolic data throughout the entire analytical process. Specifically, XCMS Mobile and METLIN Mobile provide the capabilities for remote monitoring of data processing, real time notifications for the data processing, visualization and interactive analysis of processed data (e.g., cloud plots, principle component analysis, box-plots, extracted ion chromatograms, and hierarchical cluster analysis), and database searching for metabolite identification. These apps, available on Apple iOS and Google Android operating systems, allow for the migration of metabolomic research onto mobile devices for better accessibility beyond direct instrument operation. The utility of XCMS Mobile and METLIN Mobile functionalities was developed and is demonstrated here through the metabolomic LC-MS analyses of stem cells, colon cancer, aging, and bacterial metabolism.

Results of radioactivity measurements on foodstuffs in Romania

International Nuclear Information System (INIS)

Ferdes, O.; Cojocariu, T.

1996-01-01

There are presented the results of gamma-spectrometric measurements performed between 1986-1995 on: milk and dairy products; meat and meat products; fish; wheat flour; fresh fruits and vegetables. The foodstuffs are sampled from some representative areas like: Bucharest, Bechet (affected by Kozloduj NPP, Bulgaria), Cernavoda, middle of Transylvania, Neamt. The radioactivity measurements are performed by high-resolution γ-ray spectrometry. There are identified and analysed mainly 134 Cs, 137 Cs, 40 K and, sometimes, other radionuclides. There are pointed out: the constancy of natural radionuclides amounts; the drastic increasing in radioactive concentration in May 1986; the seasonal variation of radioactivity in some food items; the time - exponential diminution of radioactivity in 1991-1995; and the maximum permitted levels of radioactive contamination of foodstuffs following a nuclear accident. (author)

Radioactive sedimentary deposits concerning the coasts of the Camargue

International Nuclear Information System (INIS)

2000-01-01

CRII-RAD has detected abnormal levels of radioactivity on some beaches situated near the Espiguette lighthouse in the south-east coast of France. This document presents the in-situ measurements performed by IPSN. These results confirm a relevant increase of gamma radiation in sedimentary deposits. Chemical analyses have shown that this radioactivity is due to potassium 40 and radionuclides from thorium and uranium series. There is no doubt about the natural origin of this radioactivity but thorough geo-chemical studies are necessary to see whether these radioactive sands are a consequence of nearby industrial activities concerning ore dressing. (A.C.)

Electromagnetic imaging of multiple-scattering small objects: non-iterative analytical approach

International Nuclear Information System (INIS)

Chen, X; Zhong, Y

2008-01-01

Multiple signal classification (MUSIC) imaging method and the least squares method are applied to solve the electromagnetic inverse scattering problem of determining the locations and polarization tensors of a collection of small objects embedded in a known background medium. Based on the analysis of induced electric and magnetic dipoles, the proposed MUSIC method is able to deal with some special scenarios, due to the shapes and materials of objects, to which the standard MUSIC doesn't apply. After the locations of objects are obtained, the nonlinear inverse problem of determining the polarization tensors of objects accounting for multiple scattering between objects is solved by a non-iterative analytical approach based on the least squares method

Truck transportation of radioactive materials

International Nuclear Information System (INIS)

Madsen, M.M.; Wilmot, E.L.

1983-01-01

Analytical models in RADTRAN II are used to calculate risks to population subgroups such as people along transport routes, people at stops, and crewman. The stops model, which calculates the dose to persons adjacent to the transport vehicle while it is stopped, frequently provides the largest contribution to incident-free radiological impacts. Components such as distances from the vehicle containing radioactive material to nearby people at stops, stop duration, and number of crew members are required for the stops model as well as other incident-free models. To provide supporting data for RADTRAN II based on operational experience, selected truck shipments of radioactive material were observed from origin to destination. Other important aspects of this program were to correlate package size to effective shipment transport index (TI) using radiological surveys and to characterize population distributions and proximities of people to the shipment at a generic truck stop

Radioactivity in foodstuffs 1988

International Nuclear Information System (INIS)

1989-01-01

The average radioactivity dose level to which the Norwegian population was exposed through the ingestion of food in 1988 was between 0.10 and 0.15 mSv. This was about the same as in 1987. The radioactivity dose to which individuals with certain special dietary habits (large proportions of freshwater fish and reindeer meat in the diet) were exposed, was, however, up to three times higher in 1988 than in 1987. This was due firstly to the fact that reindeer meat which had been produced prior to the Chernobyl accident was no longer available, and secondly, to dietary advice not being followed as closely as before. The cost-benefit ratio of the measures introduced to reduce radioactivity levels in food, i.e. resources employed compared with the actual reduction in radioactivity levels achieved, has proved to be reasonably satisfactory, both in 1987 and 1988. Action levels and dietary advice remained unchanged in 1988. The present report summarizes results of analyses performed in 1988, and describes the measures introduced concerning various categorites of foods. Measures introduced were, as in 1987, primarily focused on the production of sheep meat (mutton/lamb) and on reindeer farming. 4 figs., 1 tab

Radioactivity in food crops

Energy Technology Data Exchange (ETDEWEB)

Drury, J.S.; Baldauf, M.F.; Daniel, E.W.; Fore, C.S.; Uziel, M.S.

1983-05-01

Published levels of radioactivity in food crops from 21 countries and 4 island chains of Oceania are listed. The tabulation includes more than 3000 examples of 100 different crops. Data are arranged alphabetically by food crop and geographical origin. The sampling date, nuclide measured, mean radioactivity, range of radioactivities, sample basis, number of samples analyzed, and bibliographic citation are given for each entry, when available. Analyses were reported most frequently for /sup 137/Cs, /sup 40/K, /sup 90/Sr, /sup 226/Ra, /sup 228/Ra, plutonium, uranium, total alpha, and total beta, but a few authors also reported data for /sup 241/Am, /sup 7/Be, /sup 60/Co, /sup 55/Fe, /sup 3/H, /sup 131/I, /sup 54/Mn, /sup 95/Nb, /sup 210/Pb, /sup 210/Po, /sup 106/Ru, /sup 125/Sb, /sup 228/Th, /sup 232/Th, and /sup 95/Zr. Based on the reported data it appears that radioactivity from alpha emitters in food crops is usually low, on the order of 0.1 Bq.g/sup -1/ (wet weight) or less. Reported values of beta radiation in a given crop generally appear to be several orders of magnitude greater than those of alpha emitters. The most striking aspect of the data is the great range of radioactivity reported for a given nuclide in similar food crops with different geographical origins.

National inventory of radioactive wastes and valorizable materials. Synthesis report; Inventaire national des dechets radioactifs et des matieres valorisables. Rapport de synthese

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

This national inventory of radioactive wastes is a reference document for professionals and scientists of the nuclear domain and also for any citizen interested in the management of radioactive wastes. It contains: 1 - general introduction; 2 - the radioactive wastes: definition, classification, origin and management; 3 - methodology of the inventory: organization, accounting, prospective, production forecasting, recording of valorizable materials, exhaustiveness, verification tools; 4 - general results: radioactive waste stocks recorded until December 31, 2002, forecasts for the 2003-2020 era, post-2020 prospects: dismantling operations, recording of valorizable materials; 5 - inventory per producer or owner: front-end fuel cycle facilities, power generation nuclear centers, back-end fuel cycle facilities, waste processing or maintenance facilities, civil CEA research centers, non-CEA research centers, medical activities (diagnostics, therapeutics, analyses), various industrial activities (sources fabrication, control, particular devices), military research and experiment centers, storage and disposal facilities; 6 - elements about radioactive polluted sites; 7 - examples of foreign inventories; 8 - conclusion and appendixes. (J.S.)

Potential effects on health of radioactive waste disposal

International Nuclear Information System (INIS)

Sousselier, Y.; Parmentier, N.

1983-07-01

Radioactive waste is considered to represent a potential health risk for future generation by a section of the public. The main point is that waste management must follow very strict guidelines. The radioactive waste treatment, packaging and disposal are rewieved and discussed from a safety point of view. Health physics aspects are then analysed. The major difficulties for the prediction of exposure are mainly due to the very long time periods involved. Models are studied and carried out for the prediction of radiological consequences for the transport of radioactivity through the different modules

Latest developments in the predisposal of radioactive waste at the radioactive waste management department from ifin-hh

International Nuclear Information System (INIS)

Dragolici, F.; Dogaru, G.; Neacsu, E.

2016-01-01

The Radioactive Waste Management Department (DMDR) from IFIN-HH has a wide experience in the management of the non-fuel cycle radioactive wastes from all over Romania generated from nuclear techniques and technologies application, assuring the radiological safety and security of operators, population and environment. During 2011-2015 was implemented a major upgrading programme applied both on the technological systems of the building and on equipment. The paper describes the facility developments having the scope to share to the public and stakeholders the radioactive waste predisposal capabilities available at DMDR-IFIN-HH. As a whole, today DMDR-IFIN-HH represents a complete and complex infrastructure, assuring high quality services in all the steps related to the management of the institutional radioactive waste in Romania. (authors)

7 CFR 98.4 - Analytical methods.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Analytical methods. 98.4 Section 98.4 Agriculture....4 Analytical methods. (a) The majority of analytical methods used by the USDA laboratories to perform analyses of meat, meat food products and MRE's are listed as follows: (1) Official Methods of...

Effect of radioactive chromate on the corrosion and polarisation of mild steel in sodium chloride solution

International Nuclear Information System (INIS)

Subramanyan, N.; Ramakrishnaiah, K.; Iyer, S.V.; Kapali, V.

1980-01-01

Corrosion tests of mild steel in 0.01% sodium chloride containing radioactive chromate and non-radioactive chromate have been carried out. It has been observed that the labelled sodium chromate has a deleterious effect on the inhibitive action of non-radioactive chromate. The effect of radioactive chromate on the potentiostatic polarization of m.s. in sodium chloride solution containing non-radioactive sodium chromate has also been studied. It is observed that both the cathodic and the anodic polarisation of the metal is diminished in the presence of radioactive chromate. The behaviour of the system in the presence of radioactive chromate is attributed both to the action of depolarisers produced by radiolysis of water and to the effect of gamma radiation on the metal. (author)

The performance of the remote analytical laboratory during the first fluorinel dissolution process campaign

International Nuclear Information System (INIS)

Lewis, L.C.; Henscheid, J.P.

1989-01-01

The Remote Analytical Laboratory at the Idaho Chemical Processing Plant was designed to provide analytical chemistry support to the irradiated fuel processing and associated waste processing operations. The facility was put into radioactive operation on July 7, 1986, and operated for more than a year during the first fluorinel fuel dissolution process campaign. The facility incorporated a number of innovative features and was equipped with state-of-the-art analytical instrumentation. The success of the facility is a direct function of how well the remote analytical equipment performed. The performance is discussed in this article

Legal aspects of the maritime transport of radioactive materials: its regulation in Mexico

International Nuclear Information System (INIS)

Aguilar M, S.

2001-01-01

This work has the object to analyse the International as much as National legal frameworks, the scopes and limits of the instruments which form it as well as the congruous that exist between them and the situation which actually prevails in the maritime transport field of radioactive materials in worldwide level and in Mexico taking into account the technical advances, the operational experience and radiological protection principles. In the chapter 1, the background on the uses of nuclear energy are described and its development by more of fifty years. The chapter 2 analyses about the establishment of nuclear technologies in Mexico as well as their evolution in medicine, agriculture, research and electric power generation areas. In chapter 3 it was analysed the role what the International Organizations have been playing for the establish of an International legal framework in the maritime transport of radioactive materials field. In the chapter 4, the International legal framework was analysed which is applied to the transport of radioactive materials. Finally, the chapter 5 analyses and poses the requirements and necessities which lead Mexico to legislate broadly the transport of radioactive materials taking as basis International instruments from which the state is part also from some other agreements is analysed its adhesion to them. (Author)

Radioactivity of the moon, planets, and meteorites

Science.gov (United States)

Surkou, Y. A.; Fedoseyev, G. A.

1977-01-01

Analytical data is summarized for the content of natural radioactive elements in meteorites, eruptive terrestrial rocks, and also in lunar samples returned by Apollo missions and the Luna series of automatic stations. The K-U systematics of samples analyzed in the laboratory are combined with data for orbital gamma-ray measurements for Mars (Mars 5) and with the results of direct gamma-ray measurements of the surface of Venus by the Venera 8 lander. Using information about the radioactivity of solar system bodies and evaluations of the content of K, U, and Th in the terrestrial planets, we examine certain aspects of the evolution of material in the protoplanetary gas-dust cloud and then in the planets of the solar system.

Results of the Interlaboratory Exercise CNS/CIEMAT-05 among Environmental Radioactivity Laboratories (Vegetable Ash)

International Nuclear Information System (INIS)

Romero Gonzalez, M. L.; Barrera Izquierdo, M.; Valino Garcia, F.

2006-01-01

The document describes the outcome of the CSN/CIEMAT-05 interlaboratory test comparison among environmental radioactivity laboratories. The exercise was organised according to the ISO-43 and the IUPAC I nternational harmonised protocol for the proficiency testing of analytical chemistry laboratories . The exercise has been designed to evaluate the capability of national laboratories to determine environmental levels of radionuclides in vegetable ash samples. The sample has been prepared by the Environmental Radiation Laboratory, from the University of Barcelona, and it contains the following radionuclides: Sr-90, Pu-238, Am-241, Th-230, Pb-210, U-238, Ra-226, K-40, Ra-228, TI-208, Cs- 137 and Co-60. Reference values have been established TROUGH the kind collaboration of three international laboratories of recognized experience: IAEA MEL and IRSN-Orsay. The results of the exercise were computed for 35 participating laboratories and their analytical performance was assessed using the z-score approach. Robust statistics of the participant's results was applied to obtain the median and standard deviation, to achieve a more complete and objetiva study of the laboratories' performance. Some difficulties encountered to dissolve the test sample caused a lower response of analyses involving radiochemical separation, thus some laboratories couldn't apply their routine methods and no conclusions on PU-238, Am-241 and Th-230 performances have been obtained. The exercise has revealed an homogeneous behaviour of laboratories, being statistical parameters from the results close to the reference values. The study has shown that participant laboratories perform radioactive determinations in vegetable ash samples with satisfactory quality levels. (Author) 6 refs

Post-Irradiation Non-Destructive Analyses of the AFIP-7 Experiment

Science.gov (United States)

Williams, W. J.; Robinson, A. B.; Rabin, B. H.

2017-12-01

This article reports the results and interpretation of post-irradiation non-destructive examinations performed on four curved full-size fuel plates that comprise the AFIP-7 experiment. These fuel plates, having a U-10 wt.%Mo monolithic design, were irradiated under moderate operating conditions in the Advanced Test Reactor to assess fuel performance for geometries that are prototypic of research reactor fuel assemblies. Non-destructive examinations include visual examination, neutron radiography, profilometry, and precision gamma scanning. This article evaluates the qualitative and quantitative data taken for each plate, compares corresponding data sets, and presents the results of swelling analyses. These characterization results demonstrate that the fuel meets established irradiation performance requirements for mechanical integrity, geometric stability, and stable and predictable behavior.

Safety apparatus for serious radioactive accidents (1962)

International Nuclear Information System (INIS)

Estournel, R.; Rodier, J.

1962-01-01

In the case of a serious radioactive accident, radioactive dust and gases may be released into the atmosphere. It is therefore necessary to be able to evaluate rapidly the importance of the risk to the surrounding population, and to be able to ensure, even in the event of an evacuation of the Centre, the continuation of the radioactivity analyses and the decontamination of the personnel. For this, the Anti-radiation Protection Service at Marcoule has organised mobile detection teams and designed a mobile laboratory and a mobile shower-unit. After describing the duty of the mobile teams, the report gives a description of the apparatus which would be used at the Marcoule Centre in the case of a serious radioactive accident. The method of using this apparatus is given. (authors) [fr

Analytical model development of an eddy-current-based non-contacting steel plate conveyance system

International Nuclear Information System (INIS)

Liu, C.-T.; Lin, S.-Y.; Yang, Y.-Y.; Hwang, C.-C.

2008-01-01

A concise model for analyzing and predicting the quasi-static electromagnetic characteristics of an eddy-current-based non-contacting steel plate conveyance system has been developed. Confirmed by three-dimensional (3-D) finite element analysis (FEA), adequacy of the analytical model can be demonstrated. Such an effective approach, which can be conveniently used by the potential industries for preliminary system operational performance evaluations, will be essential for designers and on-site engineers

Electrodeless light source provided with radioactive material

International Nuclear Information System (INIS)

1979-01-01

Radioactive materials are used to assist in starting a discharge in an electrodeless light source. The radioactive emissions predispose on the inner surface of the lamp envelope loosely bound charges which thereafter assist in initiating discharge. The radioactive material can be enclosed within the lamp envelope in gaseous or non-gaseous form. Preferred materials are krypton 85 and americium 241. In addition, the radioactive material can be dispersed in the lamp envelope material or can be a pellet imbedded in the envelope material. Finally, the radioactive material can be located in the termination fixture. Sources of alpha particles, beta particles, or gamma rays are suitable. Because charges accumulate with time on the inner surface of the lamp envelope, activity levels as low as 10 -8 curie are effective as starting aids. (Auth.)

A kinematic model to estimate the effective dose of radioactive isotopes in the human body for radiological protection

Science.gov (United States)

Sasaki, S.; Yamada, T.

2013-12-01

The great earthquake attacked the north-east area in Japan in March 11, 2011. The system of electrical facilities to control Fukushima Daiichi nuclear power station was completely destroyed by the following tsunamis. From the damaged reactor containment vessels, an amount of radioactive substances had leaked and been diffused in the vicinity of this station. Radiological internal exposure becomes a serious social issue both in Japan and all over the world. The present study provides an easily understandable, kinematic-based model to estimate the effective dose of radioactive substances in a human body by simplified the complicated mechanism of metabolism. International Commission on Radiological Protection (ICRP) has developed an exact model, which is well-known as a standard method to calculate the effective dose for radiological protection. However, owing to that the above method accord too much with the actual mechanism of metabolism in human bodies, it becomes rather difficult for non-professional people of radiology to gasp the whole images of the movement and the influences of radioactive substances in a human body. Therefore, in the present paper we propose a newly-derived and easily-understandable model to estimate the effective dose. The present method is very similar with the traditional and conventional hydrological tank model. Ingestion flux of radioactive substances corresponds to rain intensity and the storage of radioactive substances to the water storage in a basin in runoff analysis. The key of this method is to estimate the energy radiated from the radioactive nuclear disintegration of an atom by using classical theory of E. Fermi of beta decay and special relativity for various kinds of radioactive atoms. The parameters used in this study are only physical half-time and biological half-time, and there are no intentional and operational parameters of coefficients to adjust our theoretical runoff to observation of ICRP. Figure.1 compares time

Analytical solutions for non-linear conversion of a porous solid particle in a gas–I. Isothermal conversion

NARCIS (Netherlands)

Brem, Gerrit; Brouwers, J.J.H.

1990-01-01

Analytical description are presented for non-linear heterogeneous conversion of a porous solid particle reacting with a surrounding gas. Account has been taken of a reaction rate of general order with respect to gas concentration, intrinsic reaction surface area and pore diffusion, which change with

Results of radioactivity measurements on foodstuffs in Romania

Energy Technology Data Exchange (ETDEWEB)

Ferdes, O [National Agency for Atomic Energy, Bucharest (Romania); Cojocariu, T [Institute for Food Research, Bucharest (Romania)

1997-12-31

There are presented the results of gamma-spectrometric measurements performed between 1986-1995 on: milk and dairy products; meat and meat products; fish; wheat flour; fresh fruits and vegetables. The foodstuffs are sampled from some representative areas like: Bucharest, Bechet (affected by Kozloduj NPP, Bulgaria), Cernavoda, middle of Transylvania, Neamt. The radioactivity measurements are performed by high-resolution {gamma}-ray spectrometry. There are identified and analysed mainly {sup 134}Cs, {sup 137}Cs, {sup 40}K and, sometimes, other radionuclides. There are pointed out: the constancy of natural radionuclides amounts; the drastic increasing in radioactive concentration in May 1986; the seasonal variation of radioactivity in some food items; the time - exponential diminution of radioactivity in 1991-1995; and the maximum permitted levels of radioactive contamination of foodstuffs following a nuclear accident. (author). 2 figs., 2 tabs., 8 refs.

Development of analytical cell support for vitrification at the West Valley Demonstration Project. Topical report

Energy Technology Data Exchange (ETDEWEB)

Barber, F.H.; Borek, T.T.; Christopher, J.Z. [and others

1997-12-01

Analytical and Process Chemistry (A&PC) support is essential to the high-level waste vitrification campaign at the West Valley Demonstration Project (WVDP). A&PC characterizes the waste, providing information necessary to formulate the recipe for the target radioactive glass product. High-level waste (HLW) samples are prepared and analyzed in the analytical cells (ACs) and Sample Storage Cell (SSC) on the third floor of the main plant. The high levels of radioactivity in the samples require handling them in the shielded cells with remote manipulators. The analytical hot cells and third floor laboratories were refurbished to ensure optimal uninterrupted operation during the vitrification campaign. New and modified instrumentation, tools, sample preparation and analysis techniques, and equipment and training were required for A&PC to support vitrification. Analytical Cell Mockup Units (ACMUs) were designed to facilitate method development, scientist and technician training, and planning for analytical process flow. The ACMUs were fabricated and installed to simulate the analytical cell environment and dimensions. New techniques, equipment, and tools could be evaluated m in the ACMUs without the consequences of generating or handling radioactive waste. Tools were fabricated, handling and disposal of wastes was addressed, and spatial arrangements for equipment were refined. As a result of the work at the ACMUs the remote preparation and analysis methods and the equipment and tools were ready for installation into the ACs and SSC m in July 1995. Before use m in the hot cells, all remote methods had been validated and four to eight technicians were trained on each. Fine tuning of the procedures has been ongoing at the ACs based on input from A&PC technicians. Working at the ACs presents greater challenges than had development at the ACMUs. The ACMU work and further refinements m in the ACs have resulted m in a reduction m in analysis turnaround time (TAT).

Material model for non-linear finite element analyses of large concrete structures

NARCIS (Netherlands)

Engen, Morten; Hendriks, M.A.N.; Øverli, Jan Arve; Åldstedt, Erik; Beushausen, H.

2016-01-01

A fully triaxial material model for concrete was implemented in a commercial finite element code. The only required input parameter was the cylinder compressive strength. The material model was suitable for non-linear finite element analyses of large concrete structures. The importance of including

An experiment on radioactive equilibrium and its modelling using the ‘radioactive dice’ approach

Science.gov (United States)

Santostasi, Davide; Malgieri, Massimiliano; Montagna, Paolo; Vitulo, Paolo

2017-07-01

In this article we describe an educational activity on radioactive equilibrium we performed with secondary school students (17-18 years old) in the context of a vocational guidance stage for talented students at the Department of Physics of the University of Pavia. Radioactive equilibrium is investigated experimentally by having students measure the activity of 214Bi from two different samples, obtained using different preparation procedures from an uraniferous rock. Students are guided in understanding the mathematical structure of radioactive equilibrium through a modelling activity in two parts. Before the lab measurements, a dice game, which extends the traditional ‘radioactive dice’ activity to the case of a chain of two decaying nuclides, is performed by students divided into small groups. At the end of the laboratory work, students design and run a simple spreadsheet simulation modelling the same basic radioactive chain with user defined decay constants. By setting the constants to realistic values corresponding to nuclides of the uranium decay chain, students can deepen their understanding of the meaning of the experimental data, and also explore the difference between cases of non-equilibrium, transient and secular equilibrium.

Analytical chemistry

Energy Technology Data Exchange (ETDEWEB)

Chae, Myeong Hu; Lee, Hu Jun; Kim, Ha Seok

1989-02-15

This book give explanations on analytical chemistry with ten chapters, which deal with development of analytical chemistry, the theory of error with definition and classification, sample and treatment gravimetry on general process of gravimetry in aqueous solution and non-aqueous solution, precipitation titration about precipitation reaction and types, complexometry with summary and complex compound, oxidation-reduction equilibrium on electrode potential and potentiometric titration, solvent extraction and chromatograph and experiment with basic operation for chemical experiment.

Analytical chemistry

International Nuclear Information System (INIS)

Chae, Myeong Hu; Lee, Hu Jun; Kim, Ha Seok

1989-02-01

This book give explanations on analytical chemistry with ten chapters, which deal with development of analytical chemistry, the theory of error with definition and classification, sample and treatment gravimetry on general process of gravimetry in aqueous solution and non-aqueous solution, precipitation titration about precipitation reaction and types, complexometry with summary and complex compound, oxidation-reduction equilibrium on electrode potential and potentiometric titration, solvent extraction and chromatograph and experiment with basic operation for chemical experiment.

Preparation of radioactive ''mixed'' waste samples for measurement of RCRA [Resource Conservation and Recovery Act] organic compounds

International Nuclear Information System (INIS)

Tomkins, B.A.; Caton, J.E.

1987-01-01

A radioactive ''mixed'' waste typically contains alpha-, beta-, or gamma-emitting radionuclides and varying quantities of semivolatile or volatile organic species, some or all of which may be named specifically by the Resource Conservation and Recovery Act (RCRA). Because there are no acceptable means available currently for disposing of these mixed wastes, they are presently stored above-ground in sealed drums. For this reason, analytical procedures which can determine RCRA organics in radioactive waste are necessary for deciding the proper approach for disposal. An important goal of this work is the development of methods for preparing mixed waste samples in a manner which allows the RCRA organics to be measured in conventional organic analysis laboratories without special precautions. Analytical procedures developed for handling mixed waste samples must satisfy not only the usual constraints present in any trace-level organic chemical determination, but also those needed to insure the protection of the operator from radioactive contamination. Consequently, procedures should be designed to use the least amount of radioactive sample commensurate with achieving acceptable sensitivity with the RCRA analytical methods. Furthermore, the unusual laboratory glassware which would normally be used should be replaced with disposable materials wherever possible, in order to reduce the ''clean-up'' time required, and thereby reduce the operator's exposure to radioactivity. Actual sample handling should be reduced to the absolute minimum. Finally, the final isolate must exhibit a sufficiently low level of alpha, beta, or gamma activity to permit detailed characterization in a conventional organic analysis laboratory. 4 refs., 5 tabs

Response to Illicit Trafficking of Radioactive Materials

International Nuclear Information System (INIS)

2010-01-01

Two response paths are discussed in the presentation. Reactive response follows when an alarm of a border monitor goes off or a notification is received about an incident involving or suspected to involve radioactive materials. The response can also be the result of the finding of a discrepancy between a customs declaration form and the corresponding actual shipment. Proactive response is undertaken upon receipt of intelligence information suggesting the illicit trafficking of radioactive materials, notification about the discovery of non-compliance with transport regulations or if discrepancies are found in an inventory of radioactive materials.

Early detection of radioactive fall-out by gamma-spectrometry

DEFF Research Database (Denmark)

Aage, Helle Karina; Korsbech, Uffe C C; Bargholz, K.

2003-01-01

Radioactive fallout should be detected as early as possible. A new and efficient method for detection of low-level irradiation from manmade radioactivity is developed. Radiation abnormalities are detectable down to air kerma rate, of 0.5 to 1.0 nGy h(-1) for Cs-137 and even lower for I-131...... For multi-gamma energy radioactivity the detection level is 2.6-3.5 nGy h(-1). A standard NaI detector and a 512-channel analyser are used together with noise adjusted singular value decomposition (NASVD). Statistical noise is removed and the measured spectra are reproduced using spectral components...... radioactive sources need to be detected....

Establishing community trust at radioactively contaminated sites

International Nuclear Information System (INIS)

Simpson, E.

1999-01-01

Establishing community trust is an essential element in the successful remediation of a radioactively contaminated site. The US Environmental Protection Agency (EPA), Region 2 has been involved in the clean up of numerous radioactively contaminated Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), Resource Conservation Recovery Act (RCRA), and Formerly Utilized Site Remedial Action Program (FUSRAP) sites in New Jersey and New York. Each site presented a unique challenge which centered around establishing and, often, re-establishing the trust of the surrounding community. Thanks to the United States government's history regarding the use of radioactive materials, people question whether governmental regulators could possibly have the public's best interests in mind when it comes to addressing radioactively contaminated sites. It has been our experience that EPA can use its position as guardian of the environment to help establish public confidence in remedial actions. The EPA can even use its position to lend credibility to remedial activities in situations where it is not directly responsible for the clean-up. Some ways that we have found to instill community confidence are: establishing radioanalytical cross-check programs using EPA's National Air and Radiation Environmental Laboratory to provide analytical quality assurance; and establishing an environmental radiation monitoring program for the contaminated site and surrounding community. (author)

Review and evaluation of spark source mass spectrometry as an analytical method

International Nuclear Information System (INIS)

Beske, H.E.

1981-01-01

The analytical features and most important fields of application of spark source mass spectrometry are described with respect to the trace analysis of high-purity materials and the multielement analysis of technical alloys, geochemical and cosmochemical, biological and radioactive materials, as well as in environmental analysis. Comparisons are made to other analytical methods. The distribution of the method as well as opportunities for contract analysis are indicated and developmental tendencies discussed. (orig.) [de

An analytical expression for the non-singlet structure functions at small χ in the double logarithmic approximation

International Nuclear Information System (INIS)

Lublinsky, M.

2004-01-01

A simple analytic expression for the non-singlet structure function fns is given. The expression is derived from the result of B. I. Ermolaev et al. (1996) obtained by low x resummation of the quark ladder diagrams in the double logarithmic approximation of perturbative QCD. (orig.)

IAEA mode-related research in the safe transport of radioactive material

Energy Technology Data Exchange (ETDEWEB)

Blalock, L.G.; Rawl, R.R. [International Atomic Energy Agency, IAEA, Vienna (Austria)

1998-07-01

The International Atomic Energy Agency sponsors Co-ordinated Research Programmes (CRP) in the safe transport of radioactive material. The CRPs are intended to encourage research by Member States in identified areas and to facilitate co-ordination of exchange of information and resources to reach a common understanding of the problem and alternative solutions. Two of these programmes are: Accident Severity at Sea During the Transport of Radioactive Material and Accident Severity During the Air Transport of Radioactive Material. This paper will discuss these two programmes and their relationship to the continuing regulatory revision process and interfaces with the International Maritime Organization (IMO) and the International Civil Aviation Organization (ICAO). Some Member States and non-governmental organizations in IMO meetings expressed concerns that accidents on board ships may be more severe than the IAEA regulatory tests account for, and that package failure with subsequent release of radioactive material may occur. The CRP on accident severity at sea was established to develop further quantitative information on potential accident severities during the transport of radioactive material by ships. The primary objective of this programme is to collect and evaluate statistical data of marine accidents, perform analyses of potential accident conditions and evaluate the risks resulting from such shipments. The CRP on air transport was established to make a major international effort to collect relevant frequency and severity data and to analyze it so the accident forces to which a packages of radioactive material might be subjected to in a severe air accident can be more confidently quantified. Several countries have ongoing data collection activities related to aircraft accidents and severity and other sources of statistics for in-flight aircraft accidents will be explored. The International Civil Aviation Organization informed the IAEA of their plans to improve

IAEA mode-related research in the safe transport of radioactive material

International Nuclear Information System (INIS)

Blalock, L.G.; Rawl, R.R.

1998-01-01

The International Atomic Energy Agency sponsors Co-ordinated Research Programmes (CRP) in the safe transport of radioactive material. The CRPs are intended to encourage research by Member States in identified areas and to facilitate co-ordination of exchange of information and resources to reach a common understanding of the problem and alternative solutions. Two of these programmes are: Accident Severity at Sea During the Transport of Radioactive Material and Accident Severity During the Air Transport of Radioactive Material. This paper will discuss these two programmes and their relationship to the continuing regulatory revision process and interfaces with the International Maritime Organization (IMO) and the International Civil Aviation Organization (ICAO). Some Member States and non-governmental organizations in IMO meetings expressed concerns that accidents on board ships may be more severe than the IAEA regulatory tests account for, and that package failure with subsequent release of radioactive material may occur. The CRP on accident severity at sea was established to develop further quantitative information on potential accident severities during the transport of radioactive material by ships. The primary objective of this programme is to collect and evaluate statistical data of marine accidents, perform analyses of potential accident conditions and evaluate the risks resulting from such shipments. The CRP on air transport was established to make a major international effort to collect relevant frequency and severity data and to analyze it so the accident forces to which a packages of radioactive material might be subjected to in a severe air accident can be more confidently quantified. Several countries have ongoing data collection activities related to aircraft accidents and severity and other sources of statistics for in-flight aircraft accidents will be explored. The International Civil Aviation Organization informed the IAEA of their plans to improve

Radioactivity in Dutch consumer products

CERN Document Server

Janssen, M P M

2002-01-01

This study took place within the framework of a general update of the average radiation dose for the Dutch population. It focuses on consumer products in which radionuclides have been intentionally incorporated and on radiation-emitting devices that can be supplied to members of the public without special surveillance. Eleven consumer products were studied in more detail. The radiation from these products determined 90% of the total collective dose due to consumer products in the Netherlands in 1988. Individual and collective doses are presented here for each product. The total collective dose has decreased from 130 personSv in 1988 to 4.6 personSv at present. This reduction was attributed to: a decrease in the number of radioactive products (gas mantles), lower estimates of the number of radioactive products present in the Netherlands thanks to new information (camera lenses, smoke detectors containing Ra-226), replacement of radioactive by non-radioactive products (gas mantles, dental protheses), and a lowe...

Non-dissipative kinetic simulation and analytical solution of three-mode equations of ion temperature gradient instability

International Nuclear Information System (INIS)

Watanabe, T.-H.; Sugama, H.; Sato, T.

1999-12-01

A non-dissipative drift kinetic simulation scheme, which rigorously satisfies the time-reversibility, is applied to the three-mode coupling problem of the ion temperature gradient (ITG) instability. It is found from the simulation that the three-mode ITG system repeats growth and decay with a period which shows a logarithmic divergence for infinitesimal initial perturbations. Accordingly, time average of the mode amplitude vanishes, as the initial amplitude approaches to zero. An exact solution is analytically given for a class of initial conditions. An excellent agreement is confirmed between the analytical solution and numerical results. The results obtained here provide a useful reference for basic benchmarking of theories and simulation of the ITG modes. (author)

Nuclear radioactive techniques applied to materials research

CERN Document Server

Correia, João Guilherme; Wahl, Ulrich

2011-01-01

In this paper we review materials characterization techniques using radioactive isotopes at the ISOLDE/CERN facility. At ISOLDE intense beams of chemically clean radioactive isotopes are provided by selective ion-sources and high-resolution isotope separators, which are coupled on-line with particle accelerators. There, new experiments are performed by an increasing number of materials researchers, which use nuclear spectroscopic techniques such as Mössbauer, Perturbed Angular Correlations (PAC), beta-NMR and Emission Channeling with short-lived isotopes not available elsewhere. Additionally, diffusion studies and traditionally non-radioactive techniques as Deep Level Transient Spectroscopy, Hall effect and Photoluminescence measurements are performed on radioactive doped samples, providing in this way the element signature upon correlation of the time dependence of the signal with the isotope transmutation half-life. Current developments, applications and perspectives of using radioactive ion beams and tech...

Radioactive background with thymine dimer estimation in uv irradiated Escherichia coli cells

Energy Technology Data Exchange (ETDEWEB)

Masek, F [Slovenska Akademia Vied, Bratislava (Czechoslovakia). Vyskumny Ustav Onkologicky

1976-01-01

Ultraviolet radiation induces photoproducts in the cell DNA, mainly pyrimidine dimers responsible for the essential part of lethal and mutagenic damage. Radioactive tracers were used in determining the amount of photoproducts. Radioisotope labelling of microbial cells involves the problem of background which influences analytical results. Undesirably high radioactive background on the chromatograms of the hydrolysates of the acid-insoluble fraction of UV irradiated Escherichia coli cells complicates the determination of the amount of UV photoproducts. The background may be suppressed by chromatographic purification of radioactive precursors. Also a more thorough separation orocedure of DNA macromolecules contributes to reducing the background. From this point of view it seems advantageous to use two-dimensional paper chromatography rather than one-dimensional.

77 FR 20077 - Request for a License To Export Radioactive Waste

Science.gov (United States)

2012-04-03

... NUCLEAR REGULATORY COMMISSION Request for a License To Export Radioactive Waste Pursuant to 10 CFR..., 2012, radioactive waste tons of or disposal by a February 16, 2012, XW019, in the form of ash radioactive waste licensed facility 11005986. and non-conforming as contaminated in Mexico. material. ash and...

Radiological Risk Assessment and Survey of Radioactive Contamination for Foodstuffs

International Nuclear Information System (INIS)

Lee, W.R.; Lee, C.W.; Choi, K.S.

2007-11-01

After the Chernobyl nuclear accident in 1986, a radiological dose assessment and a survey of a radioactive contamination for foodstuffs have been investigated by many countries such as EU, Japan, USA. In the case of Japan which is similar to our country for the imported regions of foodstuffs, there were some instances of the excess for regulation on the maximum permitted levels of radioactive contamination among some imported foodstuffs. Concerns about the radioactive contamination of foodstuffs are increased because of the recently special situation (Nuclear test of North Korea). The purpose of this study is a radiological dose assessment and a survey of a radioactive contamination for foodstuffs in order to reduce the probability of intake of contaminated foodstuffs. Analytical results of the collected samples are below MDA. In this project, the model of radiological dose assessment via the food chain was also developed and radiological dose assessment was conducted based on surveys results of a radioactive contamination for foodstuffs in the Korean open markets since 2002. The results of radiological dose assessment are far below international reference level. It shows that public radiation exposure via food chain is well controlled within the international guide level. However, the radioactive contamination research of imported foodstuffs should be continuous considering the special situation(nuclear test of North Korea). These results are used to manage the radioactive contamination of the imported foodstuffs and also amend the regulation on the maximum permitted levels of radioactive contamination of foodstuffs

Report of radioactivity survey research in fiscal year 1996

International Nuclear Information System (INIS)

1997-12-01

In National Institute of Radiological Sciences, a survey was made on radioactivities in the environment due to the substances released from nuclear installations and radioactive fall-out brought out by nuclear explosion tests since 1959. As the marked progress of non-military utilization of nuclear energy the national concern on environmental radioactivity has been increasing in Japan and thus it has become more and more important to make a survey research of radioactivities, which might affect the environment and human health. In these situations, the institute attempted to make the following six surveys in the fiscal year of 1996; 'a survey on radioactive levels in environment, foods and human bodies', 'survey on the radioactive level in the regions around nuclear installations', 'works in radioactive data center', 'fundamental survey on the evaluation of the results from radioactivity survey', 'workshop for technical experts of environmental radioactivity monitoring' and 'survey research on the measurement and countermeasures for emergency exposure'. (M.N.)

Report of radioactivity survey research in fiscal year 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

In National Institute of Radiological Sciences, a survey was made on radioactivities in the environment due to the substances released from nuclear installations and radioactive fall-out brought out by nuclear explosion tests since 1959. As the marked progress of non-military utilization of nuclear energy the national concern on environmental radioactivity has been increasing in Japan and thus it has become more and more important to make a survey research of radioactivities, which might affect the environment and human health. In these situations, the institute attempted to make the following six surveys in the fiscal year of 1997; `a survey on radioactive levels in environment, foods and human bodies`, `survey on the radioactive level in the regions around nuclear installations`, `works in radioactive data center`, `fundamental survey on the evaluation of the results from radioactivity survey`, `workshop for technical experts of environmental radioactivity monitoring` and `survey research on the measurement and countermeasures for emergency exposure`. (J.P.N.)

Studying the induced radioactivity of a varian clinac 2100C/D accelerator

International Nuclear Information System (INIS)

Lu Feng; Li Hailiang; Deng Daping; Shang Yunying; Jing Zhongjun

2008-01-01

Objective: To Study the influences of dose, time, distance and irradiation mode on induced radioactivity by measuring a Varian Clinac 2100C/D accelerator. Methods: The induced radioactivity was measured in different dose, time, distance and irradiation mode by using of 450P model dosemeter. The results was analysed. Results: The induced radioactivity is direct ratio with dose, inverse ratio with time and distance. In different irradiation mode, the induced radioactivity is different. Conclusion: The induced radioactivity level of accelerator is related with dose, time, distance and irradiation mode. (authors)

Near-surface facilities for disposal radioactive waste from non-nuclear application

International Nuclear Information System (INIS)

Barinov, A.

2000-01-01

The design features of the near-surface facilities of 'Radon', an estimation of the possible emergency situations, and the scenarios of their progress are given. The possible safety enhancing during operation of near-surface facilities, so called 'Historical facilities', and newly developed ones are described. The Moscow SIA 'Radon' experience in use of mobile module plants for liquid radioactive waste purification and principal technological scheme of the plant are presented. Upgrading of the technological scheme for treatment and conditioning of radioactive waste for new-developed facilities is shown. The main activities related to management of spent ionizing sources are mentioned

Analytical Chemistry Division annual progress report for period ending December 31, 1992

Energy Technology Data Exchange (ETDEWEB)

Shults, W.D.

1993-04-01

This report is divided into: Analytical spectroscopy (optical spectroscopy, organic mass spectrometry, inorganic mass spectrometry, secondary ion mass spectrometry), inorganic and radiochemistry (transuranium and activation analysis, low-level radiochemical analysis, inorganic analysis, radioactive materials analysis, special projects), organic chemistry (organic spectroscopy, separations and synthesis, special projects, organic analysis, ORNL/UT research program), operations (quality assurance/quality control, environmental protection, safety, analytical improvement, training, radiation control), education programs, supplementary activities, and presentation of research results. Tables are included for articles reviewed or refereed for periodicals, analytical service work, division manpower and financial summary, and organization chart; a glossary is also included.

Radioactive ores from Agostinho field, Pocos de Caldas (MG), Brazil

International Nuclear Information System (INIS)

Fujimori, K.

1974-01-01

Aiming to characterize the radioactive minerals of Campo Agostinho, Pocos de Caldas - Brazil, the survey of all natural radiactive elements and their geochemical behaviors, decays and radioactive equilibrium was done. Several models of radioactive instability of the minerals or the radioactive samples were proposed to characterize the geochemistry and the mineralization of radioactive elements. The complete isotopic analysis of the elements was done by high resolution gamma spectrometry, using a Ge(Li) detector, at the temperature of liquid nitrogen, coupled to a multichannel analyser. The sample in radioactive equilibrium of Atomic Energy Comission of United States - A.S. n.6, NBL - New Brunswick Laboratory, was considered as standard sample. Fluorite, zircons, pirite, molibinite, rutile, anatase, niobophyllite, and in small ratio (bellow 0.1%) uranothorianite, coffinite, pyrochlore, monazite and apatite. (M.C.K.) [pt

Analytical Chemistry Division annual progress report for period ending December 31, 1983

International Nuclear Information System (INIS)

Lyon, W.S.

1984-05-01

Progress and activities are reported in: analytical methodology, mass and emission spectrometry, radioactive materials analysis, bio/organic analysis, general and environmental analysis, and quality assurance and safety. Supplementary activities are also discussed, and a bibliography of publications is also included

Analytical Chemistry Division annual progress report for period ending December 31, 1983

Energy Technology Data Exchange (ETDEWEB)

Lyon, W.S. (ed.)

1984-05-01

Progress and activities are reported in: analytical methodology, mass and emission spectrometry, radioactive materials analysis, bio/organic analysis, general and environmental analysis, and quality assurance and safety. Supplementary activities are also discussed, and a bibliography of publications is also included. (DLC)

HIV diversity and drug resistance from plasma and non-plasma analytes in a large treatment programme in western Kenya.

Science.gov (United States)

Kantor, Rami; DeLong, Allison; Balamane, Maya; Schreier, Leeann; Lloyd, Robert M; Injera, Wilfred; Kamle, Lydia; Mambo, Fidelis; Muyonga, Sarah; Katzenstein, David; Hogan, Joseph; Buziba, Nathan; Diero, Lameck

2014-01-01

Antiretroviral resistance leads to treatment failure and resistance transmission. Resistance data in western Kenya are limited. Collection of non-plasma analytes may provide additional resistance information. We assessed HIV diversity using the REGA tool, transmitted resistance by the WHO mutation list and acquired resistance upon first-line failure by the IAS-USA mutation list, at the Academic Model Providing Access to Healthcare (AMPATH), a major treatment programme in western Kenya. Plasma and four non-plasma analytes, dried blood-spots (DBS), dried plasma-spots (DPS), ViveST(TM)-plasma (STP) and ViveST-blood (STB), were compared to identify diversity and evaluate sequence concordance. Among 122 patients, 62 were treatment-naïve and 60 treatment-experienced; 61% were female, median age 35 years, median CD4 182 cells/µL, median viral-load 4.6 log10 copies/mL. One hundred and ninety-six sequences were available for 107/122 (88%) patients, 58/62 (94%) treatment-naïve and 49/60 (82%) treated; 100/122 (82%) plasma, 37/78 (47%) attempted DBS, 16/45 (36%) attempted DPS, 14/44 (32%) attempted STP from fresh plasma and 23/34 (68%) from frozen plasma, and 5/42 (12%) attempted STB. Plasma and DBS genotyping success increased at higher VL and shorter shipment-to-genotyping time. Main subtypes were A (62%), D (15%) and C (6%). Transmitted resistance was found in 1.8% of plasma sequences, and 7% combining analytes. Plasma resistance mutations were identified in 91% of treated patients, 76% NRTI, 91% NNRTI; 76% dual-class; 60% with intermediate-high predicted resistance to future treatment options; with novel mutation co-occurrence patterns. Nearly 88% of plasma mutations were identified in DBS, 89% in DPS and 94% in STP. Of 23 discordant mutations, 92% in plasma and 60% in non-plasma analytes were mixtures. Mean whole-sequence discordance from frozen plasma reference was 1.1% for plasma-DBS, 1.2% plasma-DPS, 2.0% plasma-STP and 2.3% plasma-STB. Of 23 plasma

Mathematical modeling of radionuclide release through a borehole in a radioactive waste repository

International Nuclear Information System (INIS)

Choi, Heui Joo

1996-02-01

The effects of inadvertent human intrusion as a form of direct drilling into a radioactive waste repository are discussed in this thesis. It has been mentioned that the inadvertent direct drilling into the repository could provide a release pathway for radionuclides even with its low occurrence probability. The following analyses are carried out regarding the problem. The maximum concentration in a water-filled borehole penetrating a repository is computed with a simple geometry. The modeling is based upon the assumption of the diffusive mass transfer in the waste forms and the complete mixing in the borehole. It is shown that the maximum concentrations of six radionuclides in the borehole could exceed the Maximum Permissible Concentration. Also, the diffusive mass transport in a water-filled borehole is investigated with a solubility-limited boundary condition. An analytic solution is derived for this case. Results show that the diffusive mass transport is fast enough to justify the assumption of the complete mixing compared with the considered time span. The axial diffusive mass transport along a water-filled borehole is modeled to compute the release rate taking account of the rock matrix diffusion. The results show that the release of short-lived radionuclides are negligible due to the low concentration gradient in early time and the rock matrix diffusion. The release rates of four long-lived radionuclides are computed. It is also shown that the model developed could be applied to a borehole at a non-cylindrically shaped repository and the off-center drilling of a cylindrical repository. The release rates of long-lived nuclides through a porous material-filled borehole are computed. The results show that the release of all the long-lived nuclides is negligible up to half million years in the case that the borehole is filled with the porous material. The radiological effects of the nuclides released through the borehole penetrating the repository are computed

Development of analytical techniques in support of waste and effluent characterization

International Nuclear Information System (INIS)

Reed, W.J.

1991-01-01

The Analytical Services Group within Sellafield Technical Department has been established for >40 yr and employs >150 analysts. The group operates >400 analytical methods across a wide range of techniques and has a yearly workload of ∼250,000 determinations. The group operates under a quality system based on statistical process control that has achieved national recognition through the accreditation of its mass spectrometry and radiochemical services to the standard of national testing laboratories. The group offers services ranging from the characterization of highly active wastes to trace elemental and radiochemical measurements in environmental, biological, and effluent streams. The group has vast experience in the management of analytical services to tight time scales and has pioneered developments not only in analytical instrumentation, but also in the adaptation of equipment to radioactive environments and the design of dedicated analytical facilities

Modelling seasonal variations of natural radioactivity in soils: A case study in southern Italy

Science.gov (United States)

Guagliardi, Ilaria; Rovella, Natalia; Apollaro, Carmine; Bloise, Andrea; Rosa, Rosanna De; Scarciglia, Fabio; Buttafuoco, Gabriele

2016-12-01

The activity of natural radionuclides in soil has become an environmental concern for local public and national authorities because of the harmful effects of radiation exposure on human health. In this context, modelling and mapping the activity of natural radionuclides in soil is an important research topic. The study was aimed to model, in a spatial sense, the soil radioactivity in an urban and peri-urban soils area in southern Italy to analyse the seasonal influence on soil radioactivity. Measures of gamma radiation naturally emitted through the decay of radioactive isotopes (potassium, uranium and thorium) were analysed using a geostatistical approach to map the spatial distribution of soil radioactivity. The activity of three radionuclides was measured at 181 locations using a high-resolution ?-ray spectrometry. To take into account the influence of season, the measurements were carried out in summer and in winter. Activity data were analysed by using a geostatistical approach and zones of relatively high or low radioactivity were delineated. Among the main processes which influence natural radioactivity such as geology, geochemical, pedological, and ecological processes, results of this study showed a prominent control of radio-emission measurements by seasonal changes. Low natural radioactivity levels were measured in December associated with winter weather and moist soil conditions (due to high rainfall and low temperature), and higher activity values in July, when the soil was dry and no precipitations occurred.

Exemption and clearance of radioactive waste from non-nuclear industry: A UK regulator's perspective

International Nuclear Information System (INIS)

McHugh, J.O.

1997-01-01

In the UK radioactive substances are regulated by means of registrations and authorizations issued under the Radioactive Substances Act. For certain practices and types of radioactive materials, there are orders which allow exemption from registration/authorization, conditionally or unconditionally. The seventeen Exemption Orders in force cover a wide variety of types of radioactive materials and practices. Conditional Exemption Orders allow a degree of regulatory control without imposing undue burdens on users of radioactivity. For most orders, radiation doses to individuals would be about 1OμSv or less, and collective doses would be less than 1 man - Sievert. The UK is reviewing the exemption orders against the requirements of the 1996 Euratom Basic Safety Standards Directive. It intends to develop a coherent strategy for exemption and to rationalize the current orders. Recently there has been a degree of public concern over the release of items from the nuclear industry. Careful presentation of exemption and clearance concepts is necessary if public confidence in the regulatory system is to be maintained. (author)

A calculation strategy for the determination of the temperature distribution in radioactive waste repositories

International Nuclear Information System (INIS)

Hahne, K.; Biurrun, E.

1989-01-01

In the past many calculation tools have been developed for the determination of instationary temperature distributions in radioactive waste repositories (single source model/large scale model/unit cell model using analytical or numerical methods; overall model using analytical or numerical methods). This paper discusses how, in practice, all these calculation tools have to be associated sensibly in a special calculation strategy making use of their actual advantages

Did you know, … Amazing facts on radioactivity and waste disposal

International Nuclear Information System (INIS)

2013-05-01

This brochure published by the Swiss National Cooperative for the Disposal of Radioactive Waste (NAGRA) provides some interesting information on several themes regarding radioactivity. Under the title of ‘Did you know that…’ various lesser-known facts on radioactivity are examined. These include information on radiation emitted by men and women, radioactive radon in buildings as well as the use of radiation to make pepper and spices non-perishable. Also, the use of radioactivity in medicine is discussed. Radioactivity in the earth’s core as the source of geothermal energy is also looked at, as is radioactivity in rock. Also, rock as a material used to screen ionizing radiation sources such as radioactive wastes is discussed. Finally, the time scales involved in radioactive decay are discussed

Comparison of analytical charge-form and equilibrium thermodynamic speciation of certain radionuclides

International Nuclear Information System (INIS)

Jenne, E.A.; Cowan, C.E.; Robertson, D.E.

1984-01-01

Calculating trace element speciation with a thermodynamic model is often challenged on the basis that the existing thermodynamic data are not sufficiently reliable. Water quality data and corresponding analytical charge-form speciation analysis were available for radionuclides occurring in a low-level radioactive groundwater. This offered an opportunity for comparing the results of an equilibrium thermodynamic model with the results of analytical charge-form speciation. The charge-form speciation was determined using the Battelle Large Volume Water Sampler, which contains consecutive layers of cation resin, anion resin and activated aluminum oxide for retention of cationic, anionic and non-ionic dissolved chemical species, respectively. The thermodynamic speciation of Cs, Cr, Fe, I, Mn, Mo, Na, and Zn was calculated using the MINTEQ geochemical model. Ce, Co, Tc, Np, Pm, and Sb were speciated by hand calculation. Excellent agreement between the analytically determined charge-form and the thermodynamic speciation was observed for 54 Mn, 144 Ce, 131 I, 24 Na, 137 Cs, 99 Mo, 99 Tc, 151 Pm, 239 Np. Organic complexation by natural and/or synthetic organics in the waters may be important in the speciation of 65 An, 60 Co, 131 I, 59 Fe and possibly 51 Cr. Both 124 Sb and 125 Sb appeared to be in redox disequilibria with the groundwater. 29 references, 2 tables

4. Danish symposium in analytical chemistry

International Nuclear Information System (INIS)

1996-01-01

At the 4th Danish Symposium of Analytical Chemistry 11 lectures and 32 posters were presented during two session days on the 20 and 21 August 1996. Various analytical techniques were discussed for foodstuff, pesticide, pharmaceutical, industrial and other analyses. (EG)

Simple quasi-analytical holonomic homogenization model for the non-linear analysis of in-plane loaded masonry panels: Part 2, structural implementation and validation

Science.gov (United States)

Milani, G.; Bertolesi, E.

2017-07-01

The simple quasi analytical holonomic homogenization approach for the non-linear analysis of in-plane loaded masonry presented in Part 1 is here implemented at a structural leveland validated. For such implementation, a Rigid Body and Spring Mass model (RBSM) is adopted, relying into a numerical modelling constituted by rigid elements interconnected by homogenized inelastic normal and shear springs placed at the interfaces between adjoining elements. Such approach is also known as HRBSM. The inherit advantage is that it is not necessary to solve a homogenization problem at each load step in each Gauss point, and a direct implementation into a commercial software by means of an external user supplied subroutine is straightforward. In order to have an insight into the capabilities of the present approach to reasonably reproduce masonry behavior at a structural level, non-linear static analyses are conducted on a shear wall, for which experimental and numerical data are available in the technical literature. Quite accurate results are obtained with a very limited computational effort.

Transient temperature distributions in geological media surrounding radioactive waste repositories

Energy Technology Data Exchange (ETDEWEB)

Beyerlein, S W; Sunderland, J E [Massachusetts Univ., Amherst (USA). Dept. of Mechanical Engineering

1981-01-01

Closed form analytical solutions are presented for the transient temperature distributions resulting from underground radioactive waste disposal. The thermal source term is represented by point or spherical sources whose strength decreases exponentially with time. The transient temperature distributions can be determined above the disposal horizon over a time interval of hundreds of years.

Low level radioactive waste disposal siting: a social and technical plan for Pennsylvania. Volume 2. Socioeconomic analyses

International Nuclear Information System (INIS)

Aron, G.; Bord, R.J.; Clemente, F.A.; Dornsife, W.P.; Jarrett, A.R.; Jester, W.A.; Schmalz, R.F.; Witzig, W.F.

1984-09-01

Volume II comprises five chapters: Socioeconomic Screening Criteria for LLRW Facility Siting and An Application to Counties in Pennsylvania; Evaluating Public Participation Options for the Case of Low Level Radioactive Waste Siting in Pennsylvania; Potential Socioeconomic Impacts of a LLRW Facility in Pennsylvania; The Role of Community Incentives in Low Level Radioactive Waste Management; and Institutional Aspects of LLRW Site Development and Operations in Pennsylvania

Framework for assessing the effects of radioactive materials transportation

International Nuclear Information System (INIS)

Zoller, J.N.

1996-01-01

Radioactive materials transport may result in environmental effects during both incident-free and accident conditions. These effects may be caused by radiation exposure, pollutants, or physical trauma. Recent environmental impact analyses involving the transportation of radioactive materials are cited to provide examples of the types of activities which may be involved as well as the environmental effects which can be estimated

Particle size of radioactive aerosols generated during machine operation in high-energy proton accelerators

International Nuclear Information System (INIS)

Oki, Yuichi; Kanda, Yukio; Kondo, Kenjiro; Endo, Akira

2000-01-01

In high-energy accelerators, non-radioactive aerosols are abundantly generated due to high radiation doses during machine operation. Under such a condition, radioactive atoms, which are produced through various nuclear reactions in the air of accelerator tunnels, form radioactive aerosols. These aerosols might be inhaled by workers who enter the tunnel just after the beam stop. Their particle size is very important information for estimation of internal exposure doses. In this work, focusing on typical radionuclides such as 7 Be and 24 Na, their particle size distributions are studied. An aluminum chamber was placed in the EP2 beam line of the 12-GeV proton synchrotron at High Energy Accelerator Research Organization (KEK). Aerosol-free air was introduced to the chamber, and aerosols formed in the chamber were sampled during machine operation. A screen-type diffusion battery was employed in the aerosol-size analysis. Assuming that the aerosols have log-normal size distributions, their size distributions were obtained from the radioactivity concentrations at the entrance and exit of the diffusion battery. Radioactivity of the aerosols was measured with Ge detector system, and concentrations of non-radioactive aerosols were obtained using condensation particle counter (CPC). The aerosol size (radius) for 7 Be and 24 Na was found to be 0.01-0.04 μm, and was always larger than that for non-radioactive aerosols. The concentration of non-radioactive aerosols was found to be 10 6 - 10 7 particles/cm 3 . The size for radioactive aerosols was much smaller than ordinary atmospheric aerosols. Internal doses due to inhalation of the radioactive aerosols were estimated, based on the respiratory tract model of ICRP Pub. 66. (author)

Application of Fast Neutron Activity for Analysing Element Content on the Air Particulate

International Nuclear Information System (INIS)

Elin Nuraini; Ngasifudin; Sunardi; Elisabeth

2003-01-01

The research on application of fast neutron activation analysis for analysing element content on the air particulate has been done. The research about analysis of the particulate matters contained in non industrial traffic territory of Surakarta and full industrial traffic territory of Karanganyar, had been done using Fast Neutron Activation Analysis Method. Fast Neutron Activation Analysis method is one of the element analysis method which it's basic principle causes radioactivity appearance from the samples after being irradiated by neutron. The qualitative analysis method is based on the measuring of specific energy which was radiated by radioactive's nucleus and quantitative analysis method is based on the measuring of the intensity of each peak gamma energy. The qualitative analysis results showed, some element were identified i.e : 51 V ; 200 Pb, 27 Al and 52 Cr. The result showed that Pb level is 2.21 ± 0.09x10 -1 mg/m 3 in non industrial traffic territory of Surakarta and 2.78 ± 0.11x10 -1 mg/m 3 full industrial traffic territory of Karanganyar, this value greater than threshold value according 6.0x10 -2 mg/m 3 . (author)

USA perspectives. Safety and security of radioactive sources

International Nuclear Information System (INIS)

Dicus, G.J.

1999-01-01

In contrast to the 103 licensed nuclear power plants in the United States, there are about 157,000 licenses that authorize the use of radioactive materials subject to US Atomic Energy Act. as amended. Each year the NRC receives about 200 reports of lost, stolen or abandoned radioactive sources and devices. The NRC has established a programme to review and analyze reports and other information on losses, thefts, abandonments, and discoveries of radioactive sources that helped to identify and characterize the problem with safety and security of radioactive sources in devices used under the general license programme. In summary, a large number of radioactive sources in use in the USA have a very good safety record. When used properly by trained personnel with effective regulatory oversight, the many uses of radioactive sources are safe and provide a net benefit to society. If problems occur such as overexposures or contamination of property, it is essential that hey are promptly reported to the regulatory authority. If necessary appropriate emergency response measures can be taken, and the problems analysed. In that way, effective risk-informed regulatory measures can be activated to assure the continued safety and security of radioactive sources

The role of national regulatory authority in monitoring of radioactivity and in case of seizure of radioactive or nuclear material

International Nuclear Information System (INIS)

Morkunas, G.

2002-01-01

Full text: The Radiation Protection Centre is a regulatory authority in radiation protection in Lithuania. Its main tasks are licensing of practices, supervision, control and enforcement of radiation protection requirements, dosimetric, radiometric and spectrometric measurements, evaluation of exposure and its sources, expertise and advice on optimization of radiation protection. Its activities may be divided into two main parts -- regulatory and analytical ones. Food, drinking water, environmental, wipe and other samples are monitored, the appropriate evaluation of doses is done. The data on concentrations of artificial radionuclides in different bodies are available. The laboratory is to be accredited according to the ISO 17025 standard in the framework of Phare Twinning Project. In case of seized radioactive or nuclear material the Radiation Protection Centre has to identify the necessary radiation protection means for members of public and emergency workers, perform measurements of dose rate and radioactive contamination, and, if necessary, evaluate doses received due to the seized radioactive or nuclear material. Since the Radiation Protection Centre has its departments in the largest cities of Lithuania the above mentioned measures can be taken very urgently, especially the ones connected with primary evaluation of situation and identification of optimized radiation protection measures. The Radiation Protection Centre has its own possibilities of identification of radionuclides in the seized material. Such installations as HpGe spectrometers (Oxford and Canberra), equipment for radiochemical separation of U, Pu and actinides, alpha spectrometer, liquid scintillation spectrometer and neutron rem counter are available. There were a few cases when seized material had to be analyzed also. Different sources were found in different places of Lithuania, and it was necessary to define the activity and isotopic content of these sources. The following scheme is used in

Pathways analyses and their role in the decision making process for selection of low-level waste disposal sites

International Nuclear Information System (INIS)

Pin, F.G.; Oblow, E.M.

1985-01-01

Pathways analyses have been extensively used to evaluate the suitability of proposed sites for disposal of low-level radioactive waste. The analyses rely on conservative scenarios to describe potential human exposure to the waste. Conceptual and numerical models are used to simulate the long-term transport of contamination to man and additional conservatism generally is built into the analysis when assumptions concerning future events have to be made or when uncertainties concerning site or waste characteristics exist. This conservatism is useful in ascertaining whether the site provides an adequate buffer to persons outside the site boundary. In reaching conclusions concerning site capacity and site acceptability, however, considerations must be given to the uncertainties involved in the analysis. Analytical methods to quantitatively assess the sensitivity of the results to data uncertainties may prove useful in the decision making process for site suitability. 7 references, 1 figure

Safe disposal of radionuclides in low-level radioactive-waste repository sites; Low-level radioactive-waste disposal workshop, U.S. Geological Survey, July 11-16, 1987, Big Bear Lake, Calif., Proceedings

Science.gov (United States)

Bedinger, Marion S.; Stevens, Peter R.

1990-01-01

In the United States, low-level radioactive waste is disposed by shallow-land burial. Low-level radioactive waste generated by non-Federal facilities has been buried at six commercially operated sites; low-level radioactive waste generated by Federal facilities has been buried at eight major and several minor Federally operated sites (fig. 1). Generally, low-level radioactive waste is somewhat imprecisely defined as waste that does not fit the definition of high-level radioactive waste and does not exceed 100 nCi/g in the concentration of transuranic elements. Most low-level radioactive waste generated by non-Federal facilities is generated at nuclear powerplants; the remainder is generated primarily at research laboratories, hospitals, industrial facilities, and universities. On the basis of half lives and concentrations of radionuclides in low-level radioactive waste, the hazard associated with burial of such waste generally lasts for about 500 years. Studies made at several of the commercially and Federally operated low-level radioactive-waste repository sites indicate that some of these sites have not provided containment of waste nor the expected protection of the environment.

76 FR 24831 - Site-Specific Analyses for Demonstrating Compliance With Subpart C Performance Objectives

Science.gov (United States)

2011-05-03

...-level radioactive waste disposal facilities to conduct site-specific analyses to demonstrate compliance... public health and safety, these amendments would enhance the safe disposal of low-level radioactive waste... would be to enhance the safe disposal of low-level radioactive waste. The NRC is also proposing...

Low-level radioactive wastes

International Nuclear Information System (INIS)

Garbay, H.; Chapuis, A.M.

1988-01-01

During dismantling operations of nuclear facilities radioctive and non radioactive wastes are produced. The distinction between both kinds of wastes is not easy. In each dismantling operation special care and rules are defined for the separation of wastes. Each case must be separately studied. The volume and the surface activites are analyzed. Part of the wastes had been disposed in a public environment. The regulations, the international recommendations, thetheoretical and experimental investigations in this field are presented. A regulation principle and examples of radioactivity limits, on the basis of international recommendations, are provided. Those limits are calculated from individual radiation dose that may reach human beings [fr

Reference intervals for selected serum biochemistry analytes in cheetahs Acinonyx jubatus.

Science.gov (United States)

Hudson-Lamb, Gavin C; Schoeman, Johan P; Hooijberg, Emma H; Heinrich, Sonja K; Tordiffe, Adrian S W

2016-02-26

Published haematologic and serum biochemistry reference intervals are very scarce for captive cheetahs and even more for free-ranging cheetahs. The current study was performed to establish reference intervals for selected serum biochemistry analytes in cheetahs. Baseline serum biochemistry analytes were analysed from 66 healthy Namibian cheetahs. Samples were collected from 30 captive cheetahs at the AfriCat Foundation and 36 free-ranging cheetahs from central Namibia. The effects of captivity-status, age, sex and haemolysis score on the tested serum analytes were investigated. The biochemistry analytes that were measured were sodium, potassium, magnesium, chloride, urea and creatinine. The 90% confidence interval of the reference limits was obtained using the non-parametric bootstrap method. Reference intervals were preferentially determined by the non-parametric method and were as follows: sodium (128 mmol/L - 166 mmol/L), potassium (3.9 mmol/L - 5.2 mmol/L), magnesium (0.8 mmol/L - 1.2 mmol/L), chloride (97 mmol/L - 130 mmol/L), urea (8.2 mmol/L - 25.1 mmol/L) and creatinine (88 µmol/L - 288 µmol/L). Reference intervals from the current study were compared with International Species Information System values for cheetahs and found to be narrower. Moreover, age, sex and haemolysis score had no significant effect on the serum analytes in this study. Separate reference intervals for captive and free-ranging cheetahs were also determined. Captive cheetahs had higher urea values, most likely due to dietary factors. This study is the first to establish reference intervals for serum biochemistry analytes in cheetahs according to international guidelines. These results can be used for future health and disease assessments in both captive and free-ranging cheetahs.

A versatile non-radioactive assay for DNA methyltransferase activity and DNA binding

Science.gov (United States)

Frauer, Carina; Leonhardt, Heinrich

2009-01-01

We present a simple, non-radioactive assay for DNA methyltransferase activity and DNA binding. As most proteins are studied as GFP fusions in living cells, we used a GFP binding nanobody coupled to agarose beads (GFP nanotrap) for rapid one-step purification. Immobilized GFP fusion proteins were subsequently incubated with different fluorescently labeled DNA substrates. The absolute amounts and molar ratios of GFP fusion proteins and bound DNA substrates were determined by fluorescence spectroscopy. In addition to specific DNA binding of GFP fusion proteins, the enzymatic activity of DNA methyltransferases can also be determined by using suicide DNA substrates. These substrates contain the mechanism-based inhibitor 5-aza-dC and lead to irreversible covalent complex formation. We obtained covalent complexes with mammalian DNA methyltransferase 1 (Dnmt1), which were resistant to competition with non-labeled canonical DNA substrates, allowing differentiation between methyltransferase activity and DNA binding. By comparison, the Dnmt1C1229W catalytic site mutant showed DNA-binding activity, but no irreversible covalent complex formation. With this assay, we could also confirm the preference of Dnmt1 for hemimethylated CpG sequences. The rapid optical read-out in a multi-well format and the possibility to test several different substrates in direct competition allow rapid characterization of sequence-specific binding and enzymatic activity. PMID:19129216

Development of an expert system for radioactive material transportation

International Nuclear Information System (INIS)

Tamanoi, K.; Ishitobi, M.; Shinohara, Y.

1990-01-01

An expert system to deal with radioactive material transportation was developed. This expert system is based on 'Regulations for the Safe Transport of Radioactive Material' by IAEA issued 1985. IAEA published the regulations under such environments that safety transportation has become increasingly being focused as uses of radioactive materials are more pervasive, not only in nuclear field but also in non-nuclear purposes. Attentions are payed for operators and environment to establish safety in handling radioactive materials. In the 1985 regulations, detailed categorization of radioactive materials and, correspondingly, new classification of packages are introduced. This categorization is more complicated than old regulations, leading us to develop an expert system to evaluate easily the packages categorization. (author)

Structural Dynamic Analyses And Test Predictions For Spacecraft Structures With Non-Linearities

Science.gov (United States)

Vergniaud, Jean-Baptiste; Soula, Laurent; Newerla, Alfred

2012-07-01

The overall objective of the mechanical development and verification process is to ensure that the spacecraft structure is able to sustain the mechanical environments encountered during launch. In general the spacecraft structures are a-priori assumed to behave linear, i.e. the responses to a static load or dynamic excitation, respectively, will increase or decrease proportionally to the amplitude of the load or excitation induced. However, past experiences have shown that various non-linearities might exist in spacecraft structures and the consequences of their dynamic effects can significantly affect the development and verification process. Current processes are mainly adapted to linear spacecraft structure behaviour. No clear rules exist for dealing with major structure non-linearities. They are handled outside the process by individual analysis and margin policy, and analyses after tests to justify the CLA coverage. Non-linearities can primarily affect the current spacecraft development and verification process on two aspects. Prediction of flights loads by launcher/satellite coupled loads analyses (CLA): only linear satellite models are delivered for performing CLA and no well-established rules exist how to properly linearize a model when non- linearities are present. The potential impact of the linearization on the results of the CLA has not yet been properly analyzed. There are thus difficulties to assess that CLA results will cover actual flight levels. Management of satellite verification tests: the CLA results generated with a linear satellite FEM are assumed flight representative. If the internal non- linearities are present in the tested satellite then there might be difficulties to determine which input level must be passed to cover satellite internal loads. The non-linear behaviour can also disturb the shaker control, putting the satellite at risk by potentially imposing too high levels. This paper presents the results of a test campaign performed in

Analyses of soils at commercial radioactive waste disposal sites

International Nuclear Information System (INIS)

Piciulo, P.L.; Shea, C.E.; Barletta, R.E.

1983-01-01

Brookhaven National Laboratory, in order to provide technical assistance to the NRC, has measured a number of physical and chemical characteristics of soils from three commercial low-level radioactive waste disposal sites. Samples were collected from an area adjacent to the disposal site at Sheffield, IL, and from two operating sites: one at Barnwell, SC, and the other near Richland, WA. The soil samples, which were analyzed from each site, were believed to include soil which was representative of that in contact with buried waste forms. Results of field measurements of earth resistivity and of soil pH will be presented. Additionally, the results of laboratory measurements of resistivity, moisture content, pH, exchange acidity and the soluble ion content of the soils will be discussed. The soluble ion content of the soils was determined by analysis of aqueous extracts of saturated soil pastes. The concentrations of the following ions were determined: Ca 2+ , Mg 2+ , K + , Na + , HCO 3 - , CO 3 2- , SO 4 2- , Cl - , S 2-

Systematic analysis method for radioactive wastes generated from nuclear research facilities

International Nuclear Information System (INIS)

Kameo, Yutaka; Ishimori, Ken-ichiro; Haraga, Tomoko; Shimada, Asako; Katayama, Atsushi; Nakashima, Mikio; Takahashi, Kuniaki

2011-01-01

Analytical methods have been developed for the simple and rapid determination of radioactive nuclides, which are selected as important nuclides for the safety assessment of the disposal of wastes generated from research facilities. We advanced the development of a high-efficiency nondestructive measurement technique for γ-ray-emitting nuclides, simple and rapid methods for the pretreatment of hard-to-dissolve samples and subsequent radiochemical separation, and rapid determination methods for long-lived nuclides. In order to establish a system to analyze the important nuclides in various kinds of sample, actual radioactive wastes such as concentrated liquid waste, activated concrete, and metal pipes were analyzed by the present method. The results showed that the present method was well suited for a rapid and simple determination of low-level radioactive wastes generated from research facilities. (author)

International Laboratory of Marine Radioactivity. Biennial Report 1981-1982

International Nuclear Information System (INIS)

1983-12-01

The Biennial Report covers the activities at the International Laboratory of Marine Radioactivity during the years 1981-82. It contains 34 short reports grouped under the headings: supporting activities - analytical methods development, intercalibration and maintenance services; studies for assessing the impacts of radionuclide releases into the marine environment; studies for obtaining scientific bases for evaluating deep-sea radioactive waste disposal; studies on processes affecting the fate of marine pollutants; and special missions. Details are also presented of the general aspects of the laboratory operations, staff list of the Monaco Laboratory, list of publications, meetings and conferences attended and reports and papers presented, oceanographic cruises and membership of regular committees, working groups and international programmes

Disposal of radioactive and other hazardous wastes

International Nuclear Information System (INIS)

Boge, R.; Bergman, C.; Bergvall, S.; Gyllander, C.

1989-01-01

The purpose of the workshop was discuss legal, scientific and practical aspects of disposal of low- and intermediate-level radioactive waste and other types of hazardous waste. During the workshop the non-radioactive wastes discussed were mainly wastes from energy production, but also industrial, chemical and household wastes. The workshop gave the participants the opportunity to exchange information on policies, national strategies and other important matters. A number of invited papers were presented and the participants brought background papers, describing the national situation, that were used in the working groups. One of the main aims of the workshop was to discuss if the same basic philosophy as that used in radiation protection could be used in the assessment of disposal of non-radioactive waste, as well as to come up with identifications of areas for future work and to propose fields for research and international cooperation. The main text of the report consists of a summary of the discussions and the conclusions reached by the workshop

Plasma vitrification program for radioactive waste treatment

International Nuclear Information System (INIS)

Hung, Tsungmin; Tzeng, Chinchin; Kuo, Pingchun

1998-01-01

In order to treat radioactive wastes effectively and solve storage problems, INER has developed the plasma arc technology and plasma process for various waste forms for several years. The plasma vitrification program is commenced via different developing stages through nine years. It includes (a) development of non-transferred DC plasma torch, (b) establishment of a lab-scale plasma system with home-made 100kW non-transferred DC plasma torch, (c) testing of plasma vitrification of simulated radioactive wastes, (d) establishment of a transferred DC plasma torch delivering output power more than 800 kW, (e) study of NOx reduction process for the plasma furnace, (f) development of a pilot-scale plasma melting furnace to verify the vitrification process, and (g) constructing a plasma furnace facility in INER. The final goal of the program is to establish a plasma processing plant with capacity of 250 kg/hr to treat the low-level radioactive wastes generated from INER itself and domestic institutes due to isotope applications. (author)

Report on the disposal of radioactive wastes and spent fuel elements from Baden-Wuerttemberg

International Nuclear Information System (INIS)

2017-04-01

The report on the disposal of radioactive wastes and spent fuel elements from Baden- Wuerttemberg covers the following issues: legal framework for the nuclear disposal; producer of spent fuels and radioactive wastes in Baden- Report on the disposal of radioactive wastes and spent fuel elements from Baden- Wuerttemberg; low- and medium-level radioactive wastes (non heat generating radioactive wastes); spent fuels and radioactive wastes from waste processing (heat generating radioactive wastes); final disposal.

Development of risk assessment methodology applicable to radioactive waste isolation

International Nuclear Information System (INIS)

Campbell, J.E.; McGrath, P.E.; Cullingford, M.C.

1978-01-01

The risk from radioactive waste disposal in a deep geologic formation has not yet been completely assessed. A complete assessment should include credible estimates of the likelihood that radioactive materials would escape the repository and enter the human environment, and the magnitude of the resultant consequences in terms of human health effects. In addition, such an assessment should identify the dominant contributors to risk and, to the extent possible, quantify the uncertainties in risk estimates. A complete risk assessment may not be possible because of our limited knowledge of various aspects of geology and hydrogeology important to the long-term safety of a radioactive waste repository. The results of past analyses are not entirely consistent, perhaps as a direct result of the limited knowledge of the phenomena involved. It may, therefore, seem premature to attempt a rigorous risk analysis of radioactive waste disposal in deep, geologic media at the present time. However, the value of such analyses lies more in the insight and information they provide than in their prediction of absolute levels of risk

Defense Waste Processing Facility radioactive operations -- Part 2, Glass making

International Nuclear Information System (INIS)

Carter, J.T.; Rueter, K.J.; Ray, J.W.; Hodoh, O.

1996-01-01

The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation's first and world's largest vitrification facility. Following a ten year construction period and nearly 3 year non-radioactive test program, the DWPF began radioactive operations in March, 1996. The results of the first 8 months of radioactive operations are presented. Topics include facility production from waste preparation batching to canister filling

Study of the radioactivity of the lower Danube during the period 1970-1974

International Nuclear Information System (INIS)

Iorgulescu, A.; Iorgulescu, St.; Rogalski, I.

1975-01-01

The control of radioactive pollution of the inferior course of Danubian river is perform in this paper. The results achieved by spectroscopic analyse of the samples of water, sediment and vegetation has indicated that; gamma radioactivity, beta radioactivity and isotopic concentration in tritium U-238, Th-232, Pb-212, Ra-226, potassium-40 is below superior limit admitted

A model to determine the radiological implications of non-fixed radioactive contamination on the surfaces of packages and conveyances

International Nuclear Information System (INIS)

Hughes, J.S.; Warner Jones, S.M.; Lizot, M.T.; Perrin, M.L.; Thierfeld, S.; Schroedl, E.; Schwarz, G.; Rawl, R.; Munakata, M.; Hirose, M.

2004-01-01

The surfaces of packages and conveyances used to transport radioactive materials can sometimes become contaminated with radioactive material. This usually occurs as a result of the transfer of radioactive material from areas in which these packages and conveyances are handled. This contamination may subsequently be transferred to transport equipment, workers and to areas accessible to the public. This can represent a significant radiation safety issue that requires careful management. The current regulatory limits for non-fixed contamination on packages and conveyances have been in use for over 40 years, and are based on a simple exposure model. However, the bases on which these limits were derived have been subject to changes, as a result of successive revisions of international recommendations. In recognition of this need for a review and analysis of the current contamination limits an IAEA Co-ordinated Research Project (CRP) on the ''Radiological Aspects of Package and Conveyance Non-Fixed Contamination'' was initiated to review the scientific basis for the current regulatory limits for surface contamination. The CRP was also to develop guidance material for evaluating the radiological significance of surface contamination to workers and the public in light of state-of-the-art research, technical developments and current transport practices. The specific objectives of the work undertaken within this multi-national CRP were, in accordance with the terms of reference: To ensure that appropriate models exist for all package types including consideration of the aspects pertinent for assessing and revising a surface contamination model for transport. To collect - where possible - contamination, operational and dosimetric data to ensure modelling consistency. To use models for assessing the limitations and optimisation of radiation doses incurred in transport operations, and to consider preventive methods for package and conveyance contamination

Processing radioactive wastes using membrane (UF/HF/RO) systems

International Nuclear Information System (INIS)

Doyle, R.D.

1988-01-01

Over the years many technologies have been utilized to process low level radioactive waste streams generated by the nuclear industry, including: demineralization, evaporation, reverse osmosis and filtration. In the early 1980's interest was generated in membrane technologies and their application to radioactive wastes. This interest was generated based on the capabilities shown by membrane systems in non-radioactive environments and the promise that reverse osmosis systems showed in early testing with radioactive wastes. Membrane technologies have developed from the early development of reverse osmosis system to also include specifically designed membranes for ultrafiltration and hyperfiltration applications

In situ multi-element analyses by energy-dispersive X-ray fluorescence on varnishes of historical violins

Energy Technology Data Exchange (ETDEWEB)

Echard, Jean-Philippe [Laboratoire de recherche et de restauration, Musee de la musique, Cite de la musique, 221, avenue Jean-Jaures, 75019 Paris (France)]. E-mail: jpechard@cite-musique.fr

2004-10-08

Varnishes of Italian violins and other historical stringed instruments have been analyzed by energy-dispersive X-ray fluorescence (EDXRF). The instruments whose varnishes were to be analyzed were chosen from the collection kept in Musee de la Musique in Paris. Direct analyses were performed on instrument varnishes, without any sampling and non-destructively, showing inorganic elements such as lead, mercury and iron that could be related to siccatives or pigments. Analytical results and their comparison with old formulae or traditional recipes of violin varnishes, as with the few previous analytical results, will be discussed.

In situ multi-element analyses by energy-dispersive X-ray fluorescence on varnishes of historical violins

International Nuclear Information System (INIS)

Echard, Jean-Philippe

2004-01-01

Varnishes of Italian violins and other historical stringed instruments have been analyzed by energy-dispersive X-ray fluorescence (EDXRF). The instruments whose varnishes were to be analyzed were chosen from the collection kept in Musee de la Musique in Paris. Direct analyses were performed on instrument varnishes, without any sampling and non-destructively, showing inorganic elements such as lead, mercury and iron that could be related to siccatives or pigments. Analytical results and their comparison with old formulae or traditional recipes of violin varnishes, as with the few previous analytical results, will be discussed

A radioactive controversy

International Nuclear Information System (INIS)

Engler, Veronica

2002-01-01

During 2002, the National Congress of Argentina began discussing the 'Agreement between the Republic of Argentina and Australia on cooperation in the peaceful uses of the nuclear energy'. This document has revived the debate regarding development of a national nuclear industry. The debate was spurred by a commercial contract signed in 2000 by INVAP, an Argentinean company who sold a nuclear reactor to the ANSTO, Australian Nuclear and Technology Organization. More than sixty non-governmental organizations are opposed to the ratification of the agreement, because they interpret that the text leaves the door wide open for the transport and deposit of Australian nuclear waste to Argentina, to be processed in national territory. Article 41 of the Argentinean National Constitution, explicitly prohibits the generation of any income from 'radioactive residues'. Those who support the agreement say that it does not promote the deposit of nuclear waste in Argentina, and argue that environmentalists are hampering efforts of this advanced technological industry to flourish in Argentina. The point of conflict in the agreement lies in article 12, which states that Argentina will continue the process of reactor-driven irradiated fuel outside Argentina. Once the treatment is completed, the fuel conditioned and the resulting waste must return to the country of origin for their storage. The possibility of spent fuel being sent to Argentina lies in the hypothetical case that the French company Cogema, which currently holds treatment responsibility, stops treatment sometime within the next fifteen years, when the fuel must be treated. The non-ratification of the agreement on Argentina part will not imply any sort of impediment in the realization of the reactor, it will only put on hold the possibility that the Australians spent fuels will complete treatment in Argentina. The constitutionality of the agreement lies in the question of waste, but this too is not a simple question. The

Decontamination and radioactivity measurement on building surfaces related to dismantling of Japan power demonstration reactor (JPDR)

International Nuclear Information System (INIS)

Hatakeyama, Mutsuo; Tachibana, Mitsuo; Yanagihara, Satoshi

1997-12-01

In the final stage of dismantling activities for decommissioning a nuclear power plant, building structures have to be demolished to release the site for unrestricted use. Since building structures are generally made from massive reinforced concrete materials, it is not a rational way to treat all concrete materials arising from its demolition as radioactive waste. Segregation of radioactive parts from building structures is therefore indispensable. The rational procedures were studied for demolition of building structures by treating arising waste as non-radioactive materials, based on the concept established by Nuclear Safety Commission, then these were implemented in the following way by the JPDR dismantling demonstration project. Areas of the JPDR facilities are categorized into two groups : possibly contaminated areas, and possibly non-contaminated areas, based on the document of the reactor operation. Radioactivity on the building surfaces was then measured to confirm that the qualitative categorization is reasonable. After that, building surfaces were decontaminated in such a way that the contaminated layers were removed with enough margin to separate radioactive parts from non-radioactive building structures. Thought it might be possible to demolish the building structures by treating arising waste as non-radioactive materials, confirmation survey for radioactivity was conducted to show that there is no artificial radioactive nuclides produced by operation in the facility. This report describes the procedures studied on measurement of radioactivity and decontamination, and the results of its implementation in the JPDR dismantling demonstration project. (author)

Radioactive waste management for a radiologically contaminated hospitalized patient

International Nuclear Information System (INIS)

Pina Jomir, G.; Michel, X.; Lecompte, Y.; Chianea, N.; Cazoulat, A.

2015-01-01

Radioactive waste management in the post-accidental phase following caring for a radiologically contaminated patient in a hospital decontamination facility must be anticipated at a local level to be truly efficient, as the volume of waste could be substantial. This management must comply with the principles set out for radioactive as well as medical waste. The first step involves identification of radiologically contaminated waste based on radioactivity measurement for volume reduction. Then, the management depends on the longest radioactive half-life of contaminative radionuclides. For a half-life inferior to 100 days, wastes are stored for their radioactivity to decay for at least 10 periods before disposal like conventional medical waste. Long-lived radioactive waste management implies treatment of liquid waste and special handling for sorting and packaging before final elimination at the French National Agency for Radioactive Waste Management (ANDRA). Following this, highly specialized waste management skills, financial responsibility issues and detention of non-medical radioactive sources are questions raised by hospital radioactive waste management in the post-accidental phase. (authors)

Nuclear analytical techniques and their application to environmental samples

International Nuclear Information System (INIS)

Lieser, K.H.

1986-01-01

A survey is given on nuclear analytical techniques and their application to environmental samples. Measurement of the inherent radioactivity of elements or radionuclides allows determination of natural radioelements (e.g. Ra), man-made radioelements (e.g. Pu) and radionuclides in the environment. Activation analysis, in particular instrumental neutron activation analysis, is a very reliable and sensitive method for determination of a great number of trace elements in environmental samples, because the most abundant main constituents are not activated. Tracer techniques are very useful for studies of the behaviour and of chemical reactions of trace elements and compounds in the environment. Radioactive sources are mainly applied for excitation of characteristic X-rays (X-ray fluorescence analysis). (author)

Use of nuclear and related analytical techniques in environmental research as exemplified by selected air pollution studies

International Nuclear Information System (INIS)

Smodis, B.; Jacimovic, R.; Jeran, Z.; Stropnik, B.; Svetina, M.

2000-01-01

Among nuclear and nuclear related analytical techniques, neutron activation analysis and X-ray fluorescence spectrometry proved to be particularly useful for environmental studies owing to their nondestructive character and multi element capability. This paper emphasizes their importance among other multielement analytical methods by discussing their specific role due to specific physics basis, quite different to other destructive non-nuclear methods, and by summarizing results obtained in several studies related to air pollution research, including analyses of airborne particulate matter, water samples, lichens and mosses. (author)

The Application and Regulation of Non-Medical radioactive Substances in Taiwan, China

International Nuclear Information System (INIS)

Chang, Chihchien; Chou, Keiden; Wang, Songfeng

1998-01-01

Based on the Atomic Energy Law of Taiwan and regulations regarding radiation protection, an operating system has been established for the approval and regulation of import (production), installation, licensing, safety inspection, record keeping, storage, transfer, transportation and abandonment of nonmedical radioactive materials and equipment capable of producing ionizing radiation. In order to ensure that all equipment capable of producing ionizing radiation can meet the respective standard of radiation protection in accordance with the ALARA principle, nonmedical equipment capable of producing ionizing radiation is divided into six categories depending on its inherent shielding ability, operation limit, characteristics of the radiation and the required degree of surveillance for achieving the purpose of radiation protection. The six categories are: 1. Protective equipment, 2. Immobile closed equipment, 3. Automatic operating equipment, 4. Mobile equipment, 5. Unsealed radioactive substances, 6. Consumer products and other radioactive sources with different properties. Each category has its specific requirements in radiation protection. (author)

Bonding of radioactive contamination. III. Auger electron spectroscopic investigation

International Nuclear Information System (INIS)

Rankin, W.N.; Whitkop, P.G.

1983-01-01

The mechanisms by which radioactive contamination would be bonded to a DWPF canister surface are being investigated. Tests with low pressure water and air-injected water decontamination of radioactive specimens showed that bonding of contamination increases rapidly with postoxidation temperature. Even with the least severe temperature conditions expected on the waste glass canister, bonding is so great that decontamination cannot be affected by water-only techniques. A preoxidation film increased rather than decreased bonding. This memorandum describes detailed surface analyses of coupons simulating DWPF canister surfaces. Based on this examination we conclude: contamination will be dispersed throughout the oxide film on DWPF canisters. Contamination is concentrated at the surface, decreasing farther into the oxide film; some samples contain sludge contamination at the steel/oxide interface. This was not the case for semi-volatile (Cs 2 O) contamination; in samples with contamination at the steel/oxide interface, at least 80% of the contamination is usually in the oxide layer; no difference in contamination dispersion between preoxidized and non-preoxidized samples was found; and postoxidation atmosphere had no effect on the contamination dispersion within the oxide layer. 6 references, 9 figures

Facilities for the examination of radioactive bodies

International Nuclear Information System (INIS)

Ginniff, M.E.; Richardson, E.K.

1981-01-01

A facility for the examination of radioactive bodies comprises carriages, each transporting one or more radioactive bodies, e.g. nuclear fuel elements, which travel along a shielded passage to bring the bodies to examination stations spaced along the passage. The passage comprises a circular section tube surrounded by a thick cylinder of shielding material e.g. lead. The transverse sectional dimensions of the passage are not much larger than the corresponding dimensions of the carriages in order to maintain the radioactive region as small as possible. Equipment for the examination of the radioactive bodies is located outside the shielded passage, and may be for metallurgical examination, e.g. by ultrasonics, radiography or other non-destructive testing means, or for mensuration to identify changes in shape, dimensions or weight. (author)

Radioactive waste from non-licensed activities - identification of waste, compilation of principles and guidance, and proposed system for final management; Radioaktivt avfall fraan icke tillstaandsbunden verksamhet (RAKET) - identifiering av aktuellt avfall, sammanstaellning av relevanta regler och principer, foerslag paa system foer omhaendertagande

Energy Technology Data Exchange (ETDEWEB)

Jones, C.; Pers, K. [Kemakta Konsult AB, Stockholm (Sweden)

2001-07-01

Presently national guidelines for the handling of radioactive waste from non-licensed activities are lacking in Sweden. Results and information presented in this report are intended to form a part of the basis for decisions on further work within the Swedish Radiation Protection Institute on regulations or other guidelines on final management and final disposal of this type of waste. An inventory of radioactive waste from non-licensed activities is presented in the report. In addition, existing rules and principles used in Sweden - and internationally - on the handling of radioactive and toxic waste and non-radioactive material are summarized. Based on these rules and principles a system is suggested for the final management of radioactive material from non-licensed activities. A model is shown for the estimation of dose as a consequence of leaching of radio-nuclides from different deposits. The model is applied on different types of waste, e.g. peat ashes, light concrete and low-level waste from a nuclear installation.

78 FR 9746 - Request To Amend a License To Export Radioactive Waste

Science.gov (United States)

2013-02-11

... NUCLEAR REGULATORY COMMISSION Request To Amend a License To Export Radioactive Waste Pursuant to... radioactive disposition. Amend which was imported mixed waste) in to: 1) add four from Canada under NRC a....; docket No. country Diversified Scientific Class A radioactive Up to a maximum Return of non- Canada...

Radioactive waste management in sealed sources laboratory production

International Nuclear Information System (INIS)

Carvalho, Gilberto

2001-01-01

The laboratory of sealed sources production, of Instituto de Pesquisas Energeticas e Nucleares, was created in 1983 and since then, has produced radioactive sources for industry and engineering in general, having specialization in assembly of radiation sources for non destructive testings, by gammagraphy, with Iridium-192, that represents 98% of the production of laboratory and 2% with the Cobalt-60, used in nuclear gages. The aim of this work, is to quantify and qualify the radioactive wastes generated annually, taking into account, the average of radioactive sources produced, that are approximately 220 sources per year

Radioactive wastes in Oklo

International Nuclear Information System (INIS)

Balcazar, M.; Flores R, J.H.; Pena, P.; Lopez, A.

2006-01-01

The acceptance of the Nuclear Energy as electric power supply implies to give answer to the population on the two main challenges to conquer in the public opinion: the nuclear accidents and the radioactive wastes. Several of the questions that are made on the radioactive wastes, its are the mobility migration of them, the geologic stability of the place where its are deposited and the possible migration toward the aquifer mantels. Since the half lives of the radioactive waste of a Nuclear Reactor are of several hundred of thousands of years, the technical explanations to the previous questions little convince to the public in general. In this work summary the results of the radioactive waste generated in a natural reactor, denominated Oklo effect that took place in Gabon, Africa, it makes several thousands of millions of years, a lot before the man appeared in the Earth. The identification of at least 17 reactors in Oklo it was carried out thanks to the difference in the concentrations of Uranium 235 and 238 prospective, and to the analysis of the non-mobility of the radioactive waste in the site. It was able by this way to determine that the reactors with sizes of hardly some decimeter and powers of around 100 kilowatts were operating in intermittent and spontaneous form for space of 150,000 years, with operation cycles of around 30 minutes. Recent studies have contributed information valuable on the natural confinement of the radioactive waste of the Oklo reactors in matrixes of minerals of aluminum phosphate that caught and immobilized them for thousands of millions of years. This extracted information from the nature contributes guides and it allows 'to verify' the validity of the current proposals on the immobilization of radioactive wastes of a nuclear reactor. This work presents in clear and accessible form to the public in general on the secure 'design', operation, 'decommissioning' and 'storage' of the radioactive waste of the reactors that the nature put

Preparation of radioactive colloidal gold 198Au

International Nuclear Information System (INIS)

Cammarosano, S.A.

1979-01-01

The preparation with simple equipment of radioactive colloidal gold of particle size about approximately 300 A from seed colloid stabilized by gelatine is described. Some physico-chemical parameters which can affect the process of formation of these colloidal particles are analysed; particle size has been meassured with an electron microscope. The colloid stability has been studied as a function of dilution, age and pH. Nucleation and growth of radioactive colloidal gold have been studied using spectrophotometry. Absorption spectra of the two ones are presented and compared. Quality control of the production process is verified through measurement of parameters, such as radioactive and radiochemical purity and biological distribution in laboratorial animals. This distribution was evalusted for rats injected endovenously with the gold colloidal solution.(Author) [pt

Use of radioactive tracers in chemical reactions

International Nuclear Information System (INIS)

Paci, B.

1979-01-01

A method for the determination of small quantities of nickel using radioactive tracers is presented. An analytical application of the displacement reaction between nickel and zinc ethylenediaminetetraacetate labeled with zinc-65 is pursued. This method is based on the extraction of radioactive zinc displaced by nickel from the zinc chelate into a dithizone-carbon tetracloride solution and the subsequent measurement of the activity of an aliquot of the extract. The method is very sensitive and nickel can be measured in concentrations as small as 0.1μg/ml or even less, depending on the specific activity of the radioreagent used. The precision and the accuracy of the method are determined. The problem of interferences, trying to eliminate them by using masking agents or by means of a previous separation between nickel and other interfering metals, is also investigated [pt

AN ANALYTICAL FRAMEWORK FOR ASSESSING RELIABLE NUCLEAR FUEL SERVICE APPROACHES: ECONOMIC AND NON-PROLIFERATION MERITS OF NUCLEAR FUEL LEASING

International Nuclear Information System (INIS)

Kreyling, Sean J.; Brothers, Alan J.; Short, Steven M.; Phillips, Jon R.; Weimar, Mark R.

2010-01-01

The goal of international nuclear policy since the dawn of nuclear power has been the peaceful expansion of nuclear energy while controlling the spread of enrichment and reprocessing technology. Numerous initiatives undertaken in the intervening decades to develop international agreements on providing nuclear fuel supply assurances, or reliable nuclear fuel services (RNFS) attempted to control the spread of sensitive nuclear materials and technology. In order to inform the international debate and the development of government policy, PNNL has been developing an analytical framework to holistically evaluate the economics and non-proliferation merits of alternative approaches to managing the nuclear fuel cycle (i.e., cradle-to-grave). This paper provides an overview of the analytical framework and discusses preliminary results of an economic assessment of one RNFS approach: full-service nuclear fuel leasing. The specific focus of this paper is the metrics under development to systematically evaluate the non-proliferation merits of fuel-cycle management alternatives. Also discussed is the utility of an integrated assessment of the economics and non-proliferation merits of nuclear fuel leasing.

Monitoring system with integrated measuring sensors for radioactively contaminated iron and non-iron scrap metal (MerEN). Final report; Ueberwachungssystem mit integrierter Messsensorik fuer radioaktiv belastete Eisen- und Nichteisenschrotte (MerEN). Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Celebic, Enis; Gentes, Sascha [Karlsruher Institut fuer Technologie (KIT), Karlsruhe (Germany). Inst. fuer Technologie und Management im Baubetrieb; Rutschmann, Michael; Goerisch, Uwe [Prof. Dr.-Ing. Uwe Goerisch GmbH Ingenieurbuero fuer Abfallwirtschaft, Karlsruhe (Germany); Wetzel, Ramona [Schrott Wetzel GmbH, Mannheim (Germany)

2015-08-15

Radioactive sources are used in the industry, in nuclear medicine, the military, as well as in research. Accidents and losses rarely occur, a proper and responsible handling of those sources provided. Radioactive sources represent a risk when divulged, moved, passed on without authorization or lost. Time and again, radioactive sources are found at scrap yards and metal processing facilities. The supervision of these radioactive materials is gaining importance in the light of the worldwide import and export of ferrous and non-ferrous scrap. The aim of the project was to develop a space monitoring system for radioactively contaminated ferrous and non-ferrous scrap, so it can be removed from the operating range and to protect staff. The monitoring system combines technical and application-specific requirements. As part of the research project, the system was designed based on the operational framework conditions, technical and economic possibilities, and the findings from the experimental phase. The prototype mainly consists of a mainframe computer, stationary and mobile detection units, and the data transfer technology. This has successfully been tested at a scrap yard. The effects of vibrations that occur on scrapyards were investigated. This was necessary to obtain functionality of the hardware. The experimental phase was carried out based on a pre-defined set-up. The aim was to test the individual scenarios, processing and logging of the date as well to interpret the test results. In the event of radioactive sources being found in discarded metal, a standard sequence of actions was designed to protect the yard's processes and its personnel against further radioactive damage. For the first time, active radiation monitoring was performed on scrap-processing machines and in the working range of mobile devices. With this, scrap yard operators will have the opportunity to detect radioactively contaminated material at an early stage and before radiation sources are

Regulatory, administrative and financial problems raised by radioactive waste disposal

International Nuclear Information System (INIS)

Reyners, P.

1980-03-01

This paper analyses the salient aspects of the non-technical problems involved in radioactive waste disposal: the division of operational, regulatory and administrative responsibilities, the usefulness of providing a form of institutional control of the waste disposed of, and the question of the length of time for such mechanisms, both of which are closely linked to the preceding point. A description follows of the R and D financing mechanisms in the field and of the surveillance systems to be set up. Finally, mention is made of the legal and practical difficulties encountered in the application of the third party liability and insurance regime to long-term waste management and the international dimension of all these questions. (NEA) [fr

Current situation with the centralized storage facilities for non-power radioactive wastes in Latin American countries

International Nuclear Information System (INIS)

Benitez, Juan C.; Salgado, Mercedes; Idoyaga Navarro, Maria L.; Escobar, Carolina; Mallaupoma, Mario; Sbriz, Luciano; Moreno, Sandra; Gozalez, Olga; Gomez, Patricia; Mora, Patricia; Miranda, Alberto; Aguilar, Lola; Zarate, Norma; Rodriguez, Carmen

2008-01-01

Full text: Several Latin American (LA) countries have been firmly committed to the peaceful applications of ionizing radiations in medicine, industry, agriculture and research in order to achieve socioeconomic development in diverse sectors. Consequently the use of radioactive materials and radiation sources as well as the production of radioisotopes and labeled compounds may always produce radioactive wastes which require adequate management and, in the end, disposal. However, there are countries in the Latin American region whose radioactive waste volumes do not easily justify a national repository. Moreover, such facilities are extremely expensive to develop. It is unlikely that such an option will become available in the foreseeable future for most of these countries, which do not have nuclear industries. Storage has long been incorporated as a step in the management of radioactive wastes. In the recent years, there have been developments that have led some countries to consider whether the roles of storage might be expanded to provide longer-term care of long-live radioactive wastes The aim of this paper is to discuss the current situation with the storage facilities/conditions for the radioactive wastes and disused sealed radioactive sources in Latin-American countries. In some cases a brief description of the existing facilities for certain countries are provided. In other cases, when no centralized facility exists, general information on the radioactive inventories and disused sealed sources is given. (author)

Nuclear safety requirements for upgrading the National Repository for Radioactive Wastes-Baita Bihor

International Nuclear Information System (INIS)

Vladescu, Gabriela; Necula, Daniela

2000-01-01

The upgrading project of National Repository for Radioactive Wastes-Baita Bihor is based on the integrated concept of nuclear safety. Its ingredients are the following: A. The principles of nuclear safety regarding the management of radioactive wastes and radioprotection; B. Safety objectives for final disposal of low- and intermediate-level radioactive wastes; C. Safety criteria for final disposal of low- and intermediate-level radioactive wastes; D. Assessment of safety criteria fulfillment for final disposal of low- and intermediate-level radioactive wastes. Concerning the nuclear safety in radioactive waste management the following issues are considered: population health protection, preventing transfrontier contamination, future generation radiation protection, national legislation, control of radioactive waste production, interplay between radioactive waste production and management, radioactive waste repository safety. The safety criteria of final disposal of low- and intermediate-level radioactive wastes are discussed by taking into account the geological and hydrogeological configuration, the physico-chemical and geochemical characteristics, the tectonics and seismicity conditions, extreme climatic potential events at the mine location. Concerning the requirements upon the repository, the following aspects are analyzed: the impact on environment, the safety system reliability, the criticality control, the filling composition to prevent radioactive leakage, the repository final sealing, the surveillance. Concerning the radioactive waste, specific criteria taken into account are the radionuclide content, the chemical composition and stability, waste material endurance to heat and radiation. The waste packaging criteria discussed are the mechanical endurance, materials toughness and types as related to deterioration caused by handling, transportation, storing or accidents. Fulfillment of safety criteria is assessed by scenarios analyses and analyses of

Characterization of Analytical Reference Glass-1 (ARG-1)

International Nuclear Information System (INIS)

Smith, G.L.

1993-12-01

High-level radioactive waste may be immobilized in borosilicate glass at the West Valley Demonstration Project, West Valley, New York, the Defense Waste Processing Facility (DWPF), Aiken, South Carolina, and the Hanford Waste Vitrification Project (HWVP), Richland, Washington. The vitrified waste form will be stored in stainless steel canisters before its eventual transfer to a geologic repository for long-term disposal. Waste Acceptance Product Specifications (WAPS) (DOE 1993), Section 1.1.2 requires that the waste form producers must report the measured chemical composition of the vitrified waste in their production records before disposal. Chemical analysis of glass waste forms is receiving increased attention due to qualification requirements of vitrified waste forms. The Pacific Northwest Laboratory (PNL) has been supporting the glass producers' analytical laboratories by a continuing program of multilaboratory analytical testing using interlaboratory ''round robin'' methods. At the PNL Materials Characterization Center Analytical Round Robin 4 workshop ''Analysis of Nuclear Waste Glass and Related Materials,'' January 16--17, 1990, Pleasanton, California, the meeting attendees decided that simulated nuclear waste analytical reference glasses were needed for use as analytical standards. Use of common standard analytical reference materials would allow the glass producers' analytical laboratories to calibrate procedures and instrumentation, to control laboratory performance and conduct self-appraisals, and to help qualify their various waste forms

Prognosis of radioactive wastes quantity in soils of new safety confinement foundation area

International Nuclear Information System (INIS)

Klyuchnikov, A.A.; Panasyuk, N.I.; Podbereznyj, S.S.; Skorbun, A.D.; Levin, G.V. and eds.