Radiopharmaceuticals and other compounds labelled with short-lived radionuclides

CERN Document Server

Welch, Michael J

2013-01-01

Radiopharmaceuticals and Other Compounds Labelled with Short-Lived Radionuclides covers through both review and contributed articles the potential applications and developments in labeling with short-lived radionuclides whose use is restricted to institutions with accelerators. The book discusses the current and potential use of generator-produced radionuclides as well as other short-lived radionuclides, and the problems of quality control of such labeled compounds. The book is useful to nuclear medicine physicians.

Double standards with radioactive waste

International Nuclear Information System (INIS)

Parkinson, A.

2002-01-01

The author claims that whether it is short-lived waste from Commonwealth facilities, long-lived plutonium waste from an atomic bomb test site on Aboriginal land, or reactor waste from Lucas Heights, the Australian government applies double standards to suit its own agenda

The partnership experience on the disposal of low- and intermediate-level short-lived waste in Belgium

International Nuclear Information System (INIS)

Preter, P. de; Cool, W.; Hooft, E.; Waffelaert, A.; Blommaert, J.; Draulans, J.

2008-01-01

With the governmental decision of January 16, 1998, the long-term storage option for the low- and intermediate-level short-lived waste (category A waste) was abandoned and ONDRAF/NIRAS was given the mission to further examine the options of deep and surface disposal, in order to prepare a federal decision on the technical option to be developed. ONDRAF/NIRAS was also asked to develop the methods and structures of interaction with the local stakeholders, and to limit its siting activities to nuclear and candidate municipalities. This brought ONDRAF/NIRAS to the concept of local partnerships with interested municipalities, and during the pre-project phase 1998-2006 partnerships were created with the municipalities of Dessel (STOLA-Dessel, 1999), Mol (MONA, 2000) and Fleurus-Farciennes (PaLoFF, 2003). On 23 June, 2006 the Belgian Government decided that category A waste will be disposed of in a near-surface repository on the territory of the Dessel municipality. This decision implies that ONDRAF/NIRAS, in further interaction with the local stakeholders, can start the preparation of a licence application. This decision was the endpoint of the pre-project phase (1998-2006) and was based on the final reports of the partnerships of Dessel (STOLA-Dessel, now STORA) and Mol (MONA), approved by their municipality councils, and on ONDRAF/NIRAS final report, confirming the feasibility of the proposed disposal systems. As the municipality council of Fleurus did not approve the final report of the partnership PaLoFF, ONDRAF/NIRAS did not submit this report to the responsible minister. The preceding positive local decision in both Dessel (May 2005) and Mol (July 2005), and both on the partnership and municipality council level, to accept, under certain conditions, a disposal facility on their territory was the result of a 6 years long process of discussions within the partnership of all aspects of the disposal system and its integration in the municipality. During these

Prestudy of final disposal of long-lived low and intermediate level waste

International Nuclear Information System (INIS)

Wiborgh, M.

1995-01-01

The repository for long-lived low and intermediate level waste, SFL 3-5, is foreseen to be located adjacent to the deep repository for spent encapsulated fuel, SFL 2. The SFL 3-5 repository comprises of three repository parts which will be used for the different categories of waste. In this report the work performed within a pre-study of the SFL 3-5 repository concept is summarised. The aim was to make a first preliminary and simplified assessment of the near-field as a barrier to radionuclide dispersion. A major task has been to compile information on the waste foreseen to be disposed of in SFL 3-5. The waste comprises of; low and intermediate level waste from Studsvik, operational waste from the central interim storage for spent fuel, CLAB, and the encapsulation plant, decommissioning waste from these facilities, and core components and internal parts from the reactors. The total waste volume has been estimated to about 25000 m 3 . The total activity content at repository closure is estimated to be about 1 ·10 17 Bq in SFL 3-5. At repository closure the short-lived radionuclides, for example Co-60 and Fe-55, have decayed considerably and the activity is dominated by nickel isotopes in the metallic waste from the reactors, to be disposed of in SFL 5. However, other radionuclides may be more or equally important from a safety point of view, e.g cesium-isotopes and actinides which are found in largest amounts in the SFL 3 waste. A first evaluation of the long term performance or the SFL 3-5 repository has been made. A systematic methodology for scenario formulation was tested. The near-field release of contaminants was calculated for a selected number of radionuclides and chemo-toxic elements. The radionuclide release calculations revealed that Cs-137 and Ni-63 would dominate the annual release from all repository parts during the first 1000 years after repository closure and that Ni-59 would dominate at longer times

Prestudy of final disposal of long-lived low and intermediate level waste

Energy Technology Data Exchange (ETDEWEB)

Wiborgh, M [ed.; Kemakta Konsult AB., Stockholm (Sweden)

1995-01-01

The repository for long-lived low and intermediate level waste, SFL 3-5, is foreseen to be located adjacent to the deep repository for spent encapsulated fuel, SFL 2. The SFL 3-5 repository comprises of three repository parts which will be used for the different categories of waste. In this report the work performed within a pre-study of the SFL 3-5 repository concept is summarised. The aim was to make a first preliminary and simplified assessment of the near-field as a barrier to radionuclide dispersion. A major task has been to compile information on the waste foreseen to be disposed of in SFL 3-5. The waste comprises of; low and intermediate level waste from Studsvik, operational waste from the central interim storage for spent fuel, CLAB, and the encapsulation plant, decommissioning waste from these facilities, and core components and internal parts from the reactors. The total waste volume has been estimated to about 25000 m{sup 3}. The total activity content at repository closure is estimated to be about 1 {center_dot}10{sup 17} Bq in SFL 3-5. At repository closure the short-lived radionuclides, for example Co-60 and Fe-55, have decayed considerably and the activity is dominated by nickel isotopes in the metallic waste from the reactors, to be disposed of in SFL 5. However, other radionuclides may be more or equally important from a safety point of view, e.g cesium-isotopes and actinides which are found in largest amounts in the SFL 3 waste. A first evaluation of the long term performance or the SFL 3-5 repository has been made. A systematic methodology for scenario formulation was tested. The near-field release of contaminants was calculated for a selected number of radionuclides and chemo-toxic elements. The radionuclide release calculations revealed that Cs-137 and Ni-63 would dominate the annual release from all repository parts during the first 1000 years after repository closure and that Ni-59 would dominate at longer times.

How Short-Lived Ikaite Affects Calcite Crystallization

OpenAIRE

Besselink, R; Rodriguez-Blanco, JD; Stawski, TM; Benning, LG; Tobler, DJ

2017-01-01

The pathways of CaCO3 crystallization are manifold, often involving one or several metastable amorphous or nanocrystalline intermediate phases. The presence of such intermediates is often overlooked, because they are short-lived and/or occur at small molar fractions. However, their occurrence does not just impact the mechanisms and pathways of formation of the final stable CaCO3 phase, but also affects their crystal size, shape, and structure. Here we document the presence of a short-lived in...

PNGMDR - Characterisation of intermediate-level long-lived wastes

International Nuclear Information System (INIS)

2014-12-01

This document presents the status of the characterization of intermediate-level long-lived wastes which are warehoused on exploited EDF sites or which will be produced during the deconstruction of first-generation reactors. It addresses aspects related to characterisation and packaging of wastes produced before 2015. More specifically, it addresses aspects related to contamination and to activation. Contamination is assessed by measurements whereas activation assessment is based on numerical simulations associated with measurements performed during parcel production. After having mentioned the concerned reactors, the document presents the methodology adopted for these assessments, and reports the progress status of the characterization process for these intermediate-level long-lived wastes

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

Organization of low-level waste management within ANDRA, France

International Nuclear Information System (INIS)

Marque, Y.

1993-01-01

Short-lived waste contains relatively small quantities of radioelements with half-lives of no more than 30 years, and only trace amounts of long-lived radioelements, if any. Cobalt-60, produced by the activation of structural steel in nuclear power plants, accounts for approximately half the radioactivity in waste managed by ADNRA, yet it has only a 5-year half-life. For this reason protection from radiation emitted by this type of waste is not difficult; and the waste will become harmless in less than 300 years. In terms of disposal safety, the guiding principle is simply to isolate the radioactive materials from the environment by disposing of only stabilized waste packages and protecting the packages from outside forces, especially water and human intrusion. Some countries, particularly those that have elected not to sort waste into long-lived and short lived categories, like Germany and Switzerland, plan to dispose of all waste in deep underground repositories. This approach is sometimes a matter of convenience, as is the case for countries like Sweden and Finland, which have built repositories in the Scandinavian granite shield at nuclear power plant sites. France, Spain, the United States, Great Britain, Japan, and others dispose of short-lived waste in near-surface disposal facilities. The safety of the disposal system depends on its three fundamental building blocks: the waste package, the disposal facility, and the site

Disposal approach for long-lived low and intermediate-level radioactive waste

International Nuclear Information System (INIS)

Park, Jin Beak; Park, Joo Wan; Kim, Chang Lak

2005-01-01

There certainly exists the radioactive inventory that exceeds the waste acceptance criteria for final disposal of the low and intermediate-level radioactive waste. In this paper, current disposal status of the long-lived radioactive waste in several nations are summarized and the basic procedures for disposal approach are suggested. With this suggestion, intensive discussion and research activities can hopefully be launched to set down the possible resolutions to dispose of the long-lived radioactive waste

Radioactive waste management and disposal in Australia

International Nuclear Information System (INIS)

Harries, J.R.

1997-01-01

A national near-surface repository at a remote and arid location is proposed for the disposal of solid low-level and short-lived intermediate-level radioactive wastes in Australia. The repository will be designed to isolate the radioactive waste from the human environment under controlled conditions and for a period long enough for the radioactivity to decay to low levels. Compared to countries that have nuclear power programs, the amount of waste in Australia is relatively small. Nevertheless, the need for a national disposal facility for solid low-level radioactive and short-lived intermediate-level radioactive wastes is widely recognised and the Federal Government is in the process of selecting a site for a national near-surface disposal facility for low and short-lived intermediate level wastes. Some near surface disposal facilities already exist in Australia, including tailings dams at uranium mines and the Mt Walton East Intractable Waste Disposal Facility in Western Australia which includes a near surface repository for low level wastes originating in Western Australia. 7 refs, 1 fig., 2 tabs

Radioactive waste management

International Nuclear Information System (INIS)

Pahissa Campa, Jaime; Pahissa, Marta H. de

2000-01-01

Throughout this century, the application of nuclear energy has produced many benefits, in industry, in research, in medicine, and in the generation of electricity. These activities generate wastes in the same way as do other human activities. The primary objective of radioactive waste management is to protect human health and environment now and in the future without imposing undue burden on future generations, through sound, safe and efficient radioactive waste management. This paper briefly describes the different steps of the management of short lived low and intermediate level wastes, and presents and overview of the state of art in countries involved in nuclear energy, describing their organizations, methodologies used in the processing of these wastes and the final disposal concepts. It also presents the Argentine strategy, its technical and legal aspects. Worldwide experience during the past 50 years has shown that short lived low and intermediate level wastes can be successfully isolated from human and environment in near surface disposal facilities. (author)

Practical applications of short-lived radioisotopes

Energy Technology Data Exchange (ETDEWEB)

NONE

1963-01-15

The advantages of the use of short-lived radioisotopes in agriculture, food industry and medicine as well as some industrial uses are discussed. Methods for isotope production in small research reactors and laboratories are presented

Managing fusion high-level waste-A strategy for burning the long-lived products in fusion devices

International Nuclear Information System (INIS)

El-Guebaly, L.A.

2006-01-01

Fusion devices appear to be a viable option for burning their own high-level waste (HLW). We propose a novel strategy to eliminate (or minimize) the HLW generated by fusion systems. The main source of the fusion HLW includes the structural and recycled materials, refractory metals, and liquid breeders. The basic idea involves recycling and reprocessing the waste, separating the long-lived radionuclides from the bulk low-level waste, and irradiating the limited amount of HLW in a specially designed module to transmute the long-lived products into short-lived radioisotopes or preferably, stable elements. The potential performance of the new concept seems promising. Our analysis indicated moderate to excellent transmutation rates could be achieved in advanced fusion designs. Successive irradiation should burn the majority of the HLW. The figures of merit for the concept relate to the HLW burn-up fraction, neutron economy, and impact on tritium breeding. Hopefully, the added design requirements could be accommodated easily in fusion power plants and the cost of the proposed system would be much less than disposal in a deep geological HLW repository. Overall, this innovative approach offers benefits to fusion systems and helps earn public acceptance for fusion as a HLW-free source of clean nuclear energy

High-power proton linac for transmuting the long-lived fission products in nuclear waste

Energy Technology Data Exchange (ETDEWEB)

Lawrence, G.P.

1991-01-01

High power proton linacs are being considered at Los Alamos as drivers for high-flux spallation neutron sources that can be used to transmute the troublesome long-lived fission products in defense nuclear waste. The transmutation scheme being studied provides a high flux (> 10{sup 16}/cm{sup 2}{minus}s) of thermal neutrons, which efficiently converts fission products to stable or short-lived isotopes. A medium-energy proton linac with an average beam power of about 110 MW can burn the accumulated Tc99 and I129 inventory at the DOE's Hanford Site within 30 years. Preliminary concepts for this machine are described. 3 refs., 5 figs., 2 tabs.

Current status of radioactive waste disposal in Japan and foreign countries

International Nuclear Information System (INIS)

Yamamoto, Masahumi; Inagaki, Yusuke; Kurata, Mitsuyuki; Tanabe, Hiromi

2002-01-01

Various kinds of wastes are generated from operation and decommissioning of nuclear facilities such as a nuclear power plant, a reprocessing plant and so on. These wastes contain radionuclides and are called 'Radioactive Waste'. The radionuclides in the wastes vary considerably in amount from small to large and their half-lives differ in length from short-lived to long-lived. The safety principle for radioactive waste management is to prevent human beings and the environment from receiving radiation exposure over the level which the safety authority in each country approve based on the recommendations by international organizations such as the International Commission on Radiation Protection (ICRP). To assure the conformity to this safety principle, each country has examined the safety measures to dispose of radioactive wastes on the basis of their own condition. For example, high-level radioactive waste (H LW) from reprocessing plant or spent fuel designated as waste and intermediate-and low-level long-lived radioactive wastes, which contain large quantity of long-lived radionuclides, will be disposed of into a deep stable geological formation. The intermediate-and low-level short-lived radioactive wastes, which mainly contain short-lived radionuclides with limited quantity of long-lived radionuclides, have been disposed of in a controlled surface disposal facility or in a rock cavern in the depth of 50-100 m. Clearance level has been considered to be applied for the wastes, which contain very small amount of radionuclides and those wastes bellow clearance level will cause negligible hazards only even without taking any radiation control measures. Such wastes could be reused, recycled or disposed of in the same manner as general wastes from the industries, etc. (author)

Waste inventory record keeping systems (WIRKS) for the management and disposal of radioactive waste

International Nuclear Information System (INIS)

2001-06-01

This report is intended to serve Member States planning to develop or implement radioactive waste disposal programmes and to discuss possible ways for compiling and managing information about the inventories in their radioactive waste repositories, which includes low and intermediate level waste (short lived and long lived) and high level radioactive waste. This report identifies generic information that may be recorded in a Waste Inventory Record Keeping System (WIRKS), as identified by consultants and based on their collective expertise in radioactive waste management. The report provides examples of WIRKS implementation in some countries

Short-lived radiopharmaceutical development at E.R. Squibb and Sons, Inc

International Nuclear Information System (INIS)

Loberg, M.D.

1985-01-01

This paper describes the present status and future plans of E.R. Squibb and Sons, Inc. as they relate to the development of short-lived radiopharmaceuticals. The advantages of short-lived radiopharmaceuticals are summarized as are the problems inherent in their manufacture, quality control, and distribution. The nuclear generator is advocated as the best means of distributing short-lived radiopharmaceuticals. The E.R. Squibb and Sons work with the 82 Sr → 82 Rb generator is summarized

Measurements of beta-decay half-lives of short-lived nuclei

Energy Technology Data Exchange (ETDEWEB)

Hirose, T.; Tsurita, Y.; Yamamoto, H.; Kawade, K. [Nagoya Univ. (Japan); Iida, T.; Takahashi, A.; Kasugai, Y.; Ikeda, Y.

1997-03-01

The {beta}-decay half-lives of short-lived nuclei produced by 14 MeV neutron bombardments were measured with Ge detectors, a High-rate spectroscopy amplifier (EG and G ORTEC model 973) and a Spectrum multi-scaler (Laboratory equipment corporation SMS-48) in the multi-scaling mode. The adequate corrections for pile-up and dead-time losses were made by applying source and pulser methods. The half-lives of {sup 53}V, {sup 53g}Fe, {sup 89m}Y and {sup 162}Tb were determined with uncertainties of 0.13-0.65%. It has been shown that previous values shorter than 10 min were systematically longer than the present ones. (author)

Systematic measurement of beta-decay half-lives of short-lived isotopes

Energy Technology Data Exchange (ETDEWEB)

Hirose, T.; Yamamoto, H.; Kawade, K. [Nagoya Univ. (Japan); Iida, T.; Takahashi, A.; Kasugai, Y.; Ikeda, Y.

1997-03-01

We have measured the half-lives of short-lived isotopes for past decade and deduced the half-lives of 6 isotopes further. These results demonstrated that most of the literature values shorter than 10 min systematically deviated from our measurement ones. The cause seems to be that a large number of the previous half-life studies were performed with scintillation counters before 1970 and they had a difficulty in distinguishing the interest {gamma}-ray from the contamination and correcting for pile-up and dead-time losses. Moreover, the deviated data found to be quoted for evaluation. (author)

Transmutation of long-lived nuclear waste

International Nuclear Information System (INIS)

Abrahams, K.

1992-10-01

Nuclear waste disposal in geologically stable repositories is considered to be safe and effective, and the assumptions, which lead to very long term predictions seem to be satisfied. As possibilities to perturb repositories, can never be entirely excluded, it could be an attractive option to reduce the toxicity of waste by supplementing the uranium-plutonium cycle with minor actinide burning cycles. In this option the amount of mining waste is limited at the same time because uranium is used economically. If requests for reduction of long-lived actinide waste would result in much higher costs for nuclear energy, the innovative thorium-uranium cycle might become competitive. It is of vital interest that efforts are now being internationalized in networks to make proper use of experience from past civil and military programs. Visions for almost pollution-free energy production could arise if well prepared minds are concentrated on this issue. (author). 5 refs., 2 figs., 1 tab

The waste disposal facility in the Aube District

International Nuclear Information System (INIS)

Torres, Patrice

2013-06-01

The waste disposal facility in the Aube district is the second surface waste disposal facility built in France. It is located in the Aube district, and has been operated by Andra since 1992. With a footprint of 95 hectares, it is licensed for the disposal of 1 million cubic meters of low- and intermediate-level, short-lived waste packages. The CSA is located a few kilometers away another Andra facility, currently in operation for very-low-level waste, and collection and storage of non-nuclear power waste (the Cires). Contents: Andra in the Aube district, an exemplary industrial operator - The waste disposal facility in the Aube district (CSA); Low- and intermediate-level, short-lived radioactive waste (LILW-SL); The LILW-SL circuit; Protecting present and future generations

Application of accelerator-produced short-lived radionuclides in industry

International Nuclear Information System (INIS)

Kupsch, H.

1986-01-01

Several problems such as corrosion, catalysis, wear, process optimization and diagnosis, damage analysis, arising in idustry can be solved using short-lived radioisotopes. Some examples of technological target designs which have been developed are demonstrated for the radionuclide production based on p,n; d,α; α,n; α,2n; α,p; γ,n; γ,p nuclear reactions. Applications of short-lived radionuclides in plants and processes of electrodeposition and gas concrete production are described. (author)

Public participation in decision-making processes: ONDRAF/NIRAS' approach to the disposal of low-level and short-lived radioactive waste

International Nuclear Information System (INIS)

Hooft, E.

2000-01-01

January 16, 1998, is a milestone in the nuclear waste management in Belgium. On that day, the Belgian government effectively opted for a definitive or potentially definitive solution for the Iona term management of low-level, short-lived radioactive waste. The government also wanted this solution to be implemented in a progressive, flexible, and reversible manner. it was thereby definitively abandoning the prolonged interim storage option, in favour of either surface disposal or deep geological disposal. At the same time, the government entrusted new missions to ONDRAFINIRAS, aimed at enabling it to make, around 2001-2002, the necessary technical and economic choice between surface disposal and deep geological disposal. ONDRAFNIRAS had to develop, in particular, methods, including the management and dialogue strictures, necessary to integrate a repository project at the local level. Furthermore, it had to restrict from then on its investigations to the four already existing nuclear zones in Belgium namely those of Doel, Fleurus, Mol-Dessel, and Tihange, and to the local towns or villages having shown an interest in a preliminary field study. Early in 1998, ONDRAFNIRAS set up a new work programme and developed an entirely new work methodology. As we understood that the best way to take involved into account the interests of all parties, is to involve them in the decision making on the project, we developed the idea of the local partnerships. Any party that could be directly affected by a collective decision, must have a say in it. Another innovative aspect of this new methodology is that of integration: an integration at the local level which is meant to enable the development of draft repository projects creating new perspectives for the regions concerned. Extending over four to five years, ONDRAFINIRAS's new work programme assumes the active participation of all the interested local representatives. Because it has understood that any party that could be directly

Development plan. High activity-long living wastes project. Abstract

International Nuclear Information System (INIS)

2007-01-01

This brochure presents the actions that the ANDRA (the French national agency of radioactive wastes) has to implement in the framework of the project of high activity-long living (HALL) radioactive wastes (HAVL project) conformably to the requirements of the program defined in the law from June 28, 2006 (law no 2006-739). This law precises the three, complementary, research paths to explore for the management of this type of wastes: separation and transmutation of long-living radioactive elements, reversible disposal in deep geologic underground, and long duration storage. The ANDRA's action concerns the geologic disposal aspect. The following points are presented: the HALL wastes and their containers, the reversible disposal procedure, the HAVL project: financing of researches, storage concepts, development plan of the project (dynamics, information and dialogue approach, input data, main steps, schedule); the nine programs of the HAVL project (laboratory experiments and demonstration tests, surface survey, scientific program, simulation program, surface engineering studies and technological tests, information and communication program, program of environment and facilities surface observation and monitoring, waste packages management, monitoring and transport program, disposal program); the five transverse technical and scientific activities (safety, reversibility, cost, health and occupational safety, impact study). (J.S.)

Plate waste of adults in the United States measured in free-living conditions.

Directory of Open Access Journals (Sweden)

Brian E Roe

Full Text Available We analyze food-item level data collected from 50 adults from the United States using the Remote Food Photography Method® to provide the first estimates of plate waste gathered from adults across multiple consecutive meals and days in free-living conditions, and during laboratory-based meals with fixed food items and quantities. We find average plate waste in free-living conditions is 5.6 grams (7.7 kcals per item and that 3.3% of all food selected is returned as plate waste, where the percent waste figure is substantially lower than previously published plate waste estimates gathered primarily from dine-out settings in the United States such as buffets and institutional settings with limited-choice meals (e.g., school cafeterias. Plate waste from the same participants during the laboratory-based meals is significantly higher with an average of 203.2 grams of solid plate waste per meal (531.3 kcals or 39.1% of the food provided, which is similar to the plate waste percentages found reported in some school cafeteria settings. The amount of plate waste generated in free-living conditions is significantly positively associated with portion size selected for an item. In a multivariate analysis that controls for macronutrient profile, items selected from the vegetables, fats/oils/dressings, and grains categories are associated with significantly greater amounts of plate waste per item. We find no significant associations between free-living plate waste and gender, age, race or body mass index but find that women leave more plate waste in the lab meal where portion sizes are pre-determined by the researcher and similar for all respondents. We discuss possible implications of these findings for programs focused on reducing plate waste and food waste among consumers.

Plate waste of adults in the United States measured in free-living conditions

Science.gov (United States)

Allen, H. Raymond

2018-01-01

We analyze food-item level data collected from 50 adults from the United States using the Remote Food Photography Method® to provide the first estimates of plate waste gathered from adults across multiple consecutive meals and days in free-living conditions, and during laboratory-based meals with fixed food items and quantities. We find average plate waste in free-living conditions is 5.6 grams (7.7 kcals) per item and that 3.3% of all food selected is returned as plate waste, where the percent waste figure is substantially lower than previously published plate waste estimates gathered primarily from dine-out settings in the United States such as buffets and institutional settings with limited-choice meals (e.g., school cafeterias). Plate waste from the same participants during the laboratory-based meals is significantly higher with an average of 203.2 grams of solid plate waste per meal (531.3 kcals) or 39.1% of the food provided, which is similar to the plate waste percentages found reported in some school cafeteria settings. The amount of plate waste generated in free-living conditions is significantly positively associated with portion size selected for an item. In a multivariate analysis that controls for macronutrient profile, items selected from the vegetables, fats/oils/dressings, and grains categories are associated with significantly greater amounts of plate waste per item. We find no significant associations between free-living plate waste and gender, age, race or body mass index but find that women leave more plate waste in the lab meal where portion sizes are pre-determined by the researcher and similar for all respondents. We discuss possible implications of these findings for programs focused on reducing plate waste and food waste among consumers. PMID:29444094

Fiscal 1982 progress report of 'comprehensive research on the management of long-lived radioactive wastes' in the Research Center for Nuclear Science and Technology, University of Tokyo

International Nuclear Information System (INIS)

Sekiguchi, Akira; Kosako, Toshiso

1983-01-01

In the Research Center for Nuclear Science and Technology, University of Tokyo, the special research project ''Comprehensive Research on the Management of Long-lived Radioactive Wastes'' is carried out in the three-year period from fiscal 1982 to 1984. The works performed in the fiscal year 1982 are described individually, each short description on research purposes and contents, results, future plans, etc. the research works in the three fields of material science, biology and process technology are buffer materials in land disposal, canisters, corrosion of waste-container materials, thermal analysis of high-level wastes, effects of tritium on cells and marine life, biological effect of long-lived nuclides, separation of tritium wastes, actinoids and krypton-iodine, environmental migration of radionuclides, and accident analysis. (Mori, K.)

Alternative solutions for the disposal of radioactive wastes

International Nuclear Information System (INIS)

Ramsey, R.W. Jr.

1976-01-01

Besides outlining the possibility of dispatching concentrated highly radioactive waste by rockets into space, or of transmuting long-lived isotopes by nuclear reactions into short-lived ones, the author discusses further alternatives for the disposal of radioactive wastes, especially the storage in geologic formations. (HR/LN) [de

Proposed partitioning and transmutation of long-lived nuclear wastes

International Nuclear Information System (INIS)

Van Tuyle, G.J.; Rawlins, J.A.

1991-01-01

A means of transmuting key long-lived nuclear wastes, primarily the minor actinides (Np, Am, Cm) and iodine, using a hybrid proton accelerator and sub-critical lattice, is proposed. By partitioning light water reactor (LWR) spent fuel and by transmuting key elements, such as the plutonium, the minor actinides, and a few of the long-lived fission products, some of the most significant challenges in building a waste repository can be substantially reduced. The proposed machine would transmute the minor actinides and the iodine produced by 75 LWRs, and would generate usable electricity (beyond that required to run the large accelerator) of 850 MW e . 14 refs., 10 figs

Nuclear waste transmutation

International Nuclear Information System (INIS)

Leray, S.

1995-01-01

Accelerators can play a role in the disposal of long-lived radioactive waste: an alternative to the storage in deep underground repositories might transmuting long-lived elements into stable or short-lived ones in subcritical systems driven by spallation neutrons. These neutrons would be produced by a high intensity, intermediate energy proton accelerator irradiating a heavy target. Similar systems have also been proposed to produce energy with a minimized waste inventory. Since a good knowledge of the spallation process is essential for designing and optimizing the target-blanket assembly, new programmes aimed at studying spallation reactions are in progress. (author). 6 figs

Andra. Everything on the management of radioactive wastes

International Nuclear Information System (INIS)

2014-08-01

This publication briefly presents the ANDRA, the French National Agency for the management of radioactive wastes, its mission, its activities, its financing, and some key figures. It briefly presents the phenomenon of radioactivity, radioactive wastes and their storage. It presents the different classes of radioactive wastes (very-low-level, low- and intermediate-level and short-lived, low-level and long-lived, high-level and intermediate-level and long-lived) and their storage principles. It sketches the pathway followed by a waste from its production to its storage. It presents the various ANDRA sites

Radioactive waste treatment and handling in France

International Nuclear Information System (INIS)

Sivintsev, Yu.V.

1984-01-01

Classification of radioactive wastes customary in France and the program of radiation protection in handling them are discussed. Various methods of radioactive waste processing and burial are considered. The French classification of radioactive wastes differs from one used in the other countries. Wastes are classified under three categories: A, B and C. A - low- and intermediate-level radioactive wastes with short-lived radionuclides (half-life - less than 30 years, negligible or heat release, small amount of long-lived radionuclides, especially such as plutonium, americium and neptunium); B - low- and intermediate-level radioactive wastes with long-lived radionuclides (considerable amounts of long-lived radionuclides including α-emitters, low and moderate-level activity of β- and γ-emitters, low and moderate heat release); C - high-level radioactive wastes with long-lived radionuclides (high-level activity of β- and γ-emitters, high heat release, considerable amount of long-lived radionuclides). Volumetric estimations of wastes of various categories and predictions of their growth are given. It is noted that the concept of closed fuel cycle with radiochemical processing of spent fuel is customary in France

Mass Measurement of Very Short Half-Lived Nuclei

CERN Document Server

Duma, M; Iacob, V E; Thibault, C

2002-01-01

The MISTRAL (Mass measurements at ISolde with a Transmission RAdiofrequency spectrometer on-Line) experiment exploits a rapid measurement technique to make accurate mass determinations of very short-lived nuclei. The physics goals are to elucidate new nuclear structure effects and constrain nuclear mass models in regions of interest to nuclear astrophysics.\\\\ \\\\The spectrometer, installed in May 97, performed as promised in the proposal with mass resolution exceeding 100,000. In its first experiment in July 1998, neutron-rich Na isotopes having half-lives as short as 31 ms were measured. A second experiment in November 1998 enabled us to improve the measurement precision of the isotopes $^{26-30}$Na to about 20 keV. The measurement program continues as experiment IS 373.

HMPT: Hazardous Waste Transportation Live 27928, Test 27929

Energy Technology Data Exchange (ETDEWEB)

Simpson, Lewis Edward [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-03-17

HMPT: Hazardous Waste Transportation (Live 27928, suggested one time and associated Test 27929, required initially and every 36 months) addresses the Department of Transportation (DOT) function-specific training requirements of the hazardous materials packagings and transportation (HMPT) Los Alamos National Laboratory (LANL) lab-wide training. This course addresses the requirements of the DOT that are unique to hazardous waste shipments. Appendix B provides the Title 40 Code of Federal Regulations (CFR) reference material needed for this course.

Intrinsically secure fast reactors for long-lived waste free and proliferation resistant nuclear power

International Nuclear Information System (INIS)

Slessarev, Igor

2008-01-01

This paper provides description of a nuclear reactor concept aimed towards a radical safety enhancement, an increased proliferation resistance, as well as a realisation of a 'long-lived waste free' NP development. It emphasizes the achievement of considerable reduction ('by design') of residual actinides in the waste streams and of the most hazardous long-lived fission products. It allows to implement only small volume of repositories for the radioactive waste (mostly fission products) and to postpone the technically arduous problems of a large scale disposal of the long-lived wastes until the next millennium, i.e. up to the exhaustion of the fertile natural resources and/or the emergence of more effective technologies of nuclide separation/transmutation. A thorough incineration/transmutation of the wastes (residual actinides in the mixture with lanthanides as well as of the most hazardous fission products) under reactor neutron flux is proposed for their mass reduction. A gradual growth of NP park is necessary for increasing the NP park capacity for waste irradiation. This 'constraint' is not really limiting because it coincides with the permanently growing demands in energy production. The potential of long-lived waste reduction depends on the total fertile fuel resources and on NP growth rate. It was shown that the accumulated actinide long-lived radioactive masses will be reduced significantly: by factor in the range of 10 4 -10 8 in magnitude (compared with LWR once-through cycle) and by 10 2 -10 6 (compared with the ordinary fast reactor park). Thus, the total long-lived waste toxicity pollution source might be comparable with the 'burnt away' toxicity of the natural fertile feed stream. This is quite realistic taking into account the large fertile fuel (U/Th) world-wide resources which provide the NP growth for a sustained time. Along side with the radical intrinsic safety improvement, a further enhancement of core physics ('neutronics') is one of the

Long-lived radioactive waste, the French management policy

International Nuclear Information System (INIS)

Barber, P.

1994-01-01

An overwhelming majority of both chambers of the French Parliament voted in favor of Public Law 91-1381 on December 30, 1991, the Waste Act which outlines the research program to be conducted for disposal of long-lived waste. The program focuses on three main research objectives, which are briefly discussed in this presentation: reduction of waste volume and toxicity (advanced partitioning and transmutation); assessment of the waste isolation properties of deep geologic formations; and development of solidification processes and storage techniques for long-term interim storage in near surface facilities. Annual reports on this research will be reviewed by a national commission and submitted to Parliament. Within 15 years, the government will prepare a comprehensive report and may enact new legislation authorizing the creation of a repository. The Waste Act also establishes the conditions for underground geologic research laboratories; site selection, public information and monitoring procedures; and economic incentives related to these facilities, which represent major financial investments that will benefit communities in the involved regions

Measurement of short-lived particles at PETRA

International Nuclear Information System (INIS)

Saxon, D.H.

1987-04-01

The contribution of PETRA to the measurement of short-lived particles is reviewed with discussion of the detectors and analysis techniques. New results are presented on lifetimes of identified particles and the systematics of b-life measurement outlined. The first application of vertex-tagging to flavour separation is described. (author)

The ratio of long-lived to short-lived radon-222 progeny concentrations in ground-level air

International Nuclear Information System (INIS)

Hoetzl, H.; Winkler, R.

1996-01-01

The ratio of 210 Pb air concentration to the short-lived radon ( 222 Rn) decay products concentration at ground level was investigated at a semi-rural location 10 km north of Munich, south Germany, for a period of 11 years (1982-1992). The average ratio from 132 monthly mean values has been found to be (7.5±2.2) x 10 -5 (arithmetic mean±S.D.). While the time series of the short-lived radon daughter concentration exhibit a distinct seasonal pattern with maxima mostly in October of each year, the course of 210 Pb air concentration is characterized by high values from October through February. Consequently, high ratios of 210 Pb to short-lived decay product concentration are often observed in the winter months of December-February. To study the influence of meteorological conditions on this behaviour, 210 Pb and 214 Pb concentrations were measured on a short-term basis with sampling intervals of 2-3 days from October 1991 to November 1992. The air concentrations obtained within those intervals were then correlated with actual meteorological parameters. On the base of this investigation the seasonal behaviour can essentially be explained by the more frequent inversion weather conditions in winter than in the summer months. At the same location, the average ratio of 210 Po to 210 Pb concentration in ground level air has been found to be 0.079 from 459 weakly mean values between 1976 and 1985. Hence, the corresponding average ratios of the short-lived radon daughters (EEC) to 210 Pb and 210 Po, were 1:7.5x10 -5 and 1:0.6 x 10 -5 , respectively

The national plan of radioactive materials and wastes management. ASN's notice about the choice of the sites to be investigated in view of the setting up of a disposal facility for low activity/long living wastes

International Nuclear Information System (INIS)

2009-07-01

This short presentation, given by the national safety authority (ASN) at the meeting of July 1, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), presents, first, the second French national plan of radioactive materials and wastes management (PNGMDR) with its main priorities, and then, the choice of the sites to survey in view of the setting up of a disposal facility for low level/long living wastes. The ASN expresses its opinion about the criteria retained by the ANDRA (the national agency of radioactive waste management) to select the most suitable sites. (J.S.)

Technologies for destruction of long-lived radionuclides in high-level nuclear waste - overview and requirements

International Nuclear Information System (INIS)

Arthur, E.D.

1993-01-01

A major issue surrounding current nuclear power generation is the management and disposal of long-lived, high-level waste (HLW). The planned and scientifically acceptable destination for this waste is in deep underground, geologically stable, repositories. However, public concerns surrounding such disposal of long-lived nuclear wastes and other issues such as proliferation and safety negatively affect the potential role that nuclear power can play in meeting current and future national energy needs. This paper and this topical session on nuclear waste minimization, management, and remediation focus on two nuclear systems and their associated technologies that have the potential to address concerns surrounding long-lived radionuclides in HLW. Both systems offer technology applicable to HLW from current light water reactors (LWRs). In addition, these systems represent advanced nuclear power concepts that have important features associated with integrated management of wastes long-term fuel supplies, and enhanced safety. The first system is the integral fast reactor (IFR) concept. This system incorporates a metal-fueled fast reactor coupled with chemical separations based on pyroprocessing to produce power while burning long-lived actinide waste. The IFR applications include the burning of actinides from current LWR spent fuel and energy production in a breeder environment. The second concept, accelerator transmutation of waste (ATW), is based on an accelerator-induced intense source of thermal neutrons and is aimed at the destruction of long-lived actinides and fission products. This concept can be applied to long-lived radionuclides in spent-fuel HLW as well as a future fission power source built around use of natural thorium or uranium as fuels coupled with concurrent waste destruction

Ethical aspects of the disposal of long-lived radioactive waste

International Nuclear Information System (INIS)

McCombie, C.

1997-01-01

Absolving waste management responsibilities requires consensus within the present, waste-producing society, but also fairness towards future generations. This situation has been discussed at length in the formulation of disposal strategies for long-lived radioactive waste, although some other activities practised today are likely to lead to much more dramatic, permanent changes to our environment. Drawing on recent publications on ethical aspects of waste disposal, this article provides an overview of the topic, highlighting both those principles for which there already is a consensus and those which are still regarded as controversial. (author) 3 figs., 1 tab., refs

The ratio of long-lived to short-lived radon-222 progeny concentrations in ground-level air

Energy Technology Data Exchange (ETDEWEB)

Hoetzl, H.; Winkler, R. [Institut fuer Strahlenschutz, GSF-Forschungszentrum fuer Umwelt und Gesundheit, Neuherberg Oberschleissheim (Germany)

1996-02-09

The ratio of {sup 210}Pb air concentration to the short-lived radon ({sup 222}Rn) decay products concentration at ground level was investigated at a semi-rural location 10 km north of Munich, south Germany, for a period of 11 years (1982-1992). The average ratio from 132 monthly mean values has been found to be (7.5{+-}2.2) x 10{sup -5} (arithmetic mean{+-}S.D.). While the time series of the short-lived radon daughter concentration exhibit a distinct seasonal pattern with maxima mostly in October of each year, the course of {sup 210}Pb air concentration is characterized by high values from October through February. Consequently, high ratios of {sup 210}Pb to short-lived decay product concentration are often observed in the winter months of December-February. To study the influence of meteorological conditions on this behaviour, {sup 210}Pb and {sup 214}Pb concentrations were measured on a short-term basis with sampling intervals of 2-3 days from October 1991 to November 1992. The air concentrations obtained within those intervals were then correlated with actual meteorological parameters. On the base of this investigation the seasonal behaviour can essentially be explained by the more frequent inversion weather conditions in winter than in the summer months. At the same location, the average ratio of {sup 210}Po to {sup 210}Pb concentration in ground level air has been found to be 0.079 from 459 weakly mean values between 1976 and 1985. Hence, the corresponding average ratios of the short-lived radon daughters (EEC) to {sup 210}Pb and {sup 210}Po, were 1:7.5x10{sup -5} and 1:0.6 x 10{sup -5}, respectively.

Nondestructive and destructive measurements, a synergy for the wastes characterization

International Nuclear Information System (INIS)

Amoravain, S.; Dogny, S.

2001-01-01

The waste generated by nuclear industry have to be treated and conditioned to be stored in sites managed by ANDRA. Three channels are conceivable, the storage of very low activity waste, the surface storage of short live and low and intermediate activity waste, and the deep storage for long life or high activity waste. At this day, only the surface storage for waste at short life and low and intermediate activity is operational and allows to evacuate the radioactive waster. (N.C.)

Technologies for destruction of long-lived radionuclides in high-level nuclear waste: Overview and requirements

International Nuclear Information System (INIS)

Arthur, E.D.

1993-01-01

This paper, and this topical session on Nuclear Waste Minimization, Management and Remediation, focuses on two nuclear systems, and their associated technologies, that have the potential to address concerns surrounding long-lived radionuclides in high-level waste. Both systems offer technology applicable to HLW from present light-water reactors (LWR). Additionally these systems represent advanced nuclear power concepts that have important features associated with integrated management of wastes, long-term fuel supplies, and enhanced safety. The first system is the Integral Fast Reactor (IFR) concept. This system incorporates a metal-fueled fast reactor coupled with chemical separations based on pyroprocessing to produce power while simultaneously burning long-lived actinide waste. IFR applications include burning of actinides from current LWR spent fuel and energy production in a breeder environment. The second concept, Accelerator Transmutation of Waste (ATW), is based upon an accelerator-induced intense source of thermal neutrons and is aimed at destruction of long-lived actinides and fission products. This concept can be applied to long-lived radionuclides in spent fuel HLW as well as a future fission power source built around use of natural thorium or uranium as fuels coupled with concurrent waste destruction

Long-lived radioactive waste, the French management policy

International Nuclear Information System (INIS)

Barber, P.

1994-01-01

An overwhelming majority of both chambers of the French Parliament voted in favor of Public Law 91-1381 on December 30, 1991, which outlines the research program to be conducted for disposal of long-lived waste. The program focuses on three main research objectives: reduction of waste volumes and toxicity (advanced partitioning and transmutation); assessment of the waste isolation properties of deep geologic formations; and development of solidification processes and storage techniques for long-term interim storage in near-surface facilities. Annual reports on this research will be reviewed by a national commission and submitted to Parliament. Within 15 years, the government will prepare a comprehensive report and may enact new legislation authorizing the creation of a repository. The Waste Act also establishes the conditions for siting underground geologic research laboratories; site selection, public information and monitoring procedures; and economic incentives related to these facilities, which represent major financial investments that will benefit communities in the involved regions

Management of ''short-lifetime'' radioactive wastes, an industrial reality to safeguard the environment

International Nuclear Information System (INIS)

Faussat, A.

1992-01-01

On the occasion of the inauguration of the Aube waste storage center by A.Billardon, Vice Minister for Energy, the author reviews the management situation in France for short life radioactive wastes. The wastes are first defined and their characteristics explained, and then are discussed the general principles underlying the management of these wastes, which involves finding ways to avoid the dispersal of radioactive products into the environment. The author explains why the French have chosen surface storage, and then goes into the integrated management system developed to optimize the long-term management of short-term wastes on the technical and economic levels. The two storage centers existing in France (the Manche and Aube centers) are then described. The article winds up with a presentation of the system as it has been adapted abroad, and another possible adaptation for use in storing toxic industrial wastes. 2 figs., 3 photos

Dossier: management of nuclear wastes. Research, results

International Nuclear Information System (INIS)

Anon.

2001-01-01

The researches carried out since many years on nuclear wastes have led to two main ways of management: the long-term conditioning of radio-elements and their advanced separation. The French atomic energy commission (CEA) has chosen to take up also the transmutation challenge, a way to transform long-living radioactive wastes into short-living radioactive wastes or stable compounds. The transmutation programs are based both on simulation and experiments with a huge international collaboration. This dossier presents in a digest way the research activity carried out on nuclear wastes processing and management at the CEA. (J.S.)

Soot and short-lived pollutants provide political opportunity

Science.gov (United States)

Victor, David G.; Zaelke, Durwood; Ramanathan, Veerabhadran

2015-09-01

Cutting levels of soot and other short-lived pollutants delivers tangible benefits and helps governments to build confidence that collective action on climate change is feasible. After the Paris climate meeting this December, actually reducing these pollutants will be essential to the credibility of the diplomatic process.

Progress on the national low level radioactive waste repository and national intermediate level waste store

International Nuclear Information System (INIS)

Perkins, C.

2003-01-01

The Australian Government is committed to establishing two purpose-built facilities for the management of Australia's radioactive waste; the national repository for disposal of low level and short-lived intermediate level ('low level') waste, and the national store for storage of long-lived intermediate level ('intermediate level') waste. It is strongly in the interests of public security and safety to secure radioactive waste by disposal or storage in facilities specially designed for this purpose. The current arrangements where waste is stored under ad hoc arrangements at hundreds of sites around Australia does not represent international best practice in radioactive waste management. Environmental approval has been obtained for the national repository to be located at Site 40a, 20 km east of Woomera in South Australia, and licences are currently being sought from the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) to site, construct and operate the facility. The national repository may be operating in 2004 subject to obtaining the required licences. The national store will be located on Australian Government land and house intermediate level waste produced by Australian Government departments and agencies. The national store will not be located in South Australia. Short-listing of potentially suitable sites is expected to be completed soon

Short Lived Fission Product Yield Measurements in 235U, 238U and 239Pu

Science.gov (United States)

Silano, Jack; Tonchev, Anton; Tornow, Werner; Krishichayan, Fnu; Finch, Sean; Gooden, Matthew; Wilhelmy, Jerry

2017-09-01

Yields of short lived fission products (FPYs) with half lives of a few minutes to an hour contain a wealth of information about the fission process. Knowledge of short lived FPYs would contribute to existing data on longer lived FPY mass and charge distributions. Of particular interest are the relative yields between the ground states and isomeric states of FPYs since these isomeric ratios can be used to determine the angular momentum of the fragments. Over the past five years, a LLNL-TUNL-LANL collaboration has made precision measurements of FPYs from quasi-monoenergetic neutron induced fission of 235U, 238U and 239Pu. These efforts focused on longer lived FPYs, using a well characterized dual fission chamber and several days of neutron beam exposure. For the first time, this established technique will be applied to measuring short lived FPYs, with half lives of minutes to less than an hour. A feasibility study will be performed using irradiation times of < 1 hour, improving the sensitivity to short lived FPYs by limiting the buildup of long lived isotopes. Results from this exploratory study will be presented, and the implications for isomeric ratio measurements will be discussed. This work was performed under the auspices of US DOE by LLNL under Contract DE-AC52-07NA27344.

COMPAS: a European project on the ''comparison of alternative waste management strategies for long-lived radioactive wastes''. Scope, working methods and conclusions

International Nuclear Information System (INIS)

Dutton, L.M.C.; Hillis, Z.K.; Roehlig, K.J.

2004-01-01

The paper presents the content and major findings of a project on the ''COMParison of Alternative waste management Strategies for long-lived radioactive wastes'' (COMPAS) carried out within the 5 th framework programme of the European commission. Under the leadership of NNC (UK), the project was carried out by individuals representing waste management organisations from 15 European countries. After having compiled information on the nature and amount of long-lived radioactive waste to be managed, issues influencing the selection of waste management strategies and options, presently adopted national strategies as well as options for the future were addressed. Conclusions concerning key issues for the success or otherwise of strategies and management solutions were drawn. (orig.)

Applications of short lived nuclides in activation analysis, problems and progress

Energy Technology Data Exchange (ETDEWEB)

Grass, F [Atominstitut, Vienna (Austria)

1976-07-01

Short lived nuclides or isomeric transitions, respectively would have some advantages over long lived ones. Although we published a paper concerning a germanium-determination in iron meteorites some years ago, only few laboratories use this technique, the main reason being that the high matrix activity disturbs the measurement of energy-spectra. A multichannel analyzer in the time sequence mode enables Li-8 determination by a purely instrumental method which is therefore used more frequently. In the time sequence mode much higher counting rates up to 10 - 50 MHz are processed then by taking energy-spectra. This is the reason why activation analysis with short lived isomeric states is seldom applied when counting rate and pulse height are to be detected simultaneously. Exceptional difficulties are encountered in measurement of samples activated by a reactor pulse. Further difficulties arise from the fact that an optimal expelling time depends on the half life of the nuclide, and is more critical if the half life is short and the full width half maximum of the reactor pulse is small. Commercial Ge-Li-detectors can be used only at low counting rates, so that samples with high matrix activities cannot be measured. Modifying the electronic system enables registration of samples with high matrix activities. For short lived nuclides emitting hard beta-rays, e.g. B-12 or Li-8, a Cerenkov-detector is optimal. These problems are discussed in examples. (author)

Regulation of radioactive waste management

International Nuclear Information System (INIS)

2002-01-01

This bulletin contains information about activities of the Nuclear Regulatory Authority of the Slovak Republic (UJD). In this leaflet the regulation of radioactive waste management of the UJD are presented. Radioactive waste (RAW) is the gaseous, liquid or solid material that contains or is contaminated with radionuclides at concentrations or activities greater than clearance levels and for which no use is foreseen. The classification of radioactive waste on the basis of type and activity level is: - transition waste; - short lived low and intermediate level waste (LlLW-SL); - long lived low and intermediate level waste (LlLW-LL); - high level waste. Waste management (in accordance with Act 130/98 Coll.) involves collection, sorting, treatment, conditioning, transport and disposal of radioactive waste originated by nuclear facilities and conditioning, transport to repository and disposal of other radioactive waste (originated during medical, research and industrial use of radioactive sources). The final goal of radioactive waste management is RAW isolation using a system of engineered and natural barriers to protect population and environment. Nuclear Regulatory Authority of the Slovak Republic regulates radioactive waste management in accordance with Act 130/98 Coll. Inspectors regularly inspect and evaluate how the requirements for nuclear safety at nuclear facilities are fulfilled. On the basis of safety documentation evaluation, UJD issued permission for operation of four radioactive waste management facilities. Nuclear facility 'Technologies for treatment and conditioning contains bituminization plants and Bohunice conditioning centre with sorting, fragmentation, evaporation, incineration, supercompaction and cementation. Final product is waste package (Fibre reinforced container with solidified waste) acceptable for near surface repository in Mochovce. Republic repository in Mochovce is built for disposal of short lived low and intermediate level waste. Next

Production and Use of Short-Lived Radioisotopes from Reactors. Vol. II. Proceedings of a Seminar on the Practical Applications of Short-Lived Radioisotopes Produced in Small Research Reactors

International Nuclear Information System (INIS)

1963-01-01

There are many radioisotope applications in which it is important that the radiation should rapidly fall to an insignificant level once the initial intense activity has served its purpose. Such applications include diagnostic tests in medicine, where it is essential to reduce the radiation dose to the patient to a minimum, non-destructive testing methods which must be applied without contaminating the material or product concerned, and repeated routine tests which are possible only if the residual activity from the previous test is negligible. All these applications call for radionuclides whose half- lives are measured in hours or even minutes. Similarly, in the new but increasingly important technique of activation analysis, whereby the quantities of elements present in a material can be determined by irradiating the material in a reactor and assaying the radionuclides produced, the latter are mainly short-lived and must be measured immediately. While the production of long-lived radionuclides can most economically be left to the large reactors at the main radioisotope centres, short-lived isotopes must be produced, or materials activation performed, in a reactor at or near the place of intended use or analysis; this, then, represents one of the most important uses for the large number of small reactors which have been installed in recent years, or will come into operation in the near future, in many parts of the world. Since in many countries the new problems of producing, separating and applying short-lived radioisotopes are being faced for the first time, the International Atomic Energy Agency believed it would be valuable to survey the state of the art by convening an international Seminar on Practical Applications of Short-lived Radioisotopes produced in Small Research Reactors at its Vienna headquarters in November, 1962. This Seminar provided an opportunity for the producers and users of short-lived radioisotopes from many countries to meet and discuss the

Production and Use of Short-Lived Radioisotopes from Reactors. Vol. II. Proceedings of a Seminar on the Practical Applications of Short-Lived Radioisotopes Produced in Small Research Reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1963-03-15

There are many radioisotope applications in which it is important that the radiation should rapidly fall to an insignificant level once the initial intense activity has served its purpose. Such applications include diagnostic tests in medicine, where it is essential to reduce the radiation dose to the patient to a minimum, non-destructive testing methods which must be applied without contaminating the material or product concerned, and repeated routine tests which are possible only if the residual activity from the previous test is negligible. All these applications call for radionuclides whose half- lives are measured in hours or even minutes. Similarly, in the new but increasingly important technique of activation analysis, whereby the quantities of elements present in a material can be determined by irradiating the material in a reactor and assaying the radionuclides produced, the latter are mainly short-lived and must be measured immediately. While the production of long-lived radionuclides can most economically be left to the large reactors at the main radioisotope centres, short-lived isotopes must be produced, or materials activation performed, in a reactor at or near the place of intended use or analysis; this, then, represents one of the most important uses for the large number of small reactors which have been installed in recent years, or will come into operation in the near future, in many parts of the world. Since in many countries the new problems of producing, separating and applying short-lived radioisotopes are being faced for the first time, the International Atomic Energy Agency believed it would be valuable to survey the state of the art by convening an international Seminar on Practical Applications of Short-lived Radioisotopes produced in Small Research Reactors at its Vienna headquarters in November, 1962. This Seminar provided an opportunity for the producers and users of short-lived radioisotopes from many countries to meet and discuss the

Future extension of the Swedish repository for low and intermediate level waste (SFR)

International Nuclear Information System (INIS)

Carlsson, Jan

2006-01-01

The existing Swedish repository for low and intermediate level waste (SFR) is licensed for disposal of short-lived waste originated from operation and maintenance of Swedish nuclear power plants. The repository is foreseen to be extended to accommodate short-lived waste from the future decommissioning of the Nuclear Power Plants. Long-lived waste from operation, maintenance and eventually decommissioning will be stored some years before disposal in a geological repository. This repository can be build either as a further extension of the SFR facility or as a separate repository. This paper discusses the strategy of a step-wise extended repository where the extensions are performed during operation of the existing parts of the repository. It describes the process for licensing new parts of the repository (and re-license of the existing parts). (author)

Progress in long-lived radioactive waste management and disposal at the waste isolation pilot plant

International Nuclear Information System (INIS)

Triay, I.R.; Matthews, M.L.; Eriksson, L.G.

2001-01-01

The Salado Formation is buried more than 350 m beneath the sands and cacti of the Chihuahuan Desert and hosts the Waste Isolation Pilot Plant (WIPP) deep geological repository at a depth of approximately 650 m. Since the WIPP repository is at least 10 years ahead of any other repository development for long-lived radioactive waste, other radioactive waste management organizations and institutions could benefit both scientifically and politically from sharing the lessons learned at WIPP. Benefits would include using existing expertise and facilities to cost-effectively address and solve program-specific issues and to train staff. The characteristics of the WIPP repository and infrastructure are described in this paper. (author)

Progress in long-lived radioactive waste management and disposal at the waste isolation pilot plant

Energy Technology Data Exchange (ETDEWEB)

Triay, I R; Matthews, M L [U.S. Dept. of Energy Carlsbad Field Office, New Mexico (United States); Eriksson, L G [GRAM, Inc., Albuquerque, NM (United States)

2001-07-01

The Salado Formation is buried more than 350 m beneath the sands and cacti of the Chihuahuan Desert and hosts the Waste Isolation Pilot Plant (WIPP) deep geological repository at a depth of approximately 650 m. Since the WIPP repository is at least 10 years ahead of any other repository development for long-lived radioactive waste, other radioactive waste management organizations and institutions could benefit both scientifically and politically from sharing the lessons learned at WIPP. Benefits would include using existing expertise and facilities to cost-effectively address and solve program-specific issues and to train staff. The characteristics of the WIPP repository and infrastructure are described in this paper. (author)

Fast Resonance Raman Spectroscopy of Short-Lived Radicals

DEFF Research Database (Denmark)

Pagsberg, Palle Bjørn; Wilbrandt, Robert Walter; Hansen, Karina Benthin

1976-01-01

We report the first application of pulsed resonance Raman spectroscopy to the study of short-lived free radicals produced by pulse radiolysis. A single pulse from a flash-lamp pumped tunable dye laser is used to excite the resonance Raman spectrum of the p-terphenyl anion radical with an initial...

The high level and long lived radioactive wastes

International Nuclear Information System (INIS)

2005-01-01

This report presents the main conclusions of 15 years of researches managed by the CEA. This report is the preliminary version of the 2005 final report. It presents the main conclusions of the actions on the axis 1 and 3 of the law of the 30 December 1991. The synthesis report on the axis 1 concerns results obtained on the long lived radionuclides separation and transmutation in high level and long lived radioactive wastes. the synthesis report on the axis 3 presents results obtained by the processes of conditioning and of ground and underground long term storage. (A.L.B.)

Use of standard spectra for the short life radionuclides and ratios for long life radionuclides in the wastes of EDF PWR type reactors

International Nuclear Information System (INIS)

Lantes, B.; Bienvenu, Ph.

2001-01-01

This paper presents the type of declaration of radioactivity in the wastes of PWR type reactors park. Particularly, it insists on the justification of use of spectra for the declaration of short live radionuclides. It tackles the important developments of methods and measures of radiochemical analysis made by the Cea in order to determine the ratios to declare the long life radioisotopes. (N.C.)

Waste transmutation: perspectives

International Nuclear Information System (INIS)

Leray, S.

1997-01-01

After the introduction on the source and nature of nuclear waste, this lecture analyzes the different methods proposed to transmute long-lived isotopes into stable or short-lived isotopes. It is shown that direct methods (photonuclear reactions, spallation, muon catalyzed fusion) do not lead to a sufficient transmutation rate within a reasonable cost. Only the use of hybrid systems, fusion-fission or spallation-fission, can be foreseen. (author)

Studies on short-lived fission products at the Mainz TRIGA reactor

International Nuclear Information System (INIS)

Trautmann, N.

1974-01-01

Neutron-rich nuclei of medium mass number are produced by thermal-neutron-induced fission of heavy elements, e.g., 235 U, 239 Pu, and 249 Cf. Pulse irradiations lead to an enhancement of the ratio of short-lived activities to the accompanying longer-lived components. One approach for investigating the properties of short-lived nuclei consists in a combination of rapid chemical separations with higher-resolution gamma spectroscopy. This is demonstrated by the isolation of neutron-rich isotopes of niobium by sorption on glass and of ruthenium by solvent extraction. Other rapid separation procedures from aqueous solutions are briefly summarized and a few examples for their application in nuclear fission- and delayed neutron studies are given. Some experiments with an on-line mass separator of the ISOLDE-type, using chemical targets, are described. (U.S.)

The radioactive wastes: an easy and realistic approach

International Nuclear Information System (INIS)

Pradel, J.

2000-01-01

The question of radioactive waste storage is developed in this feature article. The two categories discussed are the low level and short lived radioactive wastes (period inferior to 30 years) and the long lived and high level radioactive wastes. The technical part about the storage is detailed, then, a study about unexpected troubles that could occur is made and their consequences studied. The last but not the least part is the development about the reasons that alarm the population and the solutions to bring about it. (N.C.)

Accurate mass measurements of short-lived isotopes with the MISTRAL rf spectrometer

CERN Document Server

Toader, C F; Borcea, C; Doubre, H; Duma, M; Jacotin, M; Henry, S; Képinski, J F; Lebée, G; Le Scornet, G; Lunney, M D; Monsanglant, C; De Saint-Simon, M; Thibault, C

1999-01-01

The MISTRAL experiment has measured its first masses at ISOLDE. Installed in May 1997, this radiofrequency transmission spectrometer is to concentrate on nuclides with particularly short half-lives. MISTRAL received its first stable beam in October and first radioactive beam in November 1997. These first tests, with a plasma ion source, resulted in excellent isobaric separation and reasonable transmission. Further testing and development enabled first data taking in July 1998 on neutron-rich Na isotopes having half-lives as short as 31 ms.

Complete decay of radionuclides: Implications for low-level waste disposal in municipal landfills

International Nuclear Information System (INIS)

Meck, R.A.

1996-01-01

The time required for the complete decay of a radioactive source can be quantified by specifying an acceptable probability and using an original derivation. The physical phenomenon of complete decay may be used as the technical basis to change regulations and permit, with public acceptance, the inexpensive disposal of short half-lived radioactive waste into municipal landfills. Current regulations require isolation of trash form the biosphere for 30 years during the post-closure control period for municipal landfills. Thirty years is sufficient time for complete decay of significant quantities of short-lived radionuclides, and there is a large decay capacity in the nation's landfills. As the major generators of low-level radioactive waste with relatively short half-lives, the academic, medical, and research communities likely would benefit most from such regulatory relief. Disposal of such waste is prohibited or costly. The waste must be specially packaged, stored, transported, and disposed in designated repositories. Regulatory relief can be initiated by citizens since the Administrative Procedures Act gives citizens the right to petition for regulatory change. 10 refs., 2 tabs

Management of low- and intermediate level waste in Sweden

International Nuclear Information System (INIS)

Carlsson, Jan

1999-01-01

This presentation describes how the management of radioactive waste is organised in Sweden, where Swedish law places the responsibility for such management with the waste generators. The four nuclear utilities have formed a joint company, the Swedish Nuclear Fuel and Waste Management Co., SKB, to handle the nuclear waste. The Swedish waste management system includes a final repository for short-lived low level waste (LLW) and intermediate level waste (ILW) and an interim storage facility for spent nuclear fuel and long-lived waste. Some very low-level, short-lived waste is disposed of in shallow-land repositories at the nuclear power stations. The final repository is situated in underground rock caverns close to the Forsmark nuclear power plant. The rock caverns have been excavated to a depth of more than 50 m beneath the Baltic Sea floor. LLW is compacted into bales or packaged in metal drums or cases that can be transported in standard freight containers. Radioactive materials used in other sectors such as hospitals are collected and packaged at Studsvik and later deposited in the deep repository. ILW is mixed with cement or bitumen and cast in cement or steel boxes or metal drums. The final repository has different chambers for different kinds of waste. The environmental impact of the repository is negligible. Because Sweden's nuclear power plants and the SKB facilities all are located on the coast, all the waste transport can be conducted by sea. The costs of managing and disposing of Sweden's nuclear waste are small compared to the price of electricity

Short-lived positron emitter labeled radiotracers - present status

International Nuclear Information System (INIS)

Fowler, J.S.; Wolf, A.P.

1982-01-01

The preparation of labelled compounds is important for the application of positron emission transaxial tomography (PETT) in biomedical sciences. This paper describes problems and progress in the synthesis of short-lived positron emitter ( 11 C, 18 F, 13 N) labelled tracers for PETT. Synthesis of labelled sugars, amino acids, and neurotransmitter receptors (pimozide and spiroperidol tagged with 11 C) is discussed in particular

The stakes in managing radioactive wastes

International Nuclear Information System (INIS)

Boissier, F.

2012-01-01

Like any human activity, the nuclear industry produces wastes. The wastes containing radioactive substances have to be managed as a function of the related risks. Nowadays, 1.300.000 tons of radioactive wastes have accumulated in France. More than 90% of them have short half-lives and are stored on the ground by ANDRA (national agency for the management of radioactive wastes) on 2 sites in the Aube district. ANDRA also designs solutions for stocking the other wastes. Those with long half-lives and very high activity will be stored deep underground (500 meter deep) at Cigeo in the Meuse and Haute-Marne districts. The wastes with long half-lives but low activity (less than 10 5 decays/s for graphite and less than a few thousands decays/s for radium contaminated wastes) will be disposed in a specific way. Implementing a storage solution for each type of waste is necessary for the nuclear industry's sustainability, but it does not dispense the latter from pursuing its efforts to reduce the quantity and danger of the wastes produced. This holds in particular for the so-called 'fourth generation' of future installations. It is important to take stock of all the issues related to managing nuclear wastes

Nuclear waste management in Switzerland - concept and plan of realisation

International Nuclear Information System (INIS)

1992-12-01

This reports begins by discussing some basic principles of the nuclear waste management concept, the boundary conditions imposed by social considerations, and technical, economic and organisational parameters. The overall concept will then be presented as it applies to the two disposal strategies for short-lived wastes and for high-level and long-lived intermediate-level wastes and spent fuel. The current status of project work is discussed and future plans, objectives and time schedules are presented. (author) figs., tabs., 20 refs

Low-level radioactive waste management in France: two decades of experience

International Nuclear Information System (INIS)

Marque, Y.

1993-01-01

Human activities generate wastes and these wastes have potential impacts on our environment and important implications for the twilight years of the twentieth century. Radioactive wastes, in particular, is a matter of considerable concern to the public, with emotional debate often clouding the legitimate need of the public for information for the subject. In France, the development of the nuclear power program and the widespread use of radioisotopes by the medical profession, industry and the research community called for a radioactive waste management program. In 1979, the French Government created ANDRA, the National Radioactive Waste Management Agency, which has the complete responsibility for radioactive waste disposal, including design, siting, construction and operation of waste disposal facilities. In 1991, the Waste Law reaffirmed ANDRA's principle functions and created the National Waste Observatory within ANDRA, whose the mission is to establish and maintain a current inventory of all radioactive waste storage and disposal sites on French territory. The present paper describes the generation of short-lived waste in France, the french policy on short-lived waste disposal, operation and cancellation of Manche plant, design and construction of Aube plant

Use of short-lived radionuclides in the agricultural and environmental sciences

International Nuclear Information System (INIS)

Krohn, K.A.

1985-01-01

In addition to their well-known uses in physiology, biochemistry, and medicine, short-lived radioisotopes have played an important part in promoting the authors knowledge of the agricultural and environmental sciences. Numerous investigators have found that the scientific rewards justify the additional demands associated with use of short-lived radioisotopes when novel or uniquely precise results can be achieved. This is best exemplified by examining the use of 13 N. Nitrogen-13 is the longest lived radioisotope of this very important element. The 10-min half-life of 13 N has required that the agricultural or environmental test model be brought to the laboratory where the isotope is made, but this has been done successfully in numerous instances. One major incentive for this research has probably been the fact that there is no analog of the very useful 14 C tracer to study nitrogen chemistry and biology

Low-level waste management

International Nuclear Information System (INIS)

Levin, G.B.

1980-01-01

An overview of the current situation in the United States and a look to the future of low-level waste management are presented. Current problems and challenges are discussed, such as: the need of additional disposal sites in the future; risks and costs involved in transport of low-level wastes; reduction of low-level waste volume through smelting, incineration, and storage for wastes containing nuclides with short half lives; development of a national policy for the management of low-level waste, and its implementation through a sensible system of regulations. Establishing a success with low-level waste management should provide the momentum and public confidence needed to continue on and to resolve the technical and politically more difficult low-level waste problems

Historical review of short-lived isotope applications in New Zealand

International Nuclear Information System (INIS)

More, R.D.

1986-01-01

Production of short-lived isotopes, nitrogen 13, fluorine 18 and carbon 11 with a small Van de Graaff accelerator. Applications of these isotopes in uptake and photosynthetic translocation studies in plants, and fluorine tracing in dental studies

Radioactive waste management in France

International Nuclear Information System (INIS)

Faussat, A.

1988-01-01

Solutions for radioactive waste management are already in existence and applied on an industrial scale for short-lived wastes. France has acquired an aknowledged expertise on the international level and several foreign contemporaries are interested in the relevant techniques developed. An intensive international cooperation has allowed to define bases for an underground deep repository for long-lived wastes. It is therefore important to choose a site which meets the expected storage conditions. This development work has been started in several countries in a similar way and which should be completed by the beginning of the next century. An 'open channel' with the public about this emotional topic can smooth the way for solutions by which mankind can master its technological challenges

A technique for the measurement of electron attachment to short-lived excited species

International Nuclear Information System (INIS)

Christophorou, L.G.; Pinnaduwage, L.A.; Bitouni, A.P.

1990-01-01

A technique is described for the measurement of electron attachment to short-lived (approx-lt 10 -9 s) excited species. Preliminary results are presented for photoenhanced electron attachment to short-lived electronically-excited states of triethylamine molecules produced by laser two-photon excitation. The attachment cross sections for these excited states are estimated to be >10 -11 cm 2 and are ∼10 7 larger compared to those for the unexcited (ground-state) molecules. 8 refs., 4 figs

Disentangling the effects of CO2 and short-lived climate forcer mitigation

NARCIS (Netherlands)

Rogelj, J.; Schaeffer, M.; Meinshausen, M.; Shindell, D.T.; Hare, W.; Klimont, Z.; Velders, G.J.M.; Amann, M.; Schellnhuber, H.J.

2014-01-01

Anthropogenic global warming is driven by emissions of a wide variety of radiative forcers ranging from very short-lived climate forcers (SLCFs), like black carbon, to very long-lived, like CO2. These species are often released from common sources and are therefore intricately linked. However, for

Radioactive wastes: sources, treatment, and disposal

International Nuclear Information System (INIS)

Wymer, R.G.; Blomeke, J.O.

1975-01-01

Sources, treatment, and disposal of radioactive wastes are analyzed in an attempt to place a consideration of the problem of permanent disposal at the level of established or easily attainable technology. In addition to citing the natural radioactivity present in the biosphere, the radioactive waste generated at each phase of the fuel cycle (mills, fabrication plants, reactors, reprocessing plants) is evaluated. The three treatment processes discussed are preliminary storage to permit decay of the short-lived radioisotopes, solidification of aqueous wastes, and partitioning the long-lived α emitters for separate and long-term storage. Dispersion of radioactive gases to the atmosphere is already being done, and storage in geologically stable structures such as salt mines is under active study. The transmutation of high-level wastes appears feasible in principle, but exceedingly difficult to develop

A Short History of Waste Management at the Hanford Site

International Nuclear Information System (INIS)

Gephart, Roy E.

2010-01-01

The world's first full-scale nuclear reactors and chemical reprocessing plants built at the Hanford Site in the desert of eastern Washington State produced two-thirds of the plutonium generated in the United States for nuclear weapons. Operating these facilities also created large volumes of radioactive and chemical waste, some of which was released into the environment exposing people who lived downwind and downstream. Hanford now contains the largest accumulation of nuclear waste in the Western Hemisphere. Hanford's last reactor shut down in 1987 followed by closure of the last reprocessing plant in 1990. Today, Hanford's only mission is cleanup. Most onsite radioactive waste and nuclear material lingers inside underground tanks or storage facilities. About half of the chemical waste remains in tanks while the rest persists in the soil, groundwater, and burial grounds. Six million dollars each day, or nearly two billion dollars each year, are spent on waste management and cleanup activities. There is significant uncertainty in how long cleanup will take, how much it will cost, and what risks will remain for future generations. This paper summarizes portions of the waste management history of the Hanford Site published in the book 'Hanford: A Conversation about Nuclear Waste and Cleanup.'

Cost benefit analysis, sustainability and long-lived radioactive waste management

International Nuclear Information System (INIS)

Berkhout, F.

1994-01-01

The objective of this paper is to examine how far the sustainability concept and the technique of cost-benefit analysis (CBA) can be applied to the problem of radioactive waste management. The paper begins with a slightly altered definition of the problem to the one carried in the Nea's background document (Nea 1994). A preliminary attempt is then be made to ascribe burdens to the various phases of long-lived radioactive waste management. The appropriateness of CBA and the sustainability concept for making decisions about long-term waste management policy is then discussed. The author ends with some conclusions about the appropriateness of systematic assessment approaches in the political process of constructing social consent for technological decisions. (O.L.). 12 refs., 1 tab

Management of long-lived radioactive waste: stakes and ASN actions

International Nuclear Information System (INIS)

Dandrieux, G.

2011-01-01

Due to the length of time it takes to decay, long-lived radioactive waste will remain a hazard on a timescale beyond the length of a human life, and even of several generations. In the case of this waste, long-term management solutions must be implemented to protect human health and the environment without requiring human intervention. In accordance with requirements under the Law, ANDRA (national agency for the management of radioactive waste) is carrying out research on disposal solutions in deep or subsurface geological formations. Nonetheless, until such repositories become available, ASN (authority for nuclear safety) has a duty to ensure safety at current and future interim storage facilities, as well as the safety of operations to retrieve and package this type of waste. To this end, ASN acts on several levels: it is involved in drawing up regulations and reference texts, at national and international level, it examines safety analysis reports related to radioactive waste management at basic nuclear installations, by means of inspections that it performs at every step in radioactive waste management. In its capacity as joint coordinator of the national plan for the management of nuclear waste and materials (PNGMDR) working group, ASN also plays a very active role in drawing up the provisions of the PNGMDR aimed at improving and optimising radioactive waste management. (author)

A proposal for assessing study quality: Biomonitoring, Environmental Epidemiology, and Short-lived Chemicals (BEES-C) instrument

Science.gov (United States)

LaKind, Judy S.; Sobus, Jon R.; Goodman, Michael; Barr, Dana Boyd; Fürst, Peter; Albertini, Richard J.; Arbuckle, Tye E.; Schoeters, Greet; Tan, Yu-Mei; Teeguarden, Justin; Tornero-Velez, Rogelio; Weisel, Clifford P.

2015-01-01

The quality of exposure assessment is a major determinant of the overall quality of any environmental epidemiology study. The use of biomonitoring as a tool for assessing exposure to ubiquitous chemicals with short physiologic half-lives began relatively recently. These chemicals present several challenges, including their presence in analytical laboratories and sampling equipment, difficulty in establishing temporal order in cross-sectional studies, short- and long-term variability in exposures and biomarker concentrations, and a paucity of information on the number of measurements required for proper exposure classification. To date, the scientific community has not developed a set of systematic guidelines for designing, implementing and interpreting studies of short-lived chemicals that use biomonitoring as the exposure metric or for evaluating the quality of this type of research for WOE assessments or for peer review of grants or publications. We describe key issues that affect epidemiology studies using biomonitoring data on short-lived chemicals and propose a systematic instrument – the Biomonitoring, Environmental Epidemiology, and Short-lived Chemicals (BEES-C) instrument – for evaluating the quality of research proposals and studies that incorporate biomonitoring data on short-lived chemicals. Quality criteria for three areas considered fundamental to the evaluation of epidemiology studies that include biological measurements of short-lived chemicals are described: 1) biomarker selection and measurement, 2) study design and execution, and 3) general epidemiological study design considerations. We recognize that the development of an evaluative tool such as BEES-C is neither simple nor non-controversial. We hope and anticipate that the instrument will initiate further discussion/debate on this topic. PMID:25137624

Applications of nuclear data on short-lived fission products

International Nuclear Information System (INIS)

Rudstam, G.; Aagaard, P.; Aleklett, K.; Lund, E.

1981-01-01

The study of short-lived fission products gives information about the nuclear structure on the neutron-rich side of stability. The data are also of interest for various applications both to basic science and to nuclear technology. Some of these applications, taken up by the OSIRIS group at Studsvik, are described in the present contribution. (orig.)

Impact of long-lived radionuclides on waste classification for fusion

International Nuclear Information System (INIS)

Maninger, R.C.

1985-01-01

A major goal for commercial applications of fusion reactors is to minimize radioactive wastes and to dispose of them by near-surface burial. There currently are no regulations specifically applicable to fusion wastes but those in force for fission wastes furnish a framework for expected fusion regulations. This paper recommends that all nuclides with half-lives greater than five years be assigned concentration limits as done in 10CFR61 for fission wastes. The paper gives approximate limits for all the significant long half-life sources of gamma radiation in the currently known periodic table. In the absence of working fusion reactors, computer models must be used to estimate the expected actual concentrations of radioactive nuclides. These estimates are needed to guide design parameters to achieve minimum radioactivity in fusion reactors. It is believed that the computer models and nuclear reaction libraries must be much more comprehensive than ordinarily used today to do activation calculations

Nuclear Waste Removal Using Particle Beams Incineration with Fast Neutrons

CERN Document Server

Revol, Jean Pierre Charles

1997-01-01

The management of nuclear waste is one of the major obstacles to the acceptability of nuclear power as a main source of energy for the future. TARC, a new experiment at CERN, is testing the practicality of Carlo Rubbia's idea to make use of Adiabatic Resonance Crossing to transmute long-lived fission fragments into short-lived or stable nuclides. Spallation neutrons produced in a large Lead assembly have a high probability to be captured at the energies of cross-section resonances in elements such as 99Tc, 129I, etc. An accelerator-driven sub-critical device using Thorium (Energy Amplifier) would be very effective in eliminating TRansUranic elements which constitute the most dangerous part of nuclear waste while producing from it large amounts of energy. In addition, such a system could transform, at a high rate and little energetic cost, long-lived fission fragments into short-lived elements.

Characterisation of long-lived low and intermediate-level radioactive wastes in the Nordic Countries

International Nuclear Information System (INIS)

Broden, K.; Carugati, S.; Brodersen, K.; Carlsson, T.; Viitanen, P.; Walderhaug, T.; Sneve, M.; Hornkjoel, S.; Backe, S.

1997-11-01

The present report is final report from a study on characterisation of radioactive waters in the Nordic countries. The study has mainly been focused on long-lived low and intermediate level radioactive waste. Methods to measure or estimate the activity content and the general composition are discussed. Recommendations are given regarding characterisation of waste under treatment and characterisation of already produced waste packages. (au)

Characterisation of long-lived low and intermediate-level radioactive wastes in the Nordic Countries

Energy Technology Data Exchange (ETDEWEB)

Broden, K. [Studsvik RadWaste AB, (El Salvador); Carugati, S.; Brodersen, K. [Forskningscenter Risoe, (Denmark); Carlsson, T.; Viitanen, P. [VVT, (Finland); Walderhaug, T. [Icelandic Radiation Protection Institute (Iceland); Sneve, M.; Hornkjoel, S. [Norwegian Radiation Protection Authority (Norway); Backe, S. [Institute for Energy Technology (Norway)

1997-11-01

The present report is final report from a study on characterisation of radioactive waters in the Nordic countries. The study has mainly been focused on long-lived low and intermediate level radioactive waste. Methods to measure or estimate the activity content and the general composition are discussed. Recommendations are given regarding characterisation of waste under treatment and characterisation of already produced waste packages. (au).

Management of radioactive medical waste

International Nuclear Information System (INIS)

Deschamps, S.; Mathey, J.C.

1996-01-01

Hospitals are producers of small amounts of radioactive waste. Current legislation details exactly how hospitals should manage it. Sealed sources are returned to suppliers. Disposal of unsealed sources, liquid or solid, depends upon their half-life: short-lived radioisotopes (half-life less than two months) are stocked on site while they decay; isotopes with longer half-lives (greater than two months) are handled by a specialist organization (ANDRA). (authors). 8 refs

Analysing environmental and fishing effects on a short-lived species ...

African Journals Online (AJOL)

Short-lived species are extremely dependent on the seasonal and interannual variability of environmental conditions, and determining their stock status is often difficult. This study investigates the effects of environmental variability and fishing pressure on the stock of octopus Octopus vulgaris in Senegalese waters over a ...

Safety of radioactive waste management in France

International Nuclear Information System (INIS)

Raimbault, P.

2002-01-01

Radioactive waste produced in France vary considerably by their activity level, their half lives, their volume or even their nature. In order to manage them safely, the treatment and final disposal solution must be adapted to the type of waste considered by setting up specific waste management channels. A strong principle in France is that it is the responsibility of the nuclear operators as waste producers to dispose of their waste or have them disposed of in a suitable manner. The competent authorities regulate and control the radioactive waste management activities. At present, only short-lived low and intermediate level waste have a definitive solution, the surface repository, where adequate waste packages are disposed of in concrete structures. Other types of radioactive waste are in interim storage facilities at the production sites. For very low level waste coming mainly from dismantling of nuclear facilities a dedicated repository is planned to be built in the coming years. Dedicated repositories are also planned for radiferous, tritiated and graphite waste. As for high level waste and long-lived waste coming mainly from reprocessing of spent nuclear fuel the disposal options are being sought along the lines specified by law 91-1381 concerning research on radioactive waste management, passed on December 30, 1991: research of solutions to partition and transmute long-lived radionuclides in the waste; studies of retrievable and non retrievable disposal in deep geological layers with the help of underground laboratories; studies of processes for conditioning and long term surface storage of these waste. In 2006, the French Parliament will assess the results of the research conducted by ANDRA relative to deep geological disposal as well as the work conducted by CEA in the two other areas of research and, if this research is conclusive, pass a law defining the final disposal option. (author)

Women waste pickers: living conditions, work, and health.

Science.gov (United States)

Coelho, Alexa Pupiara Flores; Beck, Carmem Lúcia Colomé; Fernandes, Marcelo Nunes da Silva; Freitas, Natiellen Quatrin; Prestes, Francine Cassol; Tonel, Juliana Zancan

2016-09-29

To know the elements of work, health, and living conditions of women who pick recyclable waste and are members of a waste cooperative in a town of the state of Rio Grande do Sul, Brazil. This is a qualitative, exploratory and descriptive study with seven subjects. Data were collected through participative observation, semi structured interview, and a focus group from July to August of 2013. The data were subjected to content analysis. The following thematic categories emerged: Women's work, informality and precariousness; Experiences of job satisfaction; and Working conditions and health: experiences with accidents, illness and health services. It was concluded that the women who collect recyclable material are exposed to precarious work conditions and potential health risks, such as work overload, accidents, illness, and social insecurity, and that nurses are responsible for promoting actions that ensure the health and inclusion of these workers.

Progress on the national low level radioactive waste repository and national intermediate level waste store

International Nuclear Information System (INIS)

Perkins, C.

2001-01-01

Over the last few years, significant progress has been made towards siting national, purpose-built facilities for Australian radioactive waste. In 2001, after an eight year search, a preferred site and two alternatives were identified in central-north South Australia for a near-surface repository for Australian low level (low level and short-lived intermediate level) radioactive waste. Site 52a at Everts Field West on the Woomera Prohibited Area was selected as the preferred site as it performs best against the selection criteria, particularly with respect to geology, ground water, transport and security. Two alternative sites, Site 45a and Site 40a, east of the Woomera-Roxby Downs Road, were also found to be highly suitable for the siting of the national repository. A project has commenced to site a national store for intermediate (long-lived intermediate level) radioactive waste on Commonwealth land for waste produced by Commonwealth agencies. Public input has been sought on relevant selection criteria

Public debate on radioactive wastes

International Nuclear Information System (INIS)

2005-01-01

The definition and implementation of safe and perennial solutions for the management of radioactive wastes is a necessity from the point of view of both the nuclear industrialists and the public authorities, but also of the overall French citizens. For the low- or medium-level or short living radioactive wastes, some solutions have been defined are are already implemented. On the other hand, no decision has been taken so far for the long living medium to high-level radioactive wastes. Researches are in progress in this domain according to 3 ways of research defined by the law from December 30, 1991: separation-transmutation, disposal in deep underground, and long duration surface or sub-surface storage. This paper presents in a digest way, the principle, the results obtained so far, and the perspectives of each of the three solutions under study. (J.S.)

Storage of radioactive wastes

International Nuclear Information System (INIS)

1992-07-01

Even if the best waste minimization measures are undertaken throughout radioisotope production or usage, significant radioactive wastes arise to make management measures essential. For developing countries with low isotope usage and little or no generation of nuclear materials, it may be possible to handle the generated waste by simply practicing decay storage for several half-lives of the radionuclides involved, followed by discharge or disposal without further processing. For those countries with much larger facilities, longer lived isotopes are produced and used. In this situation, storage is used not only for decay storage but also for in-process retention steps and for the key stage of interim storage of conditioned wastes pending final disposal. The report will serve as a technical manual providing reference material and direct step-by-step know-how to staff in radioisotope user establishments and research centres in the developing Member States without nuclear power generation. Considerations are limited to the simpler storage facilities. The restricted quantities and low activity associated with the relevant wastes will generally permit contact-handling and avoid the need for shielding requirements in the storage facilities or equipment used for handling. A small quantity of wastes from some radioisotope production cells and from reactor cooling water treatment may contain sufficient short lived activity from activated corrosion products to require some separate decay storage before contact-handling is suitable. 16 refs, 12 figs, 8 tabs

Main ecopathology syndromes of children living in the area of nuclear waste tailings

Directory of Open Access Journals (Sweden)

Saatova G. M.

2016-05-01

Full Text Available the clinical forms of ecopathology and clinical and epidemiological features of congenital and acquired diseases of children living in the area of nuclear waste tailings (city Mailu-Suu Kyrgyz Republic are studied in this article. The authors figured out that 52.6% of children living in stressful environmental conditions had a high medical and social risk of chronic disease.

Determination of gamma-ray exposure rate from short-lived fission products under criticality accident conditions

International Nuclear Information System (INIS)

Yanagisawa, Hiroshi; Ohno, Akio; Aizawa, Eijyu

2002-01-01

For the assessment of γ-ray doses from short-lived fission products (FPs) under criticality accident conditions, γ-ray exposure rates varying with time were experimentally determined in the Transient Experiment Critical Facility (TRACY). The data were obtained by reactivity insertion in the range of 1.50 to 2.93$. It was clarified from the experiments that the contribution of γ-ray from short-lived FPs to total exposure during the experiments was evaluated to be 15 to 17%. Hence, the contribution cannot be neglected for the assessment of γ-ray doses under criticality accident conditions. Computational analyses also indicated that γ-ray exposure rates from short-lived FPs calculated with the Monte Carlo code, MCNP4B, and photon sources based on the latest FP decay data, the JENDL FP Decay Data File 2000, well agreed with the experimental results. The exposure rates were, however, extremely underestimated when the photon sources were obtained by the ORIGEN2 code. The underestimation is due to lack of energy-dependent photon emission data for major short-lived FP nuclides in the photon database attached to the ORIGEN2 code. It was also confirmed that the underestimation arose in 1,000 or less of time lapse after an initial power burst. (author)

A general dead-time correction method based on live-time stamping. Application to the measurement of short-lived radionuclides.

Science.gov (United States)

Chauvenet, B; Bobin, C; Bouchard, J

2017-12-01

Dead-time correction formulae are established in the general case of superimposed non-homogeneous Poisson processes. Based on the same principles as conventional live-timed counting, this method exploits the additional information made available using digital signal processing systems, and especially the possibility to store the time stamps of live-time intervals. No approximation needs to be made to obtain those formulae. Estimates of the variances of corrected rates are also presented. This method is applied to the activity measurement of short-lived radionuclides. Copyright © 2017 Elsevier Ltd. All rights reserved.

Radioactive wastes: a proposal to its classification

International Nuclear Information System (INIS)

Domenech N, H.; Garcia L, N.; Hernandez S, A.

1996-01-01

On the basis of the quantities and the characteristics of the stored radioactive wastes in Cuba and the IAEA system of wastes classification, the concentration activities that would be used as limits for those categories are evaluated. This approach suggests a limit of 10 TBq/m 3 for short lived liquid wastes of Low and Intermediate Level (less than 30 years) and 5 TBq/m 3 for long lived liquid wastes (more than 30 years). For solid wastes the suggested limits are ten times lower. Taking into account the small quantities of arising wastes and to make easy its segregation, collection and disposal, a low level waste sub-classification in three new categories, whether or not they may be direct discharged, is suggested. As lower classification limit, while not specific exemption levels are established in the country, the use of an ALI min fraction is emphasized, meanwhile the total discharged activity will be no greater than 10 MBq or 100 MBq when the discharge occurs over the whole year. (authors). 6 refs., 5 tabs

Geochemical behavior of long-lived radioactive wastes

International Nuclear Information System (INIS)

Gera, F.

1975-07-01

The hazard potential associated with the heavy elements present in high-level radioactive waste decreases greatly in the first few tens of thousands of years of decay; however, further reduction in the hazard potential becomes extremely slow after about 100,000 years. In the time period between 100,000 and 5 million years the hazard potential of high-level waste is reduced by a factor of between 10 and 20. Current evidence seems to indicate that if radioactive waste containment were to fail after a period of 100,000 years or more, some environmental contamination would result; however, the contamination levels would be low. The radiological risk would not be significantly different from that now existing in various localities as a result of the accumulation of natural radioactive elements. With the partial exception of radium, which is concentrated in the fruit of specific perennial plants, the long-lived alpha-emitters are characterized by very low biologic availability in terrestrial ecosystems. The biologic availability may be somewhat higher in aquatic ecosystems due to the significant reconcentration factors in particular organisms. Data concerning the levels of activity in foods grown on radioactive soils seem to confirm the low biologic availability of the natural radioactive elements. Surveys of uranium mill tailings indicate little dispersal of the radioactive elements into the environment; even though untreated tailings piles would appear to be particularly vulnerable to resuspension of dust particles by wind. (U.S.)

Who wants nuclear waste

International Nuclear Information System (INIS)

Fernie, John; Openshaw, Stanley

1986-01-01

The criteria involved in selecting sites for disposal of low and short-lived intermediate-level radioactive wastes are explained. The wastes and the sources are identified and the current procedure for their disposal, at Drigg, next to the Sellafield reprocessing plant, is given. If alternative sites could be found for non-Sellafield-produced wastes the lifetime of the Drigg site could be extended. The sites chosen by NIREX (Nuclear Industry Radioactive Waste Executive) have to be cost effective. Indeed, those identified are conveniently situated and would not incur excessive transport costs. However, more remote sites may have to be chosen, even at greater transport cost, because of public protests. Even this may not be satisfactory because the transportation itself incurs risks. (UK)

Identification of short-lived neutron-rich ruthenium and rhodium isotopes in fission

International Nuclear Information System (INIS)

Franz, G.; Herrmann, G.

1975-01-01

Short-lived ruthenium and rhodium isotopes ( 107 Ru, 108 Ru, 108 Rh, 109 Ru, 109 Rh, 110 Ru, 110 Rh, 111 Ru, 111 Rh, 112 Ru, 112 Rh, 113 Ru) have been separated from fission products by a rapid chemical procedure and identified by means of γ-ray spectroscopy. Nuclides with half-lives down to 3 sec were accessible. Ruthenium isotopes up to mass number 113 have been identified. (author)

Disposal of radioactive waste from nuclear research facilities

CERN Document Server

Maxeiner, H; Kolbe, E

2003-01-01

Swiss radioactive wastes originate from nuclear power plants (NPP) and from medicine (e.g. radiation sources), industry (e.g. fire detectors) and research (e.g. CERN, PSI). Their conditioning, characterisation and documentation has to meet the demands given by the Swiss regulatory authorities including all information needed for a safe disposal in future repositories. For NPP wastes, arisings as well as the processes responsible for the buildup of short and long lived radionuclides are well known, and the conditioning procedures are established. The radiological inventories are determined on a routinely basis using a combined system of measurements and calculational programs. For waste from research, the situation is more complicated. The wide spectrum of different installations combined with a poorly known history of primary and secondary radiation results in heterogeneous waste sorts with radiological inventories quite different from NPP waste and difficult to measure long lived radionuclides. In order to c...

Feasibility of short-lived radionuclide production at Fermilab

International Nuclear Information System (INIS)

Ten Haken, R.K.; Awschalom, M.; Rosenberg, I.

1985-01-01

The requirements for establishing a short-lived radionuclide production program at Fermilab are explored. Such a program would utilize beam from the linac portion of the injector much like the present Neutron Therapy Facility. It should be possible to use approximately 10 to 20 μA of 66-MeV protons for iodine-123 production. Several additional magnets would need to be acquired and a shielded target facility would need to be constructed. However, the feasibility of establishing such a program hinges upon its harmonious operation with the high energy physics program

Extraction of long-lived radionuclides from caustic Hanford tank waste supernatants

International Nuclear Information System (INIS)

Chaiko, D.J.; Mertz, C.J.; Vojta, Y.

1995-07-01

A series of polymer-based extraction systems, based on the use of polyethylene glycols (PEGs) or polypropylene glycols (PPGs), was demonstrated to be capable of selective extraction and recovery of long-lived radionuclides, such as 99 Tc and 129 I, from Hanford SY-101 tank waste, neutralized current acid waste, and single-shell tank waste simulants. During the extraction process, anionic species like TcO 4 - and I - are selectively transferred to the less dense PEG-rich aqueous phase. The partition coefficients for a wide range of inorganic cations and anions, such as sodium, potassium, aluminum, nitrate, nitrite, and carbonate, are all less than one. The partition coefficients for pertechnetate ranged from 12 to 50, depending on the choice of waste simulant and temperature. The partition coefficient for iodide was about 5, while that of iodate was about 0.25. Irradiation of the PEG phase with gamma-ray doses up to 20 Mrad had no detectable effect on the partition coefficients. The most selective extraction systems examined were those based on PPGs, which exhibited separation factors in excess of 3000 between TcO 4 - and NO 3 - /NO 2- . An advantage of the PPG-based system is minimization of secondary waste production. These studies also highlighted the need for exercising great care in extrapolating the partitioning behavior with tank waste simulants to actual tank waste

Separation of short-lived fission products

International Nuclear Information System (INIS)

Tamai, Tadaharu; Ohyoshi, Emiko; Ohyoshi, Akira; Kiso, Yoshiyuki; Shinagawa, Mutsuaki.

1976-01-01

A rbief review is presented on the various methods of separation available for both gaseous and liquid states, for the separation of short-lived fission products formed by binary fission of neutron irradiated uranium. The means available for gaseous state are the hot atom reaction, the hydride method and on-line mass separation. For liquid state, use can be made of precipitation, ionic or atomic exchange, solvent extraction and paper electrophoresis. Particular reference is made to electrophoretic separation of ions produced by fission in aqueous solution of uranium. The principle of electrophoretic separation and the procedures for separating the element of interest from the other fission products are outlined, with reference made to the results obtained with the method by the present authors. The elements in question are alkalines, alkaline earths, rare earths, halogens, selenium and

Measurements of Short-Lived Fission Isomers

Science.gov (United States)

Finch, Sean; Bhike, Megha; Howell, Calvin; Krishichayan, Fnu; Tornow, Werner

2016-09-01

Fission yields of the short lived isomers 134mTe (T1 / 2 = 162 ns) and 136mXe (T1 / 2 = 2 . 95 μs) were measured for 235U and 238U. The isomers were detected by the γ rays associated with the decay of the isomeric states using high-purity germanium detectors. Fission was induced using both monoenergetic γ rays and neutrons. At TUNL's High-Intensity Gamma-ray Source (HI γS), γ rays of 9 and 11 MeV were produced . Monoenergetic 8 MeV neutrons were produced at TUNL's tandem accelerator laboratory. Both beams were pulsed to allow for precise time-gated spectroscopy of both prompt and delayed γ rays following fission. This technique offers a non-destructive probe of special nuclear materials that is sensitive to the isotopic identity of the fissile material.

Transport of short lived radioactive contaminants with prologed half-lives of daughters through river water

International Nuclear Information System (INIS)

Metwally, S.M.; Prohl, G.

2005-01-01

One of the main pathways for transporting contaminants to other parts in the environment, are rivers. This work is devoted for deriving and assessment the concentration of soluble radio contaminants along a river at any time after discharge, including the short-lived radionuclides in comparison with the discharge time interval, and prolonged half-life of the produced daughter nuclei. The assumed boundary conditions and deduced formulas can be applied either in case of accidental release or discharge under authority control. The formulas determining the produced daughter nuclei concentration require inequality of the parent and daughter nuclei half-lives. Because of the regional variation of river morphology, the assumed constancy of the flow velocity and dispersion coefficient requires dividing the river path into zones of similar hydrologic characteristics

Organic synthesis with short-lived positron-emitting radioisotopes

International Nuclear Information System (INIS)

Pike, V.W.

1988-01-01

Chemistry with short-lived positron-emitting radioisotopes of the non-metals, principally 11 C, 13 N and 18 F, has burgeoned over the last decade. This has been almost entirely because of the emergence of positron emission tomography (PET) as a powerful non-invasive technique for investigating pathophysiology in living man. PET is essentially an external technique for the rapid serial reconstruction of the spatial distribution of any positron-emitting radioisotope that has been administered in vivo. Such a distribution is primarily governed by the chemical form in which the positron-emitting radioisotope is incorporated, and importantly for clinical research, is often perturbed by physical, biological or clinical factors. Judicious choice of the chemical form enables specific biological information to be obtained. For example, the labelling of glucose with a positron-emitting radioisotope could be expected to provide a radiopharmaceutical for the study of glucose utilisation in both health and disease. (author)

Electron scattering off short-lived radioactive nuclei

International Nuclear Information System (INIS)

Wang, S.; Emoto, T.; Furukawa, Y.

2009-01-01

We have established a novel method which make electron scattering off short-lived radioactive nuclei come into being. This novel method was named SCRIT (Self-Confining RI ion Target). It was based on the well known "ion trapping" phenomenon in electron storage rings. Stable nucleus, 133 Cs, was used as target nucleus in the R&D experiment. The luminosity of interaction between stored electrons and Cs ions was about 1.02(0.06) × 10 26 cm -2 s -1 at beam current around 80 mA. The angular distribution of elastically scattered electrons from trapped Cs ions was measured. And an online luminosity monitor was used to monitor the change of luminosity during the experiment. (author)

Neutron-induced cross sections of short-lived nuclei via the surrogate reaction method

Directory of Open Access Journals (Sweden)

Morel P.

2011-10-01

Full Text Available The measurement of neutron-induced cross sections of short-lived nuclei is extremely difficult due to the radioactivity of the samples. The surrogate reaction method is an indirect way of determining cross sections for nuclear reactions that proceed through a compound nucleus. This method presents the advantage that the target material can be stable or less radioactive than the material required for a neutron-induced measurement. We have successfully used the surrogate reaction method to extract neutron-induced fission cross sections of various short-lived actinides. In this work, we investigate whether this technique can be used to determine neutron-induced capture cross sections in the rare-earth region.

Neutron-induced cross sections of short-lived nuclei via the surrogate reaction method

Directory of Open Access Journals (Sweden)

Tassan-Got L.

2012-02-01

Full Text Available The measurement of neutron-induced cross sections of short-lived nuclei is extremely difficult due to the radioactivity of the samples. The surrogate reaction method is an indirect way of determining cross sections for nuclear reactions that proceed through a compound nucleus. This method presents the advantage that the target material can be stable or less radioactive than the material required for a neutron-induced measurement. We have successfully used the surrogate reaction method to extract neutron-induced fission cross sections of various short-lived actinides. In this work, we investigate whether this technique can be used to determine neutron-induced capture cross sections in the rare-earth region.

Project No. 4 - Waste incineration facility

International Nuclear Information System (INIS)

2000-01-01

There are currently 12000 m 3 of combustible waste stored at the Ignalina NPP site. It is estimated that by 2005 the volume will have increase to 15000 m 3 (filters, personnel protection, clothing and plastics). As a part of the preparation for the closure of the Ignalina NPP an incineration facility will be required to process combustible wastes to reduce the overall volume of short-lived radioactive wastes stored at the Ignalina NPP site, thus reducing the overall risk to the environment. Project activities includes the design, construction and commissioning of the proposed facility, including all licensing documentation

Short-lived brain state after cued motor imagery in naive subjects

NARCIS (Netherlands)

Pfurtscheller, G.; Scherer, R.; Müller-Putz, G.R.; Lopes da Silva, F.H.

2008-01-01

Multi-channel electroencephalography recordings have shown that a visual cue, indicating right hand, left hand or foot motor imagery, can induce a short-lived brain state in the order of about 500 ms. In the present study, 10 able-bodied subjects without any motor imagery experience (naive subjects)

Passive Mobile Bandwidth Classification Using Short Lived TCP Connections

OpenAIRE

Michelinakis, Foivos; Kreitz, Gunnar; Petrocco, Riccardo; Zhang, Boxun; Widmer, Joerg

2015-01-01

Consumption of multimedia content is moving from a residential environment to mobile phones. Optimizing Quality of Experience—smooth, quick, and high quality playback—is more difficult in this setting, due to the highly dynamic nature of wireless links. A key requirement for achieving this goal is estimating the available bandwidth of mobile devices. Ideally, this should be done quickly and with low overhead. One challenge is that the majority of connections on mobiles are short-lived TCP con...

Management of very low-level radioactive waste

International Nuclear Information System (INIS)

Chapalain, E.; Damoy, J.; Joly, J.M.

2003-01-01

This document comprises 3 articles. The first article presents the concern of very low-level radioactive wastes generated in nuclear installations, the second article describes the management of the wastes issued from the dismantling operations of the ALS (linear accelerator of Saclay) and of the Saturn synchrotron both located in Saclay Cea's center. The last article presents the storage facility which is specifically dedicated to very low-level radioactive wastes. This storage facility, which is located at Morvilliers, near the 'Centre de l Aube' (used to store the low-, and medium-level, short-lived radioactive wastes), will receive the first packages next summer. Like the other storage facilities, it will be managed by ANDRA (national radioactive waste management agency)

Extraction of long-lived radionuclides from caustic Hanford tank waste supernatants

Energy Technology Data Exchange (ETDEWEB)

Chaiko, D.J.; Mertz, C.J.; Vojta, Y. [and others

1995-07-01

A series of polymer-based extraction systems, based on the use of polyethylene glycols (PEGs) or polypropylene glycols (PPGs), was demonstrated to be capable of selective extraction and recovery of long-lived radionuclides, such as {sup 99}Tc and {sup 129}I, from Hanford SY-101 tank waste, neutralized current acid waste, and single-shell tank waste simulants. During the extraction process, anionic species like TcO{sub 4}{sup {minus}} and I{sup {minus}} are selectively transferred to the less dense PEG-rich aqueous phase. The partition coefficients for a wide range of inorganic cations and anions, such as sodium, potassium, aluminum, nitrate, nitrite, and carbonate, are all less than one. The partition coefficients for pertechnetate ranged from 12 to 50, depending on the choice of waste simulant and temperature. The partition coefficient for iodide was about 5, while that of iodate was about 0.25. Irradiation of the PEG phase with gamma-ray doses up to 20 Mrad had no detectable effect on the partition coefficients. The most selective extraction systems examined were those based on PPGs, which exhibited separation factors in excess of 3000 between TcO{sub 4}{sup {minus}} and NO{sub 3}{sup {minus}}/NO{sub 2}{sub {minus}}. An advantage of the PPG-based system is minimization of secondary waste production. These studies also highlighted the need for exercising great care in extrapolating the partitioning behavior with tank waste simulants to actual tank waste.

Review of short-lived radionuclide activities in the United States

International Nuclear Information System (INIS)

Sodd, V.J.

1985-01-01

A review is given of the accelerator-produced short-lived radionuclides which are used in radiopharmaceuticals available commercially in the US and of the accelerator facilities devoted primarily to their production. Reactions for the efficient production of 67 Ga, 81 Rb → /sup 81m/Kr, 111 In, 201 Tl, and 123 I are given. Methods for the production of higher purity 123 I are suggested

An integrated approach to the management of radioactive waste in Australia

International Nuclear Information System (INIS)

Woollett, S.M.

2002-01-01

This paper draws attention to the practices and progress in radioactive waste management in Australia. A National Repository for the disposal of low-level and short-lived intermediate- level radioactive waste and a National Store for the storage of long-lived intermediate-level radioactive waste are presently being established. This has necessitated considerable activity in addressing emerging issues in the management of radioactive waste. The Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) has a major role in developing an integrated approach to manage radioactive waste in Australia. This approach begins with the development of a radioactive waste management policy and identification of the issues in radioactive waste management requiring attention. ARPANSA is developing national standards and guidance documents for the safe and responsible management of waste prior to its acceptance at the National Repository or National Store. This contributes to the Agency's promotion of uniformity of radiation protection and nuclear safety policy and practices across Australia's Commonwealth, State and Territory jurisdictions. (author)

Assessment of studies and researches on warehousing - High-level and intermediate-level-long-lived radioactive wastes - December 2012

International Nuclear Information System (INIS)

2013-01-01

This large report first presents the approach adopted for the study and research on the warehousing of high-level and intermediate-level-long-lived radioactive wastes. It outlines how reversible storage and warehousing are complementary, discusses the lessons learned from researches performed by the CEA on long duration warehousing, presents the framework of studies and researches performed since 2006, and presents the scientific and technical content of studies and researches (warehousing need analysis, search for technical options providing complementarity with storage, extension or creation of warehousing installations). The second part addresses high-level and intermediate-level-long-lived radioactive waste parcels, indicates their origins and quantities. The third part proposes an analysis of warehousing capacities: existing capacities, French industrial experience in waste parcel warehousing, foreign experience in waste warehousing. The fourth part addresses reversible storage in deep geological formation: storage safety functions, storage reversibility, storage parcels, storage architecture, chronicle draft. The fifth part proposes an inventory of warehousing needs in terms of additional capacities for the both types of wastes (high-level, and intermediate-level-long-lived), and discusses warehousing functionalities and safety objectives. The sixth and seventh parts propose a detailed overview of design options for warehousing installations, respectively for high-level and for intermediate-level-long-lived waste parcels: main technical issues, feasibility studies of different concepts or architecture shapes, results of previous studies and introduction to studies performed since 2011, possible evolutions of the HA1, HA2 and MAVL concepts. The eighth chapter reports a phenomenological analysis of warehousing and the optimisation of material selection and construction arrangements. The last part discusses the application of researches to the extension of the

PANTHER Data from SOLVE-II Through CR-AVE: A Contrast Between Long and Short Lived Compounds.

Science.gov (United States)

Moore, F. L.; Dutton, G. S.; Elkins, J. W.; Hall, B. D.; Hurst, D. F.; Nance, J. D.; Thompson, T. M.

2006-12-01

PANTHER (PAN and other Trace Hydrohalocarbons ExpeRiment) is an airborne 6-channel gas chromatograph that measures approximately 20 important atmospheric trace gases whose changing burdens impact air quality, climate change and both stratospheric and tropospheric ozone. In this presentation we will contrast measurements of the long-lived compounds against the short-lived compounds. The long-lived compounds tend to have well-defined troposphere boundary conditions and develop spatial gradients due to stratospheric processing. These measurements have played a major role in quantifying stratospheric transport, stratosphere- troposphere exchange, and ozone loss. In contrast the short-lived species develop spatial and temporal gradients in the tropical tropopause layer (TTL), due to variations in the surface boundary layer concentrations and the coupling of this surface boundary layer to the TTL via convective processes. Deep convection acts like a "conveyor belt" between the source region in the boundary layer and the relatively stable TTL region, often bypassing the free troposphere where scavenging of these short lived species takes place. Loss rates due to reaction with OH and thermal decomposition are reduced in the cold, dry air of the TTL, resulting in longer survival times. Isolation of the TTL region from the free troposphere can last from days to over a month. Significant amounts of these short-lived compound and their byproducts can therefore be transported into the lower stratosphere (LS). Of particular interest are compounds that contain bromine, iodine, and sulfur, not only because of their intrinsic harmful effects in the atmosphere, but also because they have unique source and sink regions that can help to de- convolve transport.

Development plan. High activity-long living wastes project. Abstract; Plan de developpement. Projet HAVL. Resume

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

This brochure presents the actions that the ANDRA (the French national agency of radioactive wastes) has to implement in the framework of the project of high activity-long living (HALL) radioactive wastes (HAVL project) conformably to the requirements of the program defined in the law from June 28, 2006 (law no 2006-739). This law precises the three, complementary, research paths to explore for the management of this type of wastes: separation and transmutation of long-living radioactive elements, reversible disposal in deep geologic underground, and long duration storage. The ANDRA's action concerns the geologic disposal aspect. The following points are presented: the HALL wastes and their containers, the reversible disposal procedure, the HAVL project: financing of researches, storage concepts, development plan of the project (dynamics, information and dialogue approach, input data, main steps, schedule); the nine programs of the HAVL project (laboratory experiments and demonstration tests, surface survey, scientific program, simulation program, surface engineering studies and technological tests, information and communication program, program of environment and facilities surface observation and monitoring, waste packages management, monitoring and transport program, disposal program); the five transverse technical and scientific activities (safety, reversibility, cost, health and occupational safety, impact study). (J.S.)

Transmutation prospect of long-lived nuclear waste induced by high-charge electron beam from laser plasma accelerator

Science.gov (United States)

Wang, X. L.; Xu, Z. Y.; Luo, W.; Lu, H. Y.; Zhu, Z. C.; Yan, X. Q.

2017-09-01

Photo-transmutation of long-lived nuclear waste induced by a high-charge relativistic electron beam (e-beam) from a laser plasma accelerator is demonstrated. A collimated relativistic e-beam with a high charge of approximately 100 nC is produced from high-intensity laser interaction with near-critical-density (NCD) plasma. Such e-beam impinges on a high-Z convertor and then radiates energetic bremsstrahlung photons with flux approaching 1011 per laser shot. Taking a long-lived radionuclide 126Sn as an example, the resulting transmutation reaction yield is the order of 109 per laser shot, which is two orders of magnitude higher than obtained from previous studies. It is found that at lower densities, a tightly focused laser irradiating relatively longer NCD plasmas can effectively enhance the transmutation efficiency. Furthermore, the photo-transmutation is generalized by considering mixed-nuclide waste samples, which suggests that the laser-accelerated high-charge e-beam could be an efficient tool to transmute long-lived nuclear waste.

Production of exotic, short lived carbon isotopes in ISOL-type facilities

CERN Document Server

Franberg, Hanna; Köster, Ulli; Ammann, Markus

2008-01-01

The beam intensities of short-lived carbon isotopes at Isotope Separation On-Line (ISOL) facilities have been limited in the past for technical reasons. The production of radioactive ion beams of carbon isotopes is currently of high interest for fundamental nuclear physics research. To produce radioactive ions a target station consisting of a target in a container connected to an ion source via a transfer line is commonly used. The target is heated to vaporize the product for transport. Carbon in elementary form is a very reactive element and react strongly with hot metal surfaces. Due to the strong chemisorption interaction, in the target and ion source unit, the atoms undergo significant retention on their way from the target to the ion source. Due to this the short lived isotopes decays and are lost leading to low ion yields. A first approach to tackle these limitations consists of incorporating the carbon atoms into less reactive molecules and to use materials for the target housing and the transfer line ...

Production of medical short-lived radionuclides in Canada

International Nuclear Information System (INIS)

Wiebe, L.I.

1985-01-01

The production of radionuclides for medical and biomedical research in Canada has been reviewed with respect to the national geographic and demographic characteristics which influence their use. The types of facilities available for the production of short-lived radionuclides have been summarized, and a tabulation of the radionuclides that are produced has been presented. In broad terms production facilities can be classified as belonging to one of two groups, nuclear reactor or charged-particle accelerators. The charged-particle accelerators produce the more neutron-deficient and (because of the resultant decay properties) the more useful radionuclides for medical application. The nuclear reactor facilities for radionuclide production range in size and capacity from the high-flux research reactors of AECL to the six SLOWPOKE reactors, five of which are located on university campuses across the country. The McMaster University reactor is used to produce curie quantities of fluorine-18 weekly. Millicurie amounts of a large number of radionuclides, most of which have half-lives ranging from 2 to 50 hr, are produced in the low-flux reactors, in support of basic medical research

Continuous administration of short-lived isotopes for evaluating dynamic parameters

International Nuclear Information System (INIS)

Selikson, M.

1985-01-01

In this paper it is shown that continuous but varying infusions (specifically, exponential infusions) of a short-lived radionuclide can be used to evaluate a wide range of dynamic parameters. The detector response to exponential infusions is derived. An example of an inert diffusible substrate for evaluating regional flow and a glucose model for evaluating regional metabolic rate are both worked out. The advantages of using exponential infusion methods are discussed

Short-lived radiopharmaceuticals for the diagnosis of ocular melanoma

International Nuclear Information System (INIS)

Packer, S.; Lambrecht, R.; Atkins, H.L.; Wolf, A.P.

1974-01-01

An experimental procedure has been established to evaluate radiopharmaceuticals for the specific purpose of melanoma detection by scintiscanning. By using the Greene melanoma in the hamster several labeled compounds were compared. Specifically the tumor uptake along with detailed analyses of uptake by various parts of the eye and body were determined in a hamster model. Of those short-lived radionuclides investigated 203 Pb-tris was the most promising as a non-invasive localizing agent for ocular melanoma and it should prove effective for ocular scintigraphy. (U.S.)

Nuclear Waste and Ethics

International Nuclear Information System (INIS)

Damveld, Herman

2003-01-01

In the past years in almost all conferences on storage of nuclear waste, ethics has been considered as an important theme. But what is ethics? We will first give a sketch of this branch of philosophy. We will then give a short explanation of the three principal ethical theories. In the discussion about storage of nuclear waste, the ethical theory of utilitarianism is often implicitly invoked. In this system future generations weigh less heavily than the present generation, so that people of the future are not considered as much as those now living. We reject this form of reasoning. The discussion about nuclear waste is also sometimes pursued from ethical points of departure such as equality and justice. But many loose ends remain in these arguments, which gives rise to the question of whether the production and storage of nuclear waste is responsible

Nuclear Waste and Ethics

Energy Technology Data Exchange (ETDEWEB)

Damveld, Herman [Groningen (Netherlands)

2003-10-01

In the past years in almost all conferences on storage of nuclear waste, ethics has been considered as an important theme. But what is ethics? We will first give a sketch of this branch of philosophy. We will then give a short explanation of the three principal ethical theories. In the discussion about storage of nuclear waste, the ethical theory of utilitarianism is often implicitly invoked. In this system future generations weigh less heavily than the present generation, so that people of the future are not considered as much as those now living. We reject this form of reasoning. The discussion about nuclear waste is also sometimes pursued from ethical points of departure such as equality and justice. But many loose ends remain in these arguments, which gives rise to the question of whether the production and storage of nuclear waste is responsible.

Applications of short-lived isotopes in agricultural research in New Zealand

International Nuclear Information System (INIS)

McCallum, G.J.; More, R.D.; McNaughton, G.S.; Minchin, P.E.H.; Presland, M.R.; Stout, J.D.

1981-01-01

The use of the short-lived isotopes 11 C and 13 N in agricultural research studies in New Zealand is reviewed. The methods employed to produce these radioisotopes using a 3 MV Van de Graaff accelerator are given. Experiments on transport processes and the uptake of nutrient by plants, and the study of soil processes are described. (Auth.)

The development of fast tantalum foil targets for short-lived isotopes

CERN Document Server

Bennett, J R J; Drumm, P V; Ravn, H L

2003-01-01

The development of fast tantalum foil targets for short-lived isotopes was discussed. It was found that the effusion was faster but the diffusion out of the foils was a limiting factor. The performance of the targets at ISOLDE with beams of **1**1Li, **1**2Be and **1**4Be was also analyzed. (Edited abstract) 13 Refs.

No excess risk of adverse birth outcomes in populations living near special waste landfill sites in Scotland.

Science.gov (United States)

Morris, S E; Thomson, A O; Jarup, L; de Hoogh, C; Briggs, D J; Elliott, P

2003-11-01

A recent study showed small excess risks of low birth weight, very low birth weight and certain congenital anomalies in populations living near landfill sites in Great Britain. The objective of the current study was to investigate the risk of adverse birth outcomes associated with residence near special waste landfill sites in Scotland. We studied risks of adverse birth outcomes in populations living within 2 km of 61 Scottish special waste landfill sites operational at some time between 1982 and 1997 compared with those living further away. 324,167 live births, 1,849 stillbirths, and 11,138 congenital anomalies (including terminations) were included in the study. Relative risks were computed for all congenital anomalies combined, some specific anomalies and prevalence of stillbirth and low and very low birth weight (special waste landfill sites was 0.96 (99% confidence interval 0.89 to 1.02) adjusted for confounders. Adjusted risks were 0.71 (0.36 to 1.42) for neural tube defects, 1.03 (0.85 to 1.26) for cardiovascular defects, 0.84 (0.58 to 1.22) for hypospadias and epispadias (with no excess of surgical corrections), 0.78 (0.27 to 2.23) for abdominal wall defects (1.32 (0.42-4.17) for hospital admissions), 1.22 (0.28 to 5.38) for surgical correction of gastroschisis and exomphalos and 1.01 (0.96 to 1.07) and 1.01 (0.90 to 1.15) for low and very low birth weight respectively. There was no excess risk of stillbirth. In conclusion, we found no statistically significant excess risks of congenital anomalies or low birth weight in populations living near special waste landfill sites in Scotland.

Activation analysis with neutron generators using short-lived radionuclides

International Nuclear Information System (INIS)

Salma, I.

1993-01-01

The short half-life involves a number of important differences in production, transportation and measurement of radionuclides, and in counting statistics as compared with those in traditional activation analysis. Experiments were performed to investigate the analytical possibilities and prospective utilization of short-lived radionuclides produced by 14-MeV neutron irradiation. A rapid pneumatic transfer system for use with neutron generators was installed and applied for detecting radionuclides with a half-life from 300 ms to 30 s. The transport time for samples with a total mass of 1-4 g is between 130 and 160 ms for pressurized air of 0.1-0.4 MPa. 11 elements were studied by the conventional activation method using both a typical pneumatic transport system (run time 3 s) and the fast pneumatic transport facility. The effect of the cyclic activation technique on the elemental sensitivities was also investigated. (orig.)

Radioactive waste management

International Nuclear Information System (INIS)

Blomek, D.

1980-01-01

The prospects of nuclear power development in the USA up to 2000 and the problems of the fuel cycle high-level radioactive waste processing and storage are considered. The problems of liquid and solidified radioactive waste transportation and their disposal in salt deposits and other geologic formations are discussed. It is pointed out that the main part of the high-level radioactive wastes are produced at spent fuel reprocessing plants in the form of complex aqueous mixtures. These mixtures contain the decay products of about 35 isotopes which are the nuclear fuel fission products, about 18 actinides and their daughter products as well as corrosion products of fuel cans and structural materials and chemical reagents added in the process of fuel reprocessing. The high-level radioactive waste management includes the liquid waste cooling which is necessary for the short and middle living isotope decay, separation of some most dangerous components from the waste mixture, waste solidification, their storage and disposal. The conclusion is drawn that the seccessful solution of the high-level radioactive waste management problem will permit to solve the problem of the fuel cycle radioactive waste management as a whole. The salt deposits, shales and clays are the most suitable for radioactive waste disposal [ru

Radioactive waste management solutions

International Nuclear Information System (INIS)

Siemann, Michael

2015-01-01

One of the more frequent questions that arise when discussing nuclear energy's potential contribution to mitigating climate change concerns that of how to manage radioactive waste. Radioactive waste is produced through nuclear power generation, but also - although to a significantly lesser extent - in a variety of other sectors including medicine, agriculture, research, industry and education. The amount, type and physical form of radioactive waste varies considerably. Some forms of radioactive waste, for example, need only be stored for a relatively short period while their radioactivity naturally decays to safe levels. Others remain radioactive for hundreds or even hundreds of thousands of years. Public concerns surrounding radioactive waste are largely related to long-lived high-level radioactive waste. Countries around the world with existing nuclear programmes are developing longer-term plans for final disposal of such waste, with an international consensus developing that the geological disposal of high-level waste (HLW) is the most technically feasible and safe solution. This article provides a brief overview of the different forms of radioactive waste, examines storage and disposal solutions, and briefly explores fuel recycling and stakeholder involvement in radioactive waste management decision making

Experience in presenting short courses in waste management technologies for secondary science and mathematics teachers

International Nuclear Information System (INIS)

Toth, W.J.; Smith, T.H.; Garcia, M.M.; Ferguson, J.E.

1991-01-01

The Department of Energy (DOE) and its Idaho National Engineering Laboratory (INEL) are developing educational programs that will help avert projected shortages in scientific and engineering manpower. One approach to this end is to help teachers become better prepared to teach topics that enthuse more students. INEL developed and offered a Short Course in Waste Management Technologies for Secondary Science and Mathematics Teachers. Short Course has two purposes: (1) to provide secondary-level science and mathematics teachers with training and information that will be useful to them in the classroom, and (2) to provide information on a topic of widespread interest in today's society, i.e., the management of hazardous and radioactive wastes and the restoration and preservation of the environment. This paper describes the development of the Short Course and summarizes some of the lessons learned in the preparation and presentation of such courses. 2 refs., 2 tabs

Corrections for the combined effects of decay and dead time in live-timed counting of short-lived radionuclides

International Nuclear Information System (INIS)

Fitzgerald, R.

2016-01-01

Studies and calibrations of short-lived radionuclides, for example "1"5O, are of particular interest in nuclear medicine. Yet counting experiments on such species are vulnerable to an error due to the combined effect of decay and dead time. Separate decay corrections and dead-time corrections do not account for this issue. Usually counting data are decay-corrected to the start time of the count period, or else instead of correcting the count rate, the mid-time of the measurement is used as the reference time. Correction factors are derived for both those methods, considering both extending and non-extending dead time. Series approximations are derived here and the accuracy of those approximations are discussed. - Highlights: • Derived combined effects of decay and dead time. • Derived for counting systems with extending or non-extending dead times. • Derived series expansions for both midpoint and decay-to-start-time methods. • Useful for counting experiments with short-lived radionuclides. • Examples given for "1"5O, used in PET scanning.

Radioactive waste disposal

International Nuclear Information System (INIS)

Cluchet, J.; Roger, B.

1975-10-01

After mentioning the importance of the problem of the disposal of wastes produced in the electro-nuclear industry, a short reminder on a few laws of radioactivity (nature and energy of radiations, half-life) and on some basic dosimetry is given. The conditioning and storage procedures are then indicated for solid wastes. The more active fractions of liquid wastes are incorporated into blocks of glass, whereas the less active are first concentrated by chemical treatments or by evaporation. The concentrates are then embedded into concrete, asphalt or resins. Storage is done according to the nature of each type of wastes: on a hard-surfaced area or inside concrete-lined trenches for the lowest radioactivity, in pits for the others. Transuranium elements with very long half-lives are buried in very deep natural cavities which can shelter them for centuries. From the investigations conducted so far and from the experience already gained, it can be concluded that safe solutions are within our reach [fr

Emission channeling lattice location experiments with short-lived isotopes

CERN Multimedia

Wahl, U; Ronning, C R

2007-01-01

Emission channeling with position-sensitive detectors is a well-established technique at ISOLDE for studying the lattice location of radioactive impurities implanted into single crystals. In the case of electron emitting isotopes, however, due to count rate and noise-related limitations of the detection systems, the technique was restricted to isotopes with half lives above 6 h and electron energies above 40 keV. Recently, major technical developments have been realized and new equipment has been acquired which has allowed these limitations to be overcome and made feasible electron emission channeling experiments with short-lived isotopes and at low electron energies.\\\\ As first application, making use of two new on-line emission channeling setups at ISOLDE, we propose to investigate the lattice location of the transition metals Ni (2.5 h) and Co (1.6 h) in semiconductors, in particular in ZnO and GaN, by means of on-line $\\beta^{-}$-emission channeling experiments. In addition, we would like to study the lat...

Determination of short-lived trace elements in environmental samples by neutron activation analysis

International Nuclear Information System (INIS)

Wardani, S.; Sihombing, E.; Hamzah, A.; Rochidi; Hery, P.S.; Hartaman, S.; Iman, J.

1998-01-01

Concentration of a short-lived trace elements in environmental samples were determined by neutron activation analysis, a counting loss often occur due to the high counting rate. A Pile-Up Rejecter (PUR) electric circuit was installed in counting a short-lived trace elements by a γ-ray spectrometer in order to correct a counting loss. The samples were irradiated for 30∼60 seconds at neutron flux of 3.5 x 10 12 n.cm -2 .s -1 , then the samples cooled for 120 second and counted for 180 second using this system. The nuclides concentration in the varieties environmental samples have a difference analysis result, was more accurate and precise, which the measured result would be 30 % more higher by PUR system than the result would be counted using a conventional γ-ray spectrometry method

Nondispersive x-ray diagnostics of short lived plasmas

International Nuclear Information System (INIS)

Day, R.H.

1983-01-01

In this NATO Advanced Study Institute, we have discussed in detail the diagnosis of many pulse power machine properties, including their electrical behavior, grounding and shielding, and related data acquisition techniques. The purpose for many of these machines is to create high temperature/high density plasmas and, therefore, the subsequent behavior of these plasmas is of critical concern. The energy density of these plasmas is such that they will naturally radiate in the x-ray regime and thus the diagnosis of their x-ray emission is a crucial measurement of the entire system performance. In this lecture, I describe the general techniques used to perform nondispersive x-ray diagnostics of these short lived plasmas

Involvement of AVN as TSO in the safety analysis of radioactive waste disposal

International Nuclear Information System (INIS)

Gelder, P. de; Nys, V.; Smidts, O.; Boeck, B. de

2004-01-01

In 1998, ONDRAF/NIRAS, the agency responsible for radioactive waste management in Belgium, was requested by the government to involve the nuclear safety authorities in its activities of safety evaluation of site-specific waste disposal options (deep or surface disposal) for the short-lived low-level waste. A working group was created in which ONDRAF/NIRAS, FANC (the Federal Agency for Nuclear Control) and AVN discuss different aspects of the ONDRAF/NIRAS program concerning the long-term management of short-lived low-level radioactive waste disposal. It includes also the review of technical safety assessments performed by ONDRAF/NIRAS or by contractors for ONDRAF/NIRAS. The involvement of AVN (the Belgian TSO) in the pre-project phase appears to be positive for all partners. Indeed, all felt the need for an independent actor, with a strong technical basis. Through this presentation, the experience and the topics discussed since 1998 will be developed. Mainly, the presentation will focus on the approach followed to develop competency in the radioactive waste field, on the discussions about the development of a regulatory framework adapted to final disposal of low-level radioactive waste, and on the technical regulatory positions developed so far. Also the experience related to the interaction with local stakeholders will be described. (orig.)

Harvard--MIT research program in short-lived radiopharmaceuticals. Progress report, September 1, 1977--April 30, 1978

International Nuclear Information System (INIS)

Adelstein, S.J.; Brownell, G.L.

1978-05-01

Progress is reported on the following studies: chemistry studies designed to achieve a more complete understanding of the fundamental chemistry of technetium in order to facilitate the design of future radiopharmaceuticals incorporating the radionuclide /sup 99m/Tc; the development of new radiopharmaceuticals intended to improve image quality and lower radiation doses by the use of short-lived radionuclides and disease-specific agents; the development of short-lived positron-emitting radionuclides which offer advantages in transverse section imaging of regional physiological processes; and studies of the toxic effects of particulate radiation

Recycling polyethylene terephthalate wastes as short fibers in Strain-Hardening Cementitious Composites (SHCC).

Science.gov (United States)

Lin, Xiuyi; Yu, Jing; Li, Hedong; Lam, Jeffery Y K; Shih, Kaimin; Sham, Ivan M L; Leung, Christopher K Y

2018-05-26

As an important portion of the total plastic waste bulk but lack of reuse and recycling, the enormous amounts of polyethylene terephthalate (PET) solid wastes have led to serious environmental issues. This study explores the feasibility of recycling PET solid wastes as short fibers in Strain-Hardening Cementitious Composites (SHCCs), which exhibit strain-hardening and multiple cracking under tension, and therefore have clear advantages over conventional concrete for many construction applications. Based on micromechanical modeling, fiber dispersion and alkali resistance, the size of recycled PET fibers was first determined. Then the hydrophobic PET surface was treated with NaOH solution followed by a silane coupling agent to achieve the dual purpose of improving the fiber/matrix interfacial frictional bond (from 0.64 MPa to 0.80 MPa) and enhancing the alkali resistance for applications in alkaline cementitious environment. With surface treatment, recycling PET wastes as fibers in SHCCs is a promising approach to significantly reduce the material cost of SHCCs while disposing hazardous PET wastes in construction industry. Copyright © 2018 Elsevier B.V. All rights reserved.

Proceedings of the public debate on the general options of management of high and intermediate activity and long-lived radioactive wastes

International Nuclear Information System (INIS)

2006-01-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprised 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is a summary of the main questions tackled during this debate from its preparation to its closing meeting and dealing with: the acceptation of the debate, the progress of the debate, the socio-technical problem of gathering the different points to be debated with respect to the different areas in concern, the general questions about the overall nuclear wastes and materials (radioactivity, health, radioprotection, management, reprocessing, control, actors organization, knowledge sharing, perenniality of the financing), the specific questions about long-lived wastes (inventory, separation-transmutation feasibility, nuclear energy and energy policy, management solutions, storage and geologic disposal feasibility, impact of debates on the 2006 law, long-lived waste territories), the conclusions for the 2006 law: mastering the overall nuclear wastes and materials and step-by-step building up of a solution for long-lived wastes (difficulties, lessons learnt from foreign experience, first draft of the 2006 law). Some opinions expressed by some participants about these proposals conclude

Long term radioactive waste management

International Nuclear Information System (INIS)

Lavie, J.M.

1984-01-01

In France, waste management, a sensitive issue in term of public opinion, is developing quickly, and due to twenty years of experience, is now reaching maturity. With the launching of the French nuclear programme, the use of radioactive sources in radiotherapy and industry, waste management has become an industrial activity. Waste management is an integrated system dealing with the wastes from their production to the long term disposal, including their identification, sortage, treatment, packaging, collection and transport. This system aims at guaranteing the protection of present and future populations with an available technology. In regard to their long term management, and the design of disposals, radioactive wastes are divided in three categories. This classification takes into account the different radioisotopes contained, their half life and their total activity. Presently short-lived wastes are stored in the shallowland disposal of the ''Centre de la Manche''. Set up within the French Atomic Energy Commission (CEA), the National Agency for waste management (ANDRA) is responsible within the framework of legislative and regulatory provisions for long term waste management in France [fr

Alternate form and placement of short lived reactor waste and associated fuel hardware for decommissioning of EBR-II

Energy Technology Data Exchange (ETDEWEB)

Planchon, H.P.; Singleterry, R.C. Jr.

1995-12-01

Upon the termination of EBR-II operation in 1994, the mission has progressed to decommissioning and waste cleanup of the facility. The simplest method to achieve this goal is to bury the raw fuel and activated steel in an approved burial ground or deep geologic repository. While this might be simple, it could be very expensive, consume much needed burial space for other materials, and leave large amounts of fissile easily available to future generations. Also, as with any operation, an associated risk to personnel and the public from the buried waste exists. To try and reduce these costs and risks, alternatives to burial are sought. One alternative explored here for EBR-II is to condition the fuel and store the fission products and steel either permanently or temporarily in the sealed primary boundary of the decommissioned reactor. The first problem is to identify which subassemblies are going to be conditioned and their current composition and decay time. The next problem is to identify the conditioning process and determine the composition and form of the waste streams. The volume, mass, heat, and curie load of the waste streams needs to be determined so a waste-assembly can be designed. The reactor vessel and internals need to be analyzed to determine if they can handle these loads. If permanent storage is the goal, then mechanisms for placing the waste-assembly in the reactor vessel and sealing the vessel are needed. If temporary storage is the goal, then mechanisms for waste-assembly placement and retrieval are needed. This paper answers the technical questions of volume, mass, heat, and curie loads while just addressing the other questions found in a safety analysis. The final conclusion will compare estimated risks from the burial option and this option.

Management of radioactive waste from 99Mo production

International Nuclear Information System (INIS)

1998-11-01

99m Tc used for labelling different pharmaceuticals is the most important radionuclide in nuclear medicine practice, and probably will continue to play this important role for the foreseeable future. 99m Tc is the short lived daughter product of the parent 99 Mo, which is mainly produced by the nuclear fission of 235 U. Recognizing the importance of the waste management issue associated with 99 Mo production the IAEA initiated preparation of this report to provide Member States and existing and potential producers of 99 Mo with practical approaches and the available information on the subject. Waste management in the context of this report encompasses all waste-related aspects, for example, handling, treatment, conditioning, storage, transport, and disposal. The document is organized in several chapters giving the following information: short description of the basic nuclear and physical properties of 99 Mo and 99m Tc; an overview of past, present and possible future production methods; characteristics of the various waste streams produced in the aforementioned processes; description of the necessary waste management practices needed to handle the relevant waste streams in a responsible and internationally-accepted manner; conclusion and recommendations

Interest of the Department of Energy in production and development of short-lived radionuclides

International Nuclear Information System (INIS)

Thiessen, J.W.

1985-01-01

The Department of Energy has developed production of potentially useful radionuclides for applications in medicine. The Department's financial commitment and the short-lived radionuclide production program, with emphasis on iodine-123, is discussed

Continuous administration of short-lived radioisotope tracers and the analogous Laplace transform

International Nuclear Information System (INIS)

Orr, J.S.

1979-01-01

Short-lived radioactive tracers are used because of the low radiation dose to patients. Another advantage finding increasing use, however, is that the equilibrium activities achieved by continuous administration to a steady state contain kinetic information. This is not the case with long-lived isotopes. The derivation of quantitative kinetic information in the form of rate constants or flows requires the formulation of a model of the system being studied. Several approaches to this have been published based on a model of single compartments with simultaneous arrival of tracer. To deal with more realistic models a method is proposed which uses the analogy between the procedure of continuous administration of short-lived tracer and the Laplace transform. This analogy permits all the theorems of Laplace transform theory to be applied to the analysis of measured activities. The basis of the analogy is explained and examples are given of its application to a number of models which represent actual physiology more realistically than single compartment models. In these applications the transformed equations representing the model, with measured values of activity inserted for each transform, are solved to derive the rate constants. This is different from the use of Laplace transforms where the constant coefficients are known and the initial value problem is solved to find the behaviour of the variables. (author)

The environmental and ethical basis of the geological disposal of long-lived radioactive waste

International Nuclear Information System (INIS)

Vuori, S.

1995-01-01

This partial translation into Finnish of the recently issued Collective Opinion of the Radioactive Waste Management Committee (RWMC) of the OECD Nuclear Energy Agency is published here to provide general information to the members of the Finnish Nuclear Society. Full translation will be published later by the Ministry of Trade and Industry. The collective opinion addresses the strategy for the final disposal of long-lived radioactive wastes seen from an environmental and ethical perspective, including considerations of equity and fairness within and between generations

The concept of responsibility to future generations for the management and storage of radioactive waste

International Nuclear Information System (INIS)

Vial, E.

2004-01-01

Recognition of the concept of responsibility to future generations seems, to imply the need to assume responsibility today for radioactive waste legacy of the past as well as for the waste that is currently being generated. However, this view of things, or more precisely this interpretation, is clouded by the lack of a clear definition of the concept of responsibility towards future generations. The concept has been used mainly in connection with long-lived radioactive wastes, which pose the greatest management problem as it so so far exceeds any human scale of reference. Consideration for future generations has to be a factor in the management of all types of radioactive waste, be it short, medium or long-lived waste or very low, low, intermediate or highly radioactive waste. As a general rule the concept of responsibility has made focus on long lived waste, whatever its level of radioactivity. The current alternatives for the management of radioactive waste may be: interim storage, final disposal, incineration, transmutation, to lower the radioactivity of the wastes. These different alternatives are discussed because they are not all genuine solutions and need to be deepened. (N.C.)

The Danish inventory of radioactive waste and the required repository type

Energy Technology Data Exchange (ETDEWEB)

Schmidt, Gerhard [Oeko-Institut e.V., Darmstadt (Germany). Div. on Nuclear Engineering and Facility Safety

2014-11-15

Denmark has a relatively small inventory of radioactive wastes. As Denmark never built and operated nuclear power plants, the wastes resulted only from various research activities. In order to manage those wastes, the Danish Government has ordered to describe those wastes and the available management options. Based on vague criteria, most of the waste types were termed as ''short-lived'' and as suitable for a surface-near disposal facility. The Government then ordered the Geological survey organization of Denmark, GEUS, to scan Denmark for suitable locations. ''Suitable'' depth was defined as 0 to 100 m below ground. Neither were isolation properties or other requirements for geological layers defined nor were those criteria agreed in a broader sense (with experts, with the public). GEUS identified a number of potentially suitable locations and selected six of those as the most promising. In this paper the basic decision of preferring surface-near disposal for most of the waste types is analysed. As a central criterion for the suitability of the waste types for surface-near disposal is defined that those waste types decay within 300 years to below today's clearance levels. The results show, that none of the Danish types of waste meets this simple requirement. All are above that criterion, most of them by several orders of magnitude and over very much longer times such as 100.000 years or even longer. The basic assumption of the performed site selection procedure, to search for near-surface locations for short-lived wastes, so proves to be invalid. The whole process should be re-done on the basis that the long-term isolation of those wastes in impermeable layers has to be guaranteed. The suitability criteria should focus on the long-term isolation of all wastes and should be agreed in advance.

Experimental studies on behaviour of long-lived radionuclides in relation to deep-ocean disposal of nuclear waste

International Nuclear Information System (INIS)

Aston, S.R.; Fowler, S.W.

1984-01-01

Laboratory experiments have been carried out to investigate the interactions of long-lived radionuclides with sediments from present or potential deep-ocean radioactive waste disposal sites. The studies have been concerned with both geochemical aspects and sediment/animal radioecology. Examples drawn from the comparative behaviour of technetium and three transuranium nuclides (neptunium, plutonium and americium) are presented in relation to their uptake from sea water by deep-ocean sediments, ease of desorption and transfer from contaminated sediments to benthic invertebrates. The results provide information for the prediction of the behaviour of long-lived radionuclides in the deep-sea water/sediment boundary after their release from wastes. (author)

The inventory model for feasibility studies of a deep geological disposal for high level and long lived waste

International Nuclear Information System (INIS)

Dutzer, M.; Lagrange, M.H.; Porcher, J.B.; Chupeau, J.

2001-01-01

A detailed inventory of high level and long lived waste packages was established to perform studies for the feasibility of an underground repository. This inventory takes into account existing conditioned waste, unconditioned waste and arisings generated by existing facilities. Grouping of waste package sorts in package types is done regarding relevant characteristics that determine the design of disposal vaults. The radiological content of each package type is derived from calculations of nuclear interactions inside the reactors, from the distribution of the nuclides in the different package types; it is cross-checked with available data on waste sorts. (author)

Studies on separation, conversion and transmutation of long-living radionuclides. A contribution to advanced disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Modolo, Giuseppe

2014-01-01

The future role and acceptance of nuclear energy will be decisively determined by the safe operation of existing and future facilities and by convincing solutions for nuclear waste management. With respect to the long half-lives of some radionuclides (actinides and fission products) and the related question as to whether the release of radionuclides from a repository can be prevented over very long periods of time, alternatives to the direct disposal of spent nuclear fuels are discussed internationally. As a potential complementary solution, the technological option with partitioning and transmutation (P and T) is considered. This method separates and converts the long-lived radionuclides into stable, short-lived nuclides via neutron reactions in dedicated facilities. Against this background, the first main chapter of the present work looks at the chemical separation of actinides from high-level reprocessing wastes. In order to achieve a better understanding of the processes at the molecular level, basic investigations were also performed on separating actinides(III) via liquid-liquid or liquid-solid extraction. At the same time, reversible processes were developed and tested on the laboratory scale with the aid of mixer-settlers and centrifugal extractors. The subsequent chapter focuses on separating the long-lived fission product iodine-129 from radioactive wastes as well as from process effluents arising from reprocessing. As part of this work, different simple chemical and physical techniques were developed for complete recovery with respect to transmutation or conditioning in host matrices that are sufficiently stable for final storage. Its high mobility and radiological properties make iodine-129 relevant for the long-term safety assessment of final repositories. In addition, transmutation experiments on iodine-127/129 targets were performed using high-energy protons (145-2600 MeV). Due to the expected low cross sections (<100 mb), transmutation with protons

Simulation Studies of Diffusion-Release and Effusive-Flow of Short-Lived Radioactive Isotopes

CERN Document Server

Zhang, Yan; Kawai, Yoko

2005-01-01

Delay times associated with diffusion release from targets and effusive-flow transport of radioactive isotopes to ion sources are principal intensity limiters at ISOL-based radioactive ion beam facilities, and simulation studies with computer models are cost effective methods for designing targets and vapor transport systems with minimum delay times to avoid excessive decay losses of short lived ion species. A finite difference code, Diffuse II, was recently developed at the Oak Ridge National Laboratory to study diffusion-release of short-lived species from three principal target geometries. Simulation results are in close agreement with analytical solutions to Fick’s second equation. Complementary to the development of Diffuse II, the Monte-Carlo code, Effusion, was developed to address issues related to the design of fast vapor transport systems. Results, derived by using Effusion, are also found to closely agree with experimental measurements. In this presentation, the codes will be used in conc...

Short-lived pollutants in the Arctic: their climate impact and possible mitigation strategies

Directory of Open Access Journals (Sweden)

S. Menon

2008-03-01

Full Text Available Several short-lived pollutants known to impact Arctic climate may be contributing to the accelerated rates of warming observed in this region relative to the global annually averaged temperature increase. Here, we present a summary of the short-lived pollutants that impact Arctic climate including methane, tropospheric ozone, and tropospheric aerosols. For each pollutant, we provide a description of the major sources and the mechanism of forcing. We also provide the first seasonally averaged forcing and corresponding temperature response estimates focused specifically on the Arctic. The calculations indicate that the forcings due to black carbon, methane, and tropospheric ozone lead to a positive surface temperature response indicating the need to reduce emissions of these species within and outside the Arctic. Additional aerosol species may also lead to surface warming if the aerosol is coincident with thin, low lying clouds. We suggest strategies for reducing the warming based on current knowledge and discuss directions for future research to address the large remaining uncertainties.

Short-lived pollutants in the Arctic: their climate impact and possible mitigation strategies

Energy Technology Data Exchange (ETDEWEB)

Menon, Surabi; Quinn, P.K.; Bates, T.S.; Baum, E.; Doubleday, N.; Fiore, A.M.; Flanner, M.; Fridlind, A.; Garrett, T.J.; Koch, D.; Menon, S.; Shindell, D.; Stohl, A.; Warren, S.G.

2007-09-24

Several short-lived pollutants known to impact Arctic climate may be contributing to the accelerated rates of warming observed in this region relative to the global annually averaged temperature increase. Here, we present a summary of the short-lived pollutants that impact Arctic climate including methane, tropospheric ozone, and tropospheric aerosols. For each pollutant, we provide a description of the major sources and the mechanism of forcing. We also provide the first seasonally averaged forcing and corresponding temperature response estimates focused specifically on the Arctic. The calculations indicate that the forcings due to black carbon, methane, and tropospheric ozone lead to a positive surface temperature response indicating the need to reduce emissions of these species within and outside the Arctic. Additional aerosol species may also lead to surface warming if the aerosol is coincident with thin, low lying clouds. We suggest strategies for reducing the warming based on current knowledge and discuss directions for future research to address the large remaining uncertainties.

Short-lived radioactive nuclides in meteorites and early solar system processes

International Nuclear Information System (INIS)

Chaussidon, M.; Gounelle, M.

2007-01-01

Now extinct, short-lived radioactive nuclides, such as 7 Be (T 1/2 = 53 days), 10 Be (T 1/2 = 1.5 Ma), 26 Al (T 1/2 = 0.74 Ma), 36 Cl (T 1/2 = 0.3 Ma), 41 Ca (T 1/2 = 0.1 Ma), 53 Mn (T 1/2 = 3.7 Ma) and 60 Fe (T 1/2 = 1.5 Ma), were present in the proto-solar nebula when the various components of meteorites formed. The presence of these radioactive isotopes requires a 'last-minute' origin, either nucleosynthesis in a massive star dying close in space and time to the nascent solar system or production by local irradiation of part of the proto-solar disk by high-energy solar cosmic rays. In this review, we list: (i) the different observations indicating the existence of multiple origins for short-lived radioactive nuclides, namely 7 Be, 10 Be and 36 Cl for irradiation scenario and 60 Fe for injection scenario; (ii) the constraints that exist on their distribution (homogeneous or heterogeneous) in the accretion disk; (iii) the constraints they brought on the timescales of nebular processes (from Ca-Al-rich inclusions to chondrules) and of the accretion and differentiation of planetesimals. (authors)

National radioactive waste repository draft EIS. 2 volumes

International Nuclear Information System (INIS)

2002-01-01

Most Australians benefit either directly or indirectly from the medical, industrial and scientific use of radioactive materials. This use produces a small amount of radioactive waste, including low level and short-lived intermediate level radioactive waste such as lightly contaminated soil, plastic, paper, laboratory equipment, smoke detectors, exit signs and gauges.This waste is temporarily stored at more than 100 urban and rural locations around Australia, much of it in buildings that were neither designed nor located for the long-term storage of radioactive material and that are nearing or have reached capacity. Storage locations include hospitals, research institutions, and industry and government stores. Storing such waste in many locations in non-purpose built facilities potentially poses greater risk to the environment and people than disposing of the material in a national, purpose-built repository where the material can be safely managed and monitored. The objectives of the national repository are to: 1. strengthen Australia's radioactive waste management arrangements by promoting the safe and environmentally sound management of low level and short-lived intermediate level radioactive waste 2. provide safe containment of these wastes until the radioactivity has decayed to background levels. To meet these objectives, it is proposed to construct a national near-surface repository at either the preferred site on the Woomera Prohibited Area (WPA) or either of the two nearby alternative sites. The facility is not intended for the disposal of radioactive ores from mining. A national store for long-lived intermediate level waste will not be co-located with the national repository, and would be subject to a separate environmental assessment process.One preferred and two alternative sites have been selected for the national repository, following an extensive site selection process. All three sites are located in northern South Australia in a region known as central

Dynamical Detection of Topological Phase Transitions in Short-Lived Atomic Systems

OpenAIRE

Setiawan, F.; Sengupta, K.; Spielman, I. B.; Sau, Jay D.

2015-01-01

We demonstrate that dynamical probes provide direct means of detecting the topological phase transition (TPT) between conventional and topological phases, which would otherwise be difficult to access because of loss or heating processes. We propose to avoid such heating by rapidly quenching in and out of the short-lived topological phase across the transition that supports gapless excitations. Following the quench, the distribution of excitations in the final conventional phase carries signat...

Validation of Six Short and Ultra-short Screening Instruments for Depression for People Living with HIV in Ontario

DEFF Research Database (Denmark)

Choi, Stephanie KY; Boyle, Eleanor; Burchell, Ann

2015-01-01

Objective Major depression affects up to half of people living with HIV. However, among HIV-positive patients, depression goes unrecognized 60–70% of the time in non-psychiatric settings. We sought to evaluate three screening instruments and their short forms to facilitate the recognition...... acceptance. This could lead to clinical benefits in fast-paced speciality HIV care settings and better management of depression in HIV-positive patients....

Biomedical waste management: Incineration vs. environmental safety

Directory of Open Access Journals (Sweden)

Gautam V

2010-01-01

Full Text Available Public concerns about incinerator emissions, as well as the creation of federal regulations for medical waste incinerators, are causing many health care facilities to rethink their choices in medical waste treatment. As stated by Health Care Without Harm, non-incineration treatment technologies are a growing and developing field. Most medical waste is incinerated, a practice that is short-lived because of environmental considerations. The burning of solid and regulated medical waste generated by health care creates many problems. Medical waste incinerators emit toxic air pollutants and toxic ash residues that are the major source of dioxins in the environment. International Agency for Research on Cancer, an arm of WHO, acknowledged dioxins cancer causing potential and classified it as human carcinogen. Development of waste management policies, careful waste segregation and training programs, as well as attention to materials purchased, are essential in minimizing the environmental and health impacts of any technology.

Centuries of thermal sea-level rise due to anthropogenic emissions of short-lived greenhouse gases.

Science.gov (United States)

Zickfeld, Kirsten; Solomon, Susan; Gilford, Daniel M

2017-01-24

Mitigation of anthropogenic greenhouse gases with short lifetimes (order of a year to decades) can contribute to limiting warming, but less attention has been paid to their impacts on longer-term sea-level rise. We show that short-lived greenhouse gases contribute to sea-level rise through thermal expansion (TSLR) over much longer time scales than their atmospheric lifetimes. For example, at least half of the TSLR due to increases in methane is expected to remain present for more than 200 y, even if anthropogenic emissions cease altogether, despite the 10-y atmospheric lifetime of this gas. Chlorofluorocarbons and hydrochlorofluorocarbons have already been phased out under the Montreal Protocol due to concerns about ozone depletion and provide an illustration of how emission reductions avoid multiple centuries of future TSLR. We examine the "world avoided" by the Montreal Protocol by showing that if these gases had instead been eliminated in 2050, additional TSLR of up to about 14 cm would be expected in the 21st century, with continuing contributions lasting more than 500 y. Emissions of the hydrofluorocarbon substitutes in the next half-century would also contribute to centuries of future TSLR. Consideration of the time scales of reversibility of TSLR due to short-lived substances provides insights into physical processes: sea-level rise is often assumed to follow air temperature, but this assumption holds only for TSLR when temperatures are increasing. We present a more complete formulation that is accurate even when atmospheric temperatures are stable or decreasing due to reductions in short-lived gases or net radiative forcing.

Short-lived cyclotron-produced radioisotopes: Medi-Physics, Inc.'s commitment

International Nuclear Information System (INIS)

Kramer, H.H.

1985-01-01

Medi-Physics, Inc., is a major US supplier of short-lived cyclotron-produced radioisotopes for radiopharmaceuticals, as well as routinely producing and distributing the greatest number of 123 I radiopharmaceuticals. The present commercial production capacity for 123 I is more than ten times the theoretical need for existing procedures and is more than adequate for the research and development of new radiopharmaceuticals. However, production capacity is only one component of many that are required to supply a radioisotope for human use. These components are summarized in this paper

Safety Aspects in Radioactive Waste Management

Directory of Open Access Journals (Sweden)

Peter W. Brennecke

2007-01-01

Full Text Available In recent years, within the framework of national as well as international programmes, notable advances and considerable experience have been reached, particularly in minimising of the production of radioactive wastes, conditioning and disposal of short-lived, low and intermediate level waste, vitrification of fission product solutions on an industrial scale and engineered storage of long-lived high level wastes, i.e. vitrified waste and spent nuclear fuel. Based on such results, near-surface repositories have successfully been operated in many countries. In contrast to that, the disposal of high level radioactive waste is still a scientific and technical challenge in many countries using the nuclear power for the electricity generation. Siting, planning and construction of repositories for the high level wastes in geological formations are gradually advancing. The site selection, the evaluation of feasible sites as well as the development of safety cases and performance of site-specific safety assessments are essential in preparing the realization of such a repository. In addition to the scientific-technical areas, issues regarding economical, environmental, ethical and political aspects have been considered increasingly during the last years. Taking differences in the national approaches, practices and the constraints into account, it is to be recognised that future developments and decisions will have to be extended in order to include further important aspects and, finally, to enhance the acceptance and confidence in the safety-related planning work as well as in the proposed radioactive waste management and disposal solutions.

Application of short-time activation analysis in the sciences

International Nuclear Information System (INIS)

Grass, F.

1991-01-01

Short-time activation analysis has proved to be a valuable tool in nearly all fields of science. To take full advantage of this technique, it is favorable to use a fast transfer system and a high resolution high rate gamma-spectroscopy system for short lived gamma-emitters and a Cherenkov detector for the determination of hard beta-emitters. It is then possible to utilize sub-minute nuclides Li-8 (740 ms), B-12 (20 ms), F-20 (11.1 s), Y-89m (16 s), and Pb-207m (800 ms) for the determination of these elements. Besides these sub-minute nuclides which constitute the only possibility for neutron activation analysis of these elements there are a number of other elements which form longer lived nuclides on short irradiation. The analysis of the halogenides F, Cl, Br, I in waste water of a sewage incineration plant can be achieved with a single 20 s irradiation and two consecutive measurement of 20 and 600 s using Cl-38m, F-20, Br-79m as well as the longer lived Cl-38, Br-80, I-128

Separation efficiency of the MASHA facility for short-lived mercury isotopes

Science.gov (United States)

Rodin, A. M.; Belozerov, A. V.; Chernysheva, E. V.; Dmitriev, S. N.; Gulyaev, A. V.; Gulyaeva, A. V.; Itkis, M. G.; Kliman, J.; Kondratiev, N. A.; Krupa, L.; Novoselov, A. S.; Oganessian, Yu. Ts.; Podshibyakin, A. V.; Salamatin, V. S.; Siváček, I.; Stepantsov, S. V.; Vanin, D. V.; Vedeneev, V. Yu.; Yukhimchuk, S. A.; Granja, C.; Pospisil, S.

2014-06-01

The mass-separator MASHA built to identify Super Heavy Elements by their mass-to-charge ratios is described. The results of the off- and on-line measurements of its separation efficiency are presented. In the former case four calibrated leaks of noble gases were used. In the latter the efficiency was measured via 284 MeV Ar beam and with using the hot catcher. The ECR ion source was used in both cases. The -radioactive isotopes of mercury produced in the complete fusion reaction Ar+SmHg+xn were detected at the mass-separator focal plane. The half-lives and the separation efficiency for the short-lived mercury isotopes were measured. Potentialities of the MEDIPIX detector system have been demonstrated for future use at the mass-separator MASHA.

Risk perception, risk evaluation and human values: cognitive bases of acceptability of a radioactive waste repository

International Nuclear Information System (INIS)

Earle, T.C.; Lindell, M.K.; Rankin, W.L.

1981-07-01

Public acceptance of radioactive waste management alternatives depends in part on public perception of the associated risks. Three aspects of those perceived risks were explored in this study: (1) synthetic measures of risk perception based on judgments of probability and consequences; (2) acceptability of hypothetical radioactive waste policies, and (3) effects of human values on risk perception. Both the work on synthetic measures of risk perception and on the acceptability of hypothetical policies included investigations of three categories of risk: (1) Short-term public risk (affecting persons living when the wastes are created), (2) Long-term public risk (affecting persons living after the time the wastes were created), and (3) Occupational risk (affecting persons working with the radioactive wastes). The human values work related to public risk perception in general, across categories of persons affected

Accelerator transmutation of wastes (ATW) - Prospects and safety

International Nuclear Information System (INIS)

Gudowski, W.; Pettersson, Kjell; Thedeen, T.

1993-11-01

Accelerator transmutation of nuclear waste (ATW) has during last years gained interest as a technologically possible method to transform radioactive wastes into short-lived or stable isotopes. Different ATW-projects are described from the physical and technical point of view. The principal sketch of the safety analysis of the ATW-idea is given. Due to the very limited technical data for existing ATW-projects the safety analysis can cause some risks for the health and environmental safety for the closest environment. General public should not be affected. 35 refs, 22 figs, 4 tabs

Rapid transfer of short-lived radioisotopes via a 2. 4 km rabbit system

Energy Technology Data Exchange (ETDEWEB)

Burgerjon, J J; Gelbart, Z; Lau, V; Lehnart, D; Lenz, J; Pate, B D; Ruth, T J; Sprenger, H P; van Oers, N S.C.

1984-09-01

A 2.4 km long pipeline between a cyclotron and a hospital is used for the rapid transfer of short-lived radiopharmaceuticals. The vials containing the pharmaceuticals are placed inside capsules (rabbits) that are blown through a tube by means of compressed air. Travel times as short as 2 min are achieved, which makes the system suitable for the transfer of /sup 15/O, which has a 2 min half-life. The construction and test results of the system are described along with a computer model, developed to explain some properties of the system. 7 references, 15 figures, 2 tables.

Increased Concentrations of Short-Lived Decay-Series Radionuclides in Groundwaters Underneath the Nopal I Uranium Deposit at Pena Blanca, Mexico

Science.gov (United States)

Luo, S.; Ku, T.; Todd, V.; Murrell, M. T.; Dinsmoor, J. C.

2007-05-01

The Nopal I uranium ore deposit at Pena Blanca, Mexico, located at > 200 meters above the groundwater table, provides an ideal natural analog for quantifying the effectiveness of geological barrier for isolation of radioactive waste nuclides from reaching the human environments through ground water transport. To fulfill such natural analog studies, three wells (PB1, PB2, and PB3 respectively) were drilled at the site from the land surface down to the saturated groundwater zone and ground waters were collected from each of these wells through large- volume sampling/in-situ Mn-filter filtration for analyses of short-lived uranium/thorium-series radionuclides. Our measurements from PB1 show that the groundwater standing in the hole has much lower 222Rn activity than the freshly pumped groundwater. From this change in 222Rn activity, we estimate the residence time of groundwater in PB1 to be about 20 days. Our measurements also show that the activities of short-lived radioisotopes of Th (234Th), Ra (228Ra, 224Ra, 223Ra), Rn (222Rn), Pb (210Pb), and Po (210Po) in PB1, PB2, and PB3 are all significantly higher than those from the other wells near the Nopal I site. These high activities provide evidence for the enrichment of long-lived U and Ra isotopes in the groundwater as well as in the associated adsorbed phases on the fractured aquifer rocks underneath the ore deposit. Such enrichment suggests a rapid dissolution of U and Ra isotopes from the uranium ore deposit in the vadose zone and the subsequent migration to the groundwater underneath. A reactive transport model can be established to characterize the in-situ transport of radionuclides at the site. The observed change of 222Rn activity at PB1 also suggests that the measured high radioactivityies in ground waters from the site isare not an artifact of drilling operations. However, further studies are needed to assess if or to what extent the radionuclide migration is affected by the previous mining activities at

Report of ICRP Task Group 80: 'radiological protection in geological disposal of long-lived solid radioactive waste'.

Science.gov (United States)

Weiss, W

2012-01-01

The report of International Commission on Radiological Protection (ICRP) Task Group 80 entitled 'Radiological protection in geological disposal of long-lived solid radioactive waste' updates and consolidates previous ICRP recommendations related to solid waste disposal (ICRP Publications 46, 77, and 81). The recommendations given in this report apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the 2007 system of radiological protection, described in ICRP Publication 103, can be applied in the context of the geological disposal of long-lived solid radioactive waste. The report is written as a self-standing document. It describes the different stages in the lifetime of a geological disposal facility, and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that influences application of the protection system over the different phases in the lifetime of a disposal facility is the level of oversight that is present. The level of oversight affects the capability to reduce or avoid exposures. Three main time frames have to be considered for the purpose of radiological protection: time of direct oversight when the disposal facility is being implemented and active oversight is taking place; time of indirect oversight when the disposal facility is sealed and indirect oversight is being exercised to provide additional assurance on behalf of the population; and time of no oversight when oversight is no longer exercised because memory is lost. Copyright © 2012. Published by Elsevier Ltd.

Researches on the management of high activity and long-lived radioactive wastes. Axis 1 - separation-transmutation

International Nuclear Information System (INIS)

2005-11-01

This document gathers the transparencies of seven presentations given at a technical workshop of the French nuclear energy society (SFEN) about the researches on separation-transmutation of high activity and long-lived radioactive wastes. The presentations deal with: inventory and radiotoxicity of the rad-wastes in concern; industrial experience; experience on chemical separation: molecules and processes; reactors physics and transmutation - reactors for transmutation; fuels and targets; scenarios that include transmutation; environmental impacts of these different scenarios. (J.S.)

Radioactive wastes. The groundwork of current solutions

International Nuclear Information System (INIS)

Grevoz, A.; Boullis, B.; Devezeaux de Lavergne, J.G.; Butez, M.; Bordier, G.; Vitart, X.; Hablot, I.; Chastagnet, F.

2005-01-01

Today the groundwork laid down by research has made processes available for the durable treatment and conditioning of all types of radioactive waste. This document illustrates the today situations in five presentations. Now standing as a national reference, the french inventory of radioactive waste, drawn up by ANDRA, has not only expanded to cover recoverable material but also features predictions of waste arisings for 2010 and 2020, including waste from the decommissioning of current installations. The current process used for spent fuel reprocessing allows extraction for recycling purpose, of uranium and plutonium, with very high recovery and purification rates. Advances in characterization and decontamination allow improvements in sorting and retrieval and conditioning to be considered for older wastes. The french National radioactive waste management agency (ANDRA) is already providing optimum industrial solutions for all short-lived, low and very low level waste on its Soulaines and Morvillers sites. For several decades, Areva has been reprocessing spent fuel and conditioning ultimate waste in its La Hague plants. (A.L.B.)

Disposal of high level and long lived radioactive waste in deep geological formation

International Nuclear Information System (INIS)

Niezborala, J.M.; Hoorelbeke, J.M.

2000-01-01

The status of ANDRA's research program on high level and long lived waste corresponds to the start of construction of the Meuse/Haute-Marne Underground Research Laboratory in an argillite layer, as well as to the selection in 1999 of preliminary disposal concepts corresponding to this layer. The paper describes the preliminary concepts dealing with transuranic waste, high level vitrified waste and potentially disposed spent fuel. Provision is made for a high level of flexibility, in particular with regard to options of reversibility of the disposal process, and to potential evolutions of the waste inventory. These concepts were selected for research purpose to assess by the year 2006 the feasibility of a potential repository, with.respect in particular to safety rules. The paper mentions the research targets of the program aiming at answering major scientific and technological questions raised by the concepts. The program includes the fitting and validation of the modelling, on the basis in particular of the experimental work to be carried out in the Underground Research Laboratory, making it possible to dimension the disposal concepts and to assess their safety. (authors)

Development of the k0-based cyclic neutron activation analysis for short-lived radionuclides

NARCIS (Netherlands)

Dung, H.M.; Blaauw, M.; Beasley, D.; Freitas, M.D.C.

2011-01-01

The k0-based cyclic neutron activation analysis (k0-CNAA) technique has been studied to explore the applicability at the Portuguese research reactor (RPI). In particular, for the determination of elements which form short-lived radionuclides, particularly fluorine (20F, 11.16 s half-life) and

Compton suppression spectrometry for analysis of short-lived neutron activation products in foods

International Nuclear Information System (INIS)

Anderson, D.L.; Cunningham, W.C.

2008-01-01

Compton suppression spectrometry was used to analyze foods for elements with short-lived neutron activation products (half-lives of about 2 minutes to 1.5 days). Analysis conditions were optimized to provide quality assurance analyses for iodine in FDA's Total Diet Study. Iodine mass fractions (0.075 to 2.03 mg/kg) were measured in 19 of 42 foods analyzed, with limits of detection (LODs) ranging from 0.03 to 1.4 mg/kg, mostly depending on NaCl content. LODs were lowered by up to a factor of 2 for 16 elements. Suppression factors ranged from about 2 to 8 over the energy range 400 to 3200 keV. (author)

Position paper: Live load design criteria for Project W-236A Multi-Function Waste Tank Facility

International Nuclear Information System (INIS)

Giller, R.A.

1995-01-01

The purpose of this paper is to discuss the live loads applied to the underground storage tanks of the Multi Function Waste Tank Facility, and to provide the basis for Project W-236A live load criteria. Project 236A provides encompasses building a Weather Enclosure over the two underground storage tanks at the 200-West area. According to the Material Handling Study, the Groves AT 1100 crane used within the Weather Enclosure will have a gross vehicle weight of 66.5 tons. Therefore, a 100-ton concentrated live load is being used for the planning of the construction of the Weather Enclosure

Kinetic aspects of the syntheses using short-lived radionuclides

International Nuclear Information System (INIS)

Laangstroem, B.; Obenius, U.; Sjoeberg, S.; Bergson, G.

1981-01-01

In syntheses using short-lived radionuclides, such as 11 C, the reaction conditions are usually such that the concentrations of the reactants, except for the labelled reactant, can be considered constant during the reaction. Two kinetic models have been investigated - irreversible and reversible bimolecular elementary reactions. The influence of the rate constants, of the equilibrium constants, and of the ratio between the starting reactants on the yield of the labelled product has been studied. The results show that, even in cases with unfavourable equilibrium constants, high yields of the labelled products can be obtained if the rate constant for the forward reaction is large. In addition, the specific activity of the labelled product as a function of time has been studied for the irreversible bimolecular case. (author)

Radiotracer diffusion in semiconductors and metallic compounds using short-lived isotopes

CERN Multimedia

Deicher, M; Kronenberg, J; Wagner, F E

The transport of atoms in solids is of central importance for solid state physics, chemistry, metallurgy, and material sciences. Since the mobility of atoms in solids contributes to many physical phenomena the study of diffusion processes is of fundamental interest for solid state physics. Diffusion processes were frequently investigated using radioactive isotopes (radiotracers). The application of short-lived isotopes delivered at ISOLDE extends substantially the possibilities of investigating diffusion processes in solids. In particular, a new experimental set-up to be installed at ISOLDE in this year will enable the use of radioactive isotopes with half-lives down to minutes. Alternatively, in special cases diffusion processes can be investigated with help of hyperfine techniques on an atomic scale, like by perturbed $\\gamma \\gamma$-angular correlation (PAC). Here, the motion of the atom of interest becomes visible directly via characteristic changes in the measured PAC spectra.

Current status of high level radioactive waste disposal in Japan and foreign countries

International Nuclear Information System (INIS)

Tanaka, Satoru; Tanabe, Hiromi; Inagaki, Yusuke; Ishida, Hisahiro; Kato, Osamu; Kurata, Mitsuyuki; Yamachika, Hidehiko

2002-01-01

At a time point of 2002, there is no country actually disposing high level radioactive wastes into grounds, but in most of countries legislative preparation and practicing agents are carried out and site selection is promoted together with energetic advancement of its R and Ds. As disposal methods of the high level radioactive wastes, various methods such as space disposal, oceanic bottom disposal, ice bed disposal, ground disposal, and so on have been examined. And, a processing technology called partitioning and transmutation technology separating long-lived radionuclides from liquid high level radioactive waste and transmutation into short-lived or harmless radionuclides has also been studied. Here was introduced their wrestling conditions in Japan and main foreign countries, as a special issue of the Current status of high level radioactive waste disposal in Japan and foreign countries'. The high level radioactive wastes (glassification solids or spent nuclear fuels) are wastes always formed by nuclear power generation and establishment of technologies is an important subject for nuclear fuel cycle. (G.K.)

First Isochronous Time-of-Flight Mass Measurements of Short-Lived Projectile Fragments in the ESR

International Nuclear Information System (INIS)

Stadlmann, J.; Geissel, H.; Hausmann, M.; Nolden, F.; Radon, T.; Schatz, H.; Scheidenberger, C.; Attallah, F.; Beckert, K.; Bosch, F.; Falch, M.; Franczak, B.; Franzke, B.; Kerscher, Th.; Klepper, O.; Kluge, H.J.; Kozhuharov, C.; Loebner, K.E.G.; Muenzenberg, G.; Novikov, Yu.N.; Steck, M.; Sun, Z.; Suemmerer, K.; Weick, H.; Wollnik, H.

2000-01-01

A new method for precise mass measurements of short-lived hot nuclei is presented. These nuclei were produced via projectile fragmentation, separated with the FRS and injected into the storage ring ESR being operated in the isochronous mode. The revolution time of the ions is measured with a time-of-flight detector sensitive to single particles. This new method allows access to exotic nuclei with half-lives in the microsecond region. First results from this novel method obtained with measurements on neutron-deficient fragments of a chromium primary beam with half-lives down to 50 ms are reported. A precision of deltam/m ≤ 5 · 10 -6 has been achieved

Evaluation of regional pulmonary function using short-lived radioactive gases

Energy Technology Data Exchange (ETDEWEB)

Ashitaka, Tsuyoshi [Toho Univ., Tokyo (Japan). School of Medicine

1993-05-01

We investigated the application of short-lived radioactive gases for the assessment of regional pulmonary function, particularly diffusing capacity, in patients with chronic obstructive lung disease and interstitial lung disease. Short-lived radioactive gases including C[sup 15]O-O, [sup 11]CO[sub 2], and [sup 11]CO were produced using a baby cyclotron for medical care. Using a [gamma] camera, breath-holding images were taken serially after inhalation of the radioactive gases. The first exponential component of time-activity curve was analyzed to obtain clearance rate, which was expressed as exponential coefficient ([lambda]). Moreover, we created a functional map which was calculated by the clearance rate of [sup 11]CO[sub 2] as a percentage. Regional clearance rates of each gas in normal volunteers revealed higher values in the lower lung field than in the upper lung field. Whole lung clearance rates ([lambda]) of each gas in patients correlated well with D[sub LCO]/V[sub A], which indicates diffusing capacity. The functional map showed decreased regional diffusion closely matched to the perfusion defects seen by [sup 99m]Tc-MAA perfusion images. However, in certain interstitial lung diseases decreased clearance of [sup 11]CO[sub 2] was observed in regions having no evidence of perfusion defects. We concluded the functional map display of [sup 11]CO[sub 2] is useful indicator of the regional diffusing capacity of both the normal and diseased lung, and that it is beneficial to analyze the pathogenic physiology of diseased lungs by making a comparison between the functional map of [sup 11]CO[sub 2] and [sup 99m]Tc-MAA perfusion images. (author).

Licence applications for low and intermediate level waste predisposal facilities: A manual for operators

International Nuclear Information System (INIS)

2009-07-01

This publication covers all predisposal waste management facilities and practices for receipt, pretreatment (sorting, segregation, characterization), treatment, conditioning, internal relocation and storage of low and intermediate level radioactive waste, including disused sealed radioactive sources. The publication contains an Annex presenting the example of a safety assessment for a small radioactive waste storage facility. Facilities dealing with both short lived and long lived low and intermediate level waste generated from nuclear applications and from operation of small nuclear research reactors are included in the scope. Processing and storage facilities for high activity disused sealed sources and sealed sources containing long lived radionuclides are also covered. The publication does not cover facilities processing or storing radioactive waste from nuclear power plants or any other industrial scale nuclear fuel cycle facilities. Disposal facilities are excluded from the scope of this publication. Authorization process can be implemented in several stages, which may start at the site planning and the feasibility study stage and will continue through preliminary design, final design, commissioning, operation and decommissioning stages. This publication covers primarily the authorization needed to take the facility into operation

Disposition of nuclear waste using subcritical accelerator-driven systems

International Nuclear Information System (INIS)

Venneri, F.; Li, N.; Williamson, M.; Houts, M.; Lawrence, G.

1998-01-01

Spent fuel from nuclear power plants contains large quantities of Pu, other actinides, and fission products (FP). This creates challenges for permanent disposal because of the long half-lives of some isotopes and the potential for diversion of the fissile material. Two issues of concern for the US repository concept are: (1) long-term radiological risk peaking tens-of-thousands of years in the future; and (2) short-term thermal loading (decay heat) that limits capacity. An accelerator-driven neutron source can destroy actinides through fission, and can convert long-lived fission products to shorter-lived or stable isotopes. Studies over the past decade have established that accelerator transmutation of waste (ATW) can have a major beneficial impact on the nuclear waste problem. Specifically, the ATW concept the authors are evaluating: (1) destroys over 99.9% of the actinides; (2) destroys over 99.9% of the Tc and I; (3) separates Sr-90 and Cs-137; (4) separates uranium from the spent fuel; (5) produces electric power

Fee structures for low-level radioactive waste disposal

International Nuclear Information System (INIS)

Sutherland, A.A.; Baird, R.D.; Rogers, V.C.

1988-01-01

Some compacts and states require that the fee system at their new low-level waste (LLW) disposal facility be based on the volume and radioactive hazard of the wastes. The fee structure discussed in this paper includes many potential fee elements that could be used to recover the costs of disposal and at the same time influence the volume and nature of waste that arrives at the disposal facility. It includes a base fee which accounts for some of the underlying administrative costs of disposal, and a broad range of charges related to certain parameters of the waste, such as volume, radioactivity, etc. It also includes credits, such as credits for waste with short-lived radionuclides or superior waste forms. The fee structure presented should contain elements of interest to all states and compacts. While no single disposal facility is likely to incorporate all of the elements discussed here in its fee structure, the paper presents a fairly exhaustive list of factors worth considering

International perspective on regulation and radioactive waste management

International Nuclear Information System (INIS)

Brennecke, P.W.

2001-01-01

In recent years, within the framework of national as well as international programmes, notable advances and considerable experience have been reached, in particular in the areas of minimisation of the production of radioactive waste, conditioning and disposal of short-lived low and intermediate level waste, vitrification of fission product solution on an industrial scale and engineered storage of long-lived high level waste, i.e. vitrified waste and spent fuel. Based on such results near-surface repositories have successfully been operated in many countries. Furthermore, geological repository development programmes are now being pursued, addressing the development and application of appropriate methods for site-specific safety assessments, too. In addition to scientific-technical areas, issues regarding economical, environmental, ethical and political aspects have been considered increasingly during the last years. Hence, there is a need for the examination of such issues in more detail and, if appropriate, for introducing respective results in further radioactive waste management and disposal options and/or planning work. Taking differences in national approaches, practices and constraints into account, it is to be recognised that future developments and decisions will have to be extended in order to include further important aspects and, finally, to enhance acceptance and confidence in safety-related planning work as well as proposed radioactive waste management and disposal solutions. In particular, international expertise and peer reviews are to be integrated. (author)

Preparing isomerically pure beams of short-lived nuclei at JYFLTRAP

Energy Technology Data Exchange (ETDEWEB)

Eronen, T. [Department of Physics, University of Jyvaeskylae, P.O. Box 35 (YFL), FIN-40014 (Finland)], E-mail: tommi.eronen@jyu.fi; Elomaa, V.-V.; Hager, U.; Hakala, J.; Jokinen, A.; Kankainen, A.; Rahaman, S.; Rissanen, J.; Weber, C.; Aystoe, J. [Department of Physics, University of Jyvaeskylae, P.O. Box 35 (YFL), FIN-40014 (Finland)

2008-10-15

A new procedure to prepare isomerically clean samples of short-lived ions with a mass resolving power of more than 1 x 10{sup 5} has been developed at the JYFLTRAP tandem Penning trap system. The method utilises a dipolar rf-excitation of the ion motion with separated oscillatory fields in the precision trap. During a subsequent retransfer to the purification trap, the contaminants are rejected and as a consequence, the remaining bunch is isomerically cleaned. This newly-developed method is suitable for very high-resolution cleaning and is at least a factor of five faster than the methods used so far in Penning trap mass spectrometry.

Public debate on radioactive wastes; Le debat public sur les dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

The definition and implementation of safe and perennial solutions for the management of radioactive wastes is a necessity from the point of view of both the nuclear industrialists and the public authorities, but also of the overall French citizens. For the low- or medium-level or short living radioactive wastes, some solutions have been defined are are already implemented. On the other hand, no decision has been taken so far for the long living medium to high-level radioactive wastes. Researches are in progress in this domain according to 3 ways of research defined by the law from December 30, 1991: separation-transmutation, disposal in deep underground, and long duration surface or sub-surface storage. This paper presents in a digest way, the principle, the results obtained so far, and the perspectives of each of the three solutions under study. (J.S.)

Use of natural analogues to support radionuclide transport models for deep geological repositories for long lived radioactive wastes

International Nuclear Information System (INIS)

1999-10-01

Plans to dispose high level and long lived radioactive wastes in deep geological repositories have raised a number of unique problems, mainly due to the very long time-scales which have to be considered. An important way to help to evaluate performance and provide confidence in the assessment of safety in the long term is to carry out natural analogue studies. Natural analogues can be regarded as long term natural experiments the results or outcome of which can be observed, but which, by definition, are uncontrolled by humans. Studies of natural analogues have been carried out for more than two decades, although the application of information from them is only relatively recently becoming scientifically well ordered. This report is part of a the IAEA's programme on radioactive waste management dealing with disposal system technology for high level and long lived radioactive waste. It presents the current status of natural analogue information in evaluating models for radionuclide transport by groundwater. In particular, emphasis is given to the most useful aspects of quantitative applications for model development and testing (geochemistry and coupled transport models). The report provides an overview of various natural analogues as reference for those planning to develop a research programme in this field. Recommendations are given on the use of natural analogues to engender confidence in the safety of disposal systems. This report is a follow up of Technical Reports Series No. 304 on Natural Analogues in Performance Assessments for the Disposal of Long Lived Radioactive Waste (1989)

Issues and Experiences on Radioactive Waste Quality Control / Quality Assurance with Regard to Future Disposal

International Nuclear Information System (INIS)

Beckmerhagen, I.; Brennecke, P.; Steyer, S.; Bandt, G.

2006-01-01

In the Federal Republic of Germany all types of radioactive waste (short-lived, long-lived) are to be disposed of in deep geological formations. Thus, the safe management of radioactive waste presupposes an appropriate conditioning of primary waste-to-waste packages suitable for emplacement in a repository as well as the documentation of pre-treatment, processing and packaging steps and the waste package characteristics being relevant for disposal. Due to the operation, decommissioning and dismantling of nuclear facilities as well as the application of radioisotopes in industry, medicine and research and development radioactive waste continuously arises in Germany. In order to manage this waste different measures and procedures regarding its conditioning and quality control/quality assurance were introduced and since many years successfully applied. Waste conditioning is especially characterized by a flexible application of the Konrad waste acceptance requirements. The rationale for this approach is due to the present non-availability of a repository in Germany. Several examples of a 'tailor-made' application of the waste acceptance requirements in treatment, conditioning and documentation processes as well as the quality assurance/quality control processes illustrate the current German approach. (authors)

Large drainages from short-lived glacial lakes in the Teskey Range, Tien Shan Mountains, Central Asia

Science.gov (United States)

Narama, Chiyuki; Daiyrov, Mirlan; Duishonakunov, Murataly; Tadono, Takeo; Sato, Hayato; Kääb, Andreas; Ukita, Jinro; Abdrakhmatov, Kanatbek

2018-04-01

Four large drainages from glacial lakes occurred during 2006-2014 in the western Teskey Range, Kyrgyzstan. These floods caused extensive damage, killing people and livestock as well as destroying property and crops. Using satellite data analysis and field surveys of this area, we find that the water volume that drained at Kashkasuu glacial lake in 2006 was 194 000 m3, at western Zyndan lake in 2008 was 437 000 m3, at Jeruy lake in 2013 was 182 000 m3, and at Karateke lake in 2014 was 123 000 m3. Due to their subsurface outlet, we refer to these short-lived glacial lakes as the tunnel-type, a type that drastically grows and drains over a few months. From spring to early summer, these lakes either appear, or in some cases, significantly expand from an existing lake (but non-stationary), and then drain during summer. Our field surveys show that the short-lived lakes form when an ice tunnel through a debris landform gets blocked. The blocking is caused either by the freezing of stored water inside the tunnel during winter or by the collapse of ice and debris around the ice tunnel. The draining then occurs through an opened ice tunnel during summer. The growth-drain cycle can repeat when the ice-tunnel closure behaves like that of typical supraglacial lakes on debris-covered glaciers. We argue here that the geomorphological characteristics under which such short-lived glacial lakes appear are (i) a debris landform containing ice (ice-cored moraine complex), (ii) a depression with water supply on a debris landform as a potential lake basin, and (iii) no visible surface outflow channel from the depression, indicating the existence of an ice tunnel. Applying these characteristics, we examine 60 depressions (> 0.01 km2) in the study region and identify here 53 of them that may become short-lived glacial lakes, with 34 of these having a potential drainage exceeding 10 m3 s-1 at peak discharge.

Risk perception, risk evaluation and human values: cognitive bases of acceptability of a radioactive waste repository

Energy Technology Data Exchange (ETDEWEB)

Earle, T.C.; Lindell, M.K.; Rankin, W.L.

1981-07-01

Public acceptance of radioactive waste management alternatives depends in part on public perception of the associated risks. Three aspects of those perceived risks were explored in this study: (1) synthetic measures of risk perception based on judgments of probability and consequences; (2) acceptability of hypothetical radioactive waste policies, and (3) effects of human values on risk perception. Both the work on synthetic measures of risk perception and on the acceptability of hypothetical policies included investigations of three categories of risk: (1) Short-term public risk (affecting persons living when the wastes are created), (2) Long-term public risk (affecting persons living after the time the wastes were created), and (3) Occupational risk (affecting persons working with the radioactive wastes). The human values work related to public risk perception in general, across categories of persons affected. Respondents were selected according to a purposive sampling strategy.

α and long-lived βγ waste source term. A first generation model for a deep cemented waste repository

International Nuclear Information System (INIS)

Lovera, P.; Mangin, J.P.; Jorda, M.; Lewi, J.

1987-01-01

According to the normal scenario of radioactivity release to the biosphere, only long-lived nuclides are able to migrate significantly to the surface. A first generation model, concerning a cemented waste of hulls and ends deeply disposed of in a granitic medium is in progress at CEA. Two nuclides have been selected: 237-Neptunium (as a reference of α emitters) and 135-Cesium (as a reference of long-lived β emitters). Attributing the long term activity to these both nuclides leads to a model which is conservative beyond ca. 150000 years. Principal difficulties arise from physico-chemical behaviour of Neptunium in aqueous phase, and from non-linear Cesium adsorption on various media. Condiment code (versions 2 and 3), which is developed parallely to the present model is conceived to take account for these phenomena

TRIUMF - The Swedish data base system for radioactive waste in SFR

International Nuclear Information System (INIS)

Skogsberg, Marie; Andersson, Per-Anders

2006-01-01

All short lived LLW/ILW from the operation and maintenance of all Swedish Nuclear Power Plants are disposed in SFR, the Swedish final repository for radioactive operational waste. It is important to save all the information about radioactive waste that is needed now and in the future. To be secure that, we have developed a database system in Sweden called Triumf, consisting information about all the waste packages that are disposed in SFR. The waste producers register data concerning individual waste package during production. Before transport to SFR a data file with all information about the individual waste packages is transferred to Triumf. When transferred, the data are checked against accepted limitations before the waste can be loaded on the ship for transport to SFR. After disposal at SFR the deposition location in the repository is added to the database for each waste package. (author)

Short-lived Isotopes from a Close-by AGB Star Triggering the Protosolar Nebula

Science.gov (United States)

Gallino, R.; Busso, M.; Wasserburg, G. J.; Straniero, O.

The presence of short-lived isotopes in the early solar system, in particular 26Al, 41Ca, 60Fe, and 107Pd, point to a close-by and fresh nucleosynthesis source, possibly triggering the collapse of the protosolar nebula. We present the results of nucleosynthesis calculations based on an AGB polluting hypothesis. A general concordance of the predicted yields of the above radioactivities relative to 26Al can be obtained in the case of an intermediate mass AGB star with hot bottom burning in the envelope (thus producing 26Al), and mixing through a series of third dredge-up episodes a fraction of the C-rich and s-processed material from the He intershell with the extended envelope. Polution of the protosolar nebula with freshly synthesized material may derive from the efficient winds of the AGB star. In AGB stars, the s-process nucleosynthesis occurs both during the maximum phase of every thermal runaway, driven by the partial activation of the 22Ne(alpha,n)25Mg reaction, and in the interpulse phase, where the 13C nuclei are fully consumed in radiative conditions by the activation of the 13C(alpha,n)16O reaction. We have used different prescriptions for the amount of the 13C nuclei present in the intershell. A minimum amount of 13C is naturally expected in the ashes of H-shell burning. Possible formation of an extra "13C-pocket" derives from the injection of a small amount of protons from the envelope into the 12C-rich intershell during any third dredge-up episode, when the H-shell is inactivated. Prediction for other short-lived, 36Cl, 135Cs, and 205Pb, are given. General consequences for the pollution of the protosolar nebula with newly synthesized stable isotopes from the AGB winds are outlined. The origin of other detected short-lived nuclei, in particular 53Mn, 129I, and 182Hf, which cannot come from an AGB source, is analysed. The alternative trigger hypothesis by a close-by Supernova is discussed.

Are crab-type supernova remnants (plerions) short-lived

International Nuclear Information System (INIS)

Weiler, K.W.; Panagia, N.

1978-01-01

Arguments are given for a possible picture of the origin, maintenance, and lifetimes of the so-called Crab-like supernova remnants. It is suggested that these objects imply the existence of at least two distinct types of supernova events. A possible connection of the remnant types with the optically defined supernovae of Type I and Type II is discussed. Accepting that a pulsar is formed in at least some supernova events, the proposal is made that a rapidly rotating, rapidly slowing pulsar is necessary to create and maintain a Crab-like supernova remnant. Finally, arguments are presented that such a supernova remnant will be relatively short lived with respect to the more common shell-type of supernova remnant, perhaps surviving only 10000-20000 yr before fading into the Galactic background. The name of plerion is proposed for these filled-center supernova remnants and observational possiblities for confirming their nature are suggested. (orig.) [de

Aube storage center for very-low-level radioactive wastes. Annual report 2010

International Nuclear Information System (INIS)

2011-09-01

The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2010 activity report of the center for very-low-level radioactive wastes. It presents a review of the activities of the center: presentation of the installations, safety, security and radiation protection, environmental monitoring and effluents, public information and communication

The Environmental and ethical basis of the geological disposal of long-lived radioactive waste. A collective opinion by the Radioactive Waste Management Committee (RWMC) of the OECD Nuclear Energy Agency

International Nuclear Information System (INIS)

1995-01-01

The report presents a consensus position of the national authorities in their search for appropriate solutions in the safe disposal of radioactive wastes in the form of a Collective Opinion of the Radioactive waste Management Committee (RWMC) of the OECD Nuclear Energy Agency. The Collective Opinion addresses the strategy for the final disposal of long-lived radioactive wastes seen from an environmental and ethical perspective, including considerations of equity and fairness within and between generations. (7 refs.)

Andra - Everything you ever wanted to know about radioactive waste management

International Nuclear Information System (INIS)

2014-08-01

Andra is a publicly owned industrial and commercial body, set up by the French act of 30 December 1991. Its role was expanded by the 2006 Planning Act on the long-term management of radioactive materials and waste. Andra is independent of the producers of radioactive waste, and is under the supervision of the ministries responsible for energy, research and the environment. Andra is responsible for identifying, implementing and guaranteeing safe management solutions for all French radioactive waste, in order to protect present and future generations from the risks inherent in such substances. Andra's role involves a number of activities: running the two existing above-ground disposal facilities in the Aube, the first one for low- and intermediate- level, short-lived waste (LILW-SL) and the other one for very-low-level waste (VLLW), the Cires facility; monitoring the Manche disposal facility, the CSM, France's first above-ground disposal facility for low- and intermediate-level waste, which is now closed; studying and designing disposal facilities for waste as yet without a special facility, that is: Low-level, long-lived waste (LLW-LL), High-level and intermediate-level long-lived waste (HLW, ILW-LL) - the Cigeo project; taking in radioactive waste from hospitals, research laboratories, universities and radioactive objects owned by private individuals (old luminous clocks and watches, health care equipment containing radium, natural laboratory salts, certain minerals, etc.); at the request of the owner or the authorities, cleaning up sites polluted by radioactivity; surveying and listing French radioactive waste and issuing the National Inventory of Radioactive Materials and Waste every three years; informing all members of the public by means of documents, exhibitions, visits to its facilities, etc.; preserving the memory of its centers; promoting and disseminating its know-how outside France. Contents: 1 - Andra, its role, its activities, its funding; 2

Development of transmutation technologies of radioactive waste by actinoid hydride

International Nuclear Information System (INIS)

Konashi, Kenji; Matsui, Hideki; Yamawaki, Michio

2001-01-01

Two waste treatment methods, geological disposal and transmutation, have been studied. The transmutation method changes long-lived radioactive nuclides to short-lived one or stabilizes them by nuclear transformation. The transmutation by actinoid hydride is exactly alike that transformation method from actinoid disposal waste to Pu fuel. For this object, OMEGA project is processing now. The transmutation is difficult by two causes such as large amount of long-lived radioactive nuclides and not enough development of control technologies of nuclear reaction except atomic reactor. The transmutation using actinoid hydride has merits that the amount of actinoid charged in the target increases and the effect of thermal neutrons on fuel decreases depending on homogeneous transmutation velocity in the target. Development of stable actinoid hydride under the conditions of reactor temperature and irradiation environment is important. The experimental results of U-ZrH 1.6 are shown in this paper. The irradiation experiment using Th hydride has been proceeding. (S.Y.)

Actinide partitioning from high level liquid waste using the Diamex process

International Nuclear Information System (INIS)

Madic, C.; Blanc, P.; Condamines, N.; Baron, P.; Berthon, L.; Nicol, C.; Pozo, C.; Lecomte, M.; Philippe, M.; Masson, M.; Hequet, C.

1994-01-01

The removal of long-lived radionuclides, which belong to the so-called minor actinides elements, neptunium, americium and curium, from the high level nuclear wastes separated during the reprocessing of the irradiated nuclear fuels in order to transmute them into short-lived nuclides, can substantially decrease the potential hazards associated with the management of these nuclear wastes. In order to separate minor actinides from high-level liquid wastes (HLLW), a liquid-liquid extraction process was considered, based on the use of diamide molecules, which display the property of being totally burnable, thus they do not generate secondary solid wastes. The main extracting properties of dimethyldibutyltetradecylmalonamide (DMDBTDMA), the diamide selected for the development of the DIAMEX process, are briefly described in this paper. Hot tests of the DIAMEX process (using DMDBTDMA) related to the treatment of an mixed oxide fuels (MOX) type HLLW, were successfully performed. The minor actinide decontamination factors of the HLLW obtained were encouraging. The main results of these tests are presented and discussed in this paper. (authors). 9 refs., 2 figs., 7 tabs

Developing role of short-lived radionuclides in nuclear medical practice. DOE symposium series; 56

International Nuclear Information System (INIS)

Paras, P.; Thiessen, J.W.

1985-01-01

The purpose was to define the developing role and state-of-the-art development of short-lived radionuclides (SLR's) in current nuclear medical practice. Special emphasis was placed on radionuclides with general-purpose labeling capabilities. The need for high-purity labeling-grade iodine-123 was emphasized in the program. Papers have been separately abstracted for the data base

Magnetic moment of short lived {beta}-emitter {sup 24m}Al

Energy Technology Data Exchange (ETDEWEB)

Nishimura, D., E-mail: daiki@vg.phys.sci.osaka-u.ac.jp; Komurasaki, J.; Matsuta, K.; Mihara, M.; Matsumiya, R. [Osaka University, Department of Physics (Japan); Momota, S. [Kochi University of Technology (Japan); Ohtsubo, T. [Niigata University, Department of Physics (Japan); Izumikawa, T. [Niigata University, RI Center (Japan); Hirano, H. [Niigata University, Department of Physics (Japan); Kitagawa, A.; Kanazawa, M.; Torikoshi, M.; Sato, S. [National Institute of Radiological Sciences (Japan); Fukuda, M.; Ishikawa, D. [Osaka University, Department of Physics (Japan); Minamisono, T. [Fukui University of Technology (Japan); Watanabe, R.; Kubo, T. [Niigata University, Department of Physics (Japan); Nojiri, Y. [Kochi University of Technology (Japan); Alonso, J. R. [Lawrence Berkeley Laboratory (United States)

2007-11-15

The magnetic moment of short lived {beta}-emitter {sup 24m}Al (426 keV, I{sup {pi}} = 1{sup +}, T{sub 1/2} = 131 ms) has been measured by means of {beta}-NMR technique, for the first time. From the {beta}-NMR spectrum, the magnetic moment was determined as |{mu}({sup 24m}Al)|=(2.99{+-}0.09){mu}{sub N}. Combined with the known magnetic moment of the mirror partner {sup 24m}Na, the expectation value of < S{sub z} > is obtained to be (0.08 {+-} 0.12). These values are reproduced well by the shell model calculation.

Extrinsic and intrinsic factors that shape the life history of the short living scallop Argopecten ventricosus

OpenAIRE

Guerra, Citlali

2011-01-01

The scallop Argopecten ventricosus is characterized by its high swimming activity, fast growth, high reproductive effort and the early age to get first sexual maturity. These traits may be the result of the adaptation to a specific environment that favors an active lifestyle and a short lifespan (2 years). This opens the question of how environmental factors modulate the way a short living marine ectotherm budget energy investments among life history traits and how this modulation impacts the...

IN-SITU RADIONUCLIDE TRANSPORT NEAR THE NOPAL I URANIUM DEPOSIT AT PENA BLANCA, MEXICO: CONSTRAINTS FROM SHORT-LIVED DECAY-SERIES RADIONUCLIDES

International Nuclear Information System (INIS)

Luo, S.; Ku, T.L.; Todd, V.; Murrell, M.; Pineda, J. Alfredo Rodriguez; Dinsmoor, J.; Mitchell, A.

2005-01-01

For nuclear waste management, an important mechanism by which radioactive waste components are isolated from returning to the human environment, the biosphere, is by the geological barrier in which the effectiveness of the barrier is characterized by in-situ retardation factor, i.e., the transport rate of a radionuclide relative to that of groundwater. As part of natural analog studies of the Yucca Mountain Project of the U. S. Department of Energy, we propose such characterization by using naturally-occurring decay-series radioisotopes as an analog. We collected large-volume (>1000 liters) groundwater samples from three wells (PB, Pozos, and PB4, respectively) near the Nopal I Uranium Ore site at Pena Blanca, Mexico, by using an in-situ Mn-cartridge filtration technique for analysis of short-lived decay-series radionuclides. Results show that the activities of short-lived radioisotopes ( 228 Ra, 224 Ra and 223 Ra) and activity ratios of 224 Ra/ 228 Ra and 224 Ra/ 223 Ra are higher at PB and Pozos than at PB4. In contrast, the 210 Po activity is much lower at PB and Pozos than at PB4. The high Ra activities and activities ratios at PB and Pozos are attributable to the high alpha-recoil input from the aquifer rocks, while the high 210 Po activity at PB4 is due to the enhanced colloidal transport. Based on a uranium-series transport model, we estimate that the in-situ retardation factor of Ra is (0.43 ± 0.02) x 10 3 at PB, (1.68 ± 0.08) x 10 3 at Pozos, and (1.19 ± 0.08) x 10 3 at PB4 and that the mean fracture width in the aquifer rocks is about 0.23 (micro)m at PB, 0.37 (micro)m at Posos, and 4.0 (micro)m at PB4, respectively. The large fracture width at PB4 as derived from the model provides an additional evidence to the inference from the Po measurements that particle-reactive radionuclides are transported mainly as colloidal forms through the large fractures in rocks. Our model also suggests that in addition to alpha recoil, decay of 226 Ra from the adsorbed

Study of spallation neutrons for the transmutation of long-lived nuclear waste

International Nuclear Information System (INIS)

Brochard, F.; Boyard, J.L.; Duchazeaubeneix, J.C.; Durand, J.M.; Faivre, J.C.; Leray, S.; Milleret, G.; Plouin, F.; Whittal, D.M.; Beau, M.; Crespin, S.; Frehaut, J.; Lochard, J.P.; Martinez, E.; Patin, Y.; Petitbon, E.; Sigaud, J.; Legrain, R.; Lepretre, A.; Terrien, Y.; Bacha, F.; Maillard, J.; Silva, J.

1994-01-01

With the renewed interest in accelerator-driven systems to transmute long-lived nuclear waste or to produce energy, new requirements for intermediate-energy nuclear data are now emerging. In all these systems, neutrons are produced by spallation reactions induced by around 1 GeV protons on a heavy target. These neutrons then drive a sub-critical blanket in which wastes are burned or energy is produced. A good knowledge of the spallation process (energy and angular distribution of the neutrons) is necessary to design and optimize the target-blanket system: for instance, to determine the best choices of beam energy, of composition and geometry of the target, in order to have the maximum neutron yield at the lowest cost, or to minimize the back-scattering of neutrons to the accelerator. A programme aimed at measuring the double differential cross-sections for the production of spallation neutrons induced by protons and deuterons GeV beams on different targets, is beginning at SATURNE. (authors). 3 refs., 3 figs

Investigation of short-living fission products from the spontaneous fission of Cf-252

International Nuclear Information System (INIS)

Klonk, H.

1976-01-01

In this paper, a method of separating and measuring fission products of Cf-252 is presented. The measurement was achieved by means of γ-spectrometry and thus provides a quantitative analysis with a good separation of the fission products with respect to both atomic number Z and mass number A. The separation of the fission products from the fission source was achieved by means of solid traps. An automatic changing apparatus made it possible to keep irradiation and measuring times short, so even very short-lived fission products could be registered. The quantitative evaluation of primary fission products was made possible by correction according to Bateman equations. With that, the yields of single nuclides and the dispersion of charge can be determined. (orig./WL) [de

Decree of the 23 February 2017 in application of the decree nr 2017-231 of the 23 February 2017 in application of the article L. 542-1-2 of the Code of the Environment, and establishing prescriptions of the National Plan of Management of Radioactive Materials and Wastes

International Nuclear Information System (INIS)

Royal, Segolene

2017-01-01

This decree defines legal arrangements about the implementation of the French national plan of management of radioactive materials and wastes (PNGMDR). It contains some general arrangements, issues related to radioactive materials (depleted uranium, uranium from reprocessing, plutonium and spent fuels, thorium-containing materials), and issues related to the long term management of radioactive wastes. These issues notably concern historical storages and the different types of radioactive wastes: very low level radioactive wastes, short lived low and intermediate level wastes, long-lived intermediate level wastes, long-lived high and intermediate level wastes, radioactive wastes requiring specific works such as mercury-containing wastes, organic liquids and oils, tritiated wastes, and so on, and uranium tailings

Radiation and Thermal Ageing of Nuclear Waste Glass

Energy Technology Data Exchange (ETDEWEB)

Weber, William J [ORNL

2014-01-01

The radioactive decay of fission products and actinides incorporated into nuclear waste glass leads to self-heating and self-radiation effects that may affect the stability, structure and performance of the glass in a closed system. Short-lived fission products cause significant self-heating for the first 600 years. Alpha decay of the actinides leads to self-radiation damage that can be significant after a few hundred years, and over the long time periods of geologic disposal, the accumulation of helium and radiation damage from alpha decay may lead to swelling, microstructural evolution and changes in mechanical properties. Four decades of research on the behavior of nuclear waste glass are reviewed.

A Short History of Hanford Waste Generation, Storage, and Release

International Nuclear Information System (INIS)

Gephart, Roy E.

2003-01-01

Nine nuclear reactors and four reprocessing plants at Hanford produced nearly two-thirds of the plutonium used in the United States for government purposes . These site operations also created large volumes of radioactive and chemical waste. Some contaminants were released into the environment, exposing people who lived downwind and downstream. Other contaminants were stored. The last reactor was shut down in 1987, and the last reprocessing plant closed in 1990. Most of the human-made radioactivity and about half of the chemicals remaining onsite are kept in underground tanks and surface facilities. The rest exists in the soil, groundwater, and burial grounds. Hanford contains about 40% of all the radioactivity that exists across the nuclear weapons complex. Today, environmental restoration activities are under way.

A Proposal for Assessing Study Quality: Biomonitoring, Environmental Epidemiology, and Short-Lived Chemicals (BEES-C) Instrument

Science.gov (United States)

The quality of exposure assessment is a major determinant of the overall quality of any environmental epidemiology study. The use of biomonitoring as a tool for assessing exposure to ubiquitous chemicals with short physiologic half-lives began relatively recently. These chemicals...

The waste management program VUB-AZ: An integrated solution for nuclear biomedical waste management

International Nuclear Information System (INIS)

Covens, P.; Sonck, M.; Eggermont, G.; Meert, D.

2001-01-01

Due to escalating costs and the lack of acceptance of near-surface disposal facilities, the University of Brussels (VUB) and its Academic hospital (AZ) have developed an on-site waste storage program in collaboration with Canberra Europe. This programme is based on selective collection, measurement before decay, storage for decay of short-lived radionuclides, measurement after decay and eventual clearance as non-nuclear waste. It has proved its effectiveness over the past 5 years. Effective characterisation for on-site storage for decay of short-lived radionuclides makes selective collection of waste streams mandatory and requires motivated and trained laboratory staff. Dynamic optimisation of this selective collection increases the efficiency of the storage for decay programme. The accurate qualitative and quantitative measurement of nuclear biomedical waste before decay has several advantages such as verification of correct selective collection, optimisation of the decay period and possibility of clearance below the minimal detectable activity. In the research phase of the program several measurement techniques were investigated. The following measurement concept was selected. Closed PE drums containing low density solid waste materials contaminated with small amounts of β/γ-or pure β-emitting radionuclides are assessed for specific activity by the Canberra measurement unit for nuclear biomedical waste, based on a HPGe-detector. Liquid waste containing (β/γ-emitters are characterised by the same technique while for pure β-emitting liquid waste a Packard liquid scintillation counter is used. Measurement results are obtained by using the gamma-spectroscopy software Genie-2000. A user-friendly interface, based on Procount-2000 and optimised by Canberra for the characterisation of nuclear biomedical waste, has increased the sample throughput of the measurement concept. The MDA (minimal detectable activity) of different radionuclides obtained by the measurement

Large drainages from short-lived glacial lakes in the Teskey Range, Tien Shan Mountains, Central Asia

Directory of Open Access Journals (Sweden)

C. Narama

2018-04-01

Full Text Available Four large drainages from glacial lakes occurred during 2006–2014 in the western Teskey Range, Kyrgyzstan. These floods caused extensive damage, killing people and livestock as well as destroying property and crops. Using satellite data analysis and field surveys of this area, we find that the water volume that drained at Kashkasuu glacial lake in 2006 was 194 000  m3, at western Zyndan lake in 2008 was 437 000 m3, at Jeruy lake in 2013 was 182 000 m3, and at Karateke lake in 2014 was 123 000 m3. Due to their subsurface outlet, we refer to these short-lived glacial lakes as the tunnel-type, a type that drastically grows and drains over a few months. From spring to early summer, these lakes either appear, or in some cases, significantly expand from an existing lake (but non-stationary, and then drain during summer. Our field surveys show that the short-lived lakes form when an ice tunnel through a debris landform gets blocked. The blocking is caused either by the freezing of stored water inside the tunnel during winter or by the collapse of ice and debris around the ice tunnel. The draining then occurs through an opened ice tunnel during summer. The growth–drain cycle can repeat when the ice-tunnel closure behaves like that of typical supraglacial lakes on debris-covered glaciers. We argue here that the geomorphological characteristics under which such short-lived glacial lakes appear are (i a debris landform containing ice (ice-cored moraine complex, (ii a depression with water supply on a debris landform as a potential lake basin, and (iii no visible surface outflow channel from the depression, indicating the existence of an ice tunnel. Applying these characteristics, we examine 60 depressions (> 0.01 km2 in the study region and identify here 53 of them that may become short-lived glacial lakes, with 34 of these having a potential drainage exceeding 10 m3 s−1 at peak discharge.

''Sleeping reactor'' irradiations: Shutdown reactor determination of short-lived activation products

International Nuclear Information System (INIS)

Jerde, E.A.; Glasgow, D.C.

1998-01-01

At the High-Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory, the principal irradiation system has a thermal neutron flux (φ) of ∼ 4 x 10 14 n/cm 2 · s, permitting the detection of elements via irradiation of 60 s or less. Irradiations of 6 or 7 s are acceptable for detection of elements with half-lives of as little as 30 min. However, important elements such as Al, Mg, Ti, and V have half-lives of only a few minutes. At HFIR, these can be determined with irradiation times of ∼ 6 s, but the requirement of immediate counting leads to increased exposure to the high activity produced by irradiation in the high flux. In addition, pneumatic system timing uncertainties (about ± 0.5 s) make irradiations of 9 Be(γ,n) 8 Be, the gamma rays principally originating in the spent fuel. Upon reactor SCRAM, the flux drops to ∼ 1 x 10 10 n/cm 2 · s within 1 h. By the time the fuel elements are removed, the flux has dropped to ∼ 6 x 10 8 . Such fluxes are ideal for the determination of short-lived elements such as Al, Ti, Mg, and V. An important feature of the sleeping reactor is a flux that is not constant

Behaviour of short-lived fission products within operating UO2 fuel elements

International Nuclear Information System (INIS)

Hastings, I.J.; Hunt, C.E.L.; Lipsett, J.J.

1983-01-01

We have carried out experiments using a ''sweep gas'' technique to determine the behaviour of short-lived fission products within operating, intact UO 2 fuel elements. The Zircaloy-4-clad elements were 500 mm long and contained fuel of density 10.65-10.71 Mg/m 3 . A He-2% H 2 carrier gas swept gaseous or volatile fission products out of the operating fuel element past a gamma spectrometer for measurement. In tests at linear powers of 45 and 60 kW/m to maximum burnups of 70 MW.h/kg U, the species measured directly at the spectrometer were generally the short-lived xenons and kryptons. We did not observe iodine or bromine during normal operation. However, we have deduced the behaviour of I-133 and I-135 from the decay of Xe-133 and Xe-135 during reactor shutdowns. Plots of R/B (released/born) against lambda (decay constant) or effective lambda for all isotopes observed at 45 and 60 kW/m show that a line of slope -0.5, corresponding with diffusion kinetics, is a good fit to the measured xenon and krypton data. Our inferred release of iodine fits the same line. From this we can extrapolate to an R/B for I-131 of about 5x10 -3 . The ANS 5.4 release correlation gives calculated results in good agreement with our measurements. (author)

Short-lived climate pollutant mitigation and the Sustainable Development Goals

Science.gov (United States)

Haines, Andy; Amann, Markus; Borgford-Parnell, Nathan; Leonard, Sunday; Kuylenstierna, Johan; Shindell, Drew

2017-12-01

The post-2015 development agenda is dominated by a set of Sustainable Development Goals (SDGs) that arose from the 2012 Rio+20 United Nations Conference on Sustainable Development. The 17 goals and 169 targets address diverse and intersecting aspects of human and environmental needs and challenges. Achieving the SDGs by 2030 requires implementing coordinated and concerted strategies and actions that minimize potential trade-offs and conflicts and maximize synergies to contribute to multiple SDGs. Measures to mitigate emissions of short-lived climate pollutants are an example of actions that contribute to multiple outcomes relevant to development. This Perspective highlights the interlinkages between these pollutants and the SDGs, and shows that implementing emissions reduction measures can contribute to achieving many of the SDGs.

DEMOGRAPHY OF ALPINE SHORT-LIVED PLANTS, LONGEVITY AND ONTOGENY STAGE DURATIONS

Directory of Open Access Journals (Sweden)

E. S. Kazantseva

2016-01-01

Full Text Available The aim - to evaluate lifespan (full cycle and ontogeny stage durations of nine alpine short-lived North- West Caucasus plants.Methods. For calculation we used a new method which was developed and suggested earlier by us. This method is based on a discrete ontogeny description and on the probability theory and random processes. The data on the monitoring of the marked individuals were collected during six years.Results. We found out that the lifespan of Anthyllis vulneraria is 2.6±0.3 years (hereinafter “±” is Standard error, Draba hispida – 4.5±0.3, Murbeckiella huetii – 4.6±1.1, Carum meifolium – 7.8±1.4, Eritrichium caucasicum – 9.1±1.4, Trifolium badium – 10.3±2.6, Sedum tenellum – 11±2.05, Androsace albana – 12.1±2.5, Minuartia recurva – 22.9±4.5. Also we demonstrated the matrix population models for studied plants, which show the probability of transition of individuals from one ontogeny stage to another in time interval (in our experiment – 1 year.Conclusion. Mortality of seedlings and juvenile plants, except Murbeckiella huetii, is around and more than 50%. Two years is the minimal amount of time that is necessary for full cycle of short-lived alpine plants, as it was shown for Anthyllis vulneraria, Murbeckiella huetii и Trifolium badium. A 3-12 years lifespan was calculated for other studied species. Persistence of Eritrichium caucasicum and Androsace albana populations provided by resistance of adult vegetative plants.

Synthesis of radiopharmaceuticals containing short-lived radionuclides. Comprehensive report, March 1, 1980-February 26, 1986

International Nuclear Information System (INIS)

Kabalka, G.W.

1985-09-01

New methods for the rapid introduction of short-lived radionuclides into agents for use in diagnostic nuclear medicine are reported. Among the new syntheses reported are those for 123 I-labeled fatty acids and steroids, for 11 C-labeled alcohols, for 13 N-labeled amines, and for 15 O-labeled alcohols. 33 refs

Synthesis of radiopharmaceuticals containing short-lived radionuclides. Progress report, March 1, 1985-February 26, 1986

International Nuclear Information System (INIS)

Kabalka, G.W.

1985-09-01

Methods for the rapid introduction of short-lived radionuclides into agents for use in diagnostic nuclear medicine are reported. Methods to synthesize radioiodinated fatty acids, lipids, and amphetamine derivatives are described. New routes for the introduction of bromine-77, chlorine-34m, and carbon-11 into agents of interest are elaborated. 46 refs

Changing-Look AGNs or Short-Lived Radio Sources?

Energy Technology Data Exchange (ETDEWEB)

Wołowska, Aleksandra [Toruń Centre for Astronomy, Faculty of Physics, Astronomy and Informatics, Nicolaus Copernicus University, Toruń (Poland); Kunert-Bajraszewska, Magdalena; Mooley, Kunal [Centre for Astrophysical Surveys, University of Oxford, Oxford (United Kingdom); Hallinan, Gregg, E-mail: ola@astro.umk.pl [Cahill Center for Astronomy, California Institute of Technology, Pasadena, CA (United States)

2017-11-17

The evolution of extragalactic radio sources has been a fundamental problem in the study of active galactic nuclei for many years. A standard evolutionary model has been created based on observations of a wide range of radio sources. In the general scenario of the evolution, the younger and smaller Gigahertz-Peaked Spectrum (GPS) and Compact Steep Spectrum (CSS) sources become large-scale FRI and FRII objects. However, a growing number of observations of low power radio sources suggests that the model cannot explain all their properties and there are still some aspects of the evolutionary path that remain unclear. There are indications, that some sources may be short-lived objects on timescales of 10{sup 4}–10{sup 5} years. Those objects represent a new population of active galaxies. Here, we present the discovery of several radio transient sources on timescales of 5–20 yrs, largely associated with renewed AGN (Active Galactic Nucleus) activity. These changing-look AGNs possibly represent behavior typical for many active galaxies.

Fast neutron activation analysis using short-lived radionuclides

International Nuclear Information System (INIS)

Salma, I.; Zemplen-Papp, E.

1993-01-01

Fast neutron activation analysis experiments were performed to investigate the analytical possibilities and prospective utilization of short-lived activation products. A rapid pneumatic transfer system for use with neutron generators has been installed and applied for detecting radionuclides with a half-life from ∼300 ms to 20 s. The transport time for samples of total mass of 1-4 g is between 130 and 160 ms for pressurized air of 0.1-0.4 MPa. The reproducibility of transport times is less than 2%. The employed method of correcting time-dependent counting losses is based on the virtual pulse generator principle. The measuring equipment consists of CAMAC modules and a special gating circuit. Typical time distributions of counting losses are presented. The same 14 elements were studied by the conventional activation method (single irradiation and single counting) by both a typical pneumatic transport system (run time 3 s) and the fast pneumatic transport facility. Furthermore, the influence of the cyclic activation technique on the elemental sensitivities was investigated. (author) 15 refs.; 5 figs.; 3 tabs

Non-destructive investigation of technical plants and processes and natural processes by short-lived radionuclides (radiotracer)

International Nuclear Information System (INIS)

Jentsch, Thorsten; Zeuner, Albert

2009-01-01

Short lived open radionuclides are very suitable to investigate transport and mixing processes. They do not pollute the product. After decay of the radionuclide, the product can be used without any restrictions. Examples are showed for technical processes investigation by aid of radiotracer. (orig.)

Germany: Management of decommissioning waste in Germany

International Nuclear Information System (INIS)

Borrmann, F.; Brennecke, P.; Koch, W.; Kugel, K.; Steyer, S.

2007-01-01

Over the past two decades, Germany has gained a substantial amount of experience in the decommissioning of nuclear facilities of different types and sizes. Many research reactors and all prototype nuclear power plants, as well as a few larger nuclear power plants and fuel cycle facilities, are currently at varying stages of decommissioning. Several facilities have been fully dismantled and the sites have been cleared for reuse. The decommissioning projects comprise 18 power and prototype reactors, 33 research reactors and 11 fuel cycle facilities which are being or have been decommissioned. In the future, further nuclear power plants will be shut down and decommissioned in accordance with Germany?s energy policy to phase out the use of nuclear power for commercial electricity generation as given in the April 2002 amendment of the Atomic Energy Act. Radioactive waste, from operations as well as from decommissioning activities, is to be conditioned in such a way as to comply with the waste acceptance requirements of a repository. In Germany, all types of radioactive waste (i.e., short-lived and long-lived) are to be disposed of in deep geological formations. A distinction is being made for heat generating waste (i.e., high level waste) and waste with negligible heat generation (i.e., low level and intermediate level waste). Radioactive decommissioning waste is waste with negligible heat generation. Waste acceptance requirements of a repository are of particular importance for the conditioning of radioactive waste, including decommissioning waste. The waste acceptance requirements, as they resulted from the Konrad licensing procedure, are being applied by the waste generators for the conditioning of decommissioning waste. Compliance with these requirements must be demonstrated through the waste package quality control, even if the waste will be disposed of in the future. In 2002 the Konrad repository was licensed for the disposal of all types of waste with negligible

Evaluating the climate and air quality impacts of short-lived pollutants

Science.gov (United States)

Stohl, A.; Aamaas, B.; Amann, M.; Baker, L. H.; Bellouin, N.; Berntsen, T. K.; Boucher, O.; Cherian, R.; Collins, W.; Daskalakis, N.; Dusinska, M.; Eckhardt, S.; Fuglestvedt, J. S.; Harju, M.; Heyes, C.; Hodnebrog, Ø.; Hao, J.; Im, U.; Kanakidou, M.; Klimont, Z.; Kupiainen, K.; Law, K. S.; Lund, M. T.; Maas, R.; MacIntosh, C. R.; Myhre, G.; Myriokefalitakis, S.; Olivié, D.; Quaas, J.; Quennehen, B.; Raut, J.-C.; Rumbold, S. T.; Samset, B. H.; Schulz, M.; Seland, Ø.; Shine, K. P.; Skeie, R. B.; Wang, S.; Yttri, K. E.; Zhu, T.

2015-09-01

This paper presents a summary of the work done within the European Union's Seventh Framework Programme project ECLIPSE (Evaluating the Climate and Air Quality Impacts of Short-Lived Pollutants). ECLIPSE had a unique systematic concept for designing a realistic and effective mitigation scenario for short-lived climate pollutants (SLCPs; methane, aerosols and ozone, and their precursor species) and quantifying its climate and air quality impacts, and this paper presents the results in the context of this overarching strategy. The first step in ECLIPSE was to create a new emission inventory based on current legislation (CLE) for the recent past and until 2050. Substantial progress compared to previous work was made by including previously unaccounted types of sources such as flaring of gas associated with oil production, and wick lamps. These emission data were used for present-day reference simulations with four advanced Earth system models (ESMs) and six chemistry transport models (CTMs). The model simulations were compared with a variety of ground-based and satellite observational data sets from Asia, Europe and the Arctic. It was found that the models still underestimate the measured seasonality of aerosols in the Arctic but to a lesser extent than in previous studies. Problems likely related to the emissions were identified for northern Russia and India, in particular. To estimate the climate impacts of SLCPs, ECLIPSE followed two paths of research: the first path calculated radiative forcing (RF) values for a large matrix of SLCP species emissions, for different seasons and regions independently. Based on these RF calculations, the Global Temperature change Potential metric for a time horizon of 20 years (GTP20) was calculated for each SLCP emission type. This climate metric was then used in an integrated assessment model to identify all emission mitigation measures with a beneficial air quality and short-term (20-year) climate impact. These measures together

Low-risk alternative waste forms for problematic high-level and long-lived nuclear wastes

International Nuclear Information System (INIS)

Stewart, M.W.A.; Begg, B.D.; Moricca, S.; Day, R.A.

2006-01-01

Full text: The highest cost component the nuclear waste clean up challenge centres on high-level waste (HLW) and consequently the greatest opportunity for cost and schedule savings lies with optimising the approach to HLW cleanup. The waste form is the key component of the immobilisation process. To achieve maximum cost savings and optimum performance the selection of the waste form should be driven by the characteristics of the specific nuclear waste to be immobilised, rather than adopting a single baseline approach. This is particularly true for problematic nuclear wastes that are often not amenable to a single baseline approach. The use of tailored, high-performance, alternative waste forms that include ceramics and glass-ceramics, coupled with mature process technologies offer significant performance improvements and efficiency savings for a nuclear waste cleanup program. It is the waste form that determines how well the waste is locked up (chemical durability), and the number of repository disposal canisters required (waste loading efficiency). The use of alternative waste forms for problematic wastes also lowers the overall risk by providing high performance HLW treatment alternatives. The benefits tailored alternative waste forms bring to the HLW cleanup program will be briefly reviewed with reference to work carried out on the following: The HLW calcines at the Idaho National Laboratory; SYNROC ANSTO has developed a process utilising a glass-ceramic combined with mature hot-isostatic pressing (HIP) technology and has demonstrated this at a waste loading of 80 % and at a 30 kg HIP scale. The use of this technology has recently been estimated to result in a 70 % reduction in waste canisters, compared to the baseline borosilicate glass technology; Actinide-rich waste streams, particularly the work being done by SYNROC ANSTO with Nexia Solutions on the Plutonium-residues wastes at Sellafield in the UK, which if implemented is forecast to result in substantial

Search for short-lived particles produced on nuclei with a heavy liquid mini bubble chamber

CERN Multimedia

2002-01-01

The aim of this experiment is to search for short-lived particles produced in hadronic interactions on nuclei with our high resolution heavy liquid mini bubble chamber BIBC, aiming to establish the cross-section for associated production in hadron-nucleus collisions, its $A$-dependence and an approximate value of the lifetime. The chamber will be operated at a bubble density of 290 bubbles/cm and with an apparent bubble size of 30 $\\mu$m in real space. In test runs at CERN we measured detection efficiencies which, together with simulations of $D\\bar{D}$ production and decay, lead to a sensitivity of 0.25 events/($\\mu$b/N) per day if the lifetime is of the order of $5\\times10^{-13}$s. A null result after 10 days running time would set an upper limit on the production cross section to $3 \\mu$b. \\\\ \\\\ In order to measure the momenta of charged decay products of short-lived particles, the bubble chamber will be placed 1.80 m upstream of the streamer chamber of the NA5 experiment (MPI). The geometrical acceptance ...

Measurements of airborne short-lived radioactivity concentration in a PET facility at a national University hospital

International Nuclear Information System (INIS)

Saito, Tadashi

2006-01-01

National universities in Japan became under regulation of Industrial Safety and Health Law since 2004FY. One of the legal obligations is working environment measurements such as airborne radioactivity concentration in the rooms where employees handle unsealed radiation sources. Both in 2004FY and in 2005FY, measurements of airborne radioactivity concentration were carried out by two different agencies. The most prominent difference among them is the measurement for short-lived PET nuclides. In 2004FY, one agency measured the radioactivity with a Ge spectrometer at its own laboratory, whereas, in 2005FY, the other agency brought a NaI scintillation counter for gross gamma counting to the Hospital. It can be shown that detection limits for short-lived PET nuclides are in principle almost the same in both methods. It is also found that, in the actual case, gamma spectrometry with a Ge spectrometer is superior in judgement of detection of the radioactivity. (author)

Different profiles of anthropogenic and naturally produced organohalogen compounds in serum from residents living near a coastal area and e-waste recycling workers in India.

Science.gov (United States)

Eguchi, Akifumi; Nomiyama, Kei; Devanathan, Gnanasekaran; Subramanian, Annamalai; Bulbule, Kesav A; Parthasarathy, Peethambaram; Takahashi, Shin; Tanabe, Shinsuke

2012-10-15

We determined the contamination status and accumulation profiles of polychlorinated biphenyls (PCBs), hydroxylated PCB congeners (OH-PCBs), polybrominated diphenyl ethers (PBDEs), hydroxylated PBDEs (OH-PBDEs), methoxylated PBDEs (MeO-PBDEs), and bromophenols (BPhs) in serum from e-waste recycling workers and residents near a coastal area in India. Residue levels of penta- to octa-chlorinated PCBs, penta- to octa-chlorinated OH-PCBs, 6MeO-BDE47, 6OH-BDE47, and 2,4,6-tri-BPh in serum from residents living near the coastal area were significantly higher than those in serum from e-waste recycling workers. Residue levels of tri- to tetra-chlorinated PCBs, tri- to tetra-chlorinated OH-PCBs, PBDEs, octa-brominated OH-PBDEs, and tetra-BPhs in serum from e-waste recycling workers were higher than those in serum from residents living near the coastal area. Principal component analysis revealed that residents living near the coastal area and e-waste recycling workers had different serum profiles of chlorinated and brominated compounds. Copyright © 2012 Elsevier Ltd. All rights reserved.

Impact of preindustrial to present-day changes in short-lived pollutant emissions on atmospheric composition and climate forcing

Science.gov (United States)

Naik, Vaishali; Horowitz, Larry W.; Fiore, Arlene M.; Ginoux, Paul; Mao, Jingqiu; Aghedo, Adetutu M.; Levy, Hiram

2013-07-01

We describe and evaluate atmospheric chemistry in the newly developed Geophysical Fluid Dynamics Laboratory chemistry-climate model (GFDL AM3) and apply it to investigate the net impact of preindustrial (PI) to present (PD) changes in short-lived pollutant emissions (ozone precursors, sulfur dioxide, and carbonaceous aerosols) and methane concentration on atmospheric composition and climate forcing. The inclusion of online troposphere-stratosphere interactions, gas-aerosol chemistry, and aerosol-cloud interactions (including direct and indirect aerosol radiative effects) in AM3 enables a more complete representation of interactions among short-lived species, and thus their net climate impact, than was considered in previous climate assessments. The base AM3 simulation, driven with observed sea surface temperature (SST) and sea ice cover (SIC) over the period 1981-2007, generally reproduces the observed mean magnitude, spatial distribution, and seasonal cycle of tropospheric ozone and carbon monoxide. The global mean aerosol optical depth in our base simulation is within 5% of satellite measurements over the 1982-2006 time period. We conduct a pair of simulations in which only the short-lived pollutant emissions and methane concentrations are changed from PI (1860) to PD (2000) levels (i.e., SST, SIC, greenhouse gases, and ozone-depleting substances are held at PD levels). From the PI to PD, we find that changes in short-lived pollutant emissions and methane have caused the tropospheric ozone burden to increase by 39% and the global burdens of sulfate, black carbon, and organic carbon to increase by factors of 3, 2.4, and 1.4, respectively. Tropospheric hydroxyl concentration decreases by 7%, showing that increases in OH sinks (methane, carbon monoxide, nonmethane volatile organic compounds, and sulfur dioxide) dominate over sources (ozone and nitrogen oxides) in the model. Combined changes in tropospheric ozone and aerosols cause a net negative top

Nuclear wastes: research programs

International Nuclear Information System (INIS)

Anon.

2003-01-01

The management of long-living and high level radioactive wastes in France belongs to the framework of the December 30, 1991 law which defines three ways of research: the separation and transmutation of radionuclides, their reversible storage or disposal in deep geologic formations, and their processing and surface storage during long duration. Research works are done in partnership between public research and industrial organizations in many French and foreign laboratories. Twelve years after its enforcement, the impact of this law has overstepped the simple research framework and has led to a deep reflection of the society about the use of nuclear energy. This short paper presents the main results obtained so far in the three research ways, the general energy policy of the French government, the industrial progresses made in the framework of the 1991 law and the international context of the management of nuclear wastes. (J.S.)

Short-lived non-coding transcripts (SLiTs): Clues to regulatory long non-coding RNA.

Science.gov (United States)

Tani, Hidenori

2017-03-22

Whole transcriptome analyses have revealed a large number of novel long non-coding RNAs (lncRNAs). Although the importance of lncRNAs has been documented in previous reports, the biological and physiological functions of lncRNAs remain largely unknown. The role of lncRNAs seems an elusive problem. Here, I propose a clue to the identification of regulatory lncRNAs. The key point is RNA half-life. RNAs with a long half-life (t 1/2 > 4 h) contain a significant proportion of ncRNAs, as well as mRNAs involved in housekeeping functions, whereas RNAs with a short half-life (t 1/2 regulatory ncRNAs and regulatory mRNAs. This novel class of ncRNAs with a short half-life can be categorized as Short-Lived non-coding Transcripts (SLiTs). I consider that SLiTs are likely to be rich in functionally uncharacterized regulatory RNAs. This review describes recent progress in research into SLiTs.

CARIBIC observations of short-lived halocarbons and carbonyl sulphide over Asia

Science.gov (United States)

Leedham, E.; Wisher, A.; Oram, D.; Baker, A. K.; Brenninkmeijer, C. A.

2013-12-01

The CARIBIC project (Civil Aircraft for the Regular Investigation of the atmosphere Based on an Instrument Container, www.caribic-atmospheric.com) aims to investigate the spatial and temporal distribution of a wide-range of compounds, including those of marine origin/influence, via ~monthly flights to collect in situ data and whole air samples aboard a commercial Lufthansa aircraft. CARIBIC measures up to an altitude of 12 km, allowing the influence of marine compounds on the upper troposphere/lower stratosphere (UTLS) to be explored. In particular, CARIBIC is a useful tool for exploring the impact of very short lived halocarbons (e.g. CH2Br2, CHBr3), whose impact on stratospheric ozone is dependent on convective uplift to the UTLS, a process which is not yet fully quantified. As part of the suite of CARIBIC measurements, whole air samples are analysed at the University of East Anglia (UEA) via gas chromatography mass spectrometry for carbonyl sulphide (OCS) and up to 40 halocarbons (accounting for virtually 100% of organic chlorine, bromine and iodine in the UTLS). Here we present an overview of short-lived halocarbons and OCS measured by CARIBIC. We focus on two regions of particular interest. (1) measurements made in 2012 over the tropical west Pacific to link with UEA measurements made during the SHIVA campaign. (2) measurements made during a collection of flights over India in 2008. Flights over India investigated the impact of monsoon circulation on the distribution of these compounds; for example, elevated concentrations of OCS were seen in CARIBIC samples taken over India during the summer monsoon (July - September). These flights, along with a wider range of flights over Asia (from Frankfurt to Guangzhou, Manila, Bangkok and Kuala Lumpur) can provide unique information on the influence of tropical convection and monsoon circulation on halocarbon and OCS transport within this region.

A growing threat to the ozone layer from short-lived anthropogenic chlorocarbons

Directory of Open Access Journals (Sweden)

D. E. Oram

2017-10-01

Full Text Available Large and effective reductions in emissions of long-lived ozone-depleting substance (ODS are being achieved through the Montreal Protocol, the effectiveness of which can be seen in the declining atmospheric abundances of many ODSs. An important remaining uncertainty concerns the role of very short-lived substances (VSLSs which, owing to their relatively short atmospheric lifetimes (less than 6 months, are not regulated under the Montreal Protocol. Recent studies have found an unexplained increase in the global tropospheric abundance of one VSLS, dichloromethane (CH2Cl2, which has increased by around 60 % over the past decade. Here we report dramatic enhancements of several chlorine-containing VSLSs (Cl-VSLSs, including CH2Cl2 and CH2ClCH2Cl (1,2-dichloroethane, observed in surface and upper-tropospheric air in East and South East Asia. Surface observations were, on occasion, an order of magnitude higher than previously reported in the marine boundary layer, whilst upper-tropospheric data were up to 3 times higher than expected. In addition, we provide further evidence of an atmospheric transport mechanism whereby substantial amounts of industrial pollution from East Asia, including these chlorinated VSLSs, can rapidly, and regularly, be transported to tropical regions of the western Pacific and subsequently uplifted to the tropical upper troposphere. This latter region is a major provider of air entering the stratosphere, and so this mechanism, in conjunction with increasing emissions of Cl-VSLSs from East Asia, could potentially slow the expected recovery of stratospheric ozone.

Radioactive waste handling and disposal at King Faisal Specialist Hospital and Research Centre.

Science.gov (United States)

Al-Haj, Abdalla N; Lobriguito, Aida M; Al Anazi, Ibrahim

2012-08-01

King Faisal Specialist Hospital & Research Centre (KFSHRC) is the largest specialized medical center in Saudi Arabia. It performs highly specialized diagnostic imaging procedures with the use of various radionuclides required by sophisticated dual imaging systems. As a leading institution in cancer research, KFSHRC uses both long-lived and short-lived radionuclides. KFSHRC established the first cyclotron facility in the Middle East, which solved the in-house high demand for radionuclides and the difficulty in importing them. As both user and producer of high standard radiopharmaceuticals, KFSHRC generates large volumes of low and high level radioactive wastes. An old and small radioactive facility that was used for storage of radioactive waste was replaced with a bigger warehouse provided with facilities that will reduce radiation exposure of the staff, members of the public, and of the environment in the framework of "as low as reasonably achievable." The experiences and the effectiveness of the radiation protection program on handling and storage of radioactive wastes are presented.

New methodology for Ozone Depletion Potentials of short-lived compounds: n-Propyl bromide as an example

Science.gov (United States)

Wuebbles, Donald J.; Patten, Kenneth O.; Johnson, Matthew T.; Kotamarthi, Rao

2001-07-01

A number of the compounds proposed as replacements for substances controlled under the Montreal Protocol have extremely short atmospheric lifetimes, on the order of days to a few months. An important example is n-propyl bromide (also referred to as 1-bromopropane, CH2BrCH2CH3 or simplified as 1-C3H7Br or nPB). This compound, useful as a solvent, has an atmospheric lifetime of less than 20 days due to its reaction with hydroxyl. Because nPB contains bromine, any amount reaching the stratosphere has the potential to affect concentrations of stratospheric ozone. The definition of Ozone Depletion Potentials (ODP) needs to be modified for such short-lived compounds to account for the location and timing of emissions. It is not adequate to treat these chemicals as if they were uniformly emitted at all latitudes and longitudes as normally done for longer-lived gases. Thus, for short-lived compounds, policymakers will need a table of ODP values instead of the single value generally provided in past studies. This study uses the MOZART2 three-dimensional chemical-transport model in combination with studies with our less computationally expensive two-dimensional model to examine potential effects of nPB on stratospheric ozone. Multiple facets of this study examine key questions regarding the amount of bromine reaching the stratosphere following emission of nPB. Our most significant findings from this study for the purposes of short-lived replacement compound ozone effects are summarized as follows. The degradation of nPB produces a significant quantity of bromoacetone which increases the amount of bromine transported to the stratosphere due to nPB. However, much of that effect is not due to bromoacetone itself, but instead to inorganic bromine which is produced from tropospheric oxidation of nPB, bromoacetone, and other degradation products and is transported above the dry and wet deposition processes of the model. The MOZART2 nPB results indicate a minimal correction of the

Annual report of the Aube storage center for very-low-level radioactive wastes (CSTFA) - 2011

International Nuclear Information System (INIS)

2012-08-01

The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2011 activity report of the center for very-low-level radioactive wastes. It presents a review of the activities of the center: presentation of the installations, safety, security and radiation protection, environmental monitoring and effluents, public information and communication

Disposition of nuclear waste using subcritical accelerator-driven systems

International Nuclear Information System (INIS)

Venneri, F.; Li, N.; Williamson, M.; Houts, M.; Lawrence, G.

1998-01-01

Studies have shown that the repository long-term radiological risk is from the long-lived transuranics and the fission products Tc-99 and I-129, thermal loading concerns arise mainly form the short-lived fission products Sr-90 and Cs-137. In relation to the disposition of nuclear waste, ATW is expected to accomplish the following: (1) destroy over 99.9% of the actinides; (2) destroy over 99.9% of the Tc and I; (3) separate Sr and Cs (short half-life isotopes); (4) separate uranium; (5) produce electricity. In the ATW concept, spent fuel would be shipped to a ATW site where the plutonium, other transuranics and selected long-lived fission products would be destroyed by fission or transmutation in their only pass through the facility. This approach contrasts with the present-day reprocessing practices in Europe and Japan, during which high purity plutonium is produced and used in the fabrication of fresh mixed-oxide fuel (MOX) that is shipped off-site for use in light water reactors

Long-lived high and intermediate level radioactive wastes: defining the context, stakes and perspectives

International Nuclear Information System (INIS)

2006-01-01

The French law from December 30, 1991 has defined an ambitious 15 years program of researches in order to explore the different possible paths for the long-term management of long-lived high and intermediate level radioactive wastes. The law foresees also that at the end of the 15 years research program, a project of law will be prepared by the French government and transmitted to the European parliament in 2006. A public debate has been organized and emceed in 2005 in order dialogue with the general public and to gather its questions, remarks and fears. In the framework of their contribution to this debate, the ministries of industry and environment have prepared this document which answers some key questions about radioactive waste management: where do wastes come from, what are the risks, how are they managed today in France and in foreign countries, what are the results of the researches carried out during 15 years, what are the advantages and drawbacks of each waste management solution considered, what is the perspective of application of each solution, what is the position of experts, what will be the decision process. This synthetic document supplies some reference marks to better understand these different points. Some pedagogical files about radioactivity, fuel cycle, and nuclear industry activities are attached to the document. (J.S.)

A new integrative methodology for desertification studies based on magnetic and short-lived radioisotope measurements

International Nuclear Information System (INIS)

Oldfield, F.; Higgitt, S.R.; Maher, B.A.; Appleby, P.G.; Scoullos, M.

1986-01-01

The use of mineral magnetic measurements and short-lived radioisotope studies with 210 Pb and 137 Cs is discussed within the ecosystem watershed conceptual framework. Used in conjunction with geomorphological, sedimentological, palaeoecological and geochemical techniques, these methods can form the core of an integrated multidisciplinary study of desertification and erosion processes on all relevant temporal and spatial scales. 30 refs.; 4 figs

IN-SITU RADIONUCLIDE TRANSPORT NEAR THE NOPAL I URANIUM DEPOSIT AT PENA BLANCA, MEXICO: CONSTRAINTS FROM SHORT-LIVED DECAY-SERIES RADIONUCLIDES

Energy Technology Data Exchange (ETDEWEB)

S. Luo; T.L. Ku; V. Todd; M. Murrell; J. Alfredo Rodriguez Pineda; J. Dinsmoor; A. Mitchell

2005-07-11

For nuclear waste management, an important mechanism by which radioactive waste components are isolated from returning to the human environment, the biosphere, is by the geological barrier in which the effectiveness of the barrier is characterized by in-situ retardation factor, i.e., the transport rate of a radionuclide relative to that of groundwater. As part of natural analog studies of the Yucca Mountain Project of the U. S. Department of Energy, we propose such characterization by using naturally-occurring decay-series radioisotopes as an analog. We collected large-volume (>1000 liters) groundwater samples from three wells (PB, Pozos, and PB4, respectively) near the Nopal I Uranium Ore site at Pena Blanca, Mexico, by using an in-situ Mn-cartridge filtration technique for analysis of short-lived decay-series radionuclides. Results show that the activities of short-lived radioisotopes ({sup 228}Ra, {sup 224}Ra and {sup 223}Ra) and activity ratios of {sup 224}Ra/{sup 228}Ra and {sup 224}Ra/{sup 223}Ra are higher at PB and Pozos than at PB4. In contrast, the {sup 210}Po activity is much lower at PB and Pozos than at PB4. The high Ra activities and activities ratios at PB and Pozos are attributable to the high alpha-recoil input from the aquifer rocks, while the high {sup 210}Po activity at PB4 is due to the enhanced colloidal transport. Based on a uranium-series transport model, we estimate that the in-situ retardation factor of Ra is (0.43 {+-} 0.02) x 10{sup 3} at PB, (1.68 {+-} 0.08) x 10{sup 3} at Pozos, and (1.19 {+-} 0.08) x 10{sup 3} at PB4 and that the mean fracture width in the aquifer rocks is about 0.23 {micro}m at PB, 0.37 {micro}m at Posos, and 4.0 {micro}m at PB4, respectively. The large fracture width at PB4 as derived from the model provides an additional evidence to the inference from the Po measurements that particle-reactive radionuclides are transported mainly as colloidal forms through the large fractures in rocks. Our model also suggests that

Radioactive Waste.

Science.gov (United States)

Blaylock, B. G.

1978-01-01

Presents a literature review of radioactive waste disposal, covering publications of 1976-77. Some of the studies included are: (1) high-level and long-lived wastes, and (2) release and burial of low-level wastes. A list of 42 references is also presented. (HM)

Method to Reduce Long-lived Fission Products by Nuclear Transmutations with Fast Spectrum Reactors.

Science.gov (United States)

Chiba, Satoshi; Wakabayashi, Toshio; Tachi, Yoshiaki; Takaki, Naoyuki; Terashima, Atsunori; Okumura, Shin; Yoshida, Tadashi

2017-10-24

Transmutation of long-lived fission products (LLFPs: 79 Se, 93 Zr, 99 Tc, 107 Pd, 129 I, and 135 Cs) into short-lived or non-radioactive nuclides by fast neutron spectrum reactors without isotope separation has been proposed as a solution to the problem of radioactive wastes disposal. Despite investigation of many methods, such transmutation remains technologically difficult. To establish an effective and efficient transmutation system, we propose a novel neutron moderator material, yttrium deuteride (YD 2 ), to soften the neutron spectrum leaking from the reactor core. Neutron energy spectra and effective half-lives of LLFPs, transmutation rates, and support ratios were evaluated with the continuous-energy Monte Carlo code MVP-II/MVP-BURN and the JENDL-4.0 cross section library. With the YD 2 moderator in the radial blanket and shield regions, effective half-lives drastically decreased from 106 to 102 years and the support ratios reached 1.0 for all six LLFPs. This successful development and implementation of a transmutation system for LLFPs without isotope separation contributes to a the ability of fast spectrum reactors to reduce radioactive waste by consuming their own LLFPs.

Online selection of short-lived particles on many-core computer architectures in the CBM experiment at FAIR

International Nuclear Information System (INIS)

Zyzak, Maksym

2016-01-01

Modern experiments in heavy ion collisions operate with huge data rates that can not be fully stored on the currently available storage devices. Therefore the data flow should be reduced by selecting those collisions that potentially carry the information of the physics interest. The future CBM experiment will have no simple criteria for selecting such collisions and requires the full online reconstruction of the collision topology including reconstruction of short-lived particles. In this work the KF Particle Finder package for online reconstruction and selection of short-lived particles is proposed and developed. It reconstructs more than 70 decays, covering signals from all the physics cases of the CBM experiment: strange particles, strange resonances, hypernuclei, low mass vector mesons, charmonium, and open-charm particles. The package is based on the Kalman filter method providing a full set of the particle parameters together with their errors including position, momentum, mass, energy, lifetime, etc. It shows a high quality of the reconstructed particles, high efficiencies, and high signal to background ratios. The KF Particle Finder is extremely fast for achieving the reconstruction speed of 1.5 ms per minimum-bias AuAu collision at 25 AGeV beam energy on single CPU core. It is fully vectorized and parallelized and shows a strong linear scalability on the many-core architectures of up to 80 cores. It also scales within the First Level Event Selection package on the many-core clusters up to 3200 cores. The developed KF Particle Finder package is a universal platform for short- lived particle reconstruction, physics analysis and online selection.

Online selection of short-lived particles on many-core computer architectures in the CBM experiment at FAIR

Energy Technology Data Exchange (ETDEWEB)

Zyzak, Maksym

2016-07-07

Modern experiments in heavy ion collisions operate with huge data rates that can not be fully stored on the currently available storage devices. Therefore the data flow should be reduced by selecting those collisions that potentially carry the information of the physics interest. The future CBM experiment will have no simple criteria for selecting such collisions and requires the full online reconstruction of the collision topology including reconstruction of short-lived particles. In this work the KF Particle Finder package for online reconstruction and selection of short-lived particles is proposed and developed. It reconstructs more than 70 decays, covering signals from all the physics cases of the CBM experiment: strange particles, strange resonances, hypernuclei, low mass vector mesons, charmonium, and open-charm particles. The package is based on the Kalman filter method providing a full set of the particle parameters together with their errors including position, momentum, mass, energy, lifetime, etc. It shows a high quality of the reconstructed particles, high efficiencies, and high signal to background ratios. The KF Particle Finder is extremely fast for achieving the reconstruction speed of 1.5 ms per minimum-bias AuAu collision at 25 AGeV beam energy on single CPU core. It is fully vectorized and parallelized and shows a strong linear scalability on the many-core architectures of up to 80 cores. It also scales within the First Level Event Selection package on the many-core clusters up to 3200 cores. The developed KF Particle Finder package is a universal platform for short- lived particle reconstruction, physics analysis and online selection.

Harvard-MIT research program in short-lived radiopharmaceuticals. Final report

International Nuclear Information System (INIS)

Adelstein, S.J.

1995-02-01

The Harvard-MIT Research Program in Short-lived Radiopharmaceuticals was established in 1977 to foster interaction among groups working in radiopharmaceutical chemistry at Harvard Medical School, the Massachusetts Institute of Technology, and the Massachusetts General Hospital. To this was added a group at The Childrens Hospital. From these collaborations and building upon the special strengths of the participating individuals, laboratories and institutions, it was hoped that original approaches would be found for the design of new, clinically useful, radiolabeled compounds. The original thrust of this proposal included: (a) examination of the coordination chemistry of technetium as a basis for rational radiopharmaceutical design, (b) development of an ultrashort-lived radionuclide generator for the diagnosis of congenital heart disease in newborns, (c) synthesis of receptor-site-directed halopharmaceuticals, (d) improved facile labeling of complex molecules with positron-emitting radionuclides. The authors' 1986 proposal was oriented toward organs and disease, emphasizing radiolabeled agents that delineate specific functions and the distribution of receptors in brain, heart, and tumors. In 1989, they further refined their purposes and focused on two major aims: (a) synthesis and utilization of neutral technetium and rhenium complexes of high specific activity, and (b) development of new approaches to the radiolabeling of proteins, peptides, immunoglobulins, and their fragments. In 1992, the authors amended this proposal to concentrate their efforts on biologically active peptides and proteins for targeted radiodiagnosis and therapy

Harvard-MIT research program in short-lived radiopharmaceuticals. Final report

Energy Technology Data Exchange (ETDEWEB)

Adelstein, S.J. [Massachusetts Inst. of Tech., Cambridge, MA (United States). Office of Sponsored Programs

1995-02-01

The Harvard-MIT Research Program in Short-lived Radiopharmaceuticals was established in 1977 to foster interaction among groups working in radiopharmaceutical chemistry at Harvard Medical School, the Massachusetts Institute of Technology, and the Massachusetts General Hospital. To this was added a group at The Childrens Hospital. From these collaborations and building upon the special strengths of the participating individuals, laboratories and institutions, it was hoped that original approaches would be found for the design of new, clinically useful, radiolabeled compounds. The original thrust of this proposal included: (a) examination of the coordination chemistry of technetium as a basis for rational radiopharmaceutical design, (b) development of an ultrashort-lived radionuclide generator for the diagnosis of congenital heart disease in newborns, (c) synthesis of receptor-site-directed halopharmaceuticals, (d) improved facile labeling of complex molecules with positron-emitting radionuclides. The authors` 1986 proposal was oriented toward organs and disease, emphasizing radiolabeled agents that delineate specific functions and the distribution of receptors in brain, heart, and tumors. In 1989, they further refined their purposes and focused on two major aims: (a) synthesis and utilization of neutral technetium and rhenium complexes of high specific activity, and (b) development of new approaches to the radiolabeling of proteins, peptides, immunoglobulins, and their fragments. In 1992, the authors amended this proposal to concentrate their efforts on biologically active peptides and proteins for targeted radiodiagnosis and therapy.

Conditioning of alpha bearing wastes

International Nuclear Information System (INIS)

1991-01-01

Alpha bearing wastes are generated during the reprocessing of spent fuel, mixed oxide fuel fabrication, decommissioning and other activities. The safe and effective management of these wastes is of particular importance owing to the radiotoxicity and long lived characteristics of certain transuranic (TRU) elements. The management of alpha bearing wastes involves a number of stages which include collection, characterization, segregation, treatment, conditioning, transport, storage and disposal. This report describes the currently available matrices and technologies for the conditioning of alpha wastes and relates them to their compatibility with the other stages of the waste management process. The selection of a specific immobilization process is dependent on the waste treatment state and the subsequent handling, transport, storage and disposal requirements. The overall objectives of immobilization are similar for all waste producers and processors, which are to produce: (a) Waste forms with sufficient mechanical, physical and chemical stability to satisfy all stages of handling, transport and storage (referred to as the short term requirements), and (b) Waste forms which will satisfy disposal requirements and inhibit the release of radionuclides to the biosphere (referred to as the long term requirements). Cement and bitumen processes have already been successfully applied to alpha waste conditioning on the industrial scale in many of the IAEA Member States. Cement systems based on BFS and pozzolanic cements have emerged as the principal encapsulation matrices for the full range of alpha bearing wastes. Alternative technologies, such as polymers and ceramics, are being developed for specific waste streams but are unlikely to meet widespread application owing to cost and process complexity. The merits of alpha waste conditioning are improved performance in transport, storage and disposal combined with enhanced public perception of waste management operations. These

Evaluating the treatment of E-waste a case study of discarded refrigerators

Institute of Scientific and Technical Information of China (English)

DENG Jian-jun; WEN Xue-feng; ZHAO Yue-min

2008-01-01

Disassembly and recycling of E-waste creates a series of environmental problems. The selection of a technologically reliable, environmentally friendly, economically affordable and socially acceptable recycling technology for E-waste is a significant question. This study establishes a Monte-Carlo mathematical model of cost minimization, given the constraints of environmentally sound handling of the e-waste, in the context of Crystal Ball risk assessment and evaluation software. By following the streams of the different treatment processes, which consist of various technologies including disassembly, recycling and disposal, the econom-ics of various possibilities were identified and the optimal recycling technology proposed. The key factors of the proposed scenarios were determined by using sensitivity analysis. The results of this study show that, for discarded refrigerators, the operating life span plays the key role. The model supports maintenance and resale of the short lived refrigerators. For the longer lived refrigerators material recycling is recommended by the model. Sensitivity analysis shows that purchase cost, plastic sale price, condenser sale price and disassembly costs are the main effects. This study provides a significant technical support for policy making in E-waste management.

Deep disposal of long-lived radioactive waste in France: The volunteering approach in site selection

International Nuclear Information System (INIS)

Raynal, M.; Barber, P.

1995-01-01

The French Waste Act of December 1991 set up important dispositions among which the deep disposal of long-lived waste should be evaluated before 2006. ANDRA, the French National Agency for Radioactive Waste Management, is particularly responsible for the siting, the construction and the operation of underground laboratories designed to study potential geologic host-formations for deep disposal. An open decision-making process started up in 1992, specially to restore the public confidence after strong contest in the early 1990. The mission of negotiation conducted in 1993 all over the country by the appointed Member of Parliament, Mr. Bataille, allowed volunteer candidates for the siting surveyed by ANDRA in 1994 and 1995. Four areas are presently under characterization investigations, proceeding with the first phase of the underground laboratory program with the objective of choosing two sites for two underground laboratories. France is now entering a new and very important phase on the long path towards the creation of an underground repository where public's understanding and acceptance is an important part of the overall process as it is shown in this paper

Contribution of the short lived radionuclides in food to the total radiation burden of man after the nuclear accident in Chernobyl

International Nuclear Information System (INIS)

Popovic, D.; Djuric, G.; Smelcerovic, M.; Maksimovic, B.

1989-01-01

The paper presents the results of the short lived radionuclides (I-131, Te(I)-132, Cs-136, Ce-141,144, Ru-103,106, Ba(La)-140, Zr-95, Mo-99, Nb-95, Sb-125) mass activities estimation in some foodstuff (milk and milk products), immediately after the nuclear accident in Chernobyl, in May 1986. The activities of the radionuclides were determined on Ge(Li) detector by standard gamma spectrometry, with the total error less than 20%. The results enabled the evaluation of the short lived radionuclides contribution in the total dose due to ingestion of milk and milk products, in the first month after the accident, compared to the contribution of I-131 and to the contribution of the main long lived radionuclides: Ce-134 and Cs-137 (author)

Radioactive waste disposal in Slovakia: Current practice and development

International Nuclear Information System (INIS)

Salzer, P.; Hanusik, V.; Ehn, L.

2002-01-01

The paper describes activities concerning the disposal of radioactive waste in the Slovak Republic. For disposal of the low and intermediate short-lived radioactive waste, the National radioactive waste repository Mochovce (near surface type) was put into operation in 1999. History and approaches to repository development, siting and construction are briefly described. Recent activities regarding the repository are concerning on the safety re-assessment and re-derivation of coherent waste acceptance criteria, studies of repository covering and possible enlargement. In the second part, attention is given to the Slovak deep geological repository development programme, which has been under way since 1996. Most of the results were obtained from the siting part of the programme, where four localities (six sites) were identified as prospective for next investigation. The paper also gives an overview on next two routes of deep repository development programme: studies resulted later in performance assessment and general activities, i.e. design studies, analysis of legislative and infrastructure conditions, planning and evaluation of works. (author)

[Hyperfine structure and isotope shift measurements of short lived elements by laser spectroscopy

International Nuclear Information System (INIS)

Schuessler, H.A.

1986-01-01

The aim of this research is to determine nuclear moments and charge distributions of short-lived isotopes produced both on-line and off-line to a nuclear facility. These measurements give detailed information on the nuclear force and are used to test current nuclear models. The small amounts of nuclei which can be produced off stability constitute the challenge in these experiments. Presently mainly neutron-rich isotopes are being studied by three ultrasensitive high-resolution laser techniques. These are collinear fast ion-beam laser spectroscopy, stored-ion laser spectroscopy and fluorescence spectroscopy. 5 figs

Applications of short-lived activation products in neutron activation analysis of bio-environmental specimens

International Nuclear Information System (INIS)

1987-03-01

This report discusses the advantages and disadvantages, special techniques, and actual and potential applications of neutron activation analysis (NAA) utilizing short-lived neutron-induced products, with special reference to the analysis of samples of biological and environmental origin. Attention is devoted mainly to products having half-lives in roughly the range of 10 milliseconds to 60 seconds, but with some discussion of the usefulness of even shorter-lived species, and ones with half-lives as long as a few minutes. Important aspects of the analytical methodology include sample preparation, irradiation/transfer systems, activity measurements, data processing and analytical quality assurance. It is concluded that several trace elements can be determined in bio-environmental samples (as well as in samples of industrial, geochemical and other origin). In particular, this method provides analytical possibilities for several elements (e.g. B, F, Li and V) that are difficult to determine in some matrices at trace levels by any other technique. These conclusions are illustrated in an annex by results of calculations in which the applicability of the techniques to the analysis of several biological and environmental reference materials is evaluated by means of an advance computer prediction program. The report concludes with an annotated bibliography of relevant publications (including abstracts, where available) taken from the INIS database. (author)

Effects of post-disposal gas generation in a repository for spent fuel, high-level waste and long-lived intermediate level waste sited in opalinus clay

International Nuclear Information System (INIS)

Johnson, L.; Marschall, P.; Zuidema, P.; Gribi, P.

2004-07-01

This comprehensive report issued by the Swiss National Cooperative for the Disposal of Radioactive Waste NAGRA takes a look at post-disposal gas generation in a repository for spent fuel and highly radioactive wastes in Opalinus clay strata. This study provides a comprehensive treatment of the issue of gas generation in a repository for spent fuel (SF), vitrified high-level waste (HLW) and long-lived intermediate-level waste (ILW), sited in the Opalinus clay of the Zuercher Weinland in northern Switzerland. The issue of how gas generation in and transport from waste repositories may influence disposal system performance has been under study for many years, both at Nagra and internationally. The report consists of three main parts: (i) A synthesis of basic information on the host rock and on details of repository construction; (ii) A discussion on gas transport characteristics of the engineered barrier system and the geosphere; (iii) A discussion on the effects of gas on system performance, based on the available information on gas generation, gas transport properties and gas pathways provided in the previous parts of the report. Simplified model calculations based on a mass balance approach for the gas generated within the repository are presented and discussed

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.

Short-lived radionuclide production capability at the Brookhaven Linac Isotope Producer

International Nuclear Information System (INIS)

Mausner, L.F.; Richards, P.

1985-01-01

The Brookhaven National Linac Isotope Producer is the first facility to demonstrate the capability of a large linear accelerator for efficient and economical production of difficult-to-make, medically useful radionuclides. The linac provides a beam of 200-MeV protons at an integrated beam current of up to 60 μA. The 200-MeV proton energy is very suitable for isotope production because the spallation process can create radionuclides unavailable at lower energy accelerators or reactors. Several medically important short-lived radionuclides are presently being prepared for on-site and off-site collaborative research programs. These are iodine-123, iron-52, manganese-52m, ruthenium-97, and the rubidium-81-krypton-81m system. The production parameters for these are summarized

A report of the symposium on 'comprehensive research on the management of long-lived radioactive wastes' in the Research Center for Nuclear Science and Technology, University of Tokyo

International Nuclear Information System (INIS)

Sekiguchi, Akira; Naito, Keiji; Suzuki, Susumu; Furuya, Hirotaka; Sato, Masatomo.

1983-01-01

In the Research Center for Nuclear Science and Technology, University of Tokyo, the special research project ''Comprehensive Research on the Management of Long-lived Radioactive WasΩtes'' is carried out in the three-year period from fiscal 1982 to 1984. In this connection, a symposium has been held on January 25, 1983. Seven lectures given by the respective speakers are summarized individually: (1) the research of transuranic elements in educational institutions, (2) an outline of the actinoid research facilities planned in Tohoku University, (3) the radiation damage and leachability of glass solids, (4) the situation and trend in Japan and abroad of the disposal of long-lived nuclide wastes, (5) practical site tests concerning the geologic-formation disposal of low-level wastes, (6) the trend in the research of geologic formations for the disposal of high-level wastes, (7) the safety in the management of long-lived radioactive wastes. (Mori, K.)

Deep repository for long-lived low- and intermediate-level waste. Preliminary safety assessment

International Nuclear Information System (INIS)

1999-11-01

A preliminary safety assessment has been performed of a deep repository for long-lived low- and intermediate-level waste, SFL 3-5. The purpose of the study is to investigate the capacity of the facility to act as a barrier to the release of radionuclides and toxic pollutants, and to shed light on the importance of the location of the repository site. A safety assessment (SR 97) of a deep repository for spent fuel has been carried out at the same time. In SR 97, three hypothetical repository sites have been selected for study. These sites exhibit fairly different conditions in terms of hydrogeology, hydrochemistry and ecosystems. To make use of information and data from the SR 97 study, we have assumed that SFL 3-5 is co-sited with the deep repository for spent fuel. A conceivable alternative is to site SFL 3-5 as a completely separate repository. The focus of the SFL 3-5 study is a quantitative analysis of the environmental impact for a reference scenario, while other scenarios are discussed and analyzed in more general terms. Migration in the repository's near- and far-field has been taken into account in the reference scenario. Environmental impact on the three sites has also been calculated. The calculations are based on an updated forecast of the waste to be disposed of in SFL 3-5. The forecast includes radionuclide content, toxic metals and other substances that have a bearing on a safety assessment. The safety assessment shows how important the site is for safety. Two factors stand out as being particularly important: the water flow at the depth in the rock where the repository is built, and the ecosystem in the areas on the ground surface where releases may take place in the future. Another conclusion is that radionuclides that are highly mobile and long-lived, such as 36 Cl and 93 Mo , are important to take into consideration. Their being long-lived means that barriers and the ecosystems must be regarded with a very long time horizon

Measurement methodology for fulfilling of waste acceptance criteria for low and intermediate level radioactive waste in storages - 59016

International Nuclear Information System (INIS)

Sokcic-Kostic, M.; Langer, F.; Schultheis, R.

2012-01-01

with half life longer than Cs-137, whereas intermediate level waste is sub-classified as short lived waste and long lived waste. Long lived isotopes are mainly alpha emitters which result from contamination of the RAW by nuclear fuel material and its fission and breeding products. The sub-classification is made on base of mass specific alpha activity of the waste. Before being sent to storage the waste has to be treated. This includes volume reduction by combustion or compaction, depending on the physical properties of the waste, as well as immobilisation by grouting, saving thereby storage space and costs. After the treatment the waste is filled into packages preferably drums or containers. Before the waste is sent to the waste storage a passport is generated which includes all relevant data to show that the waste package fulfils the requirements as defined by the waste storage operating company. NUKEM Technologies has developed a large number of monitors for a radiological waste characterisation. The preferred methods are non-destructive, allowing high throughput and giving detailed information. Parameters that cannot be measured after treatment, have to be measured during the treatment process or data has to be collected from available sources like the origin of the waste or from the waste deliverer. To optimise this process NUKEM Technologies has developed a tracking system which traces the waste during treatment starting from delivery and finishing by the transportation to the final storage. (authors)

Quantum non-locality in a two-slit interferometer for short-lived particles

International Nuclear Information System (INIS)

Klein, Spencer R.; Nystrand, Joakim

2001-01-01

We describe a new test of quantum nonlocality, using an interferometer for short-lived particles. The separation is large compared with the particle lifetimes. This interferometer is realized by vector meson production in distant heavy ion collisions. The mesons decay before waves from the two sources (ions) can overlap, so interference is only possible among the decay products. The post-decay wave function must retain amplitudes for all possible decays. The decay products are spatially separated, necessitating a non-local wave function. The interference is measurable by summing the product momenta. Alternately, the products positions could be observed, allowing new tests of the EPR paradox

1. round table - Nuclear wastes and radioactive materials. 2. round table - risks linked with nuclear wastes and materials. 3. round table - the problem of long-term management of medium-high activity and long lived wastes. The process defined by the 1991 law

International Nuclear Information System (INIS)

2005-01-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the debates of the first round table of Paris about the problems raised by nuclear wastes in the case of the geologic disposal option. Four families of questions have been tackled: 1 - the exhaustiveness of ANDRA's inventory, the solutions foreseen for the different types of wastes; 2 - the high-medium activity wastes and their processing; 3 - the management of non-reprocessed spent MOX fuels; 4 - the safety and security standards used and their establishment. Four presentations are attached to these proceedings and deal with: the measured and estimated inventory of all radioactive wastes; the inventory and management of radioactive wastes and the place of citizens; the point of view of the nuclear safety authority; conditioning and storage. (J.S.)

Public debate on the general options relative to the management of high-medium activity and long-lived radioactive wastes

International Nuclear Information System (INIS)

2005-09-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. This document presents the organizational aspects of the debate: origin, organization committee (mission, members, commitments), framework (the December 31, 1991 law, technical enlargement, society aspects), topics (summary of the debate in ten questions), organization modalities (4 main steps, schedule, venues), objectives and perspectives (sharing information, decision making processes to be implemented by 2006). (J.S.)

Seasonal variation in the behaviour of a short-lived rodent.

Science.gov (United States)

Eccard, Jana A; Herde, Antje

2013-11-15

Short lived, iteroparous animals in seasonal environments experience variable social and environmental conditions over their lifetime. Animals can be divided into those with a "young-of-the-year" life history (YY, reproducing and dying in the summer of birth) and an "overwinter" life history (OW, overwintering in a subadult state before reproducing next spring).We investigated how behavioural patterns across the population were affected by season and sex, and whether variation in behaviour reflects the variation in life history patterns of each season. Applications of pace-of-life (POL) theory would suggest that long-lived OW animals are shyer in order to increase survival, and YY are bolder in order to increase reproduction. Therefore, we expected that in winter and spring samples, when only OW can be sampled, the animals should be shyer than in summer and autumn, when both OW and YY animals can be sampled.We studied common vole (Microtus arvalis) populations, which express typical, intra-annual density fluctuation. We captured a total of 492 voles at different months over 3 years and examined boldness and activity level with two standardised behavioural experiments. Behavioural variables of the two tests were correlated with each other. Boldness, measured as short latencies in both tests, was extremely high in spring compared to other seasons. Activity level was highest in spring and summer, and higher in males than in females. Being bold in laboratory tests may translate into higher risk-taking in nature by being more mobile while seeking out partners or valuable territories. Possible explanations include asset-protection, with OW animals being rather old with low residual reproductive value in spring. Therefore, OW may take higher risks during this season. Offspring born in spring encounter a lower population density and may have higher reproductive value than offspring of later cohorts. A constant connection between life history and animal personality, as

Geological repository layout for radioactive high level long lived waste in argillite

International Nuclear Information System (INIS)

Gaussen, JL

2006-01-01

In the framework of the 1991 French radioactive waste act, ANDRA has studied the feasibility of a geological repository in the argillite layer of the Bure site for high level long lived waste. This presentation is focussed on the underground facilities which constitute the specific component of this project. The preliminary underground layout which has been elaborated is based on four categories of data: - the waste characteristics and inventory; - the geological properties of the host argillite; - the long term performance objectives of the repository; - the specifications in terms of operation and reversibility. The underground facilities consist of two types of works: the access works (shafts and drifts) and the disposal cells. The function of the access works is to permit the implementation of two concurrent activities: the nuclear operations (transfer and emplacement of the disposal packages into the disposal cells) and the construction of the next disposal cells. The design of the drifts network which matches up to this function is also influenced by two other specifications: the minimization of the drift dimensions in order to limit their influence on the integrity of the geological formation and the necessity of a safe ventilation in case of fire. The resulting layout is a network of 4 parallel drifts (2 of them being dedicated to the operation, the other two being dedicated to the construction activities). The average diameter of these access drifts is 7 meters. The link between the surface and the underground is ensured by 4 shafts. The most important function of the disposal cells is to contribute to the long term performance of the repository. In this regard, the thermal and geotechnical considerations play an important role. The B wastes (intermediate level wastes) are not (or not very) exothermic. Consequently, the design of their disposal cells result mainly from geotechnical considerations. The disposal packages (made of concrete) are piled up in

Quantifying short-lived events in multistate ionic current measurements.

Science.gov (United States)

Balijepalli, Arvind; Ettedgui, Jessica; Cornio, Andrew T; Robertson, Joseph W F; Cheung, Kin P; Kasianowicz, John J; Vaz, Canute

2014-02-25

We developed a generalized technique to characterize polymer-nanopore interactions via single channel ionic current measurements. Physical interactions between analytes, such as DNA, proteins, or synthetic polymers, and a nanopore cause multiple discrete states in the current. We modeled the transitions of the current to individual states with an equivalent electrical circuit, which allowed us to describe the system response. This enabled the estimation of short-lived states that are presently not characterized by existing analysis techniques. Our approach considerably improves the range and resolution of single-molecule characterization with nanopores. For example, we characterized the residence times of synthetic polymers that are three times shorter than those estimated with existing algorithms. Because the molecule's residence time follows an exponential distribution, we recover nearly 20-fold more events per unit time that can be used for analysis. Furthermore, the measurement range was extended from 11 monomers to as few as 8. Finally, we applied this technique to recover a known sequence of single-stranded DNA from previously published ion channel recordings, identifying discrete current states with subpicoampere resolution.

THE DEAD-LIVING-MOTHER: MARIE BONAPARTE'S INTERPRETATION OF EDGAR ALLAN POE'S SHORT STORIES.

Science.gov (United States)

Obaid, Francisco Pizarro

2016-06-01

Princess Marie Bonaparte is an important figure in the history of psychoanalysis, remembered for her crucial role in arranging Freud's escape to safety in London from Nazi Vienna, in 1938. This paper connects us to Bonaparte's work on Poe's short stories. Founded on concepts of Freudian theory and an exhaustive review of the biographical facts, Marie Bonaparte concluded that the works of Edgar Allan Poe drew their most powerful inspirational force from the psychological consequences of the early death of the poet's mother. In Bonaparte's approach, which was powerfully influenced by her recognition of the impact of the death of her own mother when she was born-an understanding she gained in her analysis with Freud-the thesis of the dead-living-mother achieved the status of a paradigmatic key to analyze and understand Poe's literary legacy. This paper explores the background and support of this hypothesis and reviews Bonaparte's interpretation of Poe's most notable short stories, in which extraordinary female figures feature in the narrative.

Variation in the local population dynamics of the short-lived Opuntia macrorhiza (Cactaceae).

Science.gov (United States)

Haridas, C V; Keeler, Kathleen H; Tenhumberg, Brigitte

2015-03-01

Spatiotemporal variation in demographic rates can have profound effects for population persistence, especially for dispersal-limited species living in fragmented landscapes. Long-term studies of plants in such habitats help with understanding the impacts of fragmentation on population persistence but such studies are rare. In this work, we reanalyzed demographic data from seven years of the short-lived cactus Opuntia macrorhiza var. macrorhiza at five plots in Boulder, Colorado. Previous work combining data from all years and all plots predicted a stable population (deterministic log lamda approximately 0). This approach assumed that all five plots were part of a single population. Since the plots were located in a suburban-agricultural interface separated by highways, grazing lands, and other barriers, and O. macrorhiza is likely dispersal limited, we analyzed the dynamics of each plot separately using stochastic matrix models assuming each plot represented a separate population. We found that the stochastic population growth rate log lamdaS varied widely between populations (log lamdaS = 0.1497, 0.0774, -0.0230, -0.2576, -0.4989). The three populations with the highest growth rates were located close together in space, while the two most isolated populations had the lowest growth rates suggesting that dispersal between populations is critical for the population viability of O. macrorhiza. With one exception, both our prospective (stochastic elasticity) and retrospective (stochastic life table response experiments) analysis suggested that means of stasis and growth, especially of smaller plants, were most important for population growth rate. This is surprising because recruitment is typically the most important vital rate in a short-lived species such as O. macrorhiza. We found that elasticity to the variance was mostly negligible, suggesting that O. macrorhiza populations are buffered against large temporal variation. Finally, single-year elasticities to means

The transport implications of siting policies for the disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

James, I.A.

1986-01-01

This report has been produced to be complementary to the previously issued report ''The Transport Implications of Regional Policies for The Disposal of Intermediate Level Radioactive Wastes''. The same combinations of disposal facilities have been used so that direct comparison with intermediate waste results can be made. Low level wastes and short-lived intermediate level wastes for near-surface disposal are assumed to share a common infrastructure on the rail system and hence a methodology of separating total costs between these two waste types has been derived. Two transport modes, road and rail have been analysed. Hybrid transport, a combination of road and rail systems, has not been examined since no site is considered to produce sufficient waste to justify a dedicated rail service. Sellafield, has not been included in this examination since it is assumed to be served by its own disposal site at Drigg. (author)

Concentration Limits in the Cement Based Swiss Repository for Long-lived, Intermediate-level Radioactive Wastes (LMA)

International Nuclear Information System (INIS)

Berner, Urs

1999-12-01

The Swiss repository concept for long-lived, intermediate-level radioactive wastes (LMA), in Swiss terminology) foresees cylindrical concrete silos surrounded by a ring of granulated bentonite to deposit the waste. As one of the possible options and similar to the repository for high level wastes, the silos will be located in a deep crystalline host rock. Solidified with concrete in steel drums, the waste is stacked into a silo and the silo is then backfilled with a porous mortar. To characterize the release of radionuclides from the repository, the safety assessment considers first the dissolution into the pore water of the concrete, and then diffusion through the outer bentonite ring into the deep crystalline groundwater. For 19 safety relevant radionuclides (isotopes of U, Th, Pa, Np, Pu, Am, Ni, Zr, Mo, Nb, Se, Sr, Ra, Tc, Sn, I, C, Cs, Cl) the report recommends maximum elemental concentrations to be expected in the cement pore water of the particularly considered repository. These limits will form the parameter base for subsequent release model chains. Concentration limits in a geochemical environment are usually obtained from thermodynamic equilibrium calculations performed with geochemical speciation codes. However, earlier studies revealed that this procedure does not always lead to reliable results. Main reasons for this are the complexity of the systems considered, as well as the lacking completeness of, and the uncertainty associated with the thermodynamic data. To improve the recommended maximum concentrations for a distinct repository design, this work includes additional design- and system-dependent criteria. The following processes, inventories and properties are considered in particular: a) recent experimental investigations, particularly from cement systems, b) thermodynamic model calculations when reliable data are available, c) total inventories of radionuclides, d) sorption- and co-precipitation processes, e) dilution with stable isotopes, f

2009 National inventory of radioactive material and wastes. In short

International Nuclear Information System (INIS)

2009-01-01

This booklet gives a summary of the national inventory report on radioactive wastes that are present on the French territory (as recorded until december, 2007). Intended for public information, the booklet explains the basics of radioactive materials and wastes and waste management, and gives some data on present and future waste volumes, information about radioactive waste classification, the geographical distribution of waste sites in France, etc. The various types of radioactive wastes are described (classified by their lifetime and activity level) as well as historical storage sites, polluted areas where wastes are stored, radioactive objects, etc. and their respective management approaches are presented

Development of a system for real-time measurements of metabolite transport in plants using short-lived positron-emitting radiotracers

Science.gov (United States)

Kiser, Matthew R.

Over the past 200 years, the Earth's atmospheric carbon dioxide (CO 2) concentration has increased by more than 35%, and climate experts predict that CO2 levels may double by the end of this century. Understanding the mechanisms of resource management in plants is fundamental for predicting how plants will respond to the increase in atmospheric CO 2. Plant productivity sustains life on Earth and is a principal component of the planet's system that regulates atmospheric CO2 concentration. As such, one of the central goals of plant science is to understand the regulatory mechanisms of plant growth in a changing environment. Short-lived positron-emitting radiotracer techniques provide time-dependent data that are critical for developing models of metabolite transport and resource distribution in plants and their microenvironments. To better understand the effects of environmental changes on resource transport and allocation in plants, we have developed a system for real-time measurements of rnetabolite transport in plants using short-lived positron-emitting radio-tracers. This thesis project includes the design, construction, and demonstration of the capabilities of this system for performing real-time measurements of metabolite transport in plants. The short-lived radiotracer system described in this dissertation takes advantage of the combined capabilities and close proximity of two research facilities at. Duke University: the Triangle Universities Nuclear Laboratory (TUNL) and the Duke University Phytotron, which are separated by approximately 100 meters. The short-lived positron-emitting radioisotopes are generated using the 10-MV tandem Van de Graaff accelerator located in the main TUNL building, which provides the capability of producing short-lived positron-emitting isotopes such as carbon-11 (11C: 20 minute half-life), nitrogen-13 (13N; 10 minute half-life), fluorine-18 (18F; 110 minute half-life), and oxygen-15 (15O; 2 minute half-life). The radioisotopes may

Status of the public debate on the general options of management of high and intermediate activity and long-lived radioactive wastes

International Nuclear Information System (INIS)

2006-01-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprised 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is a status of the general organisation and progress of the debate from its preparing to its end in mid-January 2006. It shows the challenges the CNDP had to take up to treat the scientifical and technical questions in an accessible way, allowing the participation and the hearing of the large public. A status is made of the deception and satisfaction of the public. A lack of confidence in public authorities and scientists has been expressed several times. No pro-nuclear/anti-nuclear shock has occurred and the debate has revealed a remarkable richness in its content. One contribution of the debate to the future project of law is its enlargement to the overall nuclear wastes and valorizable materials and not only to the high/intermediate-level and long-lived wastes. (J.S.)

Production cross sections of short-lived silver radionuclides from natPd(p,xn) nuclear processes

International Nuclear Information System (INIS)

Khandaker, Mayeen Uddin; Kim, Kwangsoo; Kim, Guinyun

2012-01-01

Production cross-sections of short-lived 103 Ag, 104m Ag and 104g Ag radionuclides from proton-induced reactions on natural palladium (Pd) were measured up to 41 MeV by using a stacked-foil activation technique combined with high resolution γ-ray spectrometry. The present results are compared with the available literature values as well as theoretical data calculated by the TALYS and the ALICE-IPPE computer codes. Note that production cross-sections of the 104m Ag radionuclide from nat Pd(p,xn) processes has been measured here for the first time. Physical thick target yields for the investigated radionuclides were deduced from the respective threshold energy to 41 MeV taking into account that the total energy is absorbed in the targets. Measured data of the short-lived 103 Ag radionuclide are noteworthy due to its possible applications as a precursor for the indirect production of widely used therapeutic 103 Pd radionuclide via nat Pd(p,xn) 103 Ag → 103 Pd processes. On the other hand, the investigated 104 Ag radionuclide finds importance due to its potential use as a diagnostic and positron emission tomography (PET) imaging analogue. Above all, measured data will enrich the literature database leading to various applications in science and technology.

Behaviour of short-lived iodines in operating UO2 fuel elements

International Nuclear Information System (INIS)

Lipsett, J.J.; Hastings, I.J.; Hunt, C.E.L.

1984-11-01

Sweep gas experiments have been done to determine the behaviour of short-lived fission products within operating UO 2 fuel elements at linear powers of 45, 54, and 60 KW/m, and to burnups of 70, 80, and 50 MWh/kgU respectively. Although radioiodine transport was not observed directly during normal operation, equilibrium gap inventories for I-131 were deduced from the shutdown decay behaviour of the fission gases. These inventories were a strong function of fuel power and ranged from 10 GBq (0.27 Ci) to 100 GBq (2.7 Ci) over the range tested. We conclude that the iodine inventory was adsorbed onto the fuel and/or sheath surfaces with a volatile fraction of less than 10 -2 and a charcoal-filter-penetrating fraction of less than 2x10 -4

Low-level radioactive waste management handbook series: Low-level radioactive waste management in medical and biomedical research institutions

International Nuclear Information System (INIS)

1987-03-01

Development of this handbook began in 1982 at the request of the Radhealth Branch of the California Department of Health Services. California Assembly Bill 1513 directed the DHS to ''evaluate the technical and economic feasibility of (1) reducing the volume, reactivity, and chemical and radioactive hazard of (low-level radioactive) waste and (2) substituting nonradioactive or short-lived radioactive materials for those radionuclides which require long-term isolation from the environment. A contract awarded to the University of California at Irvine-UCI (California Std. Agreement 79902), to develop a document focusing on methods for decreasing low-level radioactive waste (LLW) generation in institutions was a result of that directive. In early 1985, the US Department of Energy, through EG and G Idaho, Inc., contracted with UCI to expand, update, and revise the California text for national release

Space augmentation of military high-level waste disposal

International Nuclear Information System (INIS)

English, T.; Lees, L.; Divita, E.

1979-01-01

Space disposal of selected components of military high-level waste (HLW) is considered. This disposal option offers the promise of eliminating the long-lived radionuclides in military HLW from the earth. A space mission which meets the dual requirements of long-term orbital stability and a maximum of one space shuttle launch per week over a period of 20-40 years, is a heliocentric orbit about halfway between the orbits of earth and Venus. Space disposal of high-level radioactive waste is characterized by long-term predicability and short-term uncertainties which must be reduced to acceptably low levels. For example, failure of either the Orbit Transfer Vehicle after leaving low earth orbit, or the storable propellant stage failure at perihelion would leave the nuclear waste package in an unplanned and potentially unstable orbit. Since potential earth reencounter and subsequent burn-up in the earth's atmosphere is unacceptable, a deep space rendezvous, docking, and retrieval capability must be developed

Determination of nuclear spins of short-lived isotopes by laser induced fluorescence

International Nuclear Information System (INIS)

Buchinger, F.; Dabkiewicz, P.; Kremmling, H.; Kuehl, T.; Mueller, A.C.; Schuessler, H.A.

1980-01-01

The spins of several nuclear ground and isomeric states have been measured for a number of mercury isotopes. The fluorescent light from the 6s6p 3 P 1 state is observed at 2537 Angstroem after excitation with the frequency doubled output of a pulsed dye laser. Four different laser induced fluorescence techniques were tested for their applicability: double resonance, Hanle effect, time delayed integral Hanle beats, and time resolved quantum beats. The sensitivity and selectivity of these models are compared with emphasis on the determination of spins of nuclei far from beta-stability, where short half lives and low production yields restrict the number of available atoms. The experiments were carried out on-line with the ISOLDE isotope separator at CERN at densities as low as 10 6 atoms/cm 3 . Results for the very neutron deficient high spin mercury isomers with half lives of several seconds, but also for the ground states of the abundant low spin stable mercury isotopes, are given as examples. The test measurements determined the nuclear spins of the odd sup(185m-191m)Hg isomers to be I = 13/2. (orig.)

Long-Term Safety Analysis of Baldone Radioactive Waste Repository and Updating of Waste Acceptance Criteria

International Nuclear Information System (INIS)

2001-12-01

The main objective of the project was to provide advice to the Latvian authorities on the safety enhancements and waste acceptance criteria for near surface radioactive waste disposal facilities of the Baldone repository. The project included the following main activities: Analysis of the current status of the management of radioactive waste in Latvia in general and, at the Baldone repository in particular Development of the short and long-term safety analysis of the Baldone repository, including: the planned increasing of capacity for disposal and long term storage, the radiological analysis for the post-closure period Development of the Environment Impact Statement, for the new foreseen installations, considering the non radiological components Proposal of recommendations for future updating of radioactive waste acceptance criteria Proposal of recommendations for safety upgrades to the facility. The work programme has been developed in phases and main tasks as follows. Phase 0: Project inception, Phase 1: Establishment of current status, plans and practices (Legislation, regulation and standards, Radioactive waste management, Waste acceptance criteria), Phase 2: Development of future strategies for long-term safety management and recommendations for safety enhancements. The project team found the general approach use at the installation, the basic design and the operating practices appropriate to international standards. Nevertheless, a number of items subject to potential improvements were also identified. These upgrading recommendations deal with general aspects of the management (mainly storage versus disposal of long-lived sources), site and environmental surveillance, packaging (qualification of containers, waste characterization requirements), the design of an engineered cap and strategies for capping. (author)

Morbidity among children living around clinical waste treatment and disposal site in the Northwest region of Cameroon

Directory of Open Access Journals (Sweden)

Peter I. K. Mochungong

2011-03-01

Full Text Available Clinical waste is ineffectively treated and disposed in Cameroon. Disposal sites have unrestricted access and are located within communities. We hypothesize that vector proliferation and exposure to chronic low-level emissions will increase morbidity in children living around such sites. Self-reported disease frequency questionnaires were used to estimate the frequency of new episodes of intestinal, respiratory and skin infections among exposed children less than 10 years. Data was simultaneously collected for unexposed children of the same age, using the same questionnaire. Data reporting by the parents was done in the first week in each of the 6 months study period. The risk ratios were 3.54 (95% CI, 2.19-5.73, 3.20 (95% CI, 1.34-7.60 and 1.35 (95% CI, 0.75-2.44 for respiratory, intestinal and skin infections respectively. Their respective risk differences were 0.47 (47%, 0.18 (18% and 0.08 (8%. The study revealed that poor treatment and disposal of clinical waste sites enhance morbidity in children living close to such areas. Simple health promotion and intervention programs such as relocating such sites can significantly reduce morbidity.

Antigen modulation of the immune response. III. Evaluation of the hypothetical short-lived memory cell

International Nuclear Information System (INIS)

Feldbush, T.L.; Lande, I.; Bryan, B.; O'Neill, E.

1974-01-01

The putative short-lived memory cells, whose existence has been suggested by the results of secondary adoptive transfer experiments, were investigated. On the basis of the following evidences we have concluded that the short-lived memory cell is probably an artifact of the adoptive transfer technique: when immune thoracic duct lymphocytes, known to consist predominantly of long-lived memory cells, were transferred to irradiated recipients and challenged at various times after transfer, approximately 80 to 90 percent of the initial response was absent by Day 14 challenge; preirradiating adoptive recipients with increasing dose of x-irradiation tended to lengthen the observed half life of memory cells; single or multiple treatments of immune donors with 0.3 mg Vinblastin before transfer resulted in neither a depression of the initial secondary response nor an alteration in the rate of decline of the memory potential; reconstitution of irradiated hosts with normal spleen cells one day before transfer of memory cells and challenge resulted in inhibition of the adoptive secondary response; and the transfer of memory cells to antigen free intermediate hosts, in which they were allowed to reside for one day or fourteen days before transfer to irradiated recipients, resulted in only a slight decline in their capacity to respond. We propose that the rapid decline of memory potential in adoptive recipients challenged at various times after transfer is due to modulating effects by the hosts as it recovers from irradiation. These effects may be the result of cell crowding or the loss of irradiation-produced stimulatory factors. The relevance of these findings to adoptive transfer systems in general and the secondary response of intact animals is discussed

The high level and long lived radioactive wastes; Les dechets radioactifs a haute activite et a vie longue

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

This report presents the main conclusions of 15 years of researches managed by the CEA. This report is the preliminary version of the 2005 final report. It presents the main conclusions of the actions on the axis 1 and 3 of the law of the 30 December 1991. The synthesis report on the axis 1 concerns results obtained on the long lived radionuclides separation and transmutation in high level and long lived radioactive wastes. the synthesis report on the axis 3 presents results obtained by the processes of conditioning and of ground and underground long term storage. (A.L.B.)

Harvard--MIT research program in short-lived radiopharmaceuticals. Progress report, September 1, 1977--April 30, 1978. [/sup 99m/Tc, positron-emitting radionuclides

Energy Technology Data Exchange (ETDEWEB)

Adelstein, S.J.; Brownell, G.L.

1978-05-01

Progress is reported on the following studies: chemistry studies designed to achieve a more complete understanding of the fundamental chemistry of technetium in order to facilitate the design of future radiopharmaceuticals incorporating the radionuclide /sup 99m/Tc; the development of new radiopharmaceuticals intended to improve image quality and lower radiation doses by the use of short-lived radionuclides and disease-specific agents; the development of short-lived positron-emitting radionuclides which offer advantages in transverse section imaging of regional physiological processes; and studies of the toxic effects of particulate radiation.

Muscle Senescence in Short-Lived Wild Mammals, the Soricine Shrews Blarina brevicauda and Sorex palustris

Science.gov (United States)

HINDLE, ALLYSON G.; LAWLER, JOHN M.; CAMPBELL, KEVIN L.; HORNING, MARKUS

2015-01-01

Red-toothed (soricine) shrews are consummate predators exhibiting the highest energy turnovers and shortest life spans (ca. 18 months) of any mammal, yet virtually nothing is known regarding their physiological aging. We assessed the emerging pattern of skeletal muscle senescence (contractile/connective tissue components) in sympatric species, the semi-aquatic water shrew (WS), Sorex palustris, and the terrestrial short-tailed shrew (STS), Blarina brevicauda, to determine if muscle aging occurs in wild, short-lived mammals (H0: shrews do not survive to an age where senescence occurs), and if so, whether these alterations are species-specific. Gracilis muscles were collected from first-year (n = 17) and second-year (n = 17) field-caught shrews. Consistent with typical mammalian aging, collagen content (% area) increased with age in both species (S. palustris: ~50%; B. brevicauda: ~60%). Muscle was dominated by stiffer Type I collagen, and the ratio of collagen Type I:Type III more than doubled with age. The area ratio of muscle:collagen decreased with age in both species, but was considerably lower in adult STS, suggesting species-specificity of senescence. Extracellular space was age-elevated in B. brevicauda, but was preserved in S. palustris (~50 vs. 10% elevation). Though juvenile interspecific comparisons revealed no significance, adult WS myocytes had 68% larger cross-sectional area and occurred at 28% lower fibers/area than those of adult STS. We demonstrate that age-related muscle senescence does occur in wild-caught, short-lived mammals, and we therefore reject this classic aging theory tenet. Our findings moreover illustrate that differential age adjustments in contractile/connective tissue components of muscle occur in the two species of wild-caught shrews. PMID:19296507

Quail and other short-lived birds.

Science.gov (United States)

Ottinger, M A

2001-04-01

Japanese quail are small galliforms that are migratory and generally live 2 to 3years in the wild. Although there is evidence for other environmental cues, they primarily respond to long daylength for regulation of reproduction. In contrast to the Common Tern, a long-lived sea bird that shows little evidence of reproductive aging, Japanese quail follow a well-defined process of aging with evidence of declining function in reproductive, metabolic, and sensory systems. Our studies focus on neuroendocrine changes associated with reproductive aging in the Japanese quail, with emphasis on the male in order to study both endocrine and behavioral components of reproduction and the process of reproductive aging.

SHORT COMMUNICATION TRANSESTERIFICATION OF WASTE ...

African Journals Online (AJOL)

Preferred Customer

1College of Chemical Engineering, Qingdao University of Science and Technology, Qingdao. 266042, China ... was an efficient catalyst for the reaction under the optimum conditions: n(oil):n(methanol) 1:12, waste oil 15.0 g, ionic liquid 2.0 g ... In order to reduce the production costs and to make it competitive with petroleum ...

Review of biotechnology applications to nuclear waste treatment

International Nuclear Information System (INIS)

Ashley, N.V.; Roach, D.J.W.

1990-01-01

This paper gives an overview of the feasibility of the application of biotechnology to nuclear waste treatment. Many living and dead organisms accumulate heavy metals and radionuclides. The controlled use of this phenomenon forms the basis for the application of biotechnology to the removal of radionuclides from nuclear waste streams. An overview of biotechnology areas, namely the use of biopolymers and biosorption using biomass applicable to the removal of radionuclides from industrial nuclear effluents is given. The potential of biomagnetic separation technology, genetic engineering and monoclonal antibody technology is also to be examined. The most appropriate technologies to develop for radionuclide removal in the short term appear to be those based on biosorption of radionuclides by biomass and the use of modified and unmodified biopolymers in the medium term. (author)

Problems related to final disposal of high-level radioactive waste in Russia

International Nuclear Information System (INIS)

Velichkin, Vasily I.

1999-01-01

According to this presentation, the radioactivity of the total amount of radioactive waste accumulated in Russia to date is 1.5*10 9 Ci and of spent fuel 4.5*10 9 Ci. A table is given that shows the source, type, volume activity and storage type under the responsibility of the different departments and enterprises. 99.9% of the wastes are accumulated at the enterprises of Minatom of the Russian Federation. Some companies inject their liquid wastes from ionisation sources and intermediate liquid waste from the nuclear power industry into deep-seated reliably isolated aquifers. The Mayak plant has released liquid low-level and intermediate wastes into artificial reservoirs and Lake Karachay. Liquid high-level wastes are always stored in special tanks at interim storage facilities. A large number of nuclear submarines are laid up in North-Western Russia and East Russia, with spent fuel still in place as the interim storages in these regions are filled up and there are no conditioning plants. Underground disposal is considered the best way of isolating radioactive waste for as long as it is hazardous to the environment. Two new technologies are discussed. One involves including long-lived isotopes in high-stable mineral matrices, the other uses selective separation from the bulk of wastes. The matrices should be disposed of deep in the Earth's crust, at least 2-3 km down. Liquid waste of caesium-strontium fraction must be transformed into glass-like form and stored underground at a depth of a few hundred metres. Short-lived low level and intermediate level wastes should be conditioned and then deposited in subsurface ferroconcrete repositories constructed in clays. Finally, the presentation discusses the selection of sites and conditions for radioactive waste disposal. Two sites are discussed, the Mayak plant and a possible site at Mining Chemical Combine in Krasnoyarsk-26

Dynamical Detection of Topological Phase Transitions in Short-Lived Atomic Systems

Science.gov (United States)

Setiawan, F.; Sengupta, K.; Spielman, I. B.; Sau, Jay D.

2015-11-01

We demonstrate that dynamical probes provide direct means of detecting the topological phase transition (TPT) between conventional and topological phases, which would otherwise be difficult to access because of loss or heating processes. We propose to avoid such heating by rapidly quenching in and out of the short-lived topological phase across the transition that supports gapless excitations. Following the quench, the distribution of excitations in the final conventional phase carries signatures of the TPT. We apply this strategy to study the TPT into a Majorana-carrying topological phase predicted in one-dimensional spin-orbit-coupled Fermi gases with attractive interactions. The resulting spin-resolved momentum distribution, computed by self-consistently solving the time-dependent Bogoliubov-de Gennes equations, exhibits Kibble-Zurek scaling and Stückelberg oscillations characteristic of the TPT. We discuss parameter regimes where the TPT is experimentally accessible.

Contribution of short-lived nuclides to decay heat

International Nuclear Information System (INIS)

Katakura, Jun-ichi

1987-01-01

Comments are made on the calculation of decay heat, centering on evaluation of average decay energy. It is difficult to obtain sufficiently useful decay diagrams of short lived nucleides. High-energy levels are often missing in inferior decay diagrams, leading to an overestimation of the intensity of beta-rays at low-energy levels. Such an overestimation or underestimation due to the inferiority of a decay diagram is referred to as pandemonium effect. The pandemonium effect can be assessed by means of the ratio of the measured energy of the highest level of the daughter nuclide to the Q β -value of the beta-decay. When a satisfactory decay diagram cannot be obtained, the average decay energy has to be estimated by theoretical calculation. The gross theory for beta-decay proposed by Yamada and Takahashi is employed for the calculation. To carry out the calculation according to this theory, it is required to determine the value for the parameter Q 00 , the lowest energy of the daughter nuclide that meets the selection rule for beta-decay. Currently, Q 00 to be used for this purpose is estimated from data on the energy of the lowest level found in a decay diagram, even if it is inferior. Some examples of calculation of decay heat using the average beta- or gamma-ray energy are shown and compared with measurements. (author)

Deep repository for long-lived low- and intermediate-level waste. Preliminary safety assessment

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-11-01

A preliminary safety assessment has been performed of a deep repository for long-lived low- and intermediate-level waste, SFL 3-5. The purpose of the study is to investigate the capacity of the facility to act as a barrier to the release of radionuclides and toxic pollutants, and to shed light on the importance of the location of the repository site. A safety assessment (SR 97) of a deep repository for spent fuel has been carried out at the same time. In SR 97, three hypothetical repository sites have been selected for study. These sites exhibit fairly different conditions in terms of hydrogeology, hydrochemistry and ecosystems. To make use of information and data from the SR 97 study, we have assumed that SFL 3-5 is co-sited with the deep repository for spent fuel. A conceivable alternative is to site SFL 3-5 as a completely separate repository. The focus of the SFL 3-5 study is a quantitative analysis of the environmental impact for a reference scenario, while other scenarios are discussed and analyzed in more general terms. Migration in the repository's near- and far-field has been taken into account in the reference scenario. Environmental impact on the three sites has also been calculated. The calculations are based on an updated forecast of the waste to be disposed of in SFL 3-5. The forecast includes radionuclide content, toxic metals and other substances that have a bearing on a safety assessment. The safety assessment shows how important the site is for safety. Two factors stand out as being particularly important: the water flow at the depth in the rock where the repository is built, and the ecosystem in the areas on the ground surface where releases may take place in the future. Another conclusion is that radionuclides that are highly mobile and long-lived, such as {sup 36}Cl and {sup 93}Mo , are important to take into consideration. Their being long-lived means that barriers and the ecosystems must be regarded with a very long time horizon.

Nuclear physics with use of KUR. Reviews of 30 years studies on short-lived nuclei and perspectives for the future

International Nuclear Information System (INIS)

Kawase, Yoichi

1995-01-01

The research works which were carried out over the past 30 years on nuclear structure study have been reviewed with emphasis on the technical developments of experimental apparatus for the studies of very short-lived isotopes produced by the Kyoto University reactor(KUR). In the first chapter, nuclear structure studies of neutron-rich nuclei with use of the on-line irradiation apparatus and the on-line isotope separator(ISOL) for fission products have been described. In the second chapter, applications of nuclear methods to solid state physics by the perturbed angular correlation(PAC) technique have been examined to investigate the local electromagnetic fields in metals and compounds through the hyperfine interactions. Perspectives for the future of related research fields are given aiming at the advanced uses of short-lived radioisotopes. (author)

Combined heat and power production planning in a waste-to-energy plant on a short-term basis

International Nuclear Information System (INIS)

Touš, Michal; Pavlas, Martin; Putna, Ondřej; Stehlík, Petr; Crha, Lukáš

2015-01-01

In many cases, WtE (waste-to-energy) plants are CHP (combined heat and power) producers. They are often integrated into a central heating system and they also export electricity to the grid. Therefore, they have to plan their operation on a long-term basis (months, years) as well as on a short-term basis (hours, days). Simulation models can effectively support decision making in CHP production planning. In general, CHP production planning on a short-term basis is a challenging task for WtE plants. This article presents a simulation based support. It is demonstrated on an example involving a real WtE plant. Most of the models of relevant WtE sub-systems (boilers, steam turbine) are developed using operational data and applying linear regression and artificial neural network technique. The process randomness given mainly by fluctuating heating value of waste leads to uncertainty in a calculation of CHP production and a stochastic approach is appropriate. The models of the sub-systems are, therefore, extended of a stochastic part and Monte-Carlo simulation is applied. Compared to the current planning strategy in the involved WtE plant, the stochastic simulation based planning provides increased CHP production resulting in better net thermal efficiency and increased revenue. This is demonstrated through a comparison using real operational data. - Highlights: • Introduction of a stochastic model of a CHP production in a waste-to-energy plant. • An application of the model for the next day CHP production planning. • Better net thermal efficiency and therefore increased revenue achieved.

Status and challenges for radioactive waste management

International Nuclear Information System (INIS)

Riotte, H.

2011-01-01

In its 2008 Nuclear Energy Outlook the NEA reviewed the status of radioactive waste management world-wide and noted that the technology for disposal of short-lived low- and intermediate-level radioactive waste is well developed. The review concluded that all OECD countries with major nuclear programmes either operate corresponding waste disposal facilities or are in an advanced stage of developing them. By contrast, the developmental progress of HLW/SNF management programmes varies widely between countries; not to mention that there is currently no repository operating that could take spent nuclear fuel or high-level waste from reprocessing. In its collective opinion 'Moving forward with geological disposal' the NEA noted that deep underground disposal in geological formations is seen worldwide as the only sustainable endpoint for the management of these types of waste, as it affords unparalleled protection without reliance on active safety monitoring and controls. While waste management programmes in some countries are well matured and countries like Finland, France and Sweden aim to operate geologic repositories in the next decade, others need to develop their national strategies, plans and corresponding actions for managing radioactive waste further. Periodically reviewed national waste management plans, as legally required for EU member countries by a recent Directive, can provide a co-operation framework for all national institutional players and a means to measure progress. In implementing sustainable solutions for the long-term management of HLW/SNF, specific challenges lay in establishing an efficient policy and regulatory framework that (a) defines a desired level of safety over the various time scales to be considered and (b) allows for sustainable decision making procedures by involving public and stakeholder in a flexible, step-wise implementation process. Technical confidence in the safety of a repository needs to be demonstrated in a modern

A phase-imaging ion-cyclotron-resonance technique for mass measurements of short-lived nuclides

Energy Technology Data Exchange (ETDEWEB)

Eliseev, Sergey; Blaum, Klaus; Doerr, Andreas; Eronen, Tommi; Goncharov, Mikhail; Hoecker, Martin; Ketter, Jochen; Ramirez, Enrique Minaya; Simon, Vanessa [Max-Planck Institute for Nuclear Physics (Germany); Block, Michael [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH (Germany); Chenmarev, Stanislav; Filjanin, Pavel; Nesterenko, Dmitriy; Novikov, Yuri [Petersburg Nuclear Physics Institute (Russian Federation); Droese, Christian; Schweikhard, Lutz [Institute for Physics, Ernst-Moritz-Arndt-University (Germany)

2014-07-01

A novel approach to mass measurements on the sub-ppb level even for short-lived nuclides with half-lives well below one second is presented. It is based on the projection of the radial ion motion in a Penning trap onto a position sensitive detector. Compared to the presently employed time-of-flight ion-cyclotron-resonance technique, the novel approach is 25-times faster and provides a 40-fold gain in resolving power. With the new technique low-lying isomeric states with excitation energy on the 10-keV level can be separated from the ground state. Moreover, the new technique possesses a substantially higher sensitivity since just two ions are sufficient to determine the ion cyclotron frequency. A measurement of the mass difference of singly charged ions of {sup 132}Xe and {sup 131}Xe with an uncertainty of 25 eV has demonstrated the great potential of the new approach.

Radioactive wastes: present problems and future prospects

International Nuclear Information System (INIS)

Gauvenet, Andre

1975-01-01

The main characteristics of radioactive wastes are described and the present problems arising from liquid or gas effluents are considered. It is concluded that nuclear power stations are considerably less pollutant, at equal capacity, than conventional power stations. Programs of investigation are now being developed to meet with the foreseeable increase of activity. The problem is: first, to maintain absorbed doses at their present level and second, to study the problem of long-lived elements the storage of which would, in the long run create a nuisance on a world scale. The different waste storage techniques now in use are described and current investigations and works are exposed some of which, like vitrification, have already begun to be put into application. After having noted that the problem of wastes constitutes doubtless a difficulty in the technical field and, maybe even more so in the psychological field, the conditions are defined which will have to be met in order that this problem should not hinder the short- and long-term development of nuclear energy [fr

Muscle senescence in short-lived wild mammals, the soricine shrews Blarina brevicauda and Sorex palustris.

Science.gov (United States)

Hindle, Allyson G; Lawler, John M; Campbell, Kevin L; Horning, Markus

2009-06-01

Red-toothed (soricine) shrews are consummate predators exhibiting the highest energy turnovers and shortest life spans (ca. 18 months) of any mammal, yet virtually nothing is known regarding their physiological aging. We assessed the emerging pattern of skeletal muscle senescence (contractile/connective tissue components) in sympatric species, the semi-aquatic water shrew (WS), Sorex palustris, and the terrestrial short-tailed shrew (STS), Blarina brevicauda, to determine if muscle aging occurs in wild, short-lived mammals (H(0): shrews do not survive to an age where senescence occurs), and if so, whether these alterations are species-specific. Gracilis muscles were collected from first-year (n=17) and second-year (n=17) field-caught shrews. Consistent with typical mammalian aging, collagen content (% area) increased with age in both species (S. palustris: approximately 50%; B. brevicauda: approximately 60%). Muscle was dominated by stiffer Type I collagen, and the ratio of collagen Type I:Type III more than doubled with age. The area ratio of muscle:collagen decreased with age in both species, but was considerably lower in adult STS, suggesting species-specificity of senescence. Extracellular space was age-elevated in B. brevicauda, but was preserved in S. palustris ( approximately 50 vs. 10% elevation). Though juvenile interspecific comparisons revealed no significance, adult WS myocytes had 68% larger cross-sectional area and occurred at 28% lower fibers/area than those of adult STS. We demonstrate that age-related muscle senescence does occur in wild-caught, short-lived mammals, and we therefore reject this classic aging theory tenet. Our findings moreover illustrate that differential age adjustments in contractile/connective tissue components of muscle occur in the two species of wild-caught shrews. (c) 2009 Wiley-Liss, Inc.

From waste packages acceptance criteria to waste packages acceptance process at the Centre de l'Aube disposal facility

International Nuclear Information System (INIS)

Dutzer, M.

2003-01-01

The Centre de l'Aube disposal facility has now been operated for 10 years. At the end of 2001, about 124,000 m3 of low and intermediate level short lived waste packages, representing 180,000 packages, have been disposed, for a total capacity of 1,000,000 m3. The flow of waste packages is now between 12 and 15,000 m3 per year, that is one third of the flow that was taken into account for the design of the repository. It confirms the efforts by waste generators to minimise waste production. This flow represents 25 to 30,000 packages, 50% are conditioned into the compaction facility of the repository, so that 17,000 packages are disposed per year. 54 disposal vaults have been closed. In 1996-1999, the safety assessment of the repository have been reviewed, taking into account the experience of operation. This assessment was investigated by the regulatory body and, subsequently, a so-called 'definitive license' to operate was granted to ANDRA on September 2, 1999 with updated licensing requirements. Another review will be performed in 2004. To ensure a better consistency with the safety assessment of the facility, Andra issued new technical requirements for waste packages at the end of 2000. Discussions with waste generators also showed that the waste package acceptance process should be improved to provide a more precise definition of operational criteria to comply with in waste conditioning facilities. Consequently, a new approach has been implemented since 2000. (orig.)

A crossed-beam experiment on intramultiplet mixing collisions with short-lived Ne** {(2p)5(3p)} atoms

NARCIS (Netherlands)

Manders, M.P.I.; Ruyten, W.M.J.; van de Beucken, F..J.H.M.; Driessen, J.P.J.; Veugelers, W.J.T.; Kramer, P.H.; Vredenbregt, E.J.D.; van Hoek, W.B.M.; Sandker, G.J.; Beijerinck, H.C.W.; Verhaar, B.J.

1988-01-01

We describe the design, operation, and calibration of a crossed-beam experiment for the study of intramultiplet mixing collisions of short-lived electronically excited Ne{(2p)5(3p)}≡{α} atoms with ground-state atoms/molecules. The excellent performance of almost 1 kHz/Å2 (number of counts per unit

A contribution to the physical and chemical model of long-lived radioactive wastes by clayey materials

International Nuclear Information System (INIS)

Gorgeon, L.

1994-01-01

This work deals with the high-level and long-lived radioactive wastes confinement which come from the irradiated fuels reprocessing. These wastes are generally coated in a deep geological structure confinement matrix. The radiation protection of a such storage requires that the coating matrix, the technological barriers which separate the storage and the geological medium and the reception rock does not let the radioactive wastes pass. The materials used in this work for the confinement studies are clayey minerals and the retention mechanisms studies are realized on cesium 135, neptunium 237, americium 241 and uranium 233. The first part of this thesis concerns the clayey minerals retention properties towards ions in aqueous solutions. More particularly the relations between these properties and the chemical structure of these solids are investigated. In the second part are presented the experimental works which have allowed to specify the intrinsic characteristics of the studied minerals. Indeed the knowledge of these parameters is essential to quantitatively explain the results of the radionuclides retention. The adsorption mechanisms are described in a third part. (O.L.). 112 refs., 59 figs., 51 tabs

Operational experience from SFR - Final repository for low- and intermediate level waste in Sweden

International Nuclear Information System (INIS)

Skogsberg, Marie; Ingvarsson, Roger

2006-01-01

SFR, the Swedish Final Repository for Radioactive Waste, has been in operation since April 1988. It was designed for short lived LLW/ILW from the operation and maintenance of all Swedish Nuclear Power Plants. The first stage was constructed for 63 000 m 3 which was assumed to give a margin and flexibility for the preliminary operational period. Today this volume represents the whole prediction of operational waste. Until the end of 2005 SFR has received 30 930 m 3 waste. In average it has been 2-3 derivations per year at the repository. The most derivations happened in the years 1993-1995, and that was also the years when the repository received the most volume of waste. The most of the derivations those years was related to the waste packages. The dose rate to the personal has always been very low in the latest years the collective dose has been under 0,1 mmanSv/year. (author)

Development of a Method to Assess the Radiation Dose due to Internal Exposure to Short-lived Radioactive Materials

International Nuclear Information System (INIS)

Benmaman, D.; Koch, J.; Ribak, J.

2014-01-01

Work with radioactive materials requires monitoring of the employees' exposure to ionizing radiation. Employees may be exposed to radiation from internal and/or external exposure. Control of external exposure is mostly conducted through personal radiation dosimeters provided to employees. Control of internal exposure can be performed by measuring the concentration of radioactive substances excreted in urine or through whole-body counting in which the entire body or target organs are scanned with a sensitive detector system (1). According to the regulations in Israel an employee that may be internally exposed must undergo an exposure control at least once every three months. The idea lying behind the control of internal exposure by urine testing is that if radioactive material has penetrated into the employee body, it can be detected even if the test is performed once every three months. A model was fitted for each element describing its dispersion in the body and its excretion therefrom (2). By means of this model, one can estimate the activity that entered the body and calculate the resulting radiation dose to which the worker was exposed. There is a problem to implement this method when it comes to short-lived radioactive materials, for which it is very likely that the material that penetrated into the body has decayed and cannot be detected by testing once every three months. As a result, workers with short-lived radioactive materials are presently not monitored for internal exposure, in contradiction to the requirements of the Safety at Work Regulations. The purpose of the study is to develop an alternative method to assess the amount of radioactive material absorbed in the body and the resulting radiation dose due to internal exposure of workers to short-lived radioactive materials

Sizes and shapes of short-lived nuclei via laser spectroscopy. Progress report, May 1, 1980-January 31, 1981

International Nuclear Information System (INIS)

Lewis, D.A.

1981-02-01

The first stage of the program to study the sizes and shapes of short-lived nuclei through their atomic hyperfine structure is to develop a movable laser spectroscopy system. This system is now almost complete and is described in this report along with plans for measurements at Argonne National Laboratory and Brookhaven National Laboratory

Short-chain chlorinated paraffins in terrestrial bird species inhabiting an e-waste recycling site in South China.

Science.gov (United States)

Luo, Xiao-Jun; Sun, Yu-Xin; Wu, Jiang-Ping; Chen, She-Jun; Mai, Bi-Xian

2015-03-01

Short-chain chlorinated paraffins (SCCPs) are under review by the Stockholm Convention on Persistent Organic Pollutants. Currently, limited data are available about SCCPs in terrestrial organisms. In the present study, SCCP concentration in the muscles of seven terrestrial bird species (n = 38) inhabiting an e-waste recycling area in South China was determined. This concentration varied from 620 to 17,000 ng/g lipid. Resident birds accumulated significantly higher SCCP concentrations than migratory birds (p < 0.01). Trophic magnification was observed for migratory bird species but not for resident, which was attributed to high heterogeneity of SCCP in e-waste area. Two different homologue group patterns were observed in avian samples. The first pattern was found in five bird species dominated by C10 and C11 congeners, while the second was found in the remains, which show rather equal abundance of homologue groups. This may be caused by two sources of SCCPs (local and e-waste) in the study area. Copyright © 2014 Elsevier Ltd. All rights reserved.

ICRP PUBLICATION 122: radiological protection in geological disposal of long-lived solid radioactive waste.

Science.gov (United States)

Weiss, W; Larsson, C-M; McKenney, C; Minon, J-P; Mobbs, S; Schneider, T; Umeki, H; Hilden, W; Pescatore, C; Vesterlind, M

2013-06-01

This report updates and consolidates previous recommendations of the International Commission on Radiological Protection (ICRP) related to solid waste disposal (ICRP, 1985, 1997b, 1998). The recommendations given apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the ICRP system of radiological protection described in Publication 103 (ICRP, 2007) can be applied in the context of the geological disposal of long-lived solid radioactive waste. Although the report is written as a standalone document, previous ICRP recommendations not dealt with in depth in the report are still valid. The 2007 ICRP system of radiological protection evolves from the previous process-based protection approach relying on the distinction between practices and interventions by moving to an approach based on the distinction between three types of exposure situation: planned, emergency and existing. The Recommendations maintains the Commission's three fundamental principles of radiological protection namely: justification, optimisation of protection and the application of dose limits. They also maintain the current individual dose limits for effective dose and equivalent dose from all regulated sources in planned exposure situations. They re-enforce the principle of optimisation of radiological protection, which applies in a similar way to all exposure situations, subject to restrictions on individual doses: constraints for planned exposure situations, and reference levels for emergency and existing exposure situations. The Recommendations also include an approach for developing a framework to demonstrate radiological protection of the environment. This report describes the different stages in the life time of a geological disposal facility, and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that

ICRP PUBLICATION 122: Radiological Protection in Geological Disposal of Long-lived Solid Radioactive Waste

International Nuclear Information System (INIS)

Weiss, W.; Larsson, C-M.; McKenney, C.; Minon, J-P.; Mobbs, S.; Schneider, T.; Umeki, H.; Hilden, W.; Pescatore, C.; Vesterlind, M.

2013-01-01

This report updates and consolidates previous recommendations of the International Commission on Radiological Protection (ICRP) related to solid waste disposal (ICRP, 1985, 1997b, 1998). The recommendations given apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the ICRP system of radiological protection described in Publication 103 (ICRP, 2007) can be applied in the context of the geological disposal of long-lived solid radioactive waste. Although the report is written as a standalone document, previous ICRP recommendations not dealt with in depth in the report are still valid. The 2007 ICRP system of radiological protection evolves from the previous process-based protection approach relying on the distinction between practices and interventions by moving to an approach based on the distinction between three types of exposure situation: planned, emergency and existing. The Recommendations maintains the Commission’s three fundamental principles of radiological protection namely: justification, optimisation of protection and the application of dose limits. They also maintain the current individual dose limits for effective dose and equivalent dose from all regulated sources in planned exposure situations. They re-enforce the principle of optimisation of radiological protection, which applies in a similar way to all exposure situations, subject to restrictions on individual doses: constraints for planned exposure situations, and reference levels for emergency and existing exposure situations. The Recommendations also include an approach for developing a framework to demonstrate radiological protection of the environment. This report describes the different stages in the life time of a geological disposal facility, and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that

Gross theory of beta-decay and half-lives of short-lived nuclei

International Nuclear Information System (INIS)

Yamada, Masami; Kondo, Norikatsu.

1976-01-01

The gross theory of beta-decay has been developed, and this theory offers the means of calculating directly the function of beta-decay intensity, then half-lives, complex beta spectra and so on are estimated from it. This paper presents the more refined theory by introducing the shell effect. The shell effect is considered in the intensity function. The half-lives in the electron decay of In with spin of 9/2 + , the positron decay of Bi, Po, At and Rn, and the decay of odd-odd nuclei were estimated. The introduction of the shell effect shows better agreement between the theory and the experimental data. The inequality relations of intensity functions and half-lives of two adjacent nuclei were obtained. When the spins and parities of two nuclei are same, the inequality relations hold especially good. (Kato, T.)

Short-chain chlorinated paraffins in terrestrial bird species inhabiting an e-waste recycling site in South China

International Nuclear Information System (INIS)

Luo, Xiao-Jun; Sun, Yu-Xin; Wu, Jiang-Ping; Chen, She-Jun; Mai, Bi-Xian

2015-01-01

Short-chain chlorinated paraffins (SCCPs) are under review by the Stockholm Convention on Persistent Organic Pollutants. Currently, limited data are available about SCCPs in terrestrial organisms. In the present study, SCCP concentration in the muscles of seven terrestrial bird species (n = 38) inhabiting an e-waste recycling area in South China was determined. This concentration varied from 620 to 17,000 ng/g lipid. Resident birds accumulated significantly higher SCCP concentrations than migratory birds (p < 0.01). Trophic magnification was observed for migratory bird species but not for resident, which was attributed to high heterogeneity of SCCP in e-waste area. Two different homologue group patterns were observed in avian samples. The first pattern was found in five bird species dominated by C 10 and C 11 congeners, while the second was found in the remains, which show rather equal abundance of homologue groups. This may be caused by two sources of SCCPs (local and e-waste) in the study area. - Highlights: • SCCPs in terrestrial bird species from an e-waste area are first reported. • Elevated SCCP level was found as compared with other regions. • Resident birds accumulated significantly higher SCCP levels than migratory birds. • Trophic magnification was observed for migratory but not for resident bird species. • Two homologue patterns were found among seven bird species. - SCCP concentration in terrestrial bird species inhabiting an e-waste site was first reported in this study

NMR detection of short-lived β-emitter {sup 12}N implanted in water

Energy Technology Data Exchange (ETDEWEB)

Sugihara, T., E-mail: sugihara@vg.phys.sci.osaka-u.ac.jp; Mihara, M.; Shimaya, J.; Matsuta, K.; Fukuda, M.; Ohno, J.; Tanaka, M.; Yamaoka, S.; Watanabe, K.; Iwakiri, S.; Yanagihara, R.; Tanaka, Y.; Du, H.; Onishi, K.; Kambayashi, S.; Minamisono, T. [Osaka University, Department of Physics (Japan); Nishimura, D. [Tokyo University of Science, Department of Physics (Japan); Izumikawa, T. [Niigata University, Radioisotope Center (Japan); Ozawa, A. [University of Tsukuba, Department of Physics (Japan); Ishibashi, Y. [RIKEN Nishina Center for Accelerator-Based Science (Japan); and others

2017-11-15

The beta-detected nuclear magnetic resonance (β-NMR) in liquid H{sub 2}O has been observed for the first time using a short-lived β-ray emitter {sup 12}N (I{sup π} = 1{sup +},T{sub 1/2}=11 ms). A nuclear spin polarized {sup 12}N beam with an energy of about 20 MeV/nucleon was implanted into an enclosed water sample. About 50 % of implanted {sup 12}N ions maintained nuclear polarization and exhibited a β-NMR spectrum. The chemical shift of {sup 12}N in H{sub 2}O relative to {sup 12}N in Pt was deduced to be −(3.6±0.5) × 10{sup 2} ppm.

182Hf-182W age dating of a 26Al-poor inclusion and implications for the origin of short-lived radioisotopes in the early Solar System

DEFF Research Database (Denmark)

Holst, Jesper Christian; Olsen, Mia Bjørg Stolberg; Paton, Chad

2013-01-01

provide a unique window into the earliest Solar System, including the origin of short-lived radioisotopes. However, their chronology is unknown. Using the 182Hf–182W chronometer, we show that a FUN CAI recording a condensation origin from a solar gas formed coevally with canonical CAIs, but with 26Al/27Al......Refractory inclusions [calcium–aluminum-rich inclusions, (CAIs)] represent the oldest Solar System solids and provide information regarding the formation of the Sun and its protoplanetary disk. CAIs contain evidence of now extinct short-lived radioisotopes (e.g., 26Al, 41Ca, and 182Hf) synthesized...... in one or multiple stars and added to the protosolar molecular cloud before or during its collapse. Understanding how and when short-lived radioisotopes were added to the Solar System is necessary to assess their validity as chronometers and constrain the birthplace of the Sun. Whereas most CAIs formed...

Management of radioactive wastes from nuclear fuels and power plants in Canada

International Nuclear Information System (INIS)

Tomlinson, M.; Mayman, S.A.; Tammemagi, H.Y.; Gale, J.; Sanford, B.

1977-05-01

The nature of Canadian nuclear fuel and nuclear generating plant radioactive wastes is summarized. Principles of a scheme for disposal of long-lived radioactive wastes deep underground in isolation from man and the biosphere are outlined. The status of the development and construction program is indicated. We have demonstrated incorporation of fission products in solids that in the short term (17 years) dissolve more slowly than plutonium decays. Investigations of long-term stability are in hand. Additional capacity for storage of used fuel prior to reprocessing and disposal is required by 1986 and a preliminary design has been prepared for a pool facility to be located at a central fuel recycling and disposal complex. A demonstration of dry storage of fuel in concrete containers is in progress. The quantities of CANDU generating-station wastes and the principles and methods for managing them are summarized. A radioactive-waste operations site is being developed with several different types of surface storage, each with multiple barriers against leakage. A reactor decommissioning study has been completed. Estimated costs of the various waste management operations are summarized. (author)

Monitoring of processes with gamma-rays of neutron capture and short-living radionuclides

International Nuclear Information System (INIS)

Aripov, G.A.; Kurbanov, B.I.; Allamuratova, G.

2004-01-01

Element content is a fundamental parameter of a substance, on which all its properties, and also character of physical, chemical, biological, technological and ecological processes depend. Therefore monitoring of element content (in the course of technological process - on line; in natural conditions - in site; or in living organisms - in vivo) becomes necessary for investigation of aforementioned processes. This problem can be successfully solved by using the methods of prompt gamma activation analysis (PGAA) and instrumental neutron activation analysis (INAA) on short-living radionuclides. These methods don't depend on type of substance (biological, geological, technological etc.), since the content is determined by gamma radiation of nuclei, and allows to meet such a serious requirement like the necessity of achieving minimal irradiation of the object and its minimal residual activity. In this work minimal determinable concentrations of various elements are estimated (based on experimental data) by the method of PGAA using radionuclide 252 Cf - source of neutrons with the yield of the oil of 10 8 neutron/sec on the experimental device with preliminary focusing of neutrons /1/, and also data of determination of elements by their isotopes with maximum time efficiency /2,3/ by the method of INAA. (author)

Climate Considerations in Long-Term Safety Assessments for Nuclear Waste Repositories

Energy Technology Data Exchange (ETDEWEB)

Naeslund, Jens-Ove; Brandefelt, Jenny; Claesson Liljedahl, Lillemor [Svensk Kaernbraenslehantering AB, Stockholm (Sweden)], E-mail: jens-ove.naslund@skb.se

2013-05-15

For a deep geological repository for spent nuclear fuel planned in Sweden, the safety assessment covers up to 1 million years. Climate scenarios range from high-end global warming for the coming 100 000 years, through deep permafrost, to large ice sheets during glacial conditions. In contrast, in an existing repository for short-lived waste the activity decays to low levels within a few tens of thousands of years. The shorter assessment period, 100 000 years, requires more focus on climate development over the coming tens of thousands of years, including the earliest possibility for permafrost growth and freezing of the engineered system. The handling of climate and climate change in safety assessments must be tailor-made for each repository concept and waste type. However, due to the uncertain future climate development on these vast time scales, all safety assessments for nuclear waste repositories require a range of possible climate scenarios.

Freshly induced short-lived gamma-ray activity as a measure of fission rates in lightly re-irradiated spent fuel

Energy Technology Data Exchange (ETDEWEB)

Kroehnert, H., E-mail: hanna.kroehnert@psi.c [Paul Scherrer Institut (PSI), OPRA-E07, CH-5232 Villigen (Switzerland); Perret, G., E-mail: gregory.perret@psi.c [Paul Scherrer Institut (PSI), OPRA-E07, CH-5232 Villigen (Switzerland); Murphy, M.F., E-mail: mike.murphy@psi.c [Paul Scherrer Institut (PSI), OPRA-E07, CH-5232 Villigen (Switzerland); Chawla, R., E-mail: rakesh.chawla@epfl.c [Paul Scherrer Institut (PSI), OPRA-E07, CH-5232 Villigen (Switzerland); Ecole Polytechnique Federale de Lausanne (EPFL), CH-1015 Lausanne (Switzerland)

2010-12-01

A new measurement technique has been developed to determine fission rates in burnt fuel, following re-irradiation in a zero-power research reactor. The development has been made in the frame of the LIFE-PROTEUS program at the Paul Scherrer Institute, which aims at characterizing the interfaces between fresh and highly burnt fuel assemblies in modern LWRs. To discriminate against the high intrinsic gamma-ray activity of the burnt fuel, the proposed measurement technique uses high-energy gamma-rays, above 2000 keV, emitted by short-lived fission products freshly produced in the fuel. To demonstrate the feasibility of this technique, a fresh UO{sub 2} sample and a 36 GWd/t burnt UO{sub 2} sample were irradiated in the PROTEUS reactor and their gamma-ray activities were recorded directly after irradiation. For both fresh and the burnt fuel samples, relative fission rates were derived for different core positions, based on the short-lived {sup 142}La (2542 keV), {sup 89}Rb (2570 keV), {sup 138}Cs (2640 keV) and {sup 95}Y (3576 keV) gamma-ray lines. Uncertainties on the inter-position fission rate ratios were mainly due to the uncertainties on the net-area of the gamma-ray peaks and were about 1-3% for the fresh sample, and 3-6% for the burnt one. Thus, for the first time, it has been shown that the short-lived gamma-ray activity, induced in burnt fuel by irradiation in a zero-power reactor, can be used as a quantitative measure of the fission rate. For both fresh and burnt fuel, the measured results agreed, within the uncertainties, with Monte Carlo (MCNPX) predictions.

Measurements of neutron cross sections of radioactive waste nuclides

Energy Technology Data Exchange (ETDEWEB)

Katoh, Toshio [Gifu College of Medical Technology, Seki, Gifu (Japan); Harada, Hideo; Nakamura, Shoji; Tanase, Masakazu; Hatsukawa, Yuichi

1998-01-01

Accurate nuclear reaction cross sections of radioactive fission products and transuranic elements are required for research on nuclear transmutation methods in nuclear waste management. Important fission products in the nuclear waste management are {sup 137}Cs, {sup 135}Cs, {sup 90}Sr, {sup 99}Tc and {sup 129}I because of their large fission yields and long half-lives. The present authors have measured the neutron capture cross sections and resonance integrals of {sup 137}Cs, {sup 90}Sr and {sup 99}Tc. The purpose of this study is to measure the neutron capture cross sections and resonance integrals of nuclides, {sup 129}I and {sup 135}Cs accurately. Preliminary experiments were performed by using Rikkyo University Reactor and JRR-3 reactor at Japan Atomic Energy Research Institute (JAERI). Then, it was decided to measure the cross section and resonance integral of {sup 135}Cs by using the JRR-3 Reactor because this measurement required a high flux reactor. On the other hand, those of {sup 129}I were measured at the Rikkyo Reactor because the product nuclides, {sup 130}I and {sup 130m}I, have short half-lives and this reactor is suitable for the study of short lived nuclide. In this report, the measurements of the cross section and resonance integral of {sup 135}Cs are described. To obtain reliable values of the cross section and resonance integral of {sup 135}Cs(n, {gamma}){sup 136}Cs reaction, a quadrupole mass spectrometer was used for the mass analysis of nuclide in the sample. A progress report on the cross section of {sup 134}Cs, a neighbour of {sup 135}Cs, is included in this report. A report on {sup 129}I will be presented in the Report on the Joint-Use of Rikkyo University Reactor. (author)

Tantalum-178 - a short-lived nuclide for nuclear medicine: development of a potential generator system

International Nuclear Information System (INIS)

Neirinckx, R.D.; Jones, A.G.; Davis, M.A.; Harris, G.I.; Holman, B.L.

1978-01-01

We describe a chemical separation that may form the basis of a generator system for the short-lived radionuclide Ta-178 (T/sub 1/2/ = 9 min). The parent nuclide W-178 (T/sub 1/2/ = 21.7 days) is loaded on an anion-exchange column and the daughter eluted with a mixture of dilute hydrochloric acid and hydrogen peroxide. The yields of tantalum and the breakthrough of the tungsten parent as a function of the eluting conditions are discussed, and preliminary animal distribution data are presented for various treatments of the eluant solution

Occupational and Public Exposure During Normal Operation of Radioactive Waste Disposal Facilities

Directory of Open Access Journals (Sweden)

M. V. Vedernikova

2017-01-01

Full Text Available This paper focuses on occupational and public exposure during operation of disposal facilities receiving liquid and solid radioactive waste of various classes and provides a comparative analysis of the relevant doses: actual and calculated at the design stage. Occupational and public exposure study presented in this paper covers normal operations of a radioactive waste disposal facility receiving waste. Results: Analysis of individual and collective occupational doses was performed based on data collected during operation of near-surface disposal facilities for short-lived intermediate-, lowand very low-level waste in France, as well as nearsurface disposal facilities for long-lived waste in Russia. Further analysis of occupational and public doses calculated at the design stage was completed covering a near-surface disposal facility in Belgium and deep disposal facilities in the United Kingdom and the Nizhne-Kansk rock massive (Russia. The results show that engineering and technical solutions enable almost complete elimination of internal occupational exposure, whereas external exposure doses would fall within the range of values typical for a basic nuclear facility. Conclusion: radioactive waste disposal facilities being developed, constructed and operated meet the safety requirements effective in the Russian Federation and consistent with relevant international recommendations. It has been found that individual occupational exposure doses commensurate with those received by personnel of similar facilities abroad. Furthermore, according to the forecasts, mean individual doses for personnel during radioactive waste disposal would be an order of magnitude lower than the dose limit of 20 mSv/year. As for the public exposure, during normal operation, potential impact is virtually impossible by delaminating boundaries of a nuclear facility sanitary protection zone inside which the disposal facility is located and can be solely attributed to the use

Systematics of criticality properties of actinide nuclides and its bearing on the long lived fission waste problem

International Nuclear Information System (INIS)

Srinivasan, M.; Rao, K.S.; Garg, S.B.; Iyengar, P.K.

1989-01-01

This paper reports on a systematic analysis of the criticality parameters of over twenty fissile and fertile isotopes of eight transthorium actinide elements that has been carried out by us. It is observed that K ∞ increases and critical mass decreases monotonically with the fissility parameter (Z 2 /A) of the nuclides. This implies that each and every isotope of transuranic elements such as Np, Am, Cm etc. which are produced as by-products during reactor operation is a more valuable nuclear fuel than the corresponding fissile/fissible isotopes of plutonium. This finding has a profound bearing on the long lived fission waste problem and supports the view that the byproduct actinide elements should be separated from the high level waste stream and recycled back into fission reactors, thereby eliminating one of the commonly voiced concerns regarding the acceptability of nuclear fission power

Criteria of transformation of object ''Ukryttya'' in environmentally safe system

International Nuclear Information System (INIS)

Batyij, V.G.; Jegorov, V.V.; Rud'ko, V.M.; Shcherbyin, V.M.

2015-01-01

The analysis of criteria of division of radioactive wastes (RAW) of object ''Ukryttya'' is executed on short-lived and long-lived, and their activity. It is shown that to short-lived RAW underactive belong and insignificant part of me-dium-activity waste. Hundreds of thousands of m3 of RAW on overhead marks belong to long-lived medium-activity wastes. Organization of burial place of such wastes in stable geological structures is an unrealistic task. It is suggested to create the special depository for such RAW, and buried in stable geological structures high-activity wastes only

The short-lived African turquoise killifish: an emerging experimental model for ageing.

Science.gov (United States)

Kim, Yumi; Nam, Hong Gil; Valenzano, Dario Riccardo

2016-02-01

Human ageing is a fundamental biological process that leads to functional decay, increased risk for various diseases and, ultimately, death. Some of the basic biological mechanisms underlying human ageing are shared with other organisms; thus, animal models have been invaluable in providing key mechanistic and molecular insights into the common bases of biological ageing. In this Review, we briefly summarise the major applications of the most commonly used model organisms adopted in ageing research and highlight their relevance in understanding human ageing. We compare the strengths and limitations of different model organisms and discuss in detail an emerging ageing model, the short-lived African turquoise killifish. We review the recent progress made in using the turquoise killifish to study the biology of ageing and discuss potential future applications of this promising animal model. © 2016. Published by The Company of Biologists Ltd.

Laser generation of proton beams for the production of short-lived positron emitting radioisotopes

International Nuclear Information System (INIS)

Spencer, I.; Ledingham, K.W.D.; Singhal, R.P.; McCanny, T.; McKenna, P.; Clark, E.L.; Krushelnick, K.; Zepf, M.; Beg, F.N.; Tatarakis, M.; Dangor, A.E.; Norreys, P.A.; Clarke, R.J.; Allott, R.M.; Ross, I.N.

2001-01-01

Protons of energies up to 37 MeV have been generated when ultra-intense lasers (up to 10 20 W cm -2 ) interact with hydrogen containing solid targets. These protons can be used to induce nuclear reactions in secondary targets to produce β + -emitting nuclei of relevance to the nuclear medicine community, namely 11 C and 13 N via (p, n) and (p,α) reactions. Activities of the order of 200 kBq have been measured from a single laser pulse interacting with a thin solid target. The possibility of using ultra-intense lasers to produce commercial amounts of short-lived positron emitting sources for positron emission tomography (PET) is discussed

Development of very low-level radioactive waste sequestration process criteria

Energy Technology Data Exchange (ETDEWEB)

Chan, N.; Wong, P., E-mail: nicholas.chan@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

2015-12-15

Segregating radioactive waste at the source and reclassifying radioactive waste to lower waste classes are the key activities to reduce the environmental footprint and long-term liability. In the Canadian Standards Association's radioactive waste classification system, there are 2 sub-classes within low-level radioactive waste: very short-lived radioactive waste and very low-level radioactive waste (VLLW). VLLW has a low hazard potential but is above the Canadian unconditional clearance criteria as set out in Schedule 2 of Nuclear Substances and Devices Regulations. Long-term waste management facilities for VLLW do not require a high degree of containment and isolation. In general, a relatively low-cost near-surface facility with limited regulatory control is suitable for VLLW. At Canadian Nuclear Laboratories' Chalk River Laboratories site an initiative, VLLW Sequestration, was implemented in 2013 to set aside potential VLLW for temporary storage and to be later dispositioned in the planned VLLW facility. As of May 2015, a total of 236m{sup 3} resulting in approximately $1.1 million in total savings have been sequestered. One of the main hurdles in implementing VLLW Sequestration is the development of process criteria. Waste Acceptance Criteria (WAC) are used as a guide or as requirements for determining whether waste is accepted by the waste management facility. Establishment of the process criteria ensures that segregated waste materials have a high likelihood to meet the VLLW WAC and be accepted into the planned VLLW facility. This paper outlines the challenges and various factors which were considered in the development of interim process criteria. (author)

Transmutation of high-level radioactive waste - Perspectives

CERN Document Server

Junghans, Arnd; Grosse, Eckart; Hannaske, Roland; Kögler, Toni; Massarczyk, Ralf; Schwengner, Ronald; Wagner, Andreas

2014-01-01

In a fast neutron spectrum essentially all long-lived actinides (e.g. Plutonium) undergo fission and thus can be transmuted into generally short lived fission products. Innovative nuclear reactor concepts e.g. accelerator driven systems (ADS) are currently in development that foresee a closed fuel cycle. The majority of the fissile nuclides (uranium, plutonium) shall be used for power generation and only fission products will be put into final disposal that needs to last for a historical time scale of only 1000 years. For the transmutation of high-level radioactive waste a lot of research and development is still required. One aspect is the precise knowledge of nuclear data for reactions with fast neutrons. Nuclear reactions relevant for transmutation are being investigated in the framework of the european project ERINDA. First results from the new neutron time-of-flight facility nELBE at Helmholtz-Zentrum Dresden-Rossendorf will be presented.

French people and nuclear wastes

International Nuclear Information System (INIS)

D'Iribarne, Ph.

2005-01-01

On March 21, 2005, the French minister of industry gave to the author of this document, the mission to shade a sociological light on the radioactive wastes perception by French people. The objective of this study was to supply an additional information before the laying down in 2006 of the decisions about the management of high-level and long-lived radioactive wastes. This inquiry, carried out between April 2004 and March 2005, stresses on the knowledge and doubts of the questioned people, on the vision they have of radioactive wastes and of their hazards, and on their opinion about the actors in concern (experts, nuclear companies, government, anti-nuclear groups, public). The last two parts of the report consider the different ways of waste management under study today, and the differences between the opinion of people living close to the Bure site and the opinion of people living in other regions. (J.S.)

The opalinus clay project - disposal of medium and highly-active nuclear wastes

International Nuclear Information System (INIS)

Mueller, U.

2003-01-01

This article describes the project to demonstrate the feasibility of disposing of long-living medium-active and highly-radioactive nuclear wastes in sedimentary rock in Switzerland. The disposal tasks to be carried out are reviewed and the solutions proposed are described, including short-term handling, intermediate storage and final disposal of low, medium and highly-active wastes. The present state of affairs is described and, in particular, the feasibility of implementing a final storage facility in the opalinus clay beds to be found in northern Switzerland. The project for such a facility in the wine-growing area of the canton of Zurich is described in detail, including the storage concept, the technology to be used and operational aspects as well as questions of safety

Determination of k0-factors of short-lived nuclides and application of k0-NAA to selected trace elements

International Nuclear Information System (INIS)

Acharya, R.; Holzbecher, J.; Chatt, A.

2012-01-01

As part of the standardization program of k 0 -based NAA (k 0 -NAA) methods at the Dalhousie University SLOWPOKE-2 reactor (DUSR) facility, the k 0 -factors of 15 analytically important short-lived nuclides (half-life 197 Au). The elemental standards used were prepared mostly from their primary standard solutions. The samples were irradiated in both inner and outer pneumatic sites of the DUSR facility and counted using an HPGe-detector coupled to an ORTEC’s digital gamma-ray spectrometer. The k 0 -factors determined using both inner and outer irradiation sites were found to be within ±5% with respect to either recommended or literature values in most cases. The Z-score values at 95% confidence level were found to be in the range of ±0.03–1.6. The k 0 -NAA method was applied to three different NIST standard reference materials (SRMs) and concentrations of six elements, namely Ag, F, Hf, Rb, Sc, and Se were determined using their short-lived nuclides. The concentrations of these elements were also determined by relative NAA method for comparison purposes.

Climate considerations in long-term safety assessments for nuclear waste repositories.

Science.gov (United States)

Näslund, Jens-Ove; Brandefelt, Jenny; Liljedahl, Lillemor Claesson

2013-05-01

For a deep geological repository for spent nuclear fuel planned in Sweden, the safety assessment covers up to 1 million years. Climate scenarios range from high-end global warming for the coming 100 000 years, through deep permafrost, to large ice sheets during glacial conditions. In contrast, in an existing repository for short-lived waste the activity decays to low levels within a few tens of thousands of years. The shorter assessment period, 100 000 years, requires more focus on climate development over the coming tens of thousands of years, including the earliest possibility for permafrost growth and freezing of the engineered system. The handling of climate and climate change in safety assessments must be tailor-made for each repository concept and waste type. However, due to the uncertain future climate development on these vast time scales, all safety assessments for nuclear waste repositories require a range of possible climate scenarios.

Site investigations for repositories for solid radioactive wastes in shallow ground

International Nuclear Information System (INIS)

1982-01-01

This report provides an overview and technical guidelines for investigations on a national level for the selection and confirmation of a repository site that will provide adequately safe performance for disposal of solid radioactive wastes that are low- or intermediate-level and short-lived. It also provides basic information on technical activities to be undertaken and on techniques that are available for such investigations in the various steps in selecting suitable sites. The report supplements the information given in Shallow Ground Disposal of Radioactive Wastes: A Guidebook, IAEA Safety Series No. 53 (1981). This report focuses mainly on different aspects of earth sciences and the various investigative techniques relative to earth sciences that may be necessary for site investigations. Some major related studies in other fields are discussed briefly. It is assumed that no previous investigations have been undertaken, and the report proceeds through area site selection to the stage when the site is confirmed as suitable for a waste repository

Site investigations for repositories for solid radioactive wastes in shallow ground

Energy Technology Data Exchange (ETDEWEB)

1982-01-01

This report provides an overview and technical guidelines for investigations on a national level for the selection and confirmation of a repository site that will provide adequately safe performance for disposal of solid radioactive wastes that are low- or intermediate-level and short-lived. It also provides basic information on technical activities to be undertaken and on techniques that are available for such investigations in the various steps in selecting suitable sites. The report supplements the information given in Shallow Ground Disposal of Radioactive Wastes: A Guidebook, IAEA Safety Series No. 53 (1981). This report focuses mainly on different aspects of earth sciences and the various investigative techniques relative to earth sciences that may be necessary for site investigations. Some major related studies in other fields are discussed briefly. It is assumed that no previous investigations have been undertaken, and the report proceeds through area site selection to the stage when the site is confirmed as suitable for a waste repository.

Measurement of formation cross sections producing short-lived nuclei by 14 MeV neutrons. Pr, Ba, Ce, Sm, W, Sn, Hf

International Nuclear Information System (INIS)

Murahira, S.; Satoh, Y.; Honda, N.; Shibata, M.; Yamamoto, H.; Kawade, K.; Takahashi, A.; Iida, T.

1996-01-01

Thirteen neutron activation cross sections for (n,2n), (n,p), (n,np) and (n,α) reactions producing short-lived nuclei with half-lives between 56 s and 24 min were measured in the energy range from 13.4 MeV to 14.9 MeV for Pr, Ba, Ce, Sm, W, Sn and Hf. The cross sections of 179 Hf(n,np) 178m Lu and 180 Hf(n,p) 180 Lu were measured for the first time. (author)

Biogenic carbon in combustible waste: waste composition, variability and measurement uncertainty.

Science.gov (United States)

Larsen, Anna W; Fuglsang, Karsten; Pedersen, Niels H; Fellner, Johann; Rechberger, Helmut; Astrup, Thomas

2013-10-01

Obtaining accurate data for the contents of biogenic and fossil carbon in thermally-treated waste is essential for determination of the environmental profile of waste technologies. Relations between the variability of waste chemistry and the biogenic and fossil carbon emissions are not well described in the literature. This study addressed the variability of biogenic and fossil carbon in combustible waste received at a municipal solid waste incinerator. Two approaches were compared: (1) radiocarbon dating ((14)C analysis) of carbon dioxide sampled from the flue gas, and (2) mass and energy balance calculations using the balance method. The ability of the two approaches to accurately describe short-term day-to-day variations in carbon emissions, and to which extent these short-term variations could be explained by controlled changes in waste input composition, was evaluated. Finally, the measurement uncertainties related to the two approaches were determined. Two flue gas sampling campaigns at a full-scale waste incinerator were included: one during normal operation and one with controlled waste input. Estimation of carbon contents in the main waste types received was included. Both the (14)C method and the balance method represented promising methods able to provide good quality data for the ratio between biogenic and fossil carbon in waste. The relative uncertainty in the individual experiments was 7-10% (95% confidence interval) for the (14)C method and slightly lower for the balance method.

Long-term safety of the maintenance and decommissioning waste of the encapsulation plant

International Nuclear Information System (INIS)

Nummi, O.; Kylloenen, J.; Eurajoki, T.

2012-12-01

This report, Long-term safety of the maintenance and decommissioning waste of the encapsulation plant, presents the disposal concept for the low and intermediate level waste (L/ILW) that is generated during the operation and decommissioning of the encapsulation plant, and assesses the long-term safety of the disposal of the waste. Radioactive waste originates from the spent nuclear fuel transferred and dried in the encapsulation plant. Radioactive waste accumulates also in the maintenance of the components and systems of the encapsulation plant. The waste is collected, exempted from control if possible and treated for final disposal if necessary. The waste is disposed of in the L/ILW hall which is currently planned to be located at a depth of -180 meters along the access tunnel to the repository for spent fuel. The main engineered barrier in the L/ILW hall is a concrete basin that encases the dried liquid waste. The safety concept of L/ILW disposal is based on the slow release of radioactivity from the L/ILW hall and its limited transport through the bedrock into biosphere. The release and transport of the radioactivity is described by the assessment scenarios, which include expected evolution and unlikely events affecting the long-term safety. The scenarios act as guidelines according to which the conceptual and mathematical models are formed. The long-term safety of the L/ILW hall is assessed using deterministic and probabilistic modeling. Special issues such as human intrusion and radiation effects on other biota are also assessed. The most significant contributor to the dose rates is the short-lived radionuclide 90 Sr followed by long-lived nuclides 129 I and 108 mAg. The annual doses to the public, and release rates of radioactive substances stay below the regulatory constraints in all analyzed scenarios. (orig.)

Transmutation of nuclear waste. Status report RAS programme 1993: Recycling and transmutation of actinides and fission products

Energy Technology Data Exchange (ETDEWEB)

Abrahams, K; Bultman, J H; Cordfunke, E H.P.; Gruppelaar, H; Janssen, A J; Franken, W M.P.; Klippel, K T; Kloosterman, J L; Konings, R J.M.; Smit, J

1994-11-01

The term ``nuclear transmutation`` means a conversion of long-lived radioactive nuclides into short-lived or stable nuclides and ``recycling`` means re-use of fissile material to generate energy in power reactors. With these two processes a reduction of the radiotoxicity and of its duration may be achieved, thus reducing the potential hazard to future generations. Firstly, the report gives a survey of the present situation regarding nuclear waste: its components, how the waste is produced in current LWR and possible options for interim and final storage. Then the objective of the RAS programme, the working methods and the state of the art of the research are considered. Two chapters deal with preliminary results of national and international research. A rather tentative prediction for the future is formulated. Some conclusions are drawn: It seems to be in the best interests of the Netherlands to continue the established line of reprocessing nuclear waste, should new reactors be introduced. It may be advisable to make international agreements so that in the future fission products will contain as few traces of transuranic actinides and long-lived components as possible. Consequently, nuclear waste would become cleaner in terms of long-lived components. For the transmutation of products separated in foreign countries, the Netherlands could pursue an active policy, perform research and also consider the use of MOX fuel in future Dutch reactors. Further contributions towards the solution of these problems can only be made by the Netherlands on an international level. As such, the research and study performed within the framework of the RAS-programme represents a useful international contribution. Finally, the choice of a new generation of nuclear reactors should be made not based only on the safety aspects, but also on the extent of waste production and on the transmutation possibilities (application of MOX, etc.). (orig./HP).

Log live high activity radioactive wastes / Researches and results law of the 30 December 1991. Separation and transmutation of long lived radionuclides; Les dechets radioactifs a haute activite et a vie longue / recherches et resultats Loi du 30 decembre 1991. Separation et transmutation des radionucleides a vie longue

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-12-15

The law of the 30 December 1991 on the high activity long lived radioactive wastes reached the end. This synthesis final document presents the scientific and technological results, obtained still the end of 2005, on the separation and the transmutation of long lived radionuclides of high activity long lived radioactive wastes. It is organized in five chapters: a presentation of the context and the historical aspects, the researches, the objectives and the strategy of the axis 1, the researches results on the advanced separation, the researches results on the transmutation, the scenario of separation-transmutation and their environmental, technical and economical impacts. (A.L.B.)

Nuclear biomedical and hospital waste management at the University of Brussels (VUB): optimization in the Belgian context

International Nuclear Information System (INIS)

Eggermont, G.; Covens, P.

2002-01-01

Low level nuclear waste (LLW) from biomedical research laboratories and from hospitals has specific characteristics, requiring a different management than the LLW from nuclear energy. Biomedical waste generally does not contain emitters and essentially consists of short-lived β/γ-emitters and a range of pure β-emitters, which are difficult to measure. Except for 3 H and 1 4C , the radionuclides found in biomedical waste have half-lives less then 100 days and hence do not require nuclear disposal. Limited quantities of accelerator activation products (mainly 6 5Z n and 6 0C o) and compact sealed sources of 6 0C o, 1 37C s, 2 26R a and 1 92I r form the only exceptions. National nuclear waste agencies typically do not have a specific policy for treatment and disposal of this type of LLW. In 2001 new price increases were announced for specific categories of this waste. They were implemented by NIRAS/ONDRAF early 2002. The major universities and academic hospitals expressed concern. The Health Council has considered the problem and has recently recommended to the authorities a set of measures to prevent non authorised liberation of this waste. Moreover non-nuclear waste companies have noticed a considerable growing inventory of radioactivity in incoming waste transports before treatment. A variety of radionuclides and activities were found in a diversity of origins from municipal waste over medical waste to industrial waste. Dismantling of accelerators and their shielding could add considerable amounts of waste. Due to the escalating costs and the lack of acceptance of near-surface disposal facilities, the university of Brussels (VUB) and its hospital, have developed a successful on-site waste decay storage program in collaboration with Canberra Europe, which is discussed hereafter

Climate response to projected changes in short-lived species under an A1B scenario from 2000-2050 in the GISS climate model

Energy Technology Data Exchange (ETDEWEB)

Menon, Surabi; Shindell, Drew T.; Faluvegi, Greg; Bauer, Susanne E.; Koch, Dorothy M.; Unger, Nadine; Menon, Surabi; Miller, Ron L.; Schmidt, Gavin A.; Streets, David G.

2007-03-26

We investigate the climate forcing from and response to projected changes in short-lived species and methane under the A1B scenario from 2000-2050 in the GISS climate model. We present a meta-analysis of new simulations of the full evolution of gas and aerosol species and other existing experiments with variations of the same model. The comparison highlights the importance of several physical processes in determining radiative forcing, especially the effect of climate change on stratosphere-troposphere exchange, heterogeneous sulfate-nitrate-dust chemistry, and changes in methane oxidation and natural emissions. However, the impact of these fairly uncertain physical effects is substantially less than the difference between alternative emission scenarios for all short-lived species. The net global mean annual average direct radiative forcing from the short-lived species is .02 W/m{sup 2} or less in our projections, as substantial positive ozone forcing is largely offset by negative aerosol direct forcing. Since aerosol reductions also lead to a reduced indirect effect, the global mean surface temperature warms by {approx}0.07 C by 2030 and {approx}0.13 C by 2050, adding 19% and 17%, respectively, to the warming induced by long-lived greenhouse gases. Regional direct forcings are large, up to 3.8 W/m{sup 2}. The ensemble-mean climate response shows little regional correlation with the spatial pattern of the forcing, however, suggesting that oceanic and atmospheric mixing generally overwhelms the effect of even large localized forcings. Exceptions are the polar regions, where ozone and aerosols may induce substantial seasonal climate changes.

Waste Isolation Pilot Plant transuranic wastes experimental characterization program: executive summary

International Nuclear Information System (INIS)

Molecke, M.A.

1978-11-01

A general overview of the Waste Isolation Pilot Plant transuranic wastes experimental characterization program is presented. Objectives and outstanding concerns of this program are discussed. Characteristics of transuranic wastes are also described. Concerns for the terminal isolation of such wastes in a deep bedded salt facility are divided into two phases, those during the short-term operational phase of the facility, and those potentially occurring in the long-term, after decommissioning of the repository. An inclusive summary covering individual studies, their importance to the Waste Isolation Pilot Plant, investigators, general milestones, and comments are presented

Disposal of radioactive waste in Swedish crystalline rocks

International Nuclear Information System (INIS)

Greis Dahlberg, Christina; Wikberg, Peter

2015-01-01

SKB, Swedish Nuclear Fuel and Waste Management Company is tasked with managing Swedish nuclear and radioactive waste. Crystalline rock is the obvious alternative for deep geological disposal in Sweden. SKB is, since 1988, operating a near surface repository for short-lived low and intermediate-level waste, SFR. The waste in SFR comprises operational and decommissioning waste from nuclear plants, industrial waste, research-related waste and medical waste. Spent nuclear fuel is currently stored in an interim facility while waiting for a license to construct a deep geological repository. The Swedish long-lived low and intermediate-level waste consists mainly of BWR control rods, reactor internals and legacy waste from early research in the Swedish nuclear programs. The current plan is to dispose of this waste in a separate deep geological repository, SFL, sometimes after 2045. Understanding of the rock properties is the basis for the design of the repository concepts. Swedish crystalline rock is mechanical stable and suitable for underground constructions. The Spent Fuel Repository is planned at approximately 500 meters depth in the rock at the Forsmark site. The host rock will keep the spent fuel isolated from human and near-surface environment. The rock will also provide the stable chemical and hydraulic conditions that make it possible to select suitable technical barriers to support the containment provided by the rock. A very long lasting canister is necessary to avoid release and transport of radionuclides through water conducting fractures in the rock. A canister designed for the Swedish rock, consists of a tight, 5 cm thick corrosion barrier of copper and a load-bearing insert of cast iron. To restrict the water flow around the canister and by that prevent fast corrosion, a bentonite buffer will surround the canister. Secondary, the bentonite buffer will retard a potential release by its strong sorption of radionuclides. The SFR repository is situated in

Disposal of radioactive waste in Swedish crystalline rocks

Energy Technology Data Exchange (ETDEWEB)

Greis Dahlberg, Christina; Wikberg, Peter [Svensk Kaernbraenslehantering AB, Stockholm (Sweden)

2015-07-01

SKB, Swedish Nuclear Fuel and Waste Management Company is tasked with managing Swedish nuclear and radioactive waste. Crystalline rock is the obvious alternative for deep geological disposal in Sweden. SKB is, since 1988, operating a near surface repository for short-lived low and intermediate-level waste, SFR. The waste in SFR comprises operational and decommissioning waste from nuclear plants, industrial waste, research-related waste and medical waste. Spent nuclear fuel is currently stored in an interim facility while waiting for a license to construct a deep geological repository. The Swedish long-lived low and intermediate-level waste consists mainly of BWR control rods, reactor internals and legacy waste from early research in the Swedish nuclear programs. The current plan is to dispose of this waste in a separate deep geological repository, SFL, sometimes after 2045. Understanding of the rock properties is the basis for the design of the repository concepts. Swedish crystalline rock is mechanical stable and suitable for underground constructions. The Spent Fuel Repository is planned at approximately 500 meters depth in the rock at the Forsmark site. The host rock will keep the spent fuel isolated from human and near-surface environment. The rock will also provide the stable chemical and hydraulic conditions that make it possible to select suitable technical barriers to support the containment provided by the rock. A very long lasting canister is necessary to avoid release and transport of radionuclides through water conducting fractures in the rock. A canister designed for the Swedish rock, consists of a tight, 5 cm thick corrosion barrier of copper and a load-bearing insert of cast iron. To restrict the water flow around the canister and by that prevent fast corrosion, a bentonite buffer will surround the canister. Secondary, the bentonite buffer will retard a potential release by its strong sorption of radionuclides. The SFR repository is situated in

New three-count technique for short-lived radon decay products in air

International Nuclear Information System (INIS)

Tian Deyuan; Lu Zhizhao

1998-01-01

Up to the present, radon and its short-lived decay products in air are usually monitored by means of a detection. But radon progeny, including RaB ( 214 Pb) and RaC ( 214 Bi) which are β and γ emitters, contribute about 90% to the equilibrium equivalent radon concentration (EECRn). Therefore, this paper introduces a new three-count technique by a β detector in the light of radioactive decay law and its boundary conditions during sampling and counting times to solve the Bateman equation. β (even low level β) instruments have been fairly popularized domestically and internationally. It can be used not only as an instrument for radon and its daughters in air, but also as a monitor for β airborne activity in the environment. This new method taps further the latent power of the present instrument and realizes various uses for a unit. (author)

Present situation and issues for the French radioactive waste management agency

International Nuclear Information System (INIS)

Dupuis, M.C.

2009-01-01

This series of slides makes a status of the radioactive waste management in France: 1 - Planned disposal facilities: A - Low level long lived waste (LL-LL: Graphite Waste And Radium Bearing Waste): Implementation within a shallow clay formation (between 15 and 200 m in depth). For graphite waste: a 'repository with an intact cover' as a reference option. For radium-bearing waste: a 'repository with a reworked cover' under investigation. The required footprint on ground surface is in the order of 100 ha. Siting approach: June 2, 2008: letter from the Minister of State to the Chairman of ANDRA; June 2008: file addressed by ANDRA to the mayors of 3,115 communes. Until the end of October 2008: expression of interest by local communities. Possibility to confirm their application in late 2010. December 2008: assessment report by ANDRA and proposal of ranked zones to the government. Beginning of 2009: government decision concerning the pre-selection still pending. 2009-2010: geological surveys, consultations, territorial projects. B - High level and Intermediate level long lived waste (HL and IL-LL): Preparing disposal in a clay formation. 2012: public debate, 2013: site selection, 2015: application, 2025: start up. The Meuse Haute Marne Underground Research Laboratory Siting: the disposal facility (drilling campaigns), Construction of a Visitors' Centre designed to present the waste-repository project and its technological aspect. Inauguration scheduled in June 2009. 2 - Operated disposal facilities: A - Low and intermediate level short lived waste (LIL-SL) and Very low level waste (VLL). LIL-SL Manche Centre: 1969: start up, 1994: end of operation, 2003: institutional control period, Disposed volume (1969-1994): 527,000 m 3 , Impact of the facility ∼0,65 μSv/year (2008). Institutional control period monitoring: Radiological and chemical monitoring (Discharges, Underground water, Surface water), Capping system monitoring (Water-tightness performances, Rainfall water

Continuous monitoring α-activity on aerosol filters by the pseudo-coincidence-technique. Explicitly taking into account the short lived Po-218 activity; Kontinuierliche Ueberwachung der α-Aktivitaet eines Aerosolfilters mit der Pseudokoinzidenzmesstechnik. Explizite Beruecksichtigung der kurzlebigen Po-218 Aktivitaetsbeitraaege

Energy Technology Data Exchange (ETDEWEB)

Kraut, W.; Schwarz, W. [Duale Hochschule Baden-Wuerttemberg (DHBW), Karlsruhe (Germany). Studiengang Sicherheitswesen; Kraut, B. [Berthold Technologies GmbH und Co.KG, Bad Wildbad (Germany)

2015-07-01

Pseudo-coincidence-technique is applied to continuous monitoring of α-activity on aerosolfilters by proportional counters. Filter activity can markedly increase or decrease by changing air conditions especially by the amount of short lived Po-218 activity. Conditions of constant proportions of activity concentrations for the short lived species for operating this technique are seldom fulfilled. The dynamic behavior of artificial (long lived) and natural (short lived) activity is mathematically modelled and the measured moving count rates are analyzed under this model by a multivariate regression analysis for activity concentrations of artificial resp. short lived activity. Results are compared to standard recommendations of DIN ISO 11929.

Disposal of mixed radioactive and chemical waste

International Nuclear Information System (INIS)

Moghissi, A.A.

1986-01-01

The treatment of waste by dilution was practiced as long as nature provided sufficient unpolluted air, water, and land. The necessity for treatment, including containment and disposal of wastes is, however, relatively new. Initially, waste products from manufacturing processes were looked upon as a potential resource. The industries of Western Europe, short of raw materials, tried to recover as many chemical compounds as possible from industrial waste. However, the availability of abundant and cheap petroleum during the fifties changes this practice, at least for a short period

Radioactive waste safety appraisal. An international peer review of the licence application for the Australian near surface radioactive waste disposal facility. Report of the IAEA International Review Team

International Nuclear Information System (INIS)

2004-05-01

Radioactive waste has been generated in Australia for a number of decades from the production and use of radioactive materials in medicine and industry, from the processing of various minerals containing natural radionuclides and from various research activities. It has been decided in the overall interest of safety and security to develop a radioactive waste disposal facility to accommodate the low level and short lived intermediate level waste, which make up the bulk of the waste, other than mining and minerals processing residues. A site selection process has been undertaken and environmental impact statement report prepared and approved. A licence application has been submitted to the national nuclear regulatory authority, the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) for siting, construction and operation of the facility. In order to assist the CEO of ARPANSA with his deliberations in this regard a request was made to the IAEA, in terms of its statutory mandate to establish international safety standards for radioactive waste safety and to provide for their application, to undertake an international peer review of the licence application and to advise the CEO accordingly. The outcome and recommendations of this peer review are presented in the report

Radioactivity of radon and its short-lived decay products in room air, 2

International Nuclear Information System (INIS)

Shimo, Michikuni; Katoh, Takao

1983-01-01

In the reactor room of the Kyoto University Research Reactor Institute, the measurements of radon (Rn) and its short-lived decay products (Rn-Dts) were carried out under ventilated and non-ventilated conditions. The indoor activities were equal to outdoor ones under ventilated condition and those activities increased till about 10 times of outdoors under non-ventilated condition. We attempted to explain these results on a basis of a simple model. The calculations were performed taking into account: (1) supply of Rn and Rn-Dts from outdoor, (2) the emanation rate of Rn from the wall materials of building, (3) the removal rate of Rn-Dts by ventilation and wall deposition, and (4) the attachment rate of unattached atom to aerosols. In addition, natural ventilation were considered during periods without artificial ventilation. (author)

Simulation of radon short lived decay daughters' inhalation using the lung compartmental model

International Nuclear Information System (INIS)

Tomulescu, Vlad C.

2002-01-01

Radon and its short-lived decay daughters are the main source of radiation on natural ways for population. The radon gas, released from soil, water or construction materials is producing by radioactive decay the following solid daughters: Po-218, Bi-214, Pb-214, and Po-214, which can attach to aerosols, and consequently penetrate the organism by inhalation. The human respiratory tract can be approximated by aid of a compartment model that takes into account the different anatomical structures exposed to contamination and irradiation, as well as the respective physiological processes. This model is associated to a mathematical equation system that describes the behavior of the radioactive material inside the body. The results represent the dose equivalent on different organs and tissues, as a function of subject and the activity performed in contaminating environment. (author)

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

Detection of 210Po on filter papers 16 years after use for the collection of short-lived radon progeny in a room

International Nuclear Information System (INIS)

Abu-Jarad, F.; Fazal-ur-Rehman

2003-01-01

Radon gas was allowed to accumulate in its radium source and then injected into a 36 m 3 test room, resulting in an initial radon concentration of 15 kBq m -3 . Filter papers were used to collect the short-lived radon progeny and thus to measure the Potential Alpha Energy Concentration (PAEC) in-situ in the year 1984 at different times and conditions according to the experimental design. The radon progeny collected on the filter papers were studied as a function of aerosol particle concentration ranging from 10 2 -10 5 particles cm -3 in three different experiments. The highest aerosol particle concentration was generated by indoor cigarette smoking. Those filters were stored after the experiment, and were used after 16 years to study the activity of the radon long-lived alpha emitter progeny, 210 Po (T 1/2 =138 days). This isotope is separated from the short-lived progeny by 210 Pb beta emitter with 22.3 years half-life. After 16 years' storage of these filters, each filter paper was sandwiched and wrapped between two CR-39 nuclear track detectors, to put the detectors in contact with the surfaces of different filters, for 337 days. Correlation between the PAEC measured using filter papers in the year 1984 and the activity of long-lived alpha emitter 210 Po on the same filter papers measured in the year 2000 were studied. The results of the 210 Po activity showed a very good correlation of 0.92 with the PAEC 16 years ago. The results also depict that the PAEC and 210 Po activity in indoor air increased with the increase of aerosol particle concentration, which shows the attachment of short-lived radon progeny with the aerosol particles. The experiment proves that indoor cigarette smoking is a major source of aerosol particles carrying radon progeny and, thus, indoor cigarette smoking is an additional source of internal radiation hazard to the occupants whether smoker or non-smoker

Development of characterization methods applied to radioactive wastes and waste packages

International Nuclear Information System (INIS)

Guy, C.; Bienvenu, Ph.; Comte, J.; Excoffier, E.; Dodi, A.; Gal, O.; Gmar, M.; Jeanneau, F.; Poumarede, B.; Tola, F.; Moulin, V.; Jallu, F.; Lyoussi, A.; Ma, J.L.; Oriol, L.; Passard, Ch.; Perot, B.; Pettier, J.L.; Raoux, A.C.; Thierry, R.

2004-01-01

This document is a compilation of R and D studies carried out in the framework of the axis 3 of the December 1991 law about the conditioning and storage of high-level and long lived radioactive wastes and waste packages, and relative to the methods of characterization of these wastes. This R and D work has permitted to implement and qualify new methods (characterization of long-lived radioelements, high energy imaging..) and also to improve the existing methods by lowering detection limits and reducing uncertainties of measured data. This document is the result of the scientific production of several CEA laboratories that use complementary techniques: destructive methods and radiochemical analyses, photo-fission and active photonic interrogation, high energy imaging systems, neutron interrogation, gamma spectroscopy and active and passive imaging techniques. (J.S.)

Conceptual design and cost inputs associated with co-disposal of the spent fuel and long lived radioactive wastes in the deep geologic disposal facility

International Nuclear Information System (INIS)

Fako, R.; Sociu, F.; Nicolae, R.; Barariu, G

2013-01-01

The paper aims to be an integrated approach for the containment and isolation of spent fuel and / or long lived radioactive wastes in a Deep Geologic Repository in Romania. Several scenarios could be defined for the management of spent fuel and long lived radioactive waste in Romania considering many specific constraints in Romania (political, geological, economic, demographic, etc.). This paper intends to be an upgrade of several Research, Development and Demonstration (RD&D) works performed by SITON specialists on this subject, taking into account also the conclusions of the Workshop ôCost estimation on spent nuclear fuel disposal in Romaniaö organized by IAEA in cooperation with ANDR at the beginning of this year in Romania.This paper is, also, addressed to decision makers with target on to adopt the best strategy for construction of Deep Geologic Repository in Romania. (authors)

Harvard-MIT research program in short-lived radiopharmaceuticals. Progress report, March 1, 1985-February 28, 1986

International Nuclear Information System (INIS)

1986-03-01

The Harvard-MIT Research Program in Short-Lived Radiopharmaceuticals was established in 1977 to foster interaction among groups working at Harvard Medical School, the Massachusetts Institute of Technology and the Massachusetts General Hospital in fields related to radiopharmaceutical chemistry. From these collaborations and building upon the special, but different, strengths of the participating individuals, laboratories and institutions, it was hoped that original approaches would be found for the design of new, clinically useful, labeled compounds. We believe that examination of the record demonstrates that this has been a fruitful alliance

Harvard-MIT research program in short-lived radiopharmaceuticals. Progress report, March 1, 1983-February 29, 1984

International Nuclear Information System (INIS)

Adelstein, S.J.; Brownell, G.L.

1984-02-01

This report describes research efforts towards the achievement of a clearer understanding of the solution chemistry of technetium in order to facilitate the design of future clinical agents labeled with Tc-99m, the development of new receptor binding radiopharmaceuticals for the in vivo assessment of insulin receptors and for imaging the adrenal medulla and the brain, the examination of the utility of monoclonal antibodies and liposomes in the design of radiopharmaceuticals for diagnosis and therapy, and the synthesis of short-lived positron-emitting radiopharmaceuticals for transverse imaging of regional physiological processes

Waste Package Lifting Calculation

International Nuclear Information System (INIS)

H. Marr

2000-01-01

The objective of this calculation is to evaluate the structural response of the waste package during the horizontal and vertical lifting operations in order to support the waste package lifting feature design. The scope of this calculation includes the evaluation of the 21 PWR UCF (pressurized water reactor uncanistered fuel) waste package, naval waste package, 5 DHLW/DOE SNF (defense high-level waste/Department of Energy spent nuclear fuel)--short waste package, and 44 BWR (boiling water reactor) UCF waste package. Procedure AP-3.12Q, Revision 0, ICN 0, calculations, is used to develop and document this calculation

Amount, disposal and relative toxicity of long-lived fission products and actinides in the radioactive wastes of the nuclear fuel cycles

International Nuclear Information System (INIS)

Haug, H.O.

1975-11-01

A review is presented on the magnitude of the long-term problems of radioactive wastes from the nuclear power industry of the FRG (and Western Europe). The production of long-lived fission products and actinides has been calculated for several fuel types of the uranium-plutonium and thorium-uranium fuel cycles and related to a prediction of the development and share of LWR, FBR and HTGR. The quantities and concentrations of actinides, the radioactivity and relative toxicity index of the wastes of reprocessing (and fuel refabrication) and their changes by radioactive decay are presented. The radiotoxicity of the nuclide inventory of the solidified high-level wastes have been compared with naturally occuring uranium ores. On the long term (>10 3 years) the radiotoxicity level of the total area of the final repository in deep geological formation does not result in a significantly higher radiotoxicity level than an uranium ore deposit of low uranium content. Also discussed have been the chemical separation of the actinides from high-level wastes and recycling in fission reactors. (orig.) [de

Radioactive waste management in Sweden experiences and plans

International Nuclear Information System (INIS)

Wikstroem, M.

1999-01-01

Since some years, the necessary facilities are in operation in Sweden for the safe transport and storage of radioactive waste and spent fuel from nuclear power production. These include a final repository, SFR, for short-lived low and intermediate level waste, a central interim storage facility, CLAB, for spent fuel and a sea-based transport system. The experiences from the operation of these facilities have generally been very good. The next step is the development of an encapsulation facility and a deep repository for the spent nuclear fuel. R and D-work on direct disposal have been conducted in Sweden for more than 20 years. In the preferred method the spent fuel will be encapsulated in a copper canister with a steel internal structure, and the canister will then be disposed of at about 500 metres depth in the Swedish bedrock. The siting and design of the encapsulation facility and the deep repository is now in progress. (author)

Concerted action on the retrievability of long lived radioactive waste in deep underground repositories - progress to date

International Nuclear Information System (INIS)

Dodd, D.H.

2000-01-01

Within the EURATOM Framework Programme: Nuclear Fission Safety, a Concerted Action on the retrievability of long lived radioactive waste in deep underground repositories is being carried out. This Concerted Action commenced on the 1st of January 1998 and involves experts from nine different European countries. The Concerted Action will be completed by the 31st of December 1999. This paper gives a brief overview of the objectives of the Concerted Action, the work programme that has been defined to meet these objectives, the work performed to date, and the remaining work programme. (author)

Short-chain chlorinated paraffins in soil, paddy seeds (Oryza sativa) and snails (Ampullariidae) in an e-waste dismantling area in China: Homologue group pattern, spatial distribution and risk assessment.

Science.gov (United States)

Yuan, Bo; Fu, Jianjie; Wang, Yawei; Jiang, Guibin

2017-01-01

Short-chain chlorinated paraffins (SCCPs) in multi-environmental matrices are studied in Taizhou, Zhejiang Province, China, which is a notorious e-waste dismantling area. The investigated matrices consist of paddy field soil, paddy seeds (Oryza sativa, separated into hulls and rice unpolished) and apple snails (Ampullariidae, inhabiting the paddy fields). The sampling area covered a 65-km radius around the contamination center. C 10 and C 11 are the two predominant homologue groups in the area, accounting for about 35.7% and 33.0% of total SCCPs, respectively. SCCPs in snails and hulls are generally higher than in soil samples (30.4-530 ng/g dw), and SCCPs in hulls are approximate five times higher than in corresponding rice samples (4.90-55.1 ng/g dw). Homologue pattern analysis indicates that paddy seeds (both hull and rice) tend to accumulate relatively high volatile SCCP homologues, especially the ones with shorter carbon chain length, while snails tend to accumulate relatively high lipophilic homologues, especially the ones with more substituted chlorines. SCCPs in both paddy seeds and snails are linearly related to those in the soil. The e-waste dismantling area, which covers a radius of approximate 20 km, shows higher pollution levels for SCCPs according to their spatial distribution in four matrices. The preliminary assessment indicates that SCCP levels in local soils pose no significant ecological risk for soil dwelling organisms, but higher risks from dietary exposure of SCCPs are suspected for people living in e-waste dismantling area. Copyright © 2016 Elsevier Ltd. All rights reserved.

Impact on short-lived climate forcers increases projected warming due to deforestation.

Science.gov (United States)

Scott, C E; Monks, S A; Spracklen, D V; Arnold, S R; Forster, P M; Rap, A; Äijälä, M; Artaxo, P; Carslaw, K S; Chipperfield, M P; Ehn, M; Gilardoni, S; Heikkinen, L; Kulmala, M; Petäjä, T; Reddington, C L S; Rizzo, L V; Swietlicki, E; Vignati, E; Wilson, C

2018-01-11

The climate impact of deforestation depends on the relative strength of several biogeochemical and biogeophysical effects. In addition to affecting the exchange of carbon dioxide (CO 2 ) and moisture with the atmosphere and surface albedo, vegetation emits biogenic volatile organic compounds (BVOCs) that alter the formation of short-lived climate forcers (SLCFs), which include aerosol, ozone and methane. Here we show that a scenario of complete global deforestation results in a net positive radiative forcing (RF; 0.12 W m -2 ) from SLCFs, with the negative RF from decreases in ozone and methane concentrations partially offsetting the positive aerosol RF. Combining RFs due to CO 2 , surface albedo and SLCFs suggests that global deforestation could cause 0.8 K warming after 100 years, with SLCFs contributing 8% of the effect. However, deforestation as projected by the RCP8.5 scenario leads to zero net RF from SLCF, primarily due to nonlinearities in the aerosol indirect effect.

National Inventory of radioactive materials and wastes. The 2015 essentials. Synthesis report for 2015. 2015 descriptive catalogue of families. 2015 geographical inventory. The focus on 2015

International Nuclear Information System (INIS)

2015-03-01

This huge publication gathers several reports. He first one (The essentials) presents the stakes and principles of the management of radioactive materials and wastes, the inventory of stocks of radioactive wastes at the end of 2013 and the inventory of stocks of radioactive materials at the same date, discusses projected quantities of radioactive materials and wastes on the basis of industrial scenarios, and proposes prospective inventories. The second one is a synthesis report which addresses radioactive materials and wastes and their management (origins, classification, peculiar cases, general management principles), the general results (for radioactive materials, for radioactive wastes, perspective beyond 2030, warehousing and storages of radioactive materials and wastes), detailed results for different sectors (electronuclear, research, defence, non electronuclear industry, medicine), historical situations (storage centres for conventional wastes, historic on-site storages, storages of high natural radioactivity wastes, mining sites, sites contaminated by radioactivity, submerged wastes). It also proposes 6 thematic files: existing and projected solutions in France for the management of the different types of radioactive wastes on the long term, objectives and techniques of waste processing and packaging, dismantling of nuclear installations and decontamination of sites polluted by radioactivity, management of used radioactive sources, the case of high natural radioactivity wastes, foreign inventory of radioactive wastes. The next report addresses issues of waste classification (origin, management, family sheet of radioactive wastes, presentation of the different families (shapes, packaging, quantities, and so on): high-level, intermediate-level and long-lived, low and intermediate-level and short-lived, low-level and long-lived, very low-level, and others. Appendices notably indicate locations. The next report, after a recall on classification, origin and

Training waste generators: The first responder in proper waste management

International Nuclear Information System (INIS)

Jones, E.

1989-01-01

Dealing with waste effectively requires a ''cradle to grave'' approach to waste management. The first step in that chain of custody is the waste generator. The waste generator plays the key role in the correct identification, packaging, and disposal of waste. The Technical Resources and Training Section at the Oak Ridge National Laboratory (ORNL) has developed several short training programs for waste generators. This training presents a consistent approach to proper handling of waste within the ORNL waste management system. This training has been developed for generators of solid low-level radioactive waste, hazardous and mixed waste, and transuranic waste. In addition to the above, a Waste Minimization training program has been developed for use by all organizations at ORNL who generate any type of hazardous waste. These training programs represent a combined effort of the training staff and the technical staff to assure that all ORNL staff accept their responsibility for handling all types of radioactive and hazardous wastes correctly from its generation to its disposal. 4 refs

Short Lived Climate Pollutants cause a Long Lived Effect on Sea-level Rise: Analyzing climate metrics for sea-level rise

Science.gov (United States)

Sterner, E.; Johansson, D. J.

2013-12-01

Climate change depends on the increase of several different atmospheric pollutants. While long term global warming will be determined mainly by carbon dioxide, warming in the next few decades will depend to a large extent on short lived climate pollutants (SLCP). Reducing emissions of SLCPs could contribute to lower the global mean surface temperature by 0.5 °C already by 2050 (Shindell et al. 2012). Furthermore, the warming effect of one of the most potent SLCPs, black carbon (BC), may have been underestimated in the past. Bond et al. (2013) presents a new best estimate of the total BC radiative forcing (RF) of 1.1 W/m2 (90 % uncertainty bounds of 0.17 to 2.1 W/m2) since the beginning of the industrial era. BC is however never emitted alone and cooling aerosols from the same sources offset a majority of this RF. In the wake of calls for mitigation of SLCPs it is important to study other aspects of the climate effect of SLCPs. One key impact of climate change is sea-level rise (SLR). In a recent study, the effect of SLCP mitigation scenarios on SLR is examined. Hu et al (2013) find a substantial effect on SLR from mitigating SLCPs sharply, reducing SLR by 22-42% by 2100. We choose a different approach focusing on emission pulses and analyse a metric based on sea level rise so as to further enlighten the SLR consequences of SLCPs. We want in particular to understand the time dynamics of SLR impacts caused by SLCPs compared to other greenhouse gases. The most commonly used physical based metrics are GWP and GTP. We propose and evaluate an additional metric: The global sea-level rise potential (GSP). The GSP is defined as the sea level rise after a time horizon caused by an emissions pulse of a forcer to the sea level rise after a time horizon caused by an emissions pulse of a CO2. GSP is evaluated and compared to GWP and GTP using a set of climate forcers chosen to cover the whole scale of atmospheric perturbation life times (BC, CH4, N2O, CO2 and SF6). The study

Science, Society, and America's Nuclear Waste: Nuclear Waste, Unit 1. Teacher Guide. Second Edition.

Science.gov (United States)

Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

This guide is Unit 1 of the four-part series Science, Society, and America's Nuclear Waste produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to help students establish the relevance of the topic of nuclear waste to their everyday lives and activities. Particular attention is…

Numerical solution of stiff burnup equation with short half lived nuclides by the Krylov subspace method

International Nuclear Information System (INIS)

Yamamoto, Akio; Tatsumi, Masahiro; Sugimura, Naoki

2007-01-01

The Krylov subspace method is applied to solve nuclide burnup equations used for lattice physics calculations. The Krylov method is an efficient approach for solving ordinary differential equations with stiff nature such as the nuclide burnup with short lived nuclides. Some mathematical fundamentals of the Krylov subspace method and its application to burnup equations are discussed. Verification calculations are carried out in a PWR pin-cell geometry with UO 2 fuel. A detailed burnup chain that includes 193 fission products and 28 heavy nuclides is used in the verification calculations. Shortest half life found in the present burnup chain is approximately 30 s ( 106 Rh). Therefore, conventional methods (e.g., the Taylor series expansion with scaling and squaring) tend to require longer computation time due to numerical stiffness. Comparison with other numerical methods (e.g., the 4-th order Runge-Kutta-Gill) reveals that the Krylov subspace method can provide accurate solution for a detailed burnup chain used in the present study with short computation time. (author)

Working towards a universal container for category B waste

International Nuclear Information System (INIS)

Tallec, M.

2002-01-01

Long-lived, intermediate-level waste, known as category 8 waste, accounts for most long lived waste (> 90%), although it only accounts for a very small fraction of radiotoxicity (< 10%). It comes in a wide variety of forms. The first step to be taken is to classify it into a few families and define a standard management mode for each one. Research teams are therefore seeking to propose a range of universal containers for existing packages and waste still to be conditioned. (author)

The management of the radioactive waste generated by the EDF nuclear power plants in service

International Nuclear Information System (INIS)

Lantes, B.; Beguin, St.

2011-01-01

From the very beginning of France's nuclear power programme, EDF has developed industrial-scale management of the waste it produces, which has constantly progressed in line with changes in the regulations and the available technology. This management process, improved thanks to feedback and experience, ensures that any risk of exposure, at every stage, from production to final disposal, is controlled. The guidelines adopted by EDF for sustainable management of its waste are as follows: -) reduce the quantity of waste, from the production stage and then through recycling and reprocessing; -) sort waste according to its nature and activity level, so that it can be processed and packaged appropriately and the appropriate long-term management solution implemented; -) package waste as soon as it is produced to prevent any risk of dispersion; -) store waste, pending decay or the availability of an appropriate disposal solution; -) transport and place waste in repositories, keeping it away from Man and the environment by means of engineered or natural barriers for as long as required for the radioactivity to decay to an acceptable level. Regarding short-lived waste produced during operating and maintenance activities at power plants in service, EDF currently implements fully-integrated industrial management solutions which are constantly being optimised in conjunction with its industrial partners. (authors)

Detection of {sup 210}Po on filter papers 16 years after use for the collection of short-lived radon progeny in a room

Energy Technology Data Exchange (ETDEWEB)

Abu-Jarad, F. E-mail: falah.abujarad@aramco.com; Fazal-ur-Rehman

2003-07-01

Radon gas was allowed to accumulate in its radium source and then injected into a 36 m{sup 3} test room, resulting in an initial radon concentration of 15 kBq m{sup -3}. Filter papers were used to collect the short-lived radon progeny and thus to measure the Potential Alpha Energy Concentration (PAEC) in-situ in the year 1984 at different times and conditions according to the experimental design. The radon progeny collected on the filter papers were studied as a function of aerosol particle concentration ranging from 10{sup 2}-10{sup 5} particles cm{sup -3} in three different experiments. The highest aerosol particle concentration was generated by indoor cigarette smoking. Those filters were stored after the experiment, and were used after 16 years to study the activity of the radon long-lived alpha emitter progeny, {sup 210}Po (T{sub 1/2}=138 days). This isotope is separated from the short-lived progeny by {sup 210}Pb beta emitter with 22.3 years half-life. After 16 years' storage of these filters, each filter paper was sandwiched and wrapped between two CR-39 nuclear track detectors, to put the detectors in contact with the surfaces of different filters, for 337 days. Correlation between the PAEC measured using filter papers in the year 1984 and the activity of long-lived alpha emitter {sup 210}Po on the same filter papers measured in the year 2000 were studied. The results of the {sup 210}Po activity showed a very good correlation of 0.92 with the PAEC 16 years ago. The results also depict that the PAEC and {sup 210}Po activity in indoor air increased with the increase of aerosol particle concentration, which shows the attachment of short-lived radon progeny with the aerosol particles. The experiment proves that indoor cigarette smoking is a major source of aerosol particles carrying radon progeny and, thus, indoor cigarette smoking is an additional source of internal radiation hazard to the occupants whether smoker or non-smoker.

Time to bypass the UK's stagnant waste programme

International Nuclear Information System (INIS)

Burton, W.R.; Haslam, C.J.

1995-01-01

It is envisaged that a big expansion of nuclear power will be required in the United Kingdom to meet the demand for electric power after gas supplies run out. However, an acceptable scheme for the disposal of all kinds of radioactive waste must be demonstrated before such an expansion is contemplated. Alternatives to the plans being developed by UK Nirex for the burial of low and intermediate level wastes (LLW and ILW) are advanced. The movement of groundwater which could carry radioactivity from an underground repository back to the land surface or into the sea is the main safety issue associated with burying nuclear waste. The water movement would be induced by the head of water from surrounding hillsides or by convection in water warmed by heat-emitting high level waste (HLW). By taking advantage of the coastal situation of both Sellafield and Dounreay, the two UK sites where waste is likely to be buried, these effects can be countered. Drained trench burial with a saline groundwater underpass created by drawing in seawater, is suggested for LLW and some short-lived ILW. A stagnant saline zone, again created from drawn in sea water, is proposed for deep disposal of ILW with a ''flyover'' to drain down surrounding hills. The disposal of HLW in liquid form in nitric acid solution at even deeper levels also making use of a stagnant saline zone is also discussed. (UK)

Final disposal of high-level radioactive waste and/or long-living nuclear waste in a clay formation in the Belgian-Dutch border region; Definitieve berging van hoogradioactief en/of langlevend kernafval in een kleiformatie in de Belgisch-Nederlandse grensstreek

Energy Technology Data Exchange (ETDEWEB)

Weyns, W.

2010-10-15

Recently, the Belgian organization NIRAS presented its 'Draft Waste Plan'. In this plan NIRAS chooses clay as the reference option for final geological disposal of high-level radioactive and/or long-living nuclear waste (b and C waste). The author presents an overview of the current state of affairs in scientific research on underground storage of radioactive waste in Belgian clay layers. [Dutch] Recent presenteerde het Belgische NIRAS het 'Ontwerp Afvalplan'. In dit plan kiest NIRAS als referentieoptie voor definitieve geologische berging van hoogradioactief en/of langlevend kernafval (B- en C-afval) in klei. De auteur geeft een overzicht van de stand van zaken van wetenschappelijk onderzoek naar ondergrondse opslag van radioactief afval in Belgische kleilagen.

2005 dossier. ANDRA's researches on the geological disposal of high-level and long-lived radioactive wastes. Results and perspectives

International Nuclear Information System (INIS)

2005-06-01

This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the geologic disposal of high-level and long-lived radioactive wastes in deep geologic formations (argilites and granites). Content: 1 - Research on deep disposal of radioactive waste: general interest task: Legislative framework, ANDRA scientific objectives, Inspections and assessments; 2 - Designing a safe and reversible disposal system: Repository safety, Reversibility: an essential requirement; 3 - Clay Research on a repository in a clay formation, A long research programme, Dossier 2005 Argile; 4 - Meuse/Haute-Marne site clay: Expected properties of the rock formation, Choice of argillite, Meuse/Haute-Marne site, Conclusions from 10 years of research at the Meuse/Haute-Marne site; 5 - Repository installations: Safe and reversible architecture, Disposal of B waste, Disposal of C waste, Possible disposal of spent fuel (CU); 6 - The disposal facility in operation: From waste packages reception to their disposal in cells, Stages of the progressive closure of engineered structures; 7 - Reversible management: Freedom of choice for future generations, Various closure stages; 8 - Long-term evolution of the repository: Apprehending the repository complexity Main evolutions expected, Slow and limited release of radioactive substances; 9 - Repository safety and impact on man: Several evolution scenarios, Normal evolution, Altered evolution; 10 - Granite Research on a repository in a granite formation: A global approach, Scientific co-operations, Dossier 2005 Granite; 11 - Characteristics of French granite formations: What properties are required for a repository?, Different types of granite formations; 12 - Repository installations: Repository design adapted to granite fractures, Clay seals to prevent water flows, Waste disposal packages ensuring long-term leak-tightness, Physical and chemical environment favourable for waste packages, Architecture

A comparison of radioactive waste from first generation fusion reactors and fast fission reactors with actinide recycling

International Nuclear Information System (INIS)

Koch, M.; Kazimi, M.S.

1991-04-01

Limitations of the fission fuel resources will presumably mandate the replacement of thermal fission reactors by fast fission reactors that operate on a self-sufficient closed fuel cycle. This replacement might take place within the next one hundred years, so the direct competitors of fusion reactors will be fission reactors of the latter rather than the former type. Also, fast fission reactors, in contrast to thermal fission reactors, have the potential for transmuting long-lived actinides into short-lived fission products. The associated reduction of the long-term activation of radioactive waste due to actinides makes the comparison of radioactive waste from fast fission reactors to that from fusion reactors more rewarding than the comparison of radioactive waste from thermal fission reactors to that from fusion reactors. Radioactive waste from an experimental and a commercial fast fission reactor and an experimental and a commercial fusion reactor has been characterized. The fast fission reactors chosen for this study were the Experimental Breeder Reactor 2 and the Integral Fast Reactor. The fusion reactors chosen for this study were the International Thermonuclear Experimental Reactor and a Reduced Activation Ferrite Helium Tokamak. The comparison of radioactive waste parameters shows that radioactive waste from the experimental fast fission reactor may be less hazardous than that from the experimental fusion reactor. Inclusion of the actinides would reverse this conclusion only in the long-term. Radioactive waste from the commercial fusion reactor may always be less hazardous than that from the commercial fast fission reactor, irrespective of the inclusion or exclusion of the actinides. The fusion waste would even be far less hazardous, if advanced structural materials, like silicon carbide or vanadium alloy, were employed

A comparison of radioactive waste from first generation fusion reactors and fast fission reactors with actinide recycling

Energy Technology Data Exchange (ETDEWEB)

Koch, M.; Kazimi, M.S.

1991-04-01

Limitations of the fission fuel resources will presumably mandate the replacement of thermal fission reactors by fast fission reactors that operate on a self-sufficient closed fuel cycle. This replacement might take place within the next one hundred years, so the direct competitors of fusion reactors will be fission reactors of the latter rather than the former type. Also, fast fission reactors, in contrast to thermal fission reactors, have the potential for transmuting long-lived actinides into short-lived fission products. The associated reduction of the long-term activation of radioactive waste due to actinides makes the comparison of radioactive waste from fast fission reactors to that from fusion reactors more rewarding than the comparison of radioactive waste from thermal fission reactors to that from fusion reactors. Radioactive waste from an experimental and a commercial fast fission reactor and an experimental and a commercial fusion reactor has been characterized. The fast fission reactors chosen for this study were the Experimental Breeder Reactor 2 and the Integral Fast Reactor. The fusion reactors chosen for this study were the International Thermonuclear Experimental Reactor and a Reduced Activation Ferrite Helium Tokamak. The comparison of radioactive waste parameters shows that radioactive waste from the experimental fast fission reactor may be less hazardous than that from the experimental fusion reactor. Inclusion of the actinides would reverse this conclusion only in the long-term. Radioactive waste from the commercial fusion reactor may always be less hazardous than that from the commercial fast fission reactor, irrespective of the inclusion or exclusion of the actinides. The fusion waste would even be far less hazardous, if advanced structural materials, like silicon carbide or vanadium alloy, were employed.

Update on the national low level radioactive waste repository study

International Nuclear Information System (INIS)

Veitch, S.M.

1997-01-01

Activity to establish a national repository for low-level and short-lived intermediate-level radioactive waste in Australia began in the early 1980's. From the early 1990's computer-based geographic information systems had developed sufficiently so that all of Australia could be quickly reviewed using digital data relevant to site selection criteria. A three-phased approach to site selection was commenced which included an iterative process of data collection, interpretation, and public involvement through discussion papers. All of Australia was reviewed using national-scale data, and eight broad regions were identified and reviewed using regional-scale data. A third phase report will be released shortly which includes details on the process for identifying the preferred region of the eight. This region will be the focus for public involvement and for detailed study to identify a site for the national repository

Waste management plan for the APT

International Nuclear Information System (INIS)

England, J.L.

1997-01-01

This revision of the APT Waste Management Plan details the waste management requirements and issues specific to the APT plant for design considerations, construction, and operation. The APT Waste Management Plan is by its nature a living document and will be reviewed at least annually and revised as required

Radioactive waste management and disposal

International Nuclear Information System (INIS)

Kaluzny, Y.

1994-01-01

The public has demonstrated interest and even concern for radioactive waste. A fully demonstrated industrial solution already exists for 90% of the waste generated by the nuclear industry. Several solutions are currently under development for long-term management of long-lived waste. They could be implemented on an industrial scale within twenty years. The low volumes of this type of waste mean there is plenty of time to adopt a solution. (author). 5 photos

The principal radionuclides in high level radioactive waste management

International Nuclear Information System (INIS)

Mulyanto

1998-01-01

The principal radionuclides in high level radioactive waste management. The selection of the principal radionuclides in the high level waste (HLW) management was developed in order to improve the disposal scenario of HLW. In this study the unified criteria for selection of the principal radionuclides were proposed as; (1) the value of hazard index estimated by annual limit of intake (ALI) for long-term tendency,(2) the relative dose factor related to adsorbed migration rate transferred by ground water, and (3) heat generation in the repository. From this study it can be concluded that the principal radionuclides in the HLW management were minor actinide (MA=Np, Am, Cm, etc), Tc, I, Cs and Sr, based on the unified basic criteria introduced in this study. The remaining short-lived fission product (SLFPs), after the selected nuclides are removed, should be immobilized and solidified in a glass matrix. Potential risk due to the remaining SLFPs can be lower than that of uranium ore after about 300 year. (author)

The management of radioactive wastes

International Nuclear Information System (INIS)

1998-01-01

This educative booklet describes the role and missions of the ANDRA, the French national agency for the management of radioactive wastes, and the different aspects of the management of radioactive wastes: goal, national inventory, classification, transport (organisation, regulation, safety), drumming, labelling, surface storage of short life wastes, environmental control, management of long life wastes (composition, research, legal aspects) and the underground research laboratories (description, public information, projects, schedules). (J.S.)

Synthesis of radiopharmaceuticals containing short-lived radionuclides: Progress report, March 1, 1987-February 28, 1988

International Nuclear Information System (INIS)

Kabalka, G.W.

1987-09-01

The objective is the creation of new methods for introducing short-lived isotopes into agents for use in diagnostic nuclear medicine. Focus is on the design of new molecular architecture as opposed to the application of known reactions to the synthesis of specific radiopharmaceuticals. The new technology is utilized in nuclear medicine research at the University of Tennessee Medical Imaging Center and in collaboration with colleagues at other DOE facilities. The program provides training for students in the scientific aspects of nuclear medicine. The academic nature of the program facilitates collaborative interactions with other DOE nuclear medicine programs and helps to insure the continued availability of skilled scientists dedicated to the advancement of nuclear medicine. 70 refs., 9 figs

APEX nuclear fuel cycle for production of LWR fuel and elimination of radioactive waste

International Nuclear Information System (INIS)

Steinberg, M.; Powell, J.R.

1981-08-01

The development of a nuclear fission fuel cycle is proposed which eliminates all the radioactive fission product waste effluent and the need for geological-age high level waste storage and provides a long term supply of fissile fuel for an LWR power reactor economy. The fuel cycle consists of reprocessing LWR spent fuel (1 to 2 years old) to remove the stable nonradioactive (NRFP, e.g. lanthanides, etc.) and short-lived fission products SLFP e.g. half-lives of (1 to 2 years) and returning, in dilute form, the long-lived fission products, ((LLFPs, e.g. 30 y half-life Cs, Sr, and 10 y Kr, and 16 x 10 6 y I) and the transuranics (TUs, e.g. Pu, Am, Cm, and Np) to be refabricated into fresh fuel elements. Makeup fertile and fissile fuel are to be supplied through the use of a Spallator (linear accelerator spallation-target fuel-producer). The reprocessing of LWR fuel elements is to be performed by means of the Chelox process which consists of Airox treatment (air oxidation and hydrogen reduction) followed by chelation with an organic reagent (β-diketonate) and vapor distillation of the organometallic compounds for separation and partitioning of the fission products

Naval Waste Package Design Sensitivity

International Nuclear Information System (INIS)

T. Schmitt

2006-01-01

The purpose of this calculation is to determine the sensitivity of the structural response of the Naval waste packages to varying inner cavity dimensions when subjected to a comer drop and tip-over from elevated surface. This calculation will also determine the sensitivity of the structural response of the Naval waste packages to the upper bound of the naval canister masses. The scope of this document is limited to reporting the calculation results in terms of through-wall stress intensities in the outer corrosion barrier. This calculation is intended for use in support of the preliminary design activities for the license application design of the Naval waste package. It examines the effects of small changes between the naval canister and the inner vessel, and in these dimensions, the Naval Long waste package and Naval Short waste package are similar. Therefore, only the Naval Long waste package is used in this calculation and is based on the proposed potential designs presented by the drawings and sketches in References 2.1.10 to 2.1.17 and 2.1.20. All conclusions are valid for both the Naval Long and Naval Short waste packages

Application of dynamic and transition magnetic fields for determination of magnetic moments of short-lived nuclear states

International Nuclear Information System (INIS)

Burgov, N.A.

1986-01-01

Problem of measuring magnetic momenta of short-living nuclear states is discussed. Different methods for measuring magnetic momenta using interionic and transient magnetic fields were considered. Possibility for determining a value g by means of measuring correlation attenuation is investigated as well as measuring magnetic momenta by means of inclined foils. At present 2 + level magnetic momenta for many odd-odd nuclei have been determined by means of the above methods. The methods are only ones for determining magnetic momenta of nuclear levels with small lifetimes up to tenth and hundredth of shares of picoseconds

External tandem target system for efficient production of short-lived positron emitting radionuclides

International Nuclear Information System (INIS)

Koh, K.; Dwyer, J.; Finn, R.; Sheh, Y.; Sinnreich, J.; Wooten, T.

1983-01-01

Recent developments in radiopharmaceutical chemistry allow the incorporation of short-lived, positron-emitting radionuclides into a variety of compounds which when used with a positron emission tomograph provide a means of monitoring physiological disorders by a standard technique. To effectively meet the increased ''in-house'' clinical demands while maintaining a production schedule, a tandem target was designed and has been installed for the simultaneous ''on-line'' preparation of oxygen-15 labelled compounds such as CO 2 15 , H 2 O 15 ; and nitrogen-13 labelled compounds such as 13 NH 3 , 13 N 2 O, and 13 N 2 . The processing time required for the synthesis of the nitrogen-13 products as compared to the essentially instantaneous formation of oxygen-15 labelled compounds has provided the necessary time delay for clinical utilization. The characterisitcs of this external tandem target system as well as the automation for the dual processing are presented

Changes in oxidative stress parameters in relation to age, growth and reproduction in the short-lived catarina scallop Argopecten ventricosus reared in its natural environment.

Science.gov (United States)

Guerra, C; Zenteno-Savín, T; Maeda-Martínez, A N; Philipp, E E R; Abele, D

2012-08-01

Increase in oxidative damage and decrease in cellular maintenance is often associated with aging, but, in marine ectotherms, both processes are also strongly influenced by somatic growth, maturation and reproduction. In this study, we used a single cohort of the short-lived catarina scallop Argopecten ventricosus, to investigate the effects of somatic growth, reproduction and aging on oxidative damage parameters (protein carbonyls, TBARS and lipofuscin) and cellular maintenance mechanisms (antioxidant activity and apoptosis) in scallops, caged in their natural environment. The concentrations of protein carbonyls and TBARS increased steeply during the early period of fast growth and during reproduction in one-year-old scallops. However, oxidative damage was transient, and apoptotic cell death played a pivotal role in eliminating damage in gill, mantle and muscle tissues of young scallops. Animals were able to reproduce again in the second year, but the reduced intensity of apoptosis impaired subsequent removal of damaged cells. In late survivors low antioxidant capacity and apoptotic activity together with a fast accumulation of the age pigment lipofuscin was observed. Rates of oxygen consumption and oxidative stress markers were strongly dependent on somatic growth and reproductive state but not on temperature. Compared to longer-lived bivalves, A. ventricosus seems more susceptible to oxidative stress with higher tissue-specific protein carbonyl levels and fast accumulation of lipofuscin in animals surviving the second spawning. Superoxide dismutase activity and apoptotic cell death intensity were however higher in this short-lived scallop than in longer-lived bivalves. The life strategy of this short-lived and intensely predated scallop supports rapid somatic growth and fitness as well as early maturation at young age at the cost of fast cellular degradation in second year scallops. Copyright © 2012 Elsevier Inc. All rights reserved.

A generic risk assessment from unrestricted releases for RI waste

International Nuclear Information System (INIS)

Won-Jae Park; Sang-hoon Park

1993-01-01

It has long been recognized in the nuclear industries and the regulatory body that exemption from the regulatory control for a given practice or source of radioactive materials, which is very low radiation exposure situation where the level of risk to any of the public would be considered as trivial, may be beneficial and practical. Therefore, it is necessary to establish the exempt levels of radioactive wastes for unconditional disposal, incineration, recycle and reuse of slightly contaminated materials. In Korea, from its announcement of the Enforcement Regulation of Atomic Energy Act, the Article 97 (Exemption from Permanent Disposal) for very low-level waste disposal in January 1990, the KINS (Korea Institute of Nuclear Safety) have made their efforts to establish a de minimis level (a level of radioactivity in waste that is sufficiently low that the waste can be disposed of as ordinary, non-radioactive trash) for short-lived radioisotopes commonly used in medical, research institutes and industrial applications and to study the possibility for unrestricted deregulation of those radioisotopes. As one of preliminary works to predict environmental radiological impacts from uncontrolled and unrestricted release of RI waste, an average effective dose to any ordinary individual and a collective dose for total population in Korea was estimated, based on conservative assumptions and Korean specific environment data, by an equilibrium biosphere models with a generic probabilistic risk approach

Greater confinement disposal of radioactive wastes

International Nuclear Information System (INIS)

Trevorrow, L.E.; Gilbert, T.L.; Luner, C.; Merry-Libby, P.A.; Meshkov, N.K.; Yu, C.

1985-01-01

Low-level radioactive waste (LLW) includes a broad spectrum of different radionuclide concentrations, half-lives, and hazards. Standard shallow-land burial practice can provide adequate protection of public health and safety for most LLW. A small volume fraction (approx. 1%) containing most of the activity inventory (approx. 90%) requires specific measures known as greater-confinement disposal (GCD). Different site characteristics and different waste characteristics - such as high radionuclide concentrations, long radionuclide half-lives, high radionuclide mobility, and physical or chemical characteristics that present exceptional hazards - lead to different GCD facility design requirements. Facility design alternatives considered for GCD include the augered shaft, deep trench, engineered structure, hydrofracture, improved waste form, and high-integrity container. Selection of an appropriate design must also consider the interplay between basic risk limits for protection of public health and safety, performance characteristics and objectives, costs, waste-acceptance criteria, waste characteristics, and site characteristics

Routine short-term ureteral stent in living donor renal transplantation: introduction of a simple stent removal technique without using anesthesia and cystoscope.

Science.gov (United States)

Dong, J; Lu, J; Zu, Q; Yang, S; Sun, S; Cai, W; Zhang, L; Zhang, X

2011-12-01

We evaluated routine short-time insertion of ureteral stent in living donor renal transplant at a single center. It was easy to remove the stent without cystoscopy and anesthesia. Between October 2007 and July 2010, a single surgeon performed 76 living donor renal transplantations at one institute. All recipients underwent extravesical ureteroneocystostomy with a 2-0 silk suture passed through the venting side hole of the double-J stent into the bladder; a quadruple knot prevented the suture's slippage or distraction from the stent. After removal of the indwelling catheter at 5 days posttransplantation, the 2-0 silk passed with the urinary stream within 72 hours. The double-J stent was removed at 7 to 10 (mean 8.4) days after kidney transplantation by pulling the 2-0 silk out of the urethral orifice without anesthesia or cystoscopy. There was only one case of stenosis, which was resolved by surgery. No patient developed urinary leakage. There were three episodes of urinary tract infection in 70 patients during first 6 months' follow-up. Routine short-term stenting is a safe and effective technique in living donor renal transplantation. Removal of the stent is feasible without cystoscopy or anesthesia. Copyright © 2011 Elsevier Inc. All rights reserved.

Safety in the final disposal of radioactive waste. Final report

International Nuclear Information System (INIS)

Broden, K.; Carugati, S.; Brodersen, K.

1997-12-01

During 1994-1997 a project on the disposal of radioactive waste was carried out as part of the NKS program. The objective of the project was to give authorities and waste producers in the Nordic countries background material for determinations about the management and disposal of radioactive waste. The project NKS/AFA-1 was divided into three sub-projects: AFA-1.1, AFA-1.2 and AFA-1.3. AFA-1.1 dealt with waste characterisation, AFA-1.2 dealt with performance assessment for repositories and AFA-1.3 dealt with Environmental Impact Assessment (EIA). The studies mainly focused on the management of long-lived low- and intermediate-level radioactive waste from research, hospitals and industry. The AFA-1.1 study included an overview on waste categories in the Nordic countries and methods to determine or estimate the waste content. The results from the AFA-1.2 study include a short overview of different waste management systems existing and planned in the Nordic countries. However, the main emphasis of the study was a general discussion of methodologies developed and employed for performance assessments of waste repositories. Some of the phenomena and interactions relevant for generic types of repository were discussed as well. Among the different approaches for the development of scenarios for safety and performance assessments one particular method, the Rock Engineering System (RES), was chosen to be tested by demonstration. The possible interactions and their safety significance were discussed, employing a simplified and generic Nordic repository system as the reference system. New regulations for the inventory of a repository may demand new assessments of old radioactive waste packages. The existing documentation of a waste package is then the primary information source although additional measurements may be necessary. (EG)

Safety in the final disposal of radioactive waste. Final report

Energy Technology Data Exchange (ETDEWEB)

Broden, K.; Carugati, S.; Brodersen, K. [and others

1997-12-01

During 1994-1997 a project on the disposal of radioactive waste was carried out as part of the NKS program. The objective of the project was to give authorities and waste producers in the Nordic countries background material for determinations about the management and disposal of radioactive waste. The project NKS/AFA-1 was divided into three sub-projects: AFA-1.1, AFA-1.2 and AFA-1.3. AFA-1.1 dealt with waste characterisation, AFA-1.2 dealt with performance assessment for repositories and AFA-1.3 dealt with Environmental Impact Assessment (EIA). The studies mainly focused on the management of long-lived low- and intermediate-level radioactive waste from research, hospitals and industry. The AFA-1.1 study included an overview on waste categories in the Nordic countries and methods to determine or estimate the waste content. The results from the AFA-1.2 study include a short overview of different waste management systems existing and planned in the Nordic countries. However, the main emphasis of the study was a general discussion of methodologies developed and employed for performance assessments of waste repositories. Some of the phenomena and interactions relevant for generic types of repository were discussed as well. Among the different approaches for the development of scenarios for safety and performance assessments one particular method, the Rock Engineering System (RES), was chosen to be tested by demonstration. The possible interactions and their safety significance were discussed, employing a simplified and generic Nordic repository system as the reference system. New regulations for the inventory of a repository may demand new assessments of old radioactive waste packages. The existing documentation of a waste package is then the primary information source although additional measurements may be necessary. (EG) 33 refs.

Waste management at WAK

International Nuclear Information System (INIS)

Kuhn, K.D.; Willax, H.O.

1986-01-01

After a short description of the WAK plant and its reprocessing and intervention activities, types and sources of WAK wastes are described. Roughly half of the waste volume is generated during reprocessing, the other half during intervention periods. Most of the waste is transported to KfK for conditioning. Only waste from the head end cell is cementated on the spot. HLLW is stored in stainless steel tanks. Some results from analyzing this stuff are given. The corrosion behavior is acceptable for medium term storage. (orig.)

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

Transmutation of nuclear waste. Status report RAS programme 1993: Recycling and transmutation of actinides and fission products

International Nuclear Information System (INIS)

Abrahams, K.; Bultman, J.H.; Cordfunke, E.H.P.; Gruppelaar, H.; Janssen, A.J.; Franken, W.M.P.; Klippel, K.T.; Kloosterman, J.L.; Konings, R.J.M.; Smit, J.

1994-11-01

The term ''nuclear transmutation'' means a conversion of long-lived radioactive nuclides into short-lived or stable nuclides and ''recycling'' means re-use of fissile material to generate energy in power reactors. With these two processes a reduction of the radiotoxicity and of its duration may be achieved, thus reducing the potential hazard to future generations. Firstly, the report gives a survey of the present situation regarding nuclear waste: its components, how the waste is produced in current LWR and possible options for interim and final storage. Then the objective of the RAS programme, the working methods and the state of the art of the research are considered. Two chapters deal with preliminary results of national and international research. A rather tentative prediction for the future is formulated. Some conclusions are drawn: It seems to be in the best interests of the Netherlands to continue the established line of reprocessing nuclear waste, should new reactors be introduced. It may be advisable to make international agreements so that in the future fission products will contain as few traces of transuranic actinides and long-lived components as possible. Consequently, nuclear waste would become cleaner in terms of long-lived components. For the transmutation of products separated in foreign countries, the Netherlands could pursue an active policy, perform research and also consider the use of MOX fuel in future Dutch reactors. Further contributions towards the solution of these problems can only be made by the Netherlands on an international level. As such, the research and study performed within the framework of the RAS-programme represents a useful international contribution. The possibilities offered by the HFR are particularly of great value. Finally, the choice of a new generation of nuclear reactors should be made not based only on the safety aspects, but also on the extent of waste production and on the transmutation possibilities (application

Thyroid cancer in the Marshallese: relative risk of short-lived internal emitters and external radiation exposure

International Nuclear Information System (INIS)

Lessard, E.T.; Brill, A.B.; Adams, W.H.

1985-01-01

In a study of the comparative effects of internal versus external irradiation of the thyroid in young people, we determined that the dose from internal irradiation of the thyroid with short-lived internal emitters produced several times less thyroid cancer than did the same dose of radiation given externally. We determined this finding for a group of 85 Marshall Islands children, who were less than 10 years of age at the time of exposure and who were accidentially exposed to internal and external thyroid radiation at an average level of 1400 rad. The external risk coefficient ranged between 2.5 and 4.9 cancers per million person-rad-years at risk, and thus, from our computations, the internal risk coefficient for the Marshallese children was estimated to range between 1.0 and 1.4 cancers per million person-rad-years at risk. In contrast, for individual more than 10 years of age at the time of exposure, the dose from internal irradiation of the thyroid with short-lived internal emitters produced several times more thyroid cancer than did the same dose of radiation given externally. The external risk coefficients for the older age groups were reported in the literature to be in the range of 1.0 to 3.3 cancers per million person-rad-years-at risk. We computed internal risk coefficients of 3.3 to 8.1 cancers per million person-rad-years at risk for adolescent and adult groups. This higher sensitivity to cancer induction in the exposed adolescents and adults, is different from that seen in other exposed groups. 14 refs., 8 tabs

Synthesis of radiopharmaceuticals containing short-lived radionuclides: Comprehensive progress report, March 1, 1986-February 28, 1989

International Nuclear Information System (INIS)

Kabalka, G.W.

1988-06-01

The primary objective of the DOE Nuclear Medicine Program at The University of Tennessee is the creation of new methods for intoducing short-lived isotopes into agents for use in PET and SPECT. A portion of our effort is directed toward the design and in vivo quantitation of boron-containing neutron therapy agents. The uniqueness of the program is its focus on the design of new chemistry (molecular architecture) and technology as opposed to the application of known reactions to the synthesis of specific radiopharmaceuticals. The following topics are outlined in this paper: new isotope incorporation reactions utilizing nitrogen 13, oxygen 15, and carbon 11; technetium-boron complexes; boron-neutron-capture

Disposal and environmental assessment of solid waste and radioactive waste

International Nuclear Information System (INIS)

Tan Chenglong

2000-01-01

Along with the development of economic construction, the industrial and agricultural production, military and scientific activities of human being, large amounts of solid and radioactive wastes have been produced, causing serious pollution of ecologic environments and living space of human being itself. To assess and administer the solid and radioactive wastes in geologic-ecologic environments are duty-bound responsibilities of modern geologists and the focus of recent geo-ecologic work

Waste management plan - plant plan

International Nuclear Information System (INIS)

Gaudet, F.

2008-01-01

The author summarizes the nuclear activity of the Pierre Fabre Research Institute (sites, used radionuclides, radioprotection organisation), indicates the applied regulation, gives a brief analytical overview of the waste collection, sorting and elimination processes, of the management process for short period wastes and for long period wastes, and of the traceability and control procedures. He briefly presents some characteristics of the storing premises

Nuclear waste and hazardous waste in the public perception

International Nuclear Information System (INIS)

Kruetli, Pius; Seidl, Roman; Stauffacher, Michael

2015-01-01

The disposal of nuclear waste has gained attention of the public for decades. Accordingly, nuclear waste has been a prominent issue in natural, engineer and social science for many years. Although bearing risks for todays and future generations hazardous waste in contrast is much less an issue of public concern. In 2011, we conducted a postal survey among Swiss Germans (N = 3.082) to learn more about, how nuclear waste is perceived against hazardous waste. We created a questionnaire with two versions, nuclear waste and hazardous waste, respectively. Each version included an identical part with well-known explanatory factors for risk perception on each of the waste types separately and additional questions directly comparing the two waste types. Results show that basically both waste types are perceived similarly in terms of risk/benefit, emotion, trust, knowledge and responsibility. However, in the direct comparison of the two waste types a complete different pattern can be observed: Respondents perceive nuclear waste as more long-living, more dangerous, less controllable and it, furthermore, creates more negative emotions. On the other hand, respondents feel more responsible for hazardous waste and indicate to have more knowledge about this waste type. Moreover, nuclear waste is perceived as more carefully managed. We conclude that mechanisms driving risk perception are similar for both waste types but an overarching negative image of nuclear waste prevails. We propose that hazardous waste should be given more attention in the public as well as in science which may have implications on further management strategies of hazardous waste.

Nuclear waste and hazardous waste in the public perception

Energy Technology Data Exchange (ETDEWEB)

Kruetli, Pius; Seidl, Roman; Stauffacher, Michael [ETH Zurich (Switzerland). Inst. for Environmental Decisions

2015-07-01

The disposal of nuclear waste has gained attention of the public for decades. Accordingly, nuclear waste has been a prominent issue in natural, engineer and social science for many years. Although bearing risks for todays and future generations hazardous waste in contrast is much less an issue of public concern. In 2011, we conducted a postal survey among Swiss Germans (N = 3.082) to learn more about, how nuclear waste is perceived against hazardous waste. We created a questionnaire with two versions, nuclear waste and hazardous waste, respectively. Each version included an identical part with well-known explanatory factors for risk perception on each of the waste types separately and additional questions directly comparing the two waste types. Results show that basically both waste types are perceived similarly in terms of risk/benefit, emotion, trust, knowledge and responsibility. However, in the direct comparison of the two waste types a complete different pattern can be observed: Respondents perceive nuclear waste as more long-living, more dangerous, less controllable and it, furthermore, creates more negative emotions. On the other hand, respondents feel more responsible for hazardous waste and indicate to have more knowledge about this waste type. Moreover, nuclear waste is perceived as more carefully managed. We conclude that mechanisms driving risk perception are similar for both waste types but an overarching negative image of nuclear waste prevails. We propose that hazardous waste should be given more attention in the public as well as in science which may have implications on further management strategies of hazardous waste.

Defining a metal-based waste form for IFR pyroprocessing wastes

International Nuclear Information System (INIS)

McDeavitt, S.M.; Park, J.Y.; Ackerman, J.P.

1994-01-01

Pyrochemical electrorefining to recover actinides from metal nuclear fuel is a key element of the Integral Fast Reactor (IFR) fuel cycle. The process separates the radioactive fission products from the long-lived actinides in a molten LiCl-KCl salt, and it generates a lower waste volume with significantly less long-term toxicity as compared to spent nuclear fuel. The process waste forms include a mineral-based waste form that will contain fission products removed from an electrolyte salt and a metal-based waste form that will contain metallic fission products and the fuel cladding and process materials. Two concepts for the metal-based waste form are being investigated: (1) encapsulating the metal constituents in a Cu-Al alloy and (2) alloying the metal constituents into a uniform stainless steel-based waste form. Results are given from our recent studies of these two concepts

Liquid waste processing device

International Nuclear Information System (INIS)

Matsumoto, Kaname; Obe, Etsuji; Wakamatsu, Toshifumi.

1989-01-01

In a liquid waste processing device for processing living water wastes discharged from nuclear power plant facilities through a filtration vessel and a sampling vessel, a filtration layer disposed in the filtration vessel is divided into a plurality of layers along planes vertical to the direction of flow and the size of the filter material for each of the divided layers is made finer toward the downstream. Further, the thickness of the filtration material in each of the divided layers is also reduced toward the downstream. The filter material is packed such that the porosity in each of the divided layers is substantially identical. Further, the filtration material is packed in a mesh-like bag partitioned into a desired size and laid with no gaps to the planes vertical to the direction of the flow. Thus, liquid wastes such as living water wastes can be processed easily and simply so as to satisfy circumstantial criteria without giving undesired effects on the separation performance and life time and with easy replacement of filter. (T.M.)

Archaeology and the future: Managing nuclear waste as a living heritage

International Nuclear Information System (INIS)

Holtorf, Cornelius; Hoegberg, Anders

2015-01-01

Archaeology, the study of the remains of the ancient past, may be relevant to the long-term preservation of RK and M, because it works to recover information, knowledge and meaning that have been lost. As a discipline, archaeology studies how the past is understood in the present, potentially drawing lessons that could guide future action concerning the preservation of RK and M across time by indicating how future societies could make sense of the past. Case studies, such as an examination of European megalithic tombs, show that the understanding of the past varies across time. It was emphasised that archaeological interpretation always reflects contemporary perceptions of past and future, which are socially and culturally embedded and highly mutable over time. What is more, archaeology is a fairly recent discipline and there is no certainty that it will exist in the long term, to help recover and reconstruct lost RK and M. As a result, it cannot be assumed that information, knowledge and meaning of the past can be transmitted reliably in the long term. Based on this understanding Profs. Cornelius Holtorf and Anders Hoegberg made a case for trying to keep knowledge alive over time, continuously engaging each present. They used the notion of 'living heritage', which refers to striving for continuity in the short and medium terms as a way to reach the long term, keeping in mind that reinterpretation and knowledge development over time is a given. As a result, they suggest to 'think about the long term but act for the short and medium terms'

Characterization of household food waste in Denmark

DEFF Research Database (Denmark)

Edjabou, Vincent Maklawe Essonanawe; Petersen, C.; Scheutz, Charlotte

This paper presents a methodology and the results of compositional analysis of food waste from Danish families living in single-family houses. Residual household waste was sampled and manually sorted from 211 single-family houses in the suburb of Copenhagen. The main fractions contributing...... to the household food waste were avoidable vegetable food waste and non-avoidable vegetable food waste. Statistical analysis found a positive linear relationship between household size and the amount of the household food waste....

Social scientist on board in long-term management of high level and/or long-lived radioactive waste in Belgium

International Nuclear Information System (INIS)

Parotte, C.

2013-01-01

In Belgium, the long-term management of radioactive waste is under the exclusive competence of the Belgian Agency for Radioactive Waste and Enriched Fissile Materials (knew as ONDRAF/NIRAS). Unlike low-level waste, no institutional policy has yet been formally approved for the long-term management of high level and/or long-lived radioactive waste (knew as B and C waste). In this context, ONDRAF/NIRAS considers the public and stakeholders' participation as an essential factor in the formulation of an effective and legitimate policy. This is why it has decided to integrate them in different ways during the elaboration of the Waste Plan (ONDRAF/NIRAS-document containing guidelines to make a principled policy decision about nuclear waste management). To do so, social scientists have been regularly mobilized either as external evaluators, follow-up committee members, or participatory observants. Hence, the Waste Plan is only the first step in a long decision-making process. For a PhD student under contract with ONDRAF/NIRAS, this mandate consists of thinking out a way to construct an inter-organizational innovative communication system that would be participative, transparent and embedded in a long-term perspective, thus integrating all the further legal steps to take throughout the decision-making process. In this regard, two paradoxical constraints must be taken into account: on the one hand, my own influence on the legal decision-making process should remain limited, because of a series of constraints, lock-ins and previous decisions which have to be respected; on the other hand, ONDRAF/NIRAS expects the research conclusions to be policy relevant and useful. In this paper, the purpose is twofold. Firstly, the issues raised by this policy mandate is an opportunity to question the per-formative dimensions of the social scientist in the decision-making process and, more specifically, to have a reflexive view on our position as PhD Student. Secondly, assuming the

Social scientist on board in long-term management of high level and/or long-lived radioactive waste in Belgium

Energy Technology Data Exchange (ETDEWEB)

Parotte, C. [Spiral Research Center, Department of Political Sciences, Faculty of Law, University of Liege (Belgium)

2013-07-01

In Belgium, the long-term management of radioactive waste is under the exclusive competence of the Belgian Agency for Radioactive Waste and Enriched Fissile Materials (knew as ONDRAF/NIRAS). Unlike low-level waste, no institutional policy has yet been formally approved for the long-term management of high level and/or long-lived radioactive waste (knew as B and C waste). In this context, ONDRAF/NIRAS considers the public and stakeholders' participation as an essential factor in the formulation of an effective and legitimate policy. This is why it has decided to integrate them in different ways during the elaboration of the Waste Plan (ONDRAF/NIRAS-document containing guidelines to make a principled policy decision about nuclear waste management). To do so, social scientists have been regularly mobilized either as external evaluators, follow-up committee members, or participatory observants. Hence, the Waste Plan is only the first step in a long decision-making process. For a PhD student under contract with ONDRAF/NIRAS, this mandate consists of thinking out a way to construct an inter-organizational innovative communication system that would be participative, transparent and embedded in a long-term perspective, thus integrating all the further legal steps to take throughout the decision-making process. In this regard, two paradoxical constraints must be taken into account: on the one hand, my own influence on the legal decision-making process should remain limited, because of a series of constraints, lock-ins and previous decisions which have to be respected; on the other hand, ONDRAF/NIRAS expects the research conclusions to be policy relevant and useful. In this paper, the purpose is twofold. Firstly, the issues raised by this policy mandate is an opportunity to question the per-formative dimensions of the social scientist in the decision-making process and, more specifically, to have a reflexive view on our position as PhD Student. Secondly, assuming the

Radioactive wastes. Safety of storage facilities

International Nuclear Information System (INIS)

Devillers, Ch.

2001-01-01

A radioactive waste storage facility is designed in a way that ensures the isolation of wastes with respect to the biosphere. This function comprises the damping of the gamma and neutron radiations from the wastes, and the confinement of the radionuclides content of the wastes. The safety approach is based on two time scales: the safety of the insulation system during the main phase of radioactive decay, and the assessment of the radiological risks following this phase. The safety of a surface storage facility is based on a three-barrier concept (container, storage structures, site). The confidence in the safety of the facility is based on the quality assurance of the barriers and on their surveillance and maintenance. The safety of a deep repository will be based on the site quality, on the design and construction of structures and on the quality of the safety demonstration. This article deals with the safety approach and principles of storage facilities: 1 - recall of the different types of storage facilities; 2 - different phases of the life of a storage facility and regulatory steps; 3 - safety and radiation protection goals (time scales, radiation protection goals); 4 - safety approach and principles of storage facilities: safety of the isolation system (confinement system, safety analysis, scenarios, radiological consequences, safety principles), assessment of the radiation risks after the main phase of decay; 5 - safety of surface storage facilities: safety analysis of the confinement system of the Aube plant (barriers, scenarios, modeling, efficiency), evaluation of radiological risks after the main phase of decay; experience feedback of the Manche plant; variants of surface storage facilities in France and abroad (very low activity wastes, mine wastes, short living wastes with low and average activity); 6 - safety of deep geological disposal facilities: legal framework of the French research; international context; safety analysis of the confinement system

Partitioning and transmutation: Radioactive waste management option

International Nuclear Information System (INIS)

Stanculescu, A.

2005-01-01

destruction (coupled with Th fuel cycle). Reduction of long-term hazard of spent fuel or HLW by transforming long-lived radionuclides into short-lived or inactive elements is one of the main P and T objectives. Hazard reduction (P and T objective) requires very different and much more fundamental measures as compared to risk reduction. Nuclear Fuel Cycle Options are discussed: Conventional, once through fuel cycle with direct disposal of spent fuel, aqueous reprocessing fuel cycle with vitrification of high-level liquid waste (RFC) and advanced fuel cycle with partitioning of actinides

Waste Management Strategy in The Netherlands. Part 2. Strategy Principles and Influencing Issues

International Nuclear Information System (INIS)

Haverkate, B.R.W.

2002-01-01

This report reflects the Dutch input prepared in the framework of work package 2 of the EU thematic network COMPAS, which deals with the identification of alternative waste management strategies and issues influencing strategy selection in EU member states and their applicant countries. All elements that could have an effect in identifying alternative policies to manage (long-lived) radioactive wastes are addressed in this report. After a short introduction, in chapter 1, about some general issues influencing decision-making such as public acceptance, involvement, perception and (European) legislation, the considered disposal methods and disposal requirements are given in chapter 2. Chapter 3 of this report deals with the background topics of the current waste management strategy in The Netherlands. A detailed overview of (basic) strategy principles and their influencing issues is the subject of chapter 4. Issues considered include: safety and environmental impact; technical limitations; nuclear materials safeguards; monitoring and retrievability; ethical issues; public acceptance; (timing of) strategy development and implementation; and economical considerations. Relevant additional issues that could have an effect in identifying alternative waste management strategy are provided in appendices, including signed treaties (appendix B) and nuclear statutory regulations (appendix C)

Cyclotron production of molecules labelled with short-lived radioisotopes β+ emitters (15O, 13N, 11C) and their clinical uses

International Nuclear Information System (INIS)

Bougharouat, B.

1981-01-01

Clinical use of three short-lived radioisotopes: 15 O, 13 N and 11 C is studied on two complementary aspects. A production and purification system is realized; detection instruments in medical use are studied. The production of labelled molecules with the three radiotracers 15 O, 13 N, 11 C from the target bombardment with charged and accelerated particles was studied [fr

Overview of past activities for the use of short-lived radionuclides and the role of the Bureau of Radiological Health

International Nuclear Information System (INIS)

Paras, P.

1985-01-01

The Bureau of Radiological Health has developed a national program to control unnecessary medical radiation exposures to man and to assure the safe and effective use of radiation. The continuing interest and the role of the Bureau in the use of short-lived radionuclides (SLR's) are emphasized. An overview of the Bureau's SLR program, past accomplishments, and the status of production and use of iodine-123 are presented

Attitudes of the public about nuclear wastes

International Nuclear Information System (INIS)

Rankin, W.L.; Nealey, S.M.

1978-01-01

The disposal of nuclear wastes has become an important public issue in the past few years. In 1960, only a very small percentage of the American public questioned the safety of waste disposal methods, and no one opposed nuclear power for waste disposal reasons. By 1974, however, a slight majority of the public believed that the disposal of nuclear wastes was a serious problem associated with nuclear power, and from 1975 on, a small percentage of the public has opposed nuclear power for waste disposal reasons. More individuals believe that the technology is not available for acceptable waste management compared to the number of individuals who believe that the technology does exist. However, a majority of the public believe that modern technology can solve the waste disposal problem. Finally, nuclear technologists evaluate waste disposal problems differently from other groups. For instance, nuclear technologists believe that short-term safety is more important than long-term safety regarding waste disposal, while other groups, especially environmentalists, believe that long-term safety is more important than short-term safety. Nuclear technologists are willing to accept a higher level of waste management-related risk than other groups and evaluate waste disposal problems as being less severe than other societal problems

Radioecological activity limits for radioactive waste disposal

International Nuclear Information System (INIS)

Ahmet, E. Osmanlioglu

2006-01-01

Full text: Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides. Near surface disposal term includes broad range of facilities from simple trenches to concrete vaults. Principally, disposal of radioactive waste requires the implementation of measures that will provide safety for human health and environment now and in the future. For this reason preliminary activity limits should be determined to avoid radioecological problems. Radioactive waste has to be safely disposed in a regulated manner, consistent with internationally agreed principles and standards and with national legislations to avoid serious radioecological problems. The purpose of this study, presents a safety assessment approach to derive operational and post-closure radioecological activity limits for the disposal of radioactive waste. Disposal system has three components; the waste, the facility (incl. engineered barriers) and the site (natural barriers). Form of the waste (unconditioned or conditioned) is effective at the beginning of the migration scenerio. Existence of the engineered barriers in the facility will provide long term isolation of the waste from environment. The site characteristics (geology, groundwater, seismicity, climate etc.) are important for the safety of the system. Occupational exposure of a worker shall be controlled so that the following dose limits are not exceeded: an effective dose of 20mSv/y averaged over 5 consecutive years; and an effective dose of 50mSv in any single year. The effective dose limit for members of the public recommended by ICRP and IAEA is 1 mSv/y for exposures from all man-made sources [1,2]. Dose constraints are typically a fraction of the dose limit and ICRP recommendations (0.3 mSv/y) could be applied [3,4]. Radioecological activity concentration limits of each radionuclide in the waste (Bq/kg) were calculated. As a result of this study radioecological activity

Infrastructure needs for waste management

International Nuclear Information System (INIS)

Takahashi, M.

2001-01-01

National infrastructures are needed to safely and economically manage radioactive wastes. Considerable experience has been accumulated in industrialized countries for predisposal management of radioactive wastes, and legal, regulatory and technical infrastructures are in place. Drawing on this experience, international organizations can assist in transferring this knowledge to developing countries to build their waste management infrastructures. Infrastructure needs for disposal of long lived radioactive waste are more complex, due to the long time scale that must be considered. Challenges and infrastructure needs, particularly for countries developing geologic repositories for disposal of high level wastes, are discussed in this paper. (author)

Radioactive waste interim storage in Germany

International Nuclear Information System (INIS)

2015-12-01

The short summary on the radioactive waste interim storage in Germany covers the following issues: importance of interim storage in the frame of radioactive waste management, responsibilities and regulations, waste forms, storage containers, transport of vitrified high-level radioactive wastes from the reprocessing plants, central interim storage facilities (Gorleben, Ahaus, Nord/Lubmin), local interim storage facilities at nuclear power plant sites, federal state collecting facilities, safety, radiation exposure in Germany.

Brief overview of the long-lived radionuclide separation processes developed in France in connection with the SPIN program

International Nuclear Information System (INIS)

Madic, C.; Bourges, J.; Dozol, J.F.

1995-01-01

To reduce the long-term potential hazards associated with the management of nuclear wastes generated by nuclear fuel reprocessing, one alternative is the transmutation of long-lived radionuclides into short-lived radionuclides by nuclear means (P ampersand T strategy). In this context, according to the law passed by the French Parliament on 30 December 1991, the CEA launched the SPIN program for the design of long-lived radionuclide separation and nuclear incineration processes. The research in progress to define separation processes focused mainly on the minor actinides (neptunium, americium and curium) and some fission products, like cesium and technetium. To separate these long-lived radionuclides, two strategies were developed. The first involves research on new operating conditions for improving the PUREX fuel reprocessing technology. This approach concerns the elements neptunium and technetium (iodine and zirconium can also be considered). The second strategy involves the design of new processes; DIAMEX for the co-extraction of minor actinides from the high-level liquid waste leaving the PUREX process, An(III)/Ln(III) separation using tripyridyltriazine derivatives or picolinamide extracting agents; SESAME for the selective separation of americium after its oxidation to Am(IV) or Am(VI) in the presence of a heteropolytungstate ligand, and Cs extraction using a new class of extracting agents, calixarenes, which exhibit exceptional Cs separation properties, especially in the presence of sodium ion. This lecture focuses on the latest achievements in these research areas

Brief overview of the long-lived radionuclide separation processes developed in france in connection with the spin program

Science.gov (United States)

Madic, Charles; Bourges, Jacques; Dozol, Jean-François

1995-09-01

To reduce the long-term potential hazards associated with the management of nuclear wastes generated by nuclear fuel reprocessing, one alternative is the transmutation of long-lived radionuclides into short-lived radionuclides by nuclear means (P & T strategy). In this context, according to the law passed by the French Parliament on 30 December 1991, the CEA launched the SPIN program for the design of long-lived radionuclide separation and nuclear incineration processes. The research in progress to define separation processes focused mainly on the minor actinides (neptunium, americium and curium) and some fission products, like cesium and technetium. To separate these long-lived radionuclides, two strategies were developed. The first involves research on new operating conditions for improving the PUREX fuel reprocessing technology. This approach concerns the elements neptunium and technetium (iodine and zirconium can also be considered). The second strategy involves the design of new processes; DIAMEX for the co-extraction of minor actinides from the high-level liquid waste leaving the PUREX process, An(III)/Ln(III) separation using tripyridyltriazine derivatives or picolinamide extracting agents; SESAME for the selective separation of americium after its oxidation to Am(IV) or Am(VI) in the presence of a heteropolytungstate ligand, and Cs extraction using a new class of extracting agents, calixarenes, which exhibit exceptional Cs separation properties, especially in the presence of sodium ion. This lecture focuses on the latest achievements in these research areas.

Brief overview of the long-lived radionuclide separation processes developed in France in connection with the SPIN program

Energy Technology Data Exchange (ETDEWEB)

Madic, C.; Bourges, J. [DRDD, Fontenay-aux-Roses (France); Dozol, J.F. [DESD, Cadarache (France)

1995-10-01

To reduce the long-term potential hazards associated with the management of nuclear wastes generated by nuclear fuel reprocessing, one alternative is the transmutation of long-lived radionuclides into short-lived radionuclides by nuclear means (P & T strategy). In this context, according to the law passed by the French Parliament on 30 December 1991, the CEA launched the SPIN program for the design of long-lived radionuclide separation and nuclear incineration processes. The research in progress to define separation processes focused mainly on the minor actinides (neptunium, americium and curium) and some fission products, like cesium and technetium. To separate these long-lived radionuclides, two strategies were developed. The first involves research on new operating conditions for improving the PUREX fuel reprocessing technology. This approach concerns the elements neptunium and technetium (iodine and zirconium can also be considered). The second strategy involves the design of new processes; DIAMEX for the co-extraction of minor actinides from the high-level liquid waste leaving the PUREX process, An(III)/Ln(III) separation using tripyridyltriazine derivatives or picolinamide extracting agents; SESAME for the selective separation of americium after its oxidation to Am(IV) or Am(VI) in the presence of a heteropolytungstate ligand, and Cs extraction using a new class of extracting agents, calixarenes, which exhibit exceptional Cs separation properties, especially in the presence of sodium ion. This lecture focuses on the latest achievements in these research areas.

Assessing inventories of past radioactive waste arisings at Chalk River Laboratories

International Nuclear Information System (INIS)

Csullog, G.W.; TerHuurne, M.A.; Miller, M.T.; Edwards, N.W.; Hulley, V.R.; McCann, D.J.

1998-01-01

' is used to support the management of currently accumulating radioactive wastes and how this same 'warehouse of information' is the basis for the development of a novel way to assess historic waste inventories. Records of waste emplaced into storage facilities at CRL since the mid 1940's are in a variety of formats and the quality of the data recorded is inconsistent. In addition, prior to recent improvements in waste management, wastes that should have been collected and handled separately (short-lived versus long-lived) were usually handled and stored together on the basis of external radiation field not on their requirements for long-term management. As such, the challenge is to assess historic waste management records in the context of today's waste management practices. Recent enhancements to the WIP-III application have provided the tools for this assessment. Historic records are entered into WIP-III 'as-is'. Next, using additional data entry screens, expert interpretation is used to identify historic wastes as similar to a current waste or similar to a mixture of current wastes. Next, the historic waste is assigned the characteristics of a current waste or of a mixture of current wastes, using the 'warehouse of information'. The interpretation process improves the quality of historic waste inventory records, which will allow AECL-CRL to provide defensible estimates of the characteristics of its historic wastes. This paper describes how the interpretation process can be generically applied to any waste site with historic wastes, independently of how those sites manage their current wastes. (author)

Thyroid cancer in the Marshallese: relative risk of short-lived internal emitters and external radiation exposure

International Nuclear Information System (INIS)

Lessard, E.T.; Brill, A.B.; Adams, W.H.

1986-01-01

In a study of the comparative effects of internal versus external irradiation of the thyroid in young people, we determined that the dose from internal irradiation of the thyroid with short-lived internal emitters produced several times less thyroid cancer than did the same dose of radiation given externally. The authors determined this finding for a group of 85 Marshall Islands children, who were less than 10 years of age at the time of exposure and who were accidentally exposed to internal and external thyroid radiation at an average level of 1400 rad. The external risk coefficient ranged between 2.5 and 4.9 cancers per million person-rad-years at risk, and thus, from our computations, the internal risk coefficient for the Marshallese children was estimated to range between 1.0 and 1.4 cancers per million person-rad-years at risk. In contrast, for individuals more than 10 years of age at the time of exposure, the dose from internal irradiation of the thyroid with short-lived internal emitters produced several times more thyroid cancer than did the same dose of radiation given externally. The external risk coefficients for the older age groups were reported in the above literature to be in the range of 1.0 to 3.3 cancers per million person-rad-years-at risk. The authors computed internal risk coefficients of 3.3 to 8.1 cancers per million person-rad-years at risk for adolescent and adult groups. This higher sensitivity to cancer induction in the exposed adolescents and adults, is different from that seen in other exposed groups. The small number of cancers in the exposed population and the influence of increased levels of TSH, nonuniform irradiation of the thyroid, and thyroid cell killing at high dose make it difficult to draw firm conclusions from these studies. 14 references, 8 tables

Long-lived radionuclides in low-level waste

International Nuclear Information System (INIS)

Cline, J.E.; Coe, L.J.

1983-01-01

In July 1982, the Low-Level Waste Licensing Branch of the NRC, anticipating the impact of the proposed Part 61 to 10 CFR, funded a two-year project by SAI to study the radionuclide contents of LWR generated in low-level waste. The objectives of the study are: (1) to analyze, using verified techniques, 150 archived samples for specified beta- and x-ray-emitting nuclides that had not previously been analyzed; (2) to analyze twenty new samples obtained from operating plants for all relevant nuclides and compare them to previous data to ascertain trends; (3) to develop empirical scaling factors through the use of which concentrations of hard-to-analyze nuclides can be estimated from analyses of the gamma-ray emitting nuclides. The new samples are analyzed and the results are summarized and interpreted. Over fifty archived samples have also been analyzed. We discuss scaling factor development. Factors are presented that relate 63 Ni and 59 Ni to 60 Co for PWRs and to 58 Co for BWRs, 90 Sr to 137 Cs for BWRs and 241 Pu, 239 Pu, 241 Am, and 244 Cm to 144 Ce for all LWRs. 8 figures, 3 tables

Waste management in MOX fuel fabrication plants

International Nuclear Information System (INIS)

Schneider, V.

1982-01-01

After a short description of a MOX fuel fabrication plant's activities the waste arisings in such a plant are discussed according to nature, composition, Pu-content. Experience has shown that proper recording leads to a reduction of waste arisings by waste awareness. Aspects of the treatment of α-waste are given and a number of treatment processes are reviewed. Finally, the current waste management practice and the α-waste treatment facility under construction at ALKEM are outlined. (orig./RW)

Waste Generation Overview, Course 23263

International Nuclear Information System (INIS)

Simpson, Lewis Edward

2016-01-01

This course, Waste Generation Overview Live (COURSE 23263), provides an overview of federal and state waste management regulations, as well as Los Alamos National Laboratory (LANL) policies and procedures for waste management operations. The course covers the activities involved in the cradle-to-grave waste management process and focuses on waste characterization, waste compatibility determinations and classification, and the storage requirements for temporary waste accumulation areas at LANL. When you have completed this course, you will be able to recognize federal, state, and LANL environmental requirements and their impact on waste operations; recognize the importance of the cradle-to-grave waste management process; identify the roles and responsibilities of key LANL waste management personnel (e.g., Waste Generator, Waste Management Coordinator, Waste Stream Profile approver, and Waste Certification Official); characterize a waste stream to determine whether it meets the definition of a hazardous waste, as well as characterize the use and minimum requirements for use of acceptable knowledge (AK) for waste characterization and waste compatibility documentation requirements; and identify the requirements for setting up and managing temporary waste accumulation areas.

Waste Generation Overview, Course 23263

Energy Technology Data Exchange (ETDEWEB)

Simpson, Lewis Edward [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-11-28

This course, Waste Generation Overview Live (COURSE 23263), provides an overview of federal and state waste management regulations, as well as Los Alamos National Laboratory (LANL) policies and procedures for waste management operations. The course covers the activities involved in the cradle-to-grave waste management process and focuses on waste characterization, waste compatibility determinations and classification, and the storage requirements for temporary waste accumulation areas at LANL. When you have completed this course, you will be able to recognize federal, state, and LANL environmental requirements and their impact on waste operations; recognize the importance of the cradle-to-grave waste management process; identify the roles and responsibilities of key LANL waste management personnel (e.g., Waste Generator, Waste Management Coordinator, Waste Stream Profile approver, and Waste Certification Official); characterize a waste stream to determine whether it meets the definition of a hazardous waste, as well as characterize the use and minimum requirements for use of acceptable knowledge (AK) for waste characterization and waste compatibility documentation requirements; and identify the requirements for setting up and managing temporary waste accumulation areas.

Nuclear fuel cycle and waste management in France

International Nuclear Information System (INIS)

Sousselier, Yves.

1981-05-01

After a short description of the nuclear fuel cycle mining, milling, enrichment and reprocessing, radioactive waste management in France is exposed. The different types of radioactive wastes are examined. Storage, solidification and safe disposal of these wastes are described