WorldWideScience

Sample records for radioactive clean nuclear

  1. A new option for exploitage of future nuclear energy. Accelerator driven radioactive clean nuclear power system

    International Nuclear Information System (INIS)

    Ding Dazhao

    2000-01-01

    Nuclear energy is an effective, clean and safe energy resource. But some shortages of the nuclear energy system presently commercial available obstruct further development of the nuclear energy by heavy nuclear fission. Those are final disposal of the high level radioactive waste, inefficient use of the uranium resource and safety issue of the system. Innovative technical option is seeking for by the nuclear scientific community in recent ten years in aiming to overcome these obstacles, namely, accelerator driven sub-critical system (ADS). This hybrid system may bridge over the gap between presently commercial available nuclear power system and the full exploitation of the fusion energy. The basic principle of ADS is described and its capability in waste transmutation, conversion of the nuclear fuel are demonstrated by two examples--AD-fast reactor and AD-heavy water thermal reactor. The feasibility of ADS and some projects in US, Japan, etc are briefly discussed. The rationale in promoting the R and D of ADS in China is emphasized as China is at the beginning stage of its ambitious project in construction of the nuclear power

  2. Radioactive Waste and Clean-up: Introduction

    International Nuclear Information System (INIS)

    Collard, G.

    2007-01-01

    The primary mission of the Radioactive Waste and Clean-up division is to propose, to develop and to evaluate solutions for a safe, acceptable and sustainable management of radioactive waste. The Radioactive Waste and Clean-up division programme consists in research, studies, development and demonstration aiming to realise the objective of Agenda 21 on sustainable development in the field of radioactive waste and rehabilitation on radioactively contaminated sites. Indeed, it participates in the realisation of an objective which is to ensure that radioactive wastes are safely managed, transported, stored and disposed of, with a view to protecting human health and the environment, within a wider framework of an interactive and integrated approach to radioactive waste management and safety. We believe that nuclear energy will be necessary for the sustainable development of mankind in the 21st century, but we well understand that it would not be maintained if it is not proven that within benefits of nuclear energy a better protection of the environment is included. Although the current waste management practices are both technically and from the environmental point of view adequate, efforts in relation of future power production and waste management technologies should be put on waste minimisation. Therefore, the new and innovative reactors, fuel cycle and waste management processes and installations should be designed so that the waste generation can be kept in minimum. In addition to the design, the installations should be operated so as to create less waste; consideration should be given e.g. to keeping water chemistry clean and other quality factors. SCK-CEN in general and the Radioactive Waste and Clean-up division in particular are present in international groups preparing the development of innovative nuclear reactors, as Generation 4 and INPRO. Because performance assessments are often black boxes for the public, demonstration is needed for the acceptation of

  3. Nuclear air cleaning

    International Nuclear Information System (INIS)

    Bellamy, R.R.

    1994-01-01

    This report briefly describes the history of the use of high- efficiency particulate air filters for air cleaning at nuclear installations in the United States and discusses future uses of such filters

  4. Clean-up of a radioactive spill

    International Nuclear Information System (INIS)

    Fish, W.

    1987-01-01

    Bikini Atoll in the Marshall Islands of the South Pacific was extensively contaminated with radionuclides deposited by thermonuclear weapons testing in the 1940s and 1950s. In recent years, the U.S. government has attempted to restore the habitability of the islands by cleaning up the remaining radioactive material. Although the island no longer presents an acute radiation risk to inhabitants, plants growing on the island concentrate cesium-137 from the soil, presenting an unacceptable risk to the future population. The behavior of Cs-137 has proved to be an intractable problem that has major implications for the risks associated with transporting and processing high-level nuclear wastes in the U.S. Various proposed soil treatment strategies for Bikini are discussed, including ion-exchange treatments and competing-ion strategies. No fully satisfactory treatment currently exists and the problems and prospects of cleaning up after a major nuclear waste spill are presented

  5. Radioactive Waste and Clean-up Division

    International Nuclear Information System (INIS)

    Collard, G.

    2001-01-01

    The main objectives of the Radioactive Waste and Clean-up division of SCK-CEN are outlined. The division's programme consists of research, development and demonstration projects and aims to contribute to the objectives of Agenda 21 on sustainable development in the field of radioactive waste and rehabilitation of radioactively contaminated sites

  6. Clean nuclear power (2. part)

    International Nuclear Information System (INIS)

    Rocherolles, R.

    1998-01-01

    The 450 nuclear power plants which produce 24% of world electricity do not generate greenhouse gas effects, but 8,000 tonnes per year of irradiated, radioactive fuel. The first article which was published in the July-August 1997 issue of this journal, described the composition and management of these fuels. This article wish to show the advantage of 'advanced re-processing', which would separate fission products from actinides, in order to incinerate them separately in dedicated fuels and reactors, which, from an ecological point of view, seems more efficient than burying them underground in deep, geological layers. To rid the planet of waste which is continuing to build up, the first step is to build 'incinerators' which will eliminate fission products by slow neutron assisted neutronic capture, and actinides by fast neutron assisted fission. Various projects have been set up, in particular, in Los Alamos, Japan and the CERN. The Carlo Rubbia hybrid machine operating on the well-known thorium cycle is the most advanced project. An incinerator connected up to standard PWR reactor produces no actinide, and reduces the existing stock of plutonium. However, the proper solution, obviously, is to no longer produce waste along with power; second generation nuclear fission will do this. The CERN team bas studied a clean reactor, producing practically no actinides, or fission products, more or less. Thus, the solution to the problem of waste is at hand, and nuclear power will be cleaner that all other types of power. The world market opening up to clean nuclear power is about 1,300 Gigawatts, or 1,300 plants of 1,000 Megawatts. Remarkable progress is taking place under our very eyes; soon we will have clean power in sufficient quantities, at a lower cost than that of other forms of power. (authors)

  7. Air conditioning systems to clean radioactive air

    International Nuclear Information System (INIS)

    Ganz, G.

    1987-01-01

    The author reports a study by the Institutes fuer Klimatechnik and Umweltschutz Giessen that shows that air conditioning systems not only make the atmosphere more comfortable, they also extract dust particles. This cleaning action is also valid for radioactively contaminated air. (G.T.H./Auth.)

  8. Process for cleaning radioactively contaminated metal surfaces

    International Nuclear Information System (INIS)

    Mihram, R.G.; Snyder, G.A.

    1975-01-01

    A process is described for removing radioactive scale from a ferrous metal surface, including the steps of initially preconditioning the surface by contacting it with an oxidizing solution (such as an aqueous solution of an alkali metal permanganate or hydrogen peroxide), then, after removal or decomposition of the oxidizing solution, the metallic surface is contacted with a cleaning solution which is a mixture of a mineral acid and a complexing agent (such as sulfuric acid and oxalic acid), and which preferably contains a corrosion inhibitor. A final step in the process is the treatment of the spent cleaning solution containing radioactive waste materials in solution by adding a reagent selected from the group consisting of calcium hydroxide or potassium permanganate and an alkali metal hydroxide to thereby form easily recovered metallic compounds containing substantially all of the dissolved metals and radioactivity. (auth)

  9. Radioactivity and countermeasures like clean feeding of sheep

    International Nuclear Information System (INIS)

    2011-01-01

    It's been 25 years since the nuclear accident at Chernobyl, but there is still radioactivity remaining in the Norwegian nature. The radioactive cesium-137 is taken up by plants and fungi and transferred to animals on rangelands. In the grazing season of 2010 had 20 000 sheep on Countermeasures like clean feeding to reduce radioactivity levels in the meat before slaughter. Oppland had most sheep on Countermeasures like clean feeding with almost 12 000 animals. Total was paid 2.2 million in compensation to livestock owners in 2010. In the period 1986-2010 is about 2.2 million sheep have been suspended with a charge of approximately NOK 227 million. (AG)

  10. New Approaches to Cleaning Liquid Radioactive Waste

    Directory of Open Access Journals (Sweden)

    Zabulonov, Yu.L.

    2015-05-01

    Full Text Available The industrial cleaning methods of liquid radioactive waste and technologically contaminated solutions, which contain heavy metals and radionuclides, are considered. It is shown that in the case when heavy metal ions exclusively exist in ionic form, the cleaning method with highest efficiency is electrodialysis. In the case when components, which must be removed, are in ionic and colloidal forms at the same time, the previous destruction of colloidal and organic matter (method of hydrodynamic cavitation, lowtemperature plasma etc is necessary. The developed «PTANK» method enables an effective purification of multicomponent metalcontaining man-made solutions, which contain additionally organic substances and complexes. Development of advanced membrane technologies, creation of complex recycling schemes and their synergistic combination will provide an opportunity to achieve deep cleaning of technologically contaminated solutions and minimize the amount of secondary wastes.

  11. Environmental remediation. Strategies and techniques for cleaning radioactively contaminated sites

    International Nuclear Information System (INIS)

    Falck, W. Eberhard

    2001-01-01

    Actions for a cleaner and safety environment have risen on social and political agendas in recent years. They include efforts to remediate contaminated sites posing a radiological risk to humans and the surrounding environment. Radiological risks can result from a variety of nuclear and non-nuclear activities. They include: nuclear or radiological accidents; nuclear weapons production and testing; poor radioactive waste management and disposal practices; industrial manufacturing involving radioactive materials; conventional mining and milling of ores and other production processes, e.g. oil and gas production, resulting in enhanced concentrations of naturally occurring radioactive materials (NORMs). The IAEA has developed a comprehensive programme directed at the remediation of radioactively contaminated sites. The programme collates and distributes knowledge about contaminated sites; appropriate methods for their characterization; assessment of their potential environmental and radiological impact; and applicable methods for their clean-up, following internationally recommended safety criteria. The overall resources, and which are technologically less advanced, to focus their efforts and chose appropriate strategies for the abatement or removal of exposure to radiation. An important aspect is the intention to 'close the loop' in the nuclear fuel cycle in the interests of sustainable energy development including nuclear power

  12. Radioactivity and nuclear waste

    International Nuclear Information System (INIS)

    Saas, A.

    1996-01-01

    Radioactive wastes generated by nuclear activities must be reprocessed using specific treatments before packaging, storage and disposal. This digest paper gives first a classification of radioactive wastes according to their radionuclides content activity and half-life, and the amount of wastes from the different categories generated each year by the different industries. Then, the radiotoxicity of nuclear wastes is evaluated according to the reprocessing treatments used and to their environmental management (surface storage or burial). (J.S.)

  13. Clean contest for nuclear

    International Nuclear Information System (INIS)

    Dunn, John.

    1996-01-01

    Reinvestment in the nuclear power generation industry is identified as the key to solving the conflict between rising energy demand over the next fifty years and protecting the environment. Nuclear power, it is argued, can readily meet consumers, rising demand for electricity, but will not contribute to global warming problems or other forms of atmospheric pollution. The chief problems seem not to be technical, but rather to convince policy makers and the general public that the nuclear industry is an acceptable, environmentally sound contributer to the energy generation conundrum. (UK)

  14. Radioactivity and nuclear energy

    International Nuclear Information System (INIS)

    Hoffmann, J.; Kuczera, B.

    2001-05-01

    The terms radioactivity and nuclear energy, which have become words causing irritation in the political sphere, actually represent nothing but a large potential for innovative exploitation of natural resources. The contributions to this publication of the Karlsruhe Research Center examine more closely three major aspects of radioactivity and nuclear energy. The first paper highlights steps in the history of the discovery of radioactivity in the natural environment and presents the state of the art in health physics and research into the effects of exposure of the population to natural or artificial radionuclides. Following contributions focus on: Radiochemical methods applied in the medical sciences (diagnostic methods and devices, therapy). Nuclear energy and electricity generation, and the related safety policies, are an important subject. In this context, the approaches and pathways taken in the field of nuclear science and technology are reported and discussed from the angle of nuclear safety science, and current trends are shown in the elaboration of advanced safety standards relating to nuclear power plant operation and ultimate disposal of radioactive wastes. Finally, beneficial aspects of nuclear energy in the context of a sustainable energy policy are emphasized. In particular, the credentials of nuclear energy in the process of building an energy economy based on a balanced energy mix which combines economic and ecologic advantages are shown. (orig./CB) [de

  15. Processing method of radioactive cleaning drain

    International Nuclear Information System (INIS)

    Otsuka, Shigemitsu; Murakami, Tadashi; Kitao, Hideo

    1998-01-01

    Upon processing of radioactive cleaning drains, contained Co-60 is removed by a selectively adsorbing adsorbent. In addition, after removing suspended materials by a filtering device, Co-60 as predominant nuclides in the drain is selectively adsorbed. The concentration of objective Co-60 is in the order of 0.1 Bq/cc, and non-radioactive metal ions such as Na + ions are present in the order of ppm in addition to Co-60. A granular adsorbent for selectively adsorbing Co-60 is oxine-added activated carbon, and has a grain size of from 20 to 48 mesh. The granular adsorbent is used while being filled in an adsorbing tower. Since a relatively simple device comprising the filtering device and the adsorbing tower in combination is provided, the reduction of the construction cost can be expected. In addition, since no filtering aid is used in the filtering device, the amount of secondary wastes is small. (N.H.)

  16. Radioactive wastes of Nuclear Industry

    International Nuclear Information System (INIS)

    1995-01-01

    This conference studies the radioactive waste of nuclear industry. Nine articles and presentations are exposed here; the action of the direction of nuclear installations safety, the improvement of industrial proceedings to reduce the waste volume, the packaging of radioactive waste, the safety of radioactive waste disposal and environmental impact studies, a presentation of waste coming from nuclear power plants, the new waste management policy, the international panorama of radioactive waste management, the international transport of radioactive waste, finally an economic analysis of the treatment and ultimate storage of radioactive waste. (N.C.)

  17. Nuclear air cleaning programs in progress in France

    International Nuclear Information System (INIS)

    Mulcey, P.

    1991-01-01

    A short presentation is given of the nuclear air cleaning programs in progress in France with respect to pressurized water reactors, fuel reprocessing plants, radioactive waste management facilities, and the dismantling of nuclear facilities. The effects of fires in rooms and ventilation ducts in all nuclear facilities is being studied and computer simulation codes are being developed. A brief review of filter development and filter testing is also presented

  18. Coolant clean-up system in nuclear reactor

    International Nuclear Information System (INIS)

    Tsuburaya, Hirobumi; Akita, Minoru; Shiraishi, Tadashi; Kinoshita, Shoichiro; Okura, Minoru; Tsuji, Akio.

    1987-01-01

    Purpose: To ensure a sufficient urging pressure at the inlet of a coolant clean-up system pump in a nuclear reactor and eliminate radioactive contaminations to the pump. Constitution: Coolant clean-up system (CUW) pump in a nuclear reactor is disposed to the downstream of a filtration desalter and, for compensating the insufficiency of the urging pressure at the pump inlet, the reactor water intake port to the clean-up system is disposed to the downstream of the after-heat removing pump and the heat exchanger. By compensating the net positive suction head (NPSH) of the clean-up system from the residual heat removing system, the problems of insufficient NPSH for the CUW pump upon reactor shut-down can be dissolved and, accordingly, the reactor clean-up system can be arranged in the order of the heat exchanger, clean-up device and pump. Thus, the CUW pump acts on reactor water after cleaned-up in the clean-up device to reduce the radioactivity contamination to the pump. (Kawakami, Y.)

  19. Nuclear radioactive techniques applied to materials research

    CERN Document Server

    Correia, João Guilherme; Wahl, Ulrich

    2011-01-01

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

  20. Cleaning device for steam units in a nuclear power plant

    International Nuclear Information System (INIS)

    Sasamuro, Takemi.

    1978-01-01

    Purpose: To prevent radioactive contamination upon dismantling and inspection of steam units such as a turbine to a building containing such units and the peripheral area. Constitution: A steam generator indirectly heated by steam supplied from steam generating source in a separate system containing no radioactivity is provided to produce cleaning steam. A cleaning steam pipe is connected by way of a stop valve between separation valve of a nuclear power plant steam pipe and a high pressure turbine. Upon cleaning, the separation valve is closed, and steam supplied from the cleaning steam pipe is flown into a condenser. The water thus condensated is returned by way of a feed water heater and a condenser to a water storage tank. (Nakamura, S.)

  1. Modified microspheres for cleaning liquid wastes from radioactive nuclides

    International Nuclear Information System (INIS)

    Danilin, Lev; Drozhzhin, Valery

    2007-01-01

    An effective solution of nuclear industry problems related to deactivation of technological and natural waters polluted with toxic and radioactive elements is the development of inorganic sorbents capable of not only withdrawing radioactive nuclides, but also of providing their subsequent conservation under conditions of long-term storage. A successful technical approach to creation of sorbents can be the use of hollow aluminosilicate microspheres. Such microspheres are formed from mineral additives during coal burning in furnaces of boiler units of electric power stations. Despite some reduction in exchange capacity per a mass unit of sorbents the latter have high kinetic characteristics that makes it possible to carry out the sorption process both in static and dynamic modes. Taking into account large industrial resources of microspheres as by-products of electric power stations, a comparative simplicity of the modification process, as well as good kinetic and capacitor characteristics, this class of sorbents can be considered promising enough for solving the problems of cleaning liquid radioactive wastes of various pollution levels. (authors)

  2. Radioactive tracers in the assessment of cleaning of surgical appliances

    International Nuclear Information System (INIS)

    Mostafa, A.B.M.G.; Chackett, K.F.

    1975-01-01

    Radioactive tracers which may be used in the assessment of cleaning of surgical appliances are described. Five labelled compounds were used as soiling material and tested in the rather severe conditions that exist during cleaning cycles. Measurements of decontamination in two cases were considered reliable but in the other three some degree of decomposition of the soil occurred, which falsified the results. (author)

  3. Proceedings of the 21st DOE/NRC Nuclear Air Cleaning Conference

    International Nuclear Information System (INIS)

    First, M.W.; Harvard Univ., Boston, MA

    1991-02-01

    Separate abstracts have been prepared for the papers presented at the meeting on nuclear facility air cleaning technology in the following specific areas of interest: air cleaning technologies for the management and disposal of radioactive wastes; Canadian waste management program; radiological health effects models for nuclear power plant accident consequence analysis; filter testing; US standard codes on nuclear air and gas treatment; European community nuclear codes and standards; chemical processing off-gas cleaning; incineration and vitrification; adsorbents; nuclear codes and standards; mathematical modeling techniques; filter technology; safety; containment system venting; and nuclear air cleaning programs around the world. (MB)

  4. Proceedings of the 21st DOE/NRC Nuclear Air Cleaning Conference; Sessions 1--8

    Energy Technology Data Exchange (ETDEWEB)

    First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

    1991-02-01

    Separate abstracts have been prepared for the papers presented at the meeting on nuclear facility air cleaning technology in the following specific areas of interest: air cleaning technologies for the management and disposal of radioactive wastes; Canadian waste management program; radiological health effects models for nuclear power plant accident consequence analysis; filter testing; US standard codes on nuclear air and gas treatment; European community nuclear codes and standards; chemical processing off-gas cleaning; incineration and vitrification; adsorbents; nuclear codes and standards; mathematical modeling techniques; filter technology; safety; containment system venting; and nuclear air cleaning programs around the world. (MB)

  5. Radioactive waste management policy for nuclear power

    International Nuclear Information System (INIS)

    Andrei, V.; Glodeanu, F.; Simionov, V.

    1998-01-01

    Nuclear power is part of energy future as a clean and environmental friendly source of energy. For the case of nuclear power, two specific aspects come more often in front of public attention: how much does it cost and what happens with radioactive waste. The competitiveness of nuclear power vs other sources of energy is already proved in many developed and developing countries. As concerns the radioactive wastes treatment and disposal, industrial technologies are available. Even final solutions for disposal of high level radioactive waste, including spent fuel, are now fully developed and ready for large scale implementation. Policies and waste management strategies are established by all countries having nuclear programs. Once, the first nuclear power reactor was commissioned in Romania, and based on the national legal provisions, our company prepared the first issue of a general strategy for radioactive waste management. The general objective of the strategy is to dispose the waste according to adequate safety standards protecting the man and the environment, without undue burden on future generations. Two target objectives were established for long term: an interim spent fuel dry storage facility and a low and intermediate level waste repository. A solution for spent fuel disposal will be implemented in the next decade, based on international experience. Principles for radioactive waste management, recommended by IAEA are closely followed in the activities of our company. The continuity of responsibilities is considered to be very important. The radioactive waste management cost will be supported by the company. A tax on unit price of electricity will be applied. The implementation of radioactive waste management strategy includes as a major component the public information. A special attention will be paid by the company to an information program addressed to different categories of public in order to have a better acceptance of our nuclear power projects

  6. Clean energy : nuclear energy world

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-10-15

    This book explains the nuclear engineering to kids with easy way. There are explanations of birth of nuclear energy such as discover of nuclear and application of modern technology of nuclear energy, principles and structure of nuclear power plant, fuel, nuclear waste management, use of radiation for medical treatment, food supplies, industry, utilization of neutron. It indicates the future of nuclear energy as integral nuclear energy and nuclear fusion energy.

  7. Coolant cleaning facility for nuclear reactor

    International Nuclear Information System (INIS)

    Kuboniwa, Takao; Konno, Yasuhiro; Kumaya, Shin; Osumi, Katsumi.

    1982-01-01

    Purpose: To remove cation of radioactive cobalt 60 produced in a reactor water during the ordinary operation of the reactor and chlorine when sea water is leaked in a condenser as well as to suppress an increase in iron clad containing radioactive cobalt 60 in the reactor water when the reactor is stopped. Constitution: A large flow rate high temperature cleaning system having an electromagnetic filter capable of removing radioactive substance in a reactor water, a low temperature cleaning system having a desalting unit using ion exchanger resin, a turbidity meter for measuring the turbidity of the reactor water and a conductivity meter for measuring the conductivity are provided. Further, flow rate control means are provided in the high and low temperature cleaning systems. The flow rate control means of the high temperature cleaning system is controlled by a measured signal of the turbidity meter, and the flow rete control means of the low temperature cleaning system is controlled by the measured signal of the conductivity meter. (Aizawa, K.)

  8. Nuclear waste water being cleaned in Paldinski

    International Nuclear Information System (INIS)

    Lahtinen, A.

    1995-01-01

    The cleaning of nuclear waste water in the former military base of Paldiski, Estonia, has started with Finnish assistance. During the Soviet era, Paldiski served as a site for training nuclear submarine crews. Spent fuel has already been removed from the two nuclear reactors on the base. The volume of water to be cleaned totals some 450 cubic metres. The work is estimated to take till May 1995. The filtering technique used for cleaning has been developed in cooperation by IVO International and the Department of Radiochemistry of the University of Helsinki. The project is one aspect of an extensive international cooperation programme for reducing environmental hazards arising from the base. The experience of the cleaning obtained so far has been positive. In the first water tank, filtering reduced the cesium activity of waste water from 1,500 becquerels to less than one becquerel. Two water tanks, however, have bottom sediment that probably cannot be treated during the present project. (orig.)

  9. Physics with radioactive nuclear beams

    International Nuclear Information System (INIS)

    Boyd, R.N.; Tanihata, I.

    1992-01-01

    Recently developed facilities allow a wide range of new investigations of the reactions and properties of short-lived nuclei. These studies may help to solve puzzles of nuclear structure and the Big Bang. The purpose of nuclear physics is to measure properties of specific nuclides and infer from them global properties common to all nuclides. One goal, for example, is to understand nuclear sizes and matter distributions in terms of basic nuclear forces. Another is to understand the variation throughout the periodic table of the dominant quantum states, which are known as the open-quotes nuclear shell modelclose quotes states and are characterized, much as are atomic states, by a principal quantum number and by orbital and total angular momentum quantum numbers. In turn other nuclear phenomena, such as the collective excitations known as giant resonances, can be understood in terms of the shell-model configurations and basic nuclear parameters. Radioactive nuclear beam studies of reactions of short-lived nuclides have already yielded results with important ramifications in both nuclear physics and astrophysics. Nuclear physicists expect unstable nuclides to exhibit unusual structures or features that may test their understanding of known nuclear phenomena at extreme conditions, and perhaps even to reveal previously unknown nuclear phenomena, Astrophysicists, for their part, have known for several decades that processes in both Big Bang nucleosynthesis and stellar nucleosynthesis involve short-lived nuclides. Indeed, the original motivation for developing radioactive nuclear beams was astrophysical. 25 refs., 7 figs

  10. Physics with radioactive nuclear beams

    International Nuclear Information System (INIS)

    Boyd, R.N.

    1995-01-01

    Recently developed facilities allow a wide range of new investigations of the reactions and properties of short-lived nuclei. These studies may help to solve puzzles of nuclear structure and the Big Bang. The purpose of nuclear physics is to measure properties of specific nuclides and infer from them global properties common to all nuclides, for example, is to understand nuclear sizes and matter distributions in terms of basic nuclear forces. Another is to understand the variation throughout the periodic table of the dominant quantum states, which are known as the open-quotes nuclear shell model close quotes states and are characterized, much as are atomic states, by a principal quantum number and by orbital and total angular momentum quantum numbers. In turn other nuclear phenomena, such as the collective excitations known as giant resonances, can be understood in terms of the shell-model configurations and basic nuclear parameters. Radioactive nuclear beam studies of reactions of short-lived nuclides have already yielded results with important ramifications in both nuclear physics and astrophysics. Nuclear physicists expect unstable nuclides to exhibit unusual structures or features that may test their understanding of known nuclear phenomena at extreme conditions, and perhaps even to reveal previously unknown nuclear phenomena, Astrophysicists, for their part, have known for several decades that processes in both Big Bang nucleosynthesis and stellar nucleosynthesis involve short-lived nuclides. Indeed, the original motivation for developing radioactive nuclear beams was astrophysical. (author). 25 refs., 7 figs

  11. Nuclear and radioactivity

    International Nuclear Information System (INIS)

    2000-01-01

    Among the industrial risks of nuclear facilities, the nuclear risk is often associated to the Chernobyl accident. This paper presents the nuclear major risk in a french PWR type power plant, with consequences on the personnel, the surrounding population and the environment. (A.L.B.)

  12. Air and gas cleaning technology for nuclear applications

    International Nuclear Information System (INIS)

    First, M.W.

    1986-01-01

    All large-scale uses of radioactive materials require rigid control of off-gases and generated aerosols. Nuclear air and gas cleaning technology has answered the need from the days of the Manhattan Project to the present with a variety of devices. The one with the longest and most noteworthy service is the HEPA (high efficiency particulate air) filter that originally was referred to as an absolute filter in recognition of its extraordinary particle retention characteristics. Activated-charcoal adsorbers have been employed worldwide for retention of volatile radioiodine in molecular and combined forms and, less frequently, for retention of radioactive noble gases. HEPA filters and activated -charcoal adsorbers are often used with auxiliary devices that serve to extend their effective service life or significantly improve collection efficiency under unfavorable operating conditions. Use of both air cleaning devices and their auxiliaries figure prominently in atomic energy, disposal of high- and low-level nuclear wastes, and in the production of fissile materials. The peaceful uses of nuclear energy would be impossible without these, or equivalent, air- and gas-cleaning devices

  13. Decontamination of radioactive contaminated protective wear using dry cleaning solvent

    International Nuclear Information System (INIS)

    Muthiah, Pushpa; Chitra, S.; Paul, Biplob

    2013-01-01

    Liquid waste generated by conventional decontamination of radioactive contaminated cotton protective wear using detergent affects the chemical treatment of the plant. To reduce the generation of aqueous detergent waste, dry cleaning of cotton protective wear, highly soiled with oil and grease towards decontamination was tried with organic solvents. Mineral turpentine oil (MTO) among various other organic solvents was identified as a suitable organic solvent. As MTO leaves characteristic odour on the cloth, various commercial fragrances for the removal of the odour were tried. Application of the optimised dry cleaning solvent and commercial fragrance was adopted in plant scale operation. (author)

  14. Cleaning of stack gases from combustion of low level radioactive waste in Studsvik, Sweden

    International Nuclear Information System (INIS)

    Haard, E.

    1979-01-01

    The plant for combustion of low-level radioactive waste at Studsvik, Sweden, is described. The waste that is treated comes from nuclear power plants, industry, hospitals and universities. It is estimated to be about 270 ton/year in a few years time. The waste consists of plast, cloth, wood, paper, rubber, biological material and unburnable components such as glass and metals. The bags with waste may have a maximum surface dose rate of 10 mrem/h. For 5 % of the bags the maximum dose rate may be 100 mrem/h. During the combustion, samples of the stack gases are collected. The release of radioactivity is reported to the Swedish authorities. During 1978 three different stack gas cleaning systems, wet cleaning, electrostatic filters and textile filters were investigated. The wet cleaning gave a radioactive sludge which was difficult to take care of. In the electrostatic filters it was difficult to change components due to radioactivity. Therefore the textile filters were chosen. A textile filter will be installed during 1979. The cleaning capacity of the filter is expected to be 90 % and will decrease the collective doses from stack gases with 6.7 manrem/year. The cost is estimated to 450 000 Sw kr/year (100 000 US dollar). (K.K.)

  15. Nuclear structure from radioactive decay

    International Nuclear Information System (INIS)

    Wood, J.L.

    1991-01-01

    This report discusses nuclear structure from radioactive decay of the following: Neutron-Deficient Iridium Isotopes; Neutron-Deficient Platinum Isotopes; Neutron-Deficient Gold Isotopes; Neutron-Deficient Mercury Isotopes; Neutron-Deficient Thallium Isotopes; Neutron-Deficient Lead Isotopes; Neutron-Deficient Samarium Isotopes; Neutron-Deficient Promethium Isotopes; Neutron-Deficient Neodymium Isotopes; and Neutron-Deficient Praseodymium Isotopes. Also discussed are Nuclear Systematics and Models

  16. Continuing challenges in nuclear air cleaning

    International Nuclear Information System (INIS)

    Moeller, D.W.

    1976-01-01

    The safe operation of nuclear facilities is heavily dependent upon the adequate performance of air cleaning systems. Although many problems have been solved, new questions and new challenges continue to arise. These are well illustrated by weaknesses in air cleaning and ventilating systems revealed by the Browns Ferry fire, and the need to develop additional data on the reliability of such systems, particularly under emergency conditions, as revealed by the Reactor Safety Study. Assessments of the degree to which engineered safety features can compensate for deficiencies in nuclear power plant sites continue to challenge those involved in risk/benefit evaluations. Additional challenges are being generated by the air cleaning requirements associated with the commercial development of the liquid metal fast breeder reactor

  17. Nuclear astrophysics with radioactive beams

    International Nuclear Information System (INIS)

    Bertulani, C.A.; Gade, A.

    2010-01-01

    The quest to comprehend how nuclear processes influence astrophysical phenomena is driving experimental and theoretical research programs worldwide. One of the main goals in nuclear astrophysics is to understand how energy is generated in stars, how elements are synthesized in stellar events and what the nature of neutron stars is. New experimental capabilities, the availability of radioactive beams and increased computational power paired with new astronomical observations have advanced the present knowledge. This review summarizes the progress in the field of nuclear astrophysics with a focus on the role of indirect methods and reactions involving beams of rare isotopes.

  18. Radioactivity around naval nuclear bases

    International Nuclear Information System (INIS)

    1989-02-01

    Between 12th July and 2nd August 1988, Greenpeace took sediment samples from around four Royal Navy bases in the United Kingdom. Faslane, where nuclear powered submarines are berthed; Devonport and Rosyth where refit work is carried out and Portsmouth where US and UK nuclear submarines often visit. Samples were also taken from the US Navy base at Holy Loch, Scotland, where nuclear powered ballistic missile submarines are based. The samples were analysed at St Bartholomew Hospital Medical School, London. Identical samples were provided to the MoD personnel at Faslane and Devonport on the date taken. The purpose of carrying out the sampling programme was to highlight the fact that publicly available statistics from Ministry of Agriculture Fisheries and Food (MAFF) are too limited in range, concentrating as they do merely on radioactive levels found between tides. The findings point to the necessity of monitoring subtidal as well as intertidal areas since levels of radioactivity found in the samples at Faslane and Holy Loch were four to nine times the figures published by MAFF. Until such time as nuclear power is no longer used at sea, it is the contention of Greenpeace that a more independent and comprehensive picture of the nature of radioactive contamination from around UK naval establishments must be obtained, than that presently available from MAFF. (author)

  19. Reduction of radioactivity produced by nuclear explosives

    Energy Technology Data Exchange (ETDEWEB)

    Lessler, Richard M [Lawrence Radiation Laboratory, University of California, Livermore, CA (United States)

    1970-05-15

    Four main sources contribute to the radioactivity produced by a nuclear explosive: 1. Fission products from the nuclear explosive, 2. Fusion products from the nuclear explosive, 3. Induced radioactivity in the nuclear explosive, 4. Induced radioactivity in the environment. This paper will summarize some of the work done at the Lawrence Radiation Laboratory at Livermore to reduce the radioactivity from these sources to levels acceptable for peaceful applications. Although it is theoretically possible to have no radioactivity produced by nuclear explosives, this goal has not been achieved.

  20. Nuclear energy from radioactive waste

    International Nuclear Information System (INIS)

    Schwarzenberg, M.

    1998-01-01

    The global energy demand is increasing. Sound forecasts indicate that by the year 2020 almost eight thousand million people will be living on our planet, and generating their demand for energy will require conversion of about 20 thousand million tonnes of coal equivalents a year. Against this background scenario, a new concept for energy generation elaborated by nuclear scientists at CERN attracts particular interest. The concept describing a new nuclear energy source and technology intends to meet the following principal requirements: create a new energy source that can be exploited in compliance with extremely stringent safety requirements; reduce the amount of long-lived radioactive waste; substantially reduce the size of required radwaste repositories; use easily available natural fuels that will not need isotopic separation; prevent the risk of proliferation of radioactive materials; process and reduce unwanted actinides as are generated by the operation of current breeder reactors; achieve high efficiency both in terms of technology and economics. (orig./CB) [de

  1. Nuclear power and radioactive waste

    International Nuclear Information System (INIS)

    Grimston, M.

    1991-03-01

    The gap between the relative perceptions in the area of nuclear waste is wide. The broad view of the industry is that the disposal of nuclear waste is not a serious technical problem, and that solutions are already available to provide safe disposal of all our waste. The broad view of those who oppose the industry is that radioactive waste is so unpleasant, and will remain lethal for so long, that no acceptable policy will ever be developed, and so production of such waste (except, oddly, the significant amounts arising from uses of radioactive materials in medicine, agriculture, industrial safety research, etc) should stop immediately. This booklet will not attempt to describe in great detail the technicalities of the United Kingdom nuclear industry's current approach to radioactive waste: such issues are described in detail in other publications, especially those by Nirex. It is our intention to outline some of the main issues involved, and to associate these issues with the divergence in perceptions of various parties. (author)

  2. Testing of nuclear air-cleaning systems

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    A standard is presented which describes methods for field-testing nuclear power plant air cleaning systems. Included are specifications for visual inspection; duct and housing leak test; mounting frame pressure leak test; airflow capacity, distribution, and residence time tests; air-aerosol mixing uniformity test; in place leak test of HEPA filter banks; multiple sampling technique; in-place leak test of adsorber stage; laboratory testing of adsorbent; and duct heater performance test

  3. State perspective on how clean is clean enough when radioactive materials are involved

    International Nuclear Information System (INIS)

    Bailey, E.D.

    1992-01-01

    The question of how much radioactive material can be left behind by a user of radioactive materials or how much radioactive material can be taken to a local sanitary landfill is not so much a scientific or technical question as it is a societal, philosophical, and, therefore, political issue. The issues are mired in the debates about nuclear power, nuclear weapons, big business, and distrust of government. Scientific and regulatory bodies add to the general public's true fears, concerns, uncertainties, and mistrust of radiation and things radioactive when they fail to act in a concise, logical, and at least coordinated manner. The bifurcation of standard setting responsibility at the federal level between the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Environmental Protection Agency and the agreement state system of regulating radioactive materials all add to the public's confusion and anxiety. The purpose of this paper is to point out from the viewpoint of a state regulatory agency problems that are seen as stumbling blocks to the implementation and acceptance of a below-regulatory-concern (BRC) policy

  4. Radioactive waste processing method for a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Sugimoto, Y; Kuriyama, O

    1976-06-04

    Object is to subject radioactive liquid waste in a nuclear power plant to reverse permeation process after which it is vaporized and concentrated thereby decreasing the quantity of foam to be used to achieve effective concentration of the liquid waste. Liquid waste containing a radioactive material produced from a nuclear power plant is first applied with pressure in excess of osmotic pressure by a reverse permeation device and is separated into clean water and concentrated liquid by semi-permeable membrane. Next, the thus reverse-permeated and concentrated waste is fed to an evaporator which control foaming by the foam and then further reconcentrated for purification of the liquid waste.

  5. Sizing of air cleaning systems for access to nuclear plant spaces

    International Nuclear Information System (INIS)

    Estreich, P.J.

    A mathematical basis is developed to provide the practicing engineer with a method for sizing air-cleaning systems for nuclear facilities. In particular, general formulas are provided to relate cleaning and contamination dynamics of an enclosure such that safe conditions are obtained when working crews enter. Included in these considerations is the sizing of an air-cleaning system to provide rapid decontamination of airborne radioactivity. Multiple-nuclide contamination sources, leak rate, direct radiation, contaminant mixing efficiency, filter efficiencies, air-cleaning-system operational modes, and criteria for maximum permissible concentrations are integrated into the procedure. (author)

  6. The nuclear age. Cleaning up the mess

    International Nuclear Information System (INIS)

    Menezes, M.; Stunell, A.

    2001-01-01

    This paper focuses on just one essential component of a 'non nuclear' future - the management of nuclear waste. Waste produced by nuclear power is invariably contaminated by radioactivity. It is therefore a serious health and environmental hazard which requires special consideration. As residual radioactive contamination is generally very long lasting, the treatment and disposal options not only have to be robust in themselves, but also capable of retaining their integrity for hundreds, even thousands of years. Until now the debate over the issue of nuclear waste has been polarised; on the one hand there are those who see blocking a long-term solution to waste management as a powerful lever against further nuclear development. On the other, there are those who are in favour of a nuclear-powered future and who consequently have attempted to minimise the problem of dealing with nuclear waste. However, the time is now right for developing a long-term waste strategy for two reasons. Firstly we are confronted with reality, as nuclear plants coming to the end of their life are decommissioned, and secondly, the privatisation of the electricity generation market- has meant that nuclear cannot longer compete in the market with cheaper forms of energy generation and so new build is unlikely. Two options for storing waste have, in the main, been explored: surface storage and geological disposal with the option of retrieval. We believe that geological disposal is the only real option as it does not rely on future societal or climate stability to remain safe and secure. The most vital requirements for the success of finding a long-term solution are public support and legitimacy. Nirex's attempt to gain planning permission for the Rock Characterisation Facility and experience in other countries of gaining support for geological disposal bear this out

  7. Coolant clean up system in nuclear reactor

    International Nuclear Information System (INIS)

    Tajima, Fumio; Iwami, Hiroshi.

    1981-01-01

    Purpose: To decrease the amount of main steams and improve the plant heat efficiency by the use of condensated water as coolants for not-regenerative heat exchangers in a coolant clean up system of a nuclear reactor. Constitution: In a coolant clean up system of a nuclear reactor, a portion of condensates is transferred to the shell of a non-regenerative heat exchanger by way of a condensate pump for non-regenerative heat exchanger through a branched pipeway provided to the outlet of a condensate desalter for using the condensates as the coolants for the shell of the heat exchanger and the condensates are then returned to the inlet of a feedwater heater after the heat exchange. The branched flow rate of the condensates is controlled by the flow rate control valve mounted in the pipeway. Condensates passed through the heat exchanger and the condensates not passed through the heat exchanger are mixed and heated in a heater and then fed to the nuclear reactor. In a case where no feedwater is necessary to the nuclear reactor such as upon shutdown of the reactor, the condensates are returned by way of feedwater bypass pipeway to the condensator. By the use of the condensates as the coolants for the heat exchanger, the main steam loss can be decreased and the thermal load for the auxiliary coolant facility can be reduced. (Kawakami, Y.)

  8. Glass containing radioactive nuclear waste

    International Nuclear Information System (INIS)

    Boatner, L.A.; Sales, B.C.

    1985-01-01

    Lead-iron phosphate glasses containing a high level of Fe 2 O 3 for use as a storage medium for high-level-radioactive nuclear waste. By combining lead-iron phosphate glass with various types of simulated high-level nuclear waste, a highly corrosion resistant, homogeneous, easily processed glass can be formed. For corroding solutions at 90 C, with solution pH values in the range between 5 and 9, the corrosion rate of the lead-iron phosphate nuclear waste glass is at least 10 2 to 10 3 times lower than the corrosion rate of a comparable borosilicate nuclear waste glass. The presence of Fe 2 O 3 in forming the lead-iron phosphate glass is critical. Lead-iron phosphate nuclear waste glass can be prepared at temperatures as low as 800 C, since they exhibit very low melt viscosities in the 800 to 1050 C temperature range. These waste-loaded glasses do not readily devitrify at temperatures as high as 550 C and are not adversely affected by large doses of gamma radiation in H 2 O at 135 C. The lead-iron phosphate waste glasses can be prepared with minimal modification of the technology developed for processing borosilicate glass nuclear waste forms. (author)

  9. Technical development of nuclear air cleaning in the People's Republic of China

    International Nuclear Information System (INIS)

    Li Xue Qun; Liu Hui; Wang Tie Shen; Xin Song Niam; Guo Liang Tian.

    1985-01-01

    In the past 20 years, with the utilization of nuclear technology in China, air cleaning techniques were developed to prevent the environment from pollution caused by radioactive materials and to ensure the safety of occupational personnel. The technical developments involve many fields including the manufacture of filter media and adsorbents; the application of filters and iodine adsorbers and the testing of them; the improvement of instruments and methods for aerosol concentration measurement; the retention of radioactive noble gases; and others. As nuclear power stations are to be built in China, nuclear air cleaning will be advancing more rapidly. Many programs have been scheduled, such as producing other types of adsorbers, moisture separators, nuclear grade HEPA filters that have excellent performance to resist adverse circumstances, and in-place testing for units of ventilation systems in nuclear facilities. These programs are discussed

  10. Antiprotonic Radioactive Atom for Nuclear Structure Studies

    International Nuclear Information System (INIS)

    Wada, M.; Yamazaki, Y.

    2005-01-01

    A future experiment to synthesize antiprotonic radioactive nuclear ions is proposed for nuclear structure studies. Antiprotonic radioactive nuclear atom can be synthesized in a nested Penning trap where a cloud of antiprotons is prestored and slow radioactive nuclear ions are bunch-injected into the trap. By observing of the ratio of π+ and π- produced in the annihilation process, we can deduce the different abundance of protons and neutrons at the surface of the nuclei. The proposed method would provide a unique probe for investigating the nuclear structure of unstable nuclei

  11. Radioactive waste: the poisoned legacy of the nuclear industry

    International Nuclear Information System (INIS)

    Rousselet, Y.

    2011-01-01

    The nuclear industry produces a huge amount of radioactive waste from one end to the other of the nuclear cycle: i.e. from mining uranium to uranium enrichment through reactor operating, waste reprocessing and dismantling nuclear power plants. Nuclear power is now being 'sold' to political leaders and citizens as an effective way to deal with climate change and ensure security of energy supplies. Nonetheless, nuclear energy is not a viable solution and is thus a major obstacle to the development of clean energy for the future. In addition to safety and security issues, the nuclear industry is, above all, faced with the huge problem of how to deal with the waste it produces and for which it has no solution. This ought to put a brake on the nuclear industry, but instead, against all expectations, its development continues to gather pace. (author)

  12. Nuclear toxicology. To detect, to clean

    International Nuclear Information System (INIS)

    Garcia, D.; Lecomte-Pradines, C.; Quemeneur, E.; Petitot, F.; Souidi, M.; Bertho, J.M.; Junot, Ch.; Malard, V.; Berthomieu, C.; Chapon, V.; Gilbin, R.; Misson-Pons, J.; Vavasseur, A.; Richaud, P.; Ansoborlo, E.; Taran, F.; Benech, H.; Fattal, E.; Tsapis, N.; Menetrier, F.; Deverre, J.R.; Burgada, R.

    2009-01-01

    This file shows two complementary parts: one aiming to a better detection of exposure for man and environment and and other one relative to the treatments to be used when there is a contamination. The development of biological captors is a research axis that could be very useful for nuclear toxicologists that wish to dispose of perceptible measurement tools. In the same idea biological markers could be an important help to determine the toxic quantity in organism in case of internal radioactive contamination. About remedial actions, bacteria are able to reduce, to oxide, to capture pollutants and then it is not insane to use them in efficient and low cost remediation for waters or contaminated lands, especially by trace metals or radioactive compounds. Next to them, plants can offer the same service it is the case for sunflower able to treat water loaded in uranium. This file ends with a review of the different treatments known nowadays as therapies for contamination by radioisotopes used in nuclear industry. (N.C.)

  13. Nuclear air cleaning activities in Germany

    International Nuclear Information System (INIS)

    Wilhelm, J.

    1991-01-01

    The discussion is limited to nuclear air cleaning activities in the Federal Republic of Germany. Work is underway on containment venting with regard to filtration based on a combination of stainless steel roughing and fine filters with a decontamination factor similar to or better than that achieved with high-efficiency particulate air filters. The main point of interest is the development of relatively small filter units that can be located inside the containment. The concept of a new design for double containment having annular rooms between the steel containment and the concrete containment is discussed. Work related to the dismantling of decommissioned reactors and limited research for fuel reprocessing facilities are also noted

  14. Survey on non-nuclear radioactive waste

    International Nuclear Information System (INIS)

    2003-11-01

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

  15. Design and operation of off-gas cleaning and ventilation systems in facilities handling low and intermediate level radioactive material

    International Nuclear Information System (INIS)

    1988-01-01

    The number of developing countries constructing new nuclear facilities is increasing. These facilities include the production and processing of radioisotopes, as well as all types of laboratories and installations, which handle radioactive material and deal with the treatment of radioactive wastes. Ventilation and air cleaning systems are a vital part of the general design of any nuclear facility. The combination of a well designed ventilation system with thorough cleaning of exhaust air is the main method of preventing radioactive contamination of the air in working areas and in the surrounding atmosphere. This report provides the latest information on the design and operation of off-gas cleaning and ventilation systems for designers and regulatory authorities in the control and operation of such systems in nuclear establishments. The report presents the findings of an Advisory Group Meeting held in Vienna from 1 to 5 December 1986 and attended by 12 experts from 11 Member States. Following this meeting, a revised report was prepared by the International Atomic Energy Agency Secretariat and three consultants, M.J. Kabat (Canada), W. Stotz (Federal Republic of Germany) and W.A. Fairhurst (United Kingdom). The final draft was commented upon and approved by the participants of the meeting. 69 refs, 37 figs, 12 tabs

  16. Radioactive waste management from nuclear facilities

    International Nuclear Information System (INIS)

    2005-06-01

    This report has been published as a NSA (Nuclear Systems Association, Japan) commentary series, No. 13, and documents the present status on management of radioactive wastes produced from nuclear facilities in Japan and other countries as well. Risks for radiation accidents coming from radioactive waste disposal and storage together with risks for reactor accidents from nuclear power plants are now causing public anxiety. This commentary concerns among all high-level radioactive waste management from nuclear fuel cycle facilities, with including radioactive wastes from research institutes or hospitals. Also included is wastes produced from reactor decommissioning. For low-level radioactive wastes, the wastes is reduced in volume, solidified, and removed to the sites of storage depending on their radioactivities. For high-level radioactive wastes, some ten thousand years must be necessary before the radioactivity decays to the natural level and protection against seismic or volcanic activities, and terrorist attacks is unavoidable for final disposals. This inevitably results in underground disposal at least 300 m below the ground. Various proposals for the disposal and management for this and their evaluation techniques are described in the present document. (S. Ohno)

  17. Transmutation of radioactive nuclear waste

    International Nuclear Information System (INIS)

    Toor, A; Buck, R

    2000-01-01

    Lack of a safe disposal method for radioactive nuclear waste (RNW) is a problem of staggering proportion and impact. A typical LWR fission reactor will produce the following RNW in one year: minor actinides (i.e. 237 Np, 242-243 Am, 243-245 Cm) ∼40 kg, long-lived fission products (i.e, 99 Tc, 93 Zr, 129 I, 135 Cs) ∼80 kg, short lived fission products (e.g. 137 Cs, 90 Sr) ∼50kg and plutonium ∼280 kg. The total RNW produced by France and Canada amounts to hundreds of metric tonnes per year. Obtaining a uniform policy dealing with RNW has been blocked by the desire on one hand to harvest the energy stored in plutonium to benefit society and on the other hand the need to assure that the stockpile of plutonium will not be channeled into future nuclear weapons. In the meantime, the quantity and handling of these materials represents a potential health hazard to the world's population and particularly to people in the vicinity of temporary storage facilities. In the U.S., societal awareness of the hazards associated with RNW has effectively delayed development of U.S. nuclear fission reactors during the past decade. As a result the U.S. does not benefit from the large investment of resources in this industry. Reluctance to employ nuclear energy has compelled our society to rely increasingly on non-reusable alternative energy sources; coal, oil, and natural gas. That decision has compounded other unresolved global problems such as air pollution, acid rain, and global warming. Relying on these energy sources to meet our increasing energy demands has led the U.S. to increase its reliance on foreign oil; a policy that is disadvantageous to our economy and our national security. RNW can be simplistically thought of as being composed of two principal components: (1) actinides with half lives up to 10 6 years and (2) the broad class of fission fragments with typical half lives of a few hundred years. One approach to the RNW storage problem has been to transmute the

  18. Radioactivity and Nuclear Issues in Science Fiction

    International Nuclear Information System (INIS)

    Franic, Z.

    2008-01-01

    In this work are presented and reviewed science fiction narratives, films and comics that exploit radioactivity and nuclear issues. These topics to some science fiction authors serve as metaphor of evil and holocaust as well as nice instrument for elaborating various manipulations and conspiracy theories. In that context are of special interest science fiction works depicting apocalyptic post-nuclear worlds and societies, such works being closely connected with cyberpunk genre. However, other more technologically optimistic authors nuclear energy and research regarding nuclear technology and radioactivity consider as eligible and inevitable solution for world peace and prosperity Nowadays, public interest and global fears are shifted from radioactivity and nuclear issues to other catastrophic scenarios threatening future of the mankind, these for example being climate changes and global warming, asteroid impact, collapse of information infrastructure, nanotechnology, robotics and artificial intelligence etc. Consequently, these issues are as well increasingly reflected in contemporary science fiction stories.(author)

  19. Experience with cleaning of sodium-wetted components and decontamination at Nuclear Research Centre Karlsruhe

    Energy Technology Data Exchange (ETDEWEB)

    Menzenhauer, P; Borgstedt, U; Stamm, H H; Dippel, Th; Kunze, S; Hentschel, D [Kernforschungszentrum Karlsruhe, Karlsruhe (Germany)

    1978-08-01

    Within the framework of the Fast Breeder Project various institutes of the KarIsruhe Nuclear Research Center operate sodium loops for corrosion studies and component tests under sodium. The operation of these loops has led to extensive experience in cleaning sodium-wetted components. This experience relates to the alcohol method, the removal of sodium by melting, storage in air, and to cleaning by means of steam. Deposition samples from radioactive sodium loops were used for decontamination experiments employing various decontaminating agents. The department concerned with the treatment of radioactive waste studied the use of molten salts and paste type cleansers for components unsuitable for mechanical decontamination, primarily with the objective to reduce the amount of radioactive waste. (author)

  20. Experience with cleaning of sodium-wetted components and decontamination at Nuclear Research Centre Karlsruhe

    International Nuclear Information System (INIS)

    Menzenhauer, P.; Borgstedt, U.; Stamm, H.H.; Dippel, Th.; Kunze, S.; Hentschel, D.

    1978-01-01

    Within the framework of the Fast Breeder Project various institutes of the KarIsruhe Nuclear Research Center operate sodium loops for corrosion studies and component tests under sodium. The operation of these loops has led to extensive experience in cleaning sodium-wetted components. This experience relates to the alcohol method, the removal of sodium by melting, storage in air, and to cleaning by means of steam. Deposition samples from radioactive sodium loops were used for decontamination experiments employing various decontaminating agents. The department concerned with the treatment of radioactive waste studied the use of molten salts and paste type cleansers for components unsuitable for mechanical decontamination, primarily with the objective to reduce the amount of radioactive waste. (author)

  1. 16th DOE nuclear air cleaning conference: proceedings

    International Nuclear Information System (INIS)

    First, M.W.

    1981-02-01

    Major topics discussed during the Sixteenth DOE Nuclear Air Cleaning Conference were: waste treatment, including volume reduction and storage; system and component response to stress and accident conditions; Three Mile Island accident; iodine adsorption; treatment and storage of noble gas: treatment of offgases from chemical processing; aerosol; behavior; containment venting; laboratory and in-place filter-testing methods; and particulate filtration. Volume I of the Proceedings has 49 papers from the following sessions; HEPA filter test methods; noble gas separation; air cleaning system design; containment venting; iodine adsorption; reprocessing offgas cleaning; critical review; filtration; filter testing; and aerosols. Volume II contains 44 papers from the sessions on: nuclear waste treatment; critical review; noble gas treatment; carbon-14 and tritium; air cleaning system response to stress; nuclear standards and safety; round table; open end; and air cleaning technology at Three Mile Island. Abstracts are provided for all of these papers

  2. 16th DOE nuclear air cleaning conference: proceedings

    International Nuclear Information System (INIS)

    First, M.W.

    1981-02-01

    Major topics discussed during the Sixteenth DOE Nuclear Air Cleaning Conference were: waste treatment, including volume reduction and storage; system and component response to stress and accident conditions; Three Mile Island accident; iodine adsorption; treatment and storage of noble gas; treatment of offgases from chemical processing; aerosol behavior; containment venting; laboratory and in-place filter-testing methods; and particulate filtration. Volume I of the Proceedings has 49 papers from the following sessions: HEPA filter test methods; noble gas separation; air cleaning system design; containment venting; iodine adsorption; reprocessing offgas cleaning; critical review; filtration, filter testing, and aerosols. Volume II contains 44 papers from the sessions on: nuclear waste treatment; critical review; noble gas treatment; carbon-14 and tritium; air cleaning system response to stress; nuclear standards and safety; round table; open end; and air cleaning technology at Three Mile Island. Abstracts are provided for all of these papers

  3. Management of radioactive waste from nuclear applications

    International Nuclear Information System (INIS)

    1997-01-01

    Radioactive waste arises from the generation of nuclear energy and from the production of radioactive materials and their applications in industry, agriculture, research and medicine. The importance of safe management of radioactive waste for the protection of human health and the environment has long been recognized and considerable experience has been gained in this field. Technical expertise is a prerequisite for safe and cost-effective management of radioactive waste. A training course is considered an effective tool for providing technical expertise in various aspects of waste management. The IAEA, in co-operation with national authorities concerned with radioactive waste management, has organized and conducted a number of radioactive waste management training courses. The results of the courses conducted by the IAEA in 1991-1995 have been evaluated at consultants meetings held in December 1995 and May 1996. This guidance document for use by Member States in arranging national training courses on the management of low and intermediate level radioactive waste from nuclear applications has been prepared as the result of that effort. The report outlines the various requirements for the organization, conduct and evaluation of training courses in radioactive waste management and proposes an annotated outline of a reference training course

  4. The nuclear waste disaster. A view behind the curtain of the presumably clean nuclear power; Das Atommuell-Desaster. Blicke hinter die Kulissen der angeblich sauberen Atomenergie

    Energy Technology Data Exchange (ETDEWEB)

    Schumacher, Julia; Simon, Armin; Stay, Jochen (comps.)

    2015-04-15

    The brochure on the nuclear waste disaster - a view behind the curtain of the presumably clean nuclear power discusses the following topics: Thuringia and Saxony - radiating landscapes, Gronau - 100.000 tons for eternity, Gundremmingen - nuclear waste records and castor shortage, Brunsbuettel - castor storage facility without licensing, Juelich the pebble bed drama, Karlsruhe - the hall is filled, Obrigheim - radioactive waste for cooking pots, Asse - the ticking bomb, final repositories - an illusion without solution, stop the waste production, Germany - endless nuclear waste.

  5. Radioactive and Other Effects of Nuclear Explosion

    International Nuclear Information System (INIS)

    Ilijas, B.; Cizmek, A.; Prah, M.; Medakovic, S.

    2008-01-01

    As a result of long lasting efforts of international community to definitely ban all test nuclear explosions, the Comprehensive Nuclear-Test-Ban Treaty (CTBT) was opened for signature in New York on 24 September 1996, when it was signed by 71 states, including Croatia. The State Office for Nuclear Safety (SONS) which, as an independent state regulatory authority has a responsibility for activities relating to nuclear safety, including the national authority over this Treaty, is actively engaged in CTBTO activities. The nuclear explosion causes a lot of effects (blast, thermal, radioactive, electromagnetic) which differs a lot in its nature, reach, lasting and other. The longest lasting aftermath is from the radioactive effects that cause a radioactive fallout and a lot of radioactive elements in the environment, created by the influence of a primary beam of radiation. Fission and fusion are the main source of radionuclide created by the nuclear explosion, and the longest lasting aftermaths are by the fission products, namely their offspring in natural disintegration chains. This can make contaminated areas inappropriate for life for very long periods. Even in the case of underground nuclear explosion (when underground cavity is formed with no effects on the surface), a leakage of radioactive gases through cracks is possible. A number of radionuclide is created by the neutron activation of elements naturally present in an environment, because a very strong neutron radiation appears in the moment of nuclear explosion. The abundance of particular radionuclide is a very much dependent of a place of performing nuclear explosion and a composition of soil or water in the vicinity.(author)

  6. Management of radioactive waste nuclear power plants

    International Nuclear Information System (INIS)

    Dlouhy, Z.; Marek, J.

    1976-01-01

    The authors give a survey of the sources, types and amounts of radioactive waste in LWR nuclear power stations (1,300 MWe). The amount of solid waste produced by a Novovorenezh-type PWR reactor (2 x 400 resp. 1 x 1,000 MWe) is given in a table. Treatment, solidification and final storage of radioactive waste are shortly discussed with special reference to the problems of final storage in the CSR. (HR) [de

  7. EBR-II experience with sodium cleaning and radioactivity decontamination

    International Nuclear Information System (INIS)

    Ruther, W.E.; Smith, C.R.F.

    1978-01-01

    The EBR-II is now in Its 13th year of operation. During that period more than 2400 subassemblies have been cleaned of sodium without a serious incident of any kind by a two-step process developed at Argonne. Sodium cleaning and decontamination of other reactor components has been performed only on the relatively few occasions in which a repair or replacement has been required. A summary of the EBR-II experience will be presented. A new facility will be described for the improved cleaning and maintenance of sodium-wetted primary components

  8. EBR-II experience with sodium cleaning and radioactivity decontamination

    Energy Technology Data Exchange (ETDEWEB)

    Ruther, W E; Smith, C R.F. [Argonne National Laboratory, Argonne (United States)

    1978-08-01

    The EBR-II is now in Its 13th year of operation. During that period more than 2400 subassemblies have been cleaned of sodium without a serious incident of any kind by a two-step process developed at Argonne. Sodium cleaning and decontamination of other reactor components has been performed only on the relatively few occasions in which a repair or replacement has been required. A summary of the EBR-II experience will be presented. A new facility will be described for the improved cleaning and maintenance of sodium-wetted primary components.

  9. Sodium cleaning device for nuclear reactor equipments

    International Nuclear Information System (INIS)

    Fujisawa, Morio.

    1985-01-01

    Purpose: To enable sodium cleaning over the entire length of large size equipments such as control rod drives and primary coolant recycling pumps for use in FBR type reactors. Constitution: A plurality of warm water supply nozzles each having a valve are connected at varying height on the side of a cleaning tank, to which an exhaust line is connected. These nozzles are connected with an exhaust port at the bottom of the tank to constitute a pipeway for cleaning warm water recycling line including a water feed pump and a feedwater heater. The water level in the tank is changed stepwise by successively selecting the warm water feed nozzles. Further, the warm water in the tank is recyclically fed through the nozzles selected at each step of the water level through the recycle line while warming. On the other hand, the pressure inside the tank is reduced through the exhaust line, whereby the warm water in the tank is boiled at low temperature to clean-up sodium on the equipments to be cleaned over the entire length. (Horiuchi, T.)

  10. Radioactive waste from nuclear power stations and other nuclear facilities

    International Nuclear Information System (INIS)

    Jelinek-Fink, P.

    1976-01-01

    After estimating the amounts of liquid and solid radioactive wastes that will be produced in nuclear power plants, reprocessing plants, by the fuel cycle industry, and in the nuclear research centers in the FRG until 1990, it is reported on the state of technology and on the tendencies in the development of processing radioactive waste. The paper also describes, how waste disposal is managed by those producing radioactive waste (see above), and discusses the future development of the complex of waste disposal from the industry's point of view. (HR/LN) [de

  11. Management and disposal of radioactive waste from clean-up operations

    International Nuclear Information System (INIS)

    Lehto, J.

    1997-01-01

    Clean-up of large contaminated areas may create enormous amounts of radioactive waste which need to be safely disposed of. Disposal of the waste may include pre-treatment and transportation to a final repository. There is much experience of the removal and disposal of large amounts of radioactive contaminated material from uranium mill tailings sites. For example, in Salt Lake City, USA, two million tons of radium-containing waste was transported 140 km by rail to a disposal site. In Port Hope, Canada, 70,000 cubic meters of similar waste were moved by road to a disposal site 350 km away. The disposal of the uranium mill tailings can be pre-planned, but an accident situation is quite different. In an emergency, decisions on how to deal with the waste from the clean-up may have to be made rapidly and disposal options may be limited. After the Chernobyl accident, large amounts of contaminated material (mainly soil and trees) were disposed of in shallow pits and surface mounds. Overall, approximately 4x10 6 m 3 of waste were distributed between about 800 disposal sites. Because the amounts of waste after a major nuclear accident could be large, their final disposal may require large human and capital resources. Depending on the scale it is possible that the wastes will have to be placed in several final disposal sites. These are likely to be pits or surface mounds. Such repositories may need clay or concrete liners to prevent migration of the radionuclides from the disposal sites. (EG)

  12. Radioactive waste treatment technology at Czech nuclear power plants

    International Nuclear Information System (INIS)

    Kulovany, J.

    2001-01-01

    This presentation describes the main technologies for the treatment and conditioning of radioactive wastes at Czech nuclear power plants. The main technologies are bituminisation for liquid radioactive wastes and supercompaction for solid radioactive wastes. (author)

  13. Nuclear moments of radioactive nuclei. Final report

    International Nuclear Information System (INIS)

    Greenlees, G.W.

    1985-01-01

    An unsuccessful attempt was made to study nuclear moments of radioactive nuclear using laser spectroscopy. Although preliminary tests had indicated a sensitivity sufficient to observe signals of fluxes less than one atom/s no resonance fluorescence was detected. Activity measurements showed several hundred nuclei per second were in the beam; therefore it was postulated that, due to the the reactivity of the 126 Ba and sodium used, contaminants were the probable source of negative results. 3 refs., 2 figs

  14. Ultrasonic Cleaning of Nuclear Steam Generator by Micro Bubble

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Woo Tae [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of); Kim, Sang Tae; Yoon, Sang Jung [Sae-An Engineering Co., Seoul (Korea, Republic of)

    2012-05-15

    In this paper, we present ultrasonic cleaning technology for a nuclear steam generator using micro bubble. We could extend the boundary of ultrasonic cleaning by using micro bubbles in water. Ultrasonic energy measured was increased about 5 times after the generation of micro bubbles in water. Furthermore, ultrasound energy was measured to be strong enough to create cavitation even though the ultrasound sensor was about 2 meters away from the ultrasonic transducer

  15. Three Mile Island Nuclear Station steam generator chemical cleaning

    International Nuclear Information System (INIS)

    Hansen, C.A.

    1992-01-01

    The Three Mile Island-1 steam generators were chemically cleaned in 1991 by the B and W Nuclear Service Co. (BWNS). This secondary side cleaning was accomplished through application of the EPRI/SGOG (Electric Power Research Institute - Steam Generator Owners Group) chemical cleaning iron removal process, followed by sludge lancing. BWNS also performed on-line corrosion monitoring. Corrosion of key steam generator materials was low, and well within established limits. Liquid waste, subsequently processed by BWNS was less than expected. 7 tabs

  16. Radioactive nuclides in nuclear reactors

    International Nuclear Information System (INIS)

    Akatsu, Eiko

    1982-12-01

    In the Nuclear Engineering School of JAERI, many courses are presented for the people working in and around nuclear reactors. The curricula of the courses contain also chemical subject materials. With reference to the foreign curricula, a plan of educational subject material of chemistry was considered for students of the school in the previous report (JAERI-M 9827), where the first part of the plan, ''Fundamentals of Reactor Chemistry'', was reviewed. This report is a review of the second part of the plan containing fission products chemistry, actinoids elements chemistry and activated reactor materials chemistry. (author)

  17. Exhaust gas cleaning system for handling radioactive fission and activation gases

    International Nuclear Information System (INIS)

    Queiser, H.; Schwarz, H.

    1975-01-01

    An exhaust gas cleaning system utilizing the principle of delaying radioactive gases to permit their radioactive decay to a level acceptable for release to the atmosphere, comprising an adsorbent for adsorbing radioactive gas and a container for containing the adsorbent and for constraining gas to flow through the adsorbent, the adsorbent and the container forming simultaneously an adsorptive delay section and a mechanical delay section, by means of a predetermined ratio of volume of voids in the adsorbent to total volume of the container containing the adsorbent, for delaying radioactive gas to permit its radioactive decay to a level acceptable for release to the atmosphere is described. A method of using an adsorbent for cleaning a radioactive gas containing an isotope which is adsorbed by the adsorbent and containing an isotope whose adsorption by the adsorbent is low as compared to the isotope which is adsorbed and which is short-lived as compared to the isotope which is adsorbed, comprising constraining the gas to flow through the adsorbent with the retention time for the isotope which is adsorbed being at least the minimum for permitting radioactive decay to a level acceptable for release to the atmosphere and with the retention time for the isotope of relatively low adsorption and relatively short life being at least the minimum for permitting radioactive decay to a level acceptable for release to the atmosphere is also described. (U.S.)

  18. Transport of proximity nuclear radioactive materials

    International Nuclear Information System (INIS)

    2010-01-01

    This brief publication gives an overview of the international and national regulatory framework for the transport of radioactive substances, outlines progress orientations identified by the French Nuclear Safety Authority (ASN), indicates the parcel classification and shipment radiological criteria, and how to declare events occurring during the transport of radioactive substances, which number to phone in case of a radiological incident. Finally, the role of the ASN and its field of activity in matters of control are briefly presented with a table of its office addresses in France

  19. Radioactivity in sludge: tank cleaning procedures and sludge disposal

    International Nuclear Information System (INIS)

    Bradley, D.A.

    1995-01-01

    In the oil and gas industry management of alpha-active sludge is made more complex by the presence of hydrocarbons and heavy metals. This presentation discusses the origin of radioactivity in sludge, management of risk in terms of safe working procedures, storage and possible disposal options. The several options will generally involve aspects of dilution or of concentration; issues to be discussed will include sludge farming, bioremediation and incineration. (author)

  20. The puzzle of nuclear wastes. Radioactive threat to your health..

    International Nuclear Information System (INIS)

    2007-01-01

    This document, published by the French association 'Sortir du nucleaire' (Get out of nuclear), gives some information on what is radioactivity, the radioactive materials as a risk for living organisms, nuclear wastes all over France (list and map of the storage sites, power plants and fuel cycle centers), nuclear wastes at every step of the nuclear connection, the insolvable problem of high activity wastes, burying nuclear wastes in order to better forget them, radioactivity as a time bomb for our health, radioactive effluents as an under-estimated risk, artificial radioactivity already responsible for the death of 61 million people in the world, and so on

  1. Chemical cleaning of nuclear (PWR) steam generators

    International Nuclear Information System (INIS)

    Welty, C.S. Jr.; Mundis, J.A.

    1982-01-01

    This paper reports on a significant research program sponsored by a group of utilities (the Steam Generator Owners Group), which was undertaken to develop a process to chemically remove corrosion product deposits from the secondary side of pressurized water reactor (PWR) power plant steam generators. Results of this work have defined a process (solvent system and application methods) that is capable of removing sludge and tube-to-tube support plate crevice corrosion products generated during operation with all-volatile treatment (AVT) water chemistry. Considers a plant-specific test program that includes all materials in the steam generator to be cleaned and accounts for the physical locations (proximity and contact) of those materials. Points out that prior to applying the process in an operational unit, the utility, with the participation of the NSSR vendor, must define allowable total corrosion to the materials of construction of the unit

  2. Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products.

  3. Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range

    International Nuclear Information System (INIS)

    1997-06-01

    A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products

  4. Sciences with radioactive nuclear beams

    International Nuclear Information System (INIS)

    Kawase, Yoichi

    1992-01-01

    The unstable nuclei which are produced with accelerators and nuclear reactors and are far apart from the stability line have been used mainly in nuclear physics field as the object of the systematic research on atomic nucleus structure. Recently, the projects for developing the advanced research in many fields by accelerating the obtained unstable nuclei have been proposed. The unstable nucleus beam which was accelerated to high energy and controlled precisely keeps the possibility of qualitatively improve further conventional ion beam science, and it is expected as the breakthrough in the interdisciplinary basic research related to atomic energy, therefore, its recent trend in the world is explained, hoping for the new development. The stable isotopes existing naturally distribute along the N-Z straight line, and as they are apart from the natural stability line, they become unstable to beta decay, and their life becomes short exponentially. The significance of unstable nucleus beam science and its recent trend, the production of unstable nucleus beam, the interdisciplinary research using unstable nucleus beam, and the present state and future plan in Research Reactor Institute, Kyoto University are reported. (K.I.)

  5. A compact ultra-clean system for deploying radioactive sources inside the KamLAND detector

    NARCIS (Netherlands)

    Banks, T.I.; Freedman, S.J.; Wallig, J.; Ybarrolaza, N.; Gando, A.; Gando, Y.; Ikeda, H.; Inoue, K.; Kishimoto, Y.; Koga, M.; Mitsui, T.; Nakamura, K.; Shimizu, I.; Shirai, J.; Suzuki, A.; Takemoto, Y.; Tamae, K.; Ueshima, K.; Watanabe, H.; Xu, B.D.; Yoshida, H.; Yoshida, S.; Kozlov, A.; Grant, C.; Keefer, G.; Piepke, A.; Bloxham, T.; Fujikawa, B.K.; Han, K.; Ichimura, K.; Murayama, H.; O'Donnell, T.; Steiner, H.M.; Winslow, L.A.; Dwyer, D.A.; McKeown, R.D.; Zhang, C.; Berger, B.E.; Lane, C.E.; Maricic, J.; Miletic, T.; Batygov, M.; Learned, J.G.; Matsuno, S.; Sakai, M.; Horton-Smith, G.A.; Downum, K.E.; Gratta, G.; Efremenko, Y.; Perevozchikov, O.; Karwowski, H.J.; Markoff, D.M.; Tornow, W.; Heeger, K.M.; Detwiler, J.A.; Enomoto, S.; Decowski, M.P.

    2015-01-01

    We describe a compact, ultra-clean device used to deploy radioactive sources along the vertical axis of the KamLAND liquid-scintillator neutrino detector for purposes of calibration. The device worked by paying out and reeling in precise lengths of a hanging, small-gauge wire rope (cable); an

  6. Radioactive materials released from nuclear power plants

    International Nuclear Information System (INIS)

    Tichler, J.; Norden, K.; Congemi, J.

    1991-05-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1988 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1988 release data are summarized in tabular form. Data covering specific radionuclides are summarized. 16 tabs

  7. How the nuclear industry keeps it gases clean

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The paper surveys briefly the papers presented at a conference on gas filtration in the nuclear industry. The theory, development, design, use (under various conditions of temperature, humidity, corrosion), performance, cleaning and testing of fibrous, HEPA, metal, packed bed and magnetic filters are included, and the problems, advantages and disadvantages of the various types of filter are discussed. (U.K.)

  8. Large underground radioactive waste storage tanks successfully cleaned at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Billingsley, K.; Burks, B.L.; Johnson, M.; Mims, C.; Powell, J.; Hoesen, D. van

    1998-05-01

    Waste retrieval operations were successfully completed in two large underground radioactive waste storage tanks in 1997. The US Department of Energy (DOE) and the Gunite Tanks Team worked cooperatively during two 10-week waste removal campaigns and removed approximately 58,300 gallons of waste from the tanks. About 100 gallons of a sludge and liquid heel remain in each of the 42,500 gallon tanks. These tanks are 25 ft. in diameter and 11 ft. deep, and are located in the North Tank Farm in the center of Oak Ridge National Laboratory. Less than 2% of the radioactive contaminants remain in the tanks, proving the effectiveness of the Radioactive Tank Cleaning System, and accomplishing the first field-scale cleaning of contaminated underground storage tanks with a robotic system in the DOE complex

  9. Trends in the design and operation of off-gas cleaning systems in nuclear facilities

    International Nuclear Information System (INIS)

    First, M.W.

    1980-01-01

    Trends in the design and operation of off-gas cleaning systems in nuclear facilities reflect the normal development by manufacturers of new and improved equipment and the demand for more safety, greater reliability, and higher collection efficiency as an aftermath of the well publicized accident at Three Mile Island. The latter event has to be viewed as a watershed in the history of off-gas treatment requirements for nuclear facilities. It is too soon to predict what these will be with any degree of assurance but it seems reasonable to expect greatly increased interest in containment venting systems for light water and LMFBR nuclear power reactors and more stringent regulatory requirements for auxiliary off-gas cleaning systems. Although chemical and waste handling plants share few characteristics with reactors other than the presence of radioactive materials, often in large amounts, tighter requirements for handling reactor off-gases will surely be transferred to other kinds of nuclear facilities without delay. Currently employed nuclear off-gas cleaning technology was largely developed and applied during the decade of the 1950s. It is regrettable that the most efficient and most economical off-gas treatment systems do not always yield the best waste forms for storage or disposal. It is even more regrettable that waste management has ceased to be solely a technical matter but has been transformed instead into a highly charged political posture of major importance in many western nations. Little reinforcement has been provided by detailed studies of off-gas treatment equipment failures that show that approximately 13% of over 9000 licensee event reports to the United States Nuclear Regulatory Commission pertained to failures in ventilating and cleaning systems and their monitoring instruments

  10. Annual Report, Fall 2016: Alternative Chemical Cleaning of Radioactive High Level Waste Tanks - Corrosion Test Results

    International Nuclear Information System (INIS)

    Wyrwas, R. B.

    2016-01-01

    The testing presented in this report is in support of the investigation of the Alternative Chemical Cleaning program to aid in developing strategies and technologies to chemically clean radioactive High Level Waste tanks prior to tank closure. The data and conclusions presented here were the examination of the corrosion rates of A285 carbon steel and 304L stainless steel exposed to two proposed chemical cleaning solutions: acidic permanganate (0.18 M nitric acid and 0.05M sodium permanganate) and caustic permanganate. (10 M sodium hydroxide and 0.05M sodium permanganate). These solutions have been proposed as a chemical cleaning solution for the retrieval of actinides in the sludge in the waste tanks, and were tested with both HM and PUREX sludge simulants at a 20:1 ratio.

  11. Annual Report, Fall 2016: Alternative Chemical Cleaning of Radioactive High Level Waste Tanks - Corrosion Test Results

    Energy Technology Data Exchange (ETDEWEB)

    Wyrwas, R. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-09-01

    The testing presented in this report is in support of the investigation of the Alternative Chemical Cleaning program to aid in developing strategies and technologies to chemically clean radioactive High Level Waste tanks prior to tank closure. The data and conclusions presented here were the examination of the corrosion rates of A285 carbon steel and 304L stainless steel exposed to two proposed chemical cleaning solutions: acidic permanganate (0.18 M nitric acid and 0.05M sodium permanganate) and caustic permanganate. (10 M sodium hydroxide and 0.05M sodium permanganate). These solutions have been proposed as a chemical cleaning solution for the retrieval of actinides in the sludge in the waste tanks, and were tested with both HM and PUREX sludge simulants at a 20:1 ratio.

  12. Treatment of radioactive contaminated water in nuclear power plants

    International Nuclear Information System (INIS)

    1978-12-01

    This rule is to be applied to the design, construction, and operation of facilities for treatment of water contaminated with radioactive material in stationary nuclear power plants with LWRs and HTRs. According to the requirements of the rule these facilities are to be designed, constructed, and operated in such a way that a) uncontrolled discharge of water contaminated with radioactive material is avoided, b) the activity discharged with water is as low as possible, c) water contaminated with radioactive material will not reach the ground, d) the radiation exposure as a consequence of direct radiation, contamination, and inhalation of the persons occupied in the facilities is as low as possible and as a maximum corresponds to the values laid down in the radiation protection regulation or to the values of the operating license. This rule is not to be applied to facilities for coolant and storage pit clean-up as well as facilities for the treatment of concentrates produced during the contamination of the water. (orig./HP) [de

  13. The actual practice of air cleaning in Belgian nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Goossens, W.R. [PEGO, Mol (Belgium)

    1995-02-01

    With 60% of its power generation from nuclear stations Belgium has 7 nuclear power stations in operation with a total capacity of 5.4 MWe. Enriched uranium is imported and converted to fuel assemblies. The actinides of reprocessed fuel are recycled as MOX fuel. A main waste conditioning operation has been performed in the PAMELA vitrifier. The actual practice of nuclear air cleaning in the Belgian PWR station DOEL-4 and in the PAMELA -vitrification plant for high level liquid waste is reviewed.

  14. Radioactive wastes in nuclear fuel cycle

    International Nuclear Information System (INIS)

    Sakata, Sadahiro; Nagaike, Tadakatsu; Emura, Satoru; Matsumoto, Akira; Morisawa, Shinsuke.

    1978-01-01

    Recent topics concerning radioactive water management and disposal are widely reviewed. As the introduction, various sources of radioactivity including uranium mining, fuel fabrication, reactor operation and fuel reprocessing and their amount of wastes accumulated per 1000 MWe year operation of a LWR are presented together with the typical methods of disposal. The second section discusses the problems associated with uranium fuel fabrication and with nuclear power plants. Typical radioactive nuclides and their sources in PWRs and BWRs are discussed. The third section deals with the problems associated with reprocessing facilities and with mixed oxide fuel fabrication. Solidification of high-level wastes and the methods of the disposal of transuranic nuclides are the main topics in this section. The fourth section discusses the methods and the problems of final disposal. Various methods being proposed or studied for the final disposal of low- and high-level wastes and transuranic wastes are reviewed. The fifth section concerns with the risk analysis of waste disposal. Both deterministic and probabilistic methods are treated. As the example, the assessment of the risk due to floods is explained. The associated event tree and fault three are presented together with the estimated probability of the occurrence of each constituent failure. In the final section, the environmental problems of radioactive wastes are widely reviewed. (Aoki, K.)

  15. Methodology for estimating accidental radioactive releases in nuclear waste management

    International Nuclear Information System (INIS)

    Levy, H.B.

    1979-01-01

    Estimation of the risks of accidental radioactive releases is necessary in assessing the safety of any nuclear waste management system. The case of a radioactive waste form enclosed in a barrier system is considered. Two test calculations were carried out

  16. Evaluation of the Ventilation and Air Cleaning System Design Concepts for Safety Requirements during Fire Conditions in Nuclear Applications

    International Nuclear Information System (INIS)

    Rashad, S.; El-Fawal, M.; Kandil, M.

    2013-01-01

    The ventilation and air cleaning system in the nuclear or radiological installations is one of the essential nuclear safety concerns. It is responsible for confining the radioactive materials involved behind suitable barriers during normal and abnormal conditions. It must be designed to prevent the release of harmful products (radioactive gases, or airborne radioactive materials) from the system or facility, impacting the public or workers, and doing environmental damage. There are two important safety functions common to all ventilation and air cleaning system in nuclear facilities. They are: a) the requirements to maintain the pressure of the ventilated volume below that of surrounding, relatively non-active areas, in order to inhibit the spread of contamination during normal and abnormal conditions, and b) the need to treat the ventilated gas so as to minimize the release of any radioactive or toxic materials. Keeping the two important safety functions is achieved by applying the fire protection for the ventilation system to achieve safety and adequate protection in nuclear applications facilities during fire and accidental criticality conditions.The main purpose of this research is to assist ventilation engineers and experts in nuclear installations for safe operation and maintaining ventilation and air cleaning system during fire accident in nuclear facilities. The research focuses on fire prevention and protection of the ventilation systems in nuclear facilities. High-Efficiency particulate air (HEPA) filters are extremely susceptible to damage when exposed to the effects of fire, smoke, and water; it is the intent of this research to provide the designer with the experience gained over the years from hard lessons learned in protecting HEPA filters from fire. It describes briefly and evaluates the design safety features, constituents and working conditions of ventilation and air cleaning system in nuclear and radioactive industry.This paper provides and

  17. Nuclear power stations: environmental surveillance of radioactivity

    International Nuclear Information System (INIS)

    Pellerin, P.

    1972-01-01

    Because of the radiations they emit, radioactive substances can be detected, identified and measured at extremely low concentrations ? the corresponding masses are lower by a factor ranging from 1000 to 10 000 than those that can be measured by any other chemical or physical method, however precise, applied to non-radioactive substances. Radioisotopes can therefore be detected in the environment at levels much lower than those at which genuine public health problems begin to arise. Unfortunately, we cannot say the same of numerous non-radio active pollutants, which can be measured only at concentrations very close to, or even exceeding, the toxicity threshold. In the mind of the uninformed public confusion seems quite frequently to reign as between the detection threshold and the toxicity threshold. This undoubtedly explains the following situation which is, to say the least, paradoxical: people are afraid of the hypothetical effects of radioactivity at ridiculously low levels, whereas nobody is alarmed at the fact that the toxicity limits for a very large number of non-radioactive, but very real pollutants are being exceeded almost continuously. The sum of all artificial irradiations does not exceed the normal fluctuations of natural irradiation, and if the genetic effects of very low radiation doses were truly cumulative, the natural radiation to which we are all exposed and which is by far the highest would by itself have eliminated every trace of life on earth long ago. Lastly, let us not forget that merely the use of X-rays in medicine, particularly in radiodiagnosis, represents an additional average artificial irradiation of the population amounting to double the natural radiation (100 millirem per year). This is about 100 times the irradiation which would accrue from nuclear industry even according to the most pessimistic estimate. We have seen that the measures described above will make it genuinely possible to maintain environmental radioactivity in all

  18. Quality assurance in nuclear medicine radioactivity measurements

    International Nuclear Information System (INIS)

    Sahagia, Maria; Razdolescu Anamaria Cristina

    2007-01-01

    The paper presents some recent results of the Radionuclide Metrology Laboratory (RML) from IFIN-HH, in the assurance of quality in radioactivity measurements for nuclear medicine. Three aspects are treated: (i) Participation of the RML in the frame of the IAEA Coordinated Research Program (CRP), E 2.10.05; (ii) Improvement of the secondary standard, based on a CENTRONIC IG12/20A ionization chamber; (iii) Implementation of the quality management, according to the SR EN ISO/IEC 17025:2005. (authors)

  19. Teaching concepts in the field of radioactivity and nuclear energy

    International Nuclear Information System (INIS)

    Bleichroth, W.

    1982-01-01

    This issue of 'Naturwissenschaften im Unterricht', dealing with the subjects of physics and chemistry, gives an account of the fundamentals of radioactivity, nuclear fission, controlled nuclear fission, nuclear power plants, dosimetry, safety engineering, shielding measures to prevent the release of radioactive substances, pressure engineering, emergency core cooling systems, waste disposal and natural and artificial environmental radioactivity. Teachers will find helpful hints as to the method of instruction and the explanation of problems. (DG) [de

  20. A compact ultra-clean system for deploying radioactive sources inside the KamLAND detector

    Science.gov (United States)

    Banks, T. I.; Freedman, S. J.; Wallig, J.; Ybarrolaza, N.; Gando, A.; Gando, Y.; Ikeda, H.; Inoue, K.; Kishimoto, Y.; Koga, M.; Mitsui, T.; Nakamura, K.; Shimizu, I.; Shirai, J.; Suzuki, A.; Takemoto, Y.; Tamae, K.; Ueshima, K.; Watanabe, H.; Xu, B. D.; Yoshida, H.; Yoshida, S.; Kozlov, A.; Grant, C.; Keefer, G.; Piepke, A.; Bloxham, T.; Fujikawa, B. K.; Han, K.; Ichimura, K.; Murayama, H.; O`Donnell, T.; Steiner, H. M.; Winslow, L. A.; Dwyer, D. A.; McKeown, R. D.; Zhang, C.; Berger, B. E.; Lane, C. E.; Maricic, J.; Miletic, T.; Batygov, M.; Learned, J. G.; Matsuno, S.; Sakai, M.; Horton-Smith, G. A.; Downum, K. E.; Gratta, G.; Efremenko, Y.; Perevozchikov, O.; Karwowski, H. J.; Markoff, D. M.; Tornow, W.; Heeger, K. M.; Detwiler, J. A.; Enomoto, S.; Decowski, M. P.

    2015-01-01

    We describe a compact, ultra-clean device used to deploy radioactive sources along the vertical axis of the KamLAND liquid-scintillator neutrino detector for purposes of calibration. The device worked by paying out and reeling in precise lengths of a hanging, small-gauge wire rope (cable); an assortment of interchangeable radioactive sources could be attached to a weight at the end of the cable. All components exposed to the radiopure liquid scintillator were made of chemically compatible UHV-cleaned materials, primarily stainless steel, in order to avoid contaminating or degrading the scintillator. To prevent radon intrusion, the apparatus was enclosed in a hermetically sealed housing inside a glove box, and both volumes were regularly flushed with purified nitrogen gas. An infrared camera attached to the side of the housing permitted real-time visual monitoring of the cable's motion, and the system was controlled via a graphical user interface.

  1. A compact ultra-clean system for deploying radioactive sources inside the KamLAND detector

    Energy Technology Data Exchange (ETDEWEB)

    Banks, T.I., E-mail: tbanks@berkeley.edu [Physics Department, University of California, Berkeley, CA 94720 (United States); Lawrence Berkeley National Laboratory, Berkeley, CA 94720 (United States); Freedman, S.J. [Physics Department, University of California, Berkeley, CA 94720 (United States); Lawrence Berkeley National Laboratory, Berkeley, CA 94720 (United States); Kavli Institute for the Physics and Mathematics of the Universe (WPI), University of Tokyo, Kashiwa, Chiba 277-8583 (Japan); Wallig, J.; Ybarrolaza, N. [Lawrence Berkeley National Laboratory, Berkeley, CA 94720 (United States); Gando, A.; Gando, Y.; Ikeda, H. [Research Center for Neutrino Science, Tohoku University, Sendai 980-8578 (Japan); Inoue, K. [Research Center for Neutrino Science, Tohoku University, Sendai 980-8578 (Japan); Kavli Institute for the Physics and Mathematics of the Universe (WPI), University of Tokyo, Kashiwa, Chiba 277-8583 (Japan); Kishimoto, Y. [Kavli Institute for the Physics and Mathematics of the Universe (WPI), University of Tokyo, Kashiwa, Chiba 277-8583 (Japan); Research Center for Neutrino Science, Tohoku University, Sendai 980-8578 (Japan); Koga, M. [Research Center for Neutrino Science, Tohoku University, Sendai 980-8578 (Japan); Kavli Institute for the Physics and Mathematics of the Universe (WPI), University of Tokyo, Kashiwa, Chiba 277-8583 (Japan); Mitsui, T. [Research Center for Neutrino Science, Tohoku University, Sendai 980-8578 (Japan); Nakamura, K. [Research Center for Neutrino Science, Tohoku University, Sendai 980-8578 (Japan); Kavli Institute for the Physics and Mathematics of the Universe (WPI), University of Tokyo, Kashiwa, Chiba 277-8583 (Japan); Shimizu, I.; Shirai, J.; Suzuki, A.; Takemoto, Y.; Tamae, K.; Ueshima, K.; Watanabe, H.; Xu, B.D. [Research Center for Neutrino Science, Tohoku University, Sendai 980-8578 (Japan); and others

    2015-01-01

    We describe a compact, ultra-clean device used to deploy radioactive sources along the vertical axis of the KamLAND liquid-scintillator neutrino detector for purposes of calibration. The device worked by paying out and reeling in precise lengths of a hanging, small-gauge wire rope (cable); an assortment of interchangeable radioactive sources could be attached to a weight at the end of the cable. All components exposed to the radiopure liquid scintillator were made of chemically compatible UHV-cleaned materials, primarily stainless steel, in order to avoid contaminating or degrading the scintillator. To prevent radon intrusion, the apparatus was enclosed in a hermetically sealed housing inside a glove box, and both volumes were regularly flushed with purified nitrogen gas. An infrared camera attached to the side of the housing permitted real-time visual monitoring of the cable's motion, and the system was controlled via a graphical user interface.

  2. Environmental radioactive contamination and its control for nuclear power plants

    International Nuclear Information System (INIS)

    Shi Zhongqi; Qu Jingyuan; Cui Yongli

    1998-01-01

    The environmental radioactive releases and exposure to human being due to operation of nuclear power plants in the world and in China, environmental contamination and consequences caused by severe nuclear power plant accidents in the history, control of the radioactive contamination in China, and some nuclear laws on the radioactive contamination control established by international organizations and USA etc. are described according to literature investigation and research. Some problems and comments in radioactive contamination control for nuclear power plants in China are presented. Therefore, perfecting laws and regulations and enhancing surveillances on the contamination control are recommended

  3. Tracking of Radioactive Sources in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Mohd Fazlie Abdul Rashid; Noor Fadilla Ismail; Khairuddin Mohamad Kontol; Hairul Nizam Idris; Azimawati Ahmad; Suzilawati Muhd Sarowi; Raymond, Y.T.L.

    2014-01-01

    Radioactive materials are used in Malaysian Nuclear Agency for various purposes such as research and development, calibration, tracer and irradiation. Inventory of radioactive materials is crucial for ensuring the security and control of all radioactive materials owned and used so as not to be lost or fall into the hands of people who do not have permission to possess or use it. Experience in many countries around the world proves that the improper inventory of radioactive material would lead to loss of control of radioactive materials and will eventually cause an accident of radiation exposure. Radioactive material database has been developed for the need to ensure traceability of radioactive materials in Malaysian Nuclear Agency. Records of radioactive materials are regularly updated based on the classification of the type of radionuclide, the total distribution in each building and the initial activity of radioactive sources. (author)

  4. Update on the REIPPPP, clean coal, nuclear, natural gas

    CSIR Research Space (South Africa)

    Milazi, Dominic

    2015-12-01

    Full Text Available , clean coal, nuclear, natural gas The Sustainable Energy Resource Handbook Volume 6 Dominic Milazi, Dr Tobias Bischof-Niemz, Abstract Since its release in 2011, the Integrated Resource Plan (IRP 2010-2030), or IRP 2010, has been the authoritative... text setting out South Africa’s electricity plan over the next 20 years. The document indicates timelines on the roll out of key supply side options such as renewable energy, the nuclear, natural gas and coal build programmes, as well as peaking...

  5. Nuclear safety: transparency in radioactive clouds

    International Nuclear Information System (INIS)

    Bondy, J.Ph.

    2002-01-01

    The supervision of industry and defence on French radiation protection and withhold information during public inquiries in nuclear facilities questions make organizations anxious. Two examples are given: the first one concerns the file presented by EDF in november 1998 to get new release authorizations on the st Alban site, some information about tritium lacked( thirty analysis on tritium lacked for impact studies) and tritium is an element that represents 99.99% of released radioactivity by the nuclear power plant in the Rhone river. The Crirad organization asked for the public inquiry canceling. In vain. The second example is relative to the reprocessing plant of La Hague; at the end of 1999 the Cogema wished to extend its fuel range and increase its treatment capacity then it dropped off a file of public inquiry that did not take into account the increase of radioactive releases. The operator did not want the file to wear on this aspect, it won one's case. (N.C.)

  6. Experiments with radioactive nuclear beams II

    International Nuclear Information System (INIS)

    Aguilera R, E.F.; Martinez Q, E.; Gomez C, A.; Lizcano C, D.; Garcia M, H.; Rosales M, P.

    2001-12-01

    The studies of nuclear reactions with heavy ions have been carried out for years for the group of heavy ions of the laboratory of the Accelerator of the ININ. Especially in the last years the group has intruded in the studies of nuclear reactions with radioactive beams, frontier theme at world level. Presently Technical Report is presented in detailed form the experimental methods and the analysis procedures of the research activities carried out by the group. The chpater II is dedicated to the procedures used in the analysis of the last two experiments with radioactive beams carried out by the group. In the chapter III is presented the procedure followed to carrying out an extended analysis with the CCDEF code, to consider the transfer channel of nucleons in the description of the fusion excitation functions of a good number of previously measured systems by the group. Finally, in the chapter IV the more important steps to continue in the study of the reaction 12 C + 12 C experiment drifted to be carried out using the available resources of the Tandem Accelerator Laboratory of the ININ are described. At the end of each chapter some of the more representative results obtained in the analysis are presented and emphasis on the scientific production generated by the group for each case is made. (Author)

  7. Incineration of radioactive wastes at the Nuclear Research Center Karlsruhe

    Energy Technology Data Exchange (ETDEWEB)

    Baehr, W; Hempelmann, W; Krause, H

    1976-06-01

    In 1971 a large incineration plant started operation in the Nuclear Research Center Karlsruhe. This plant is serving for routine incineration of up to 100 kg of combustible radioactive solids or 40 l of contaminated organic liquids and oils per hour. A dry off-gas cleaning system has been developed for this installation in which the fumes are cleaned by ceramic filter candles. After passing the filtering system and cooling, the off-gas is discharged directly through a stack. The activity concentration in the off-gas is measured by a continuous monitoring system. The ashes arising from the incineration are mixed with cement grout and filled into 200 l-drums. By this way approximately one drum of fixed ashes results from 100 drums of combustible wastes. During the first four years of operation, more than 4,000 m/sup 3/ of combustible solids and about 60 m/sup 3/ organic solvents have been incinerated in the plant. The operating experiences are presented.

  8. Consequences of Illicit Trafficking of Nuclear or Other Radioactive Materials

    International Nuclear Information System (INIS)

    Moore, G.M.

    2010-01-01

    Explosion of a nuclear yield device is probably the worst consequence of Illicit Trafficking of nuclear or other radioactive materials.The nuclear yield device might be a stolen nuclear weapon, or an improvised nuclear device. An improvised nuclear device requires nuclear material design, and construction ability. Use of a radioactive dispersal device probably would not result in large numbers of casualties.However economic losses can be enormous. Non-Technical effects of nuclear trafficking (e.g. public panic, work disruption, etc.) and political and psychological consequences can far exceed technical consequences

  9. Filter to be tightly installed in a room as a partition and which can be filled with a contact material susceptible of being poured e.g. activated charcoal for cleaning especially radioactive air or gases in nuclear installations

    International Nuclear Information System (INIS)

    Neumann, G.M.

    1978-01-01

    The filter is designed in such manner that it will resist all loads - including earthquake - without loosing its operability. It consists of a box formed by stable corner irons filled with absorbing material and bounded on two sides by sieves through which the radioactive gases can flow in and out. The invention especially concerns the configuration of the perforations and the screwing of the casing elements to the frame as well as the arrangement in the concrete wall. Measures for fire fighting are also provided for. (UWI) [de

  10. Nuclear refugees after large radioactive releases

    International Nuclear Information System (INIS)

    Pascucci-Cahen, Ludivine; Groell, Jérôme

    2016-01-01

    However improbable, large radioactive releases from a nuclear power plant would entail major consequences for the surrounding population. In Fukushima, 80,000 people had to evacuate the most contaminated areas around the NPP for a prolonged period of time. These people have been called “nuclear refugees”. The paper first argues that the number of nuclear refugees is a better measure of the severity of radiological consequences than the number of fatalities, although the latter is widely used to assess other catastrophic events such as earthquakes or tsunami. It is a valuable partial indicator in the context of comprehensive studies of overall consequences. Section 2 makes a clear distinction between long-term relocation and emergency evacuation and proposes a method to estimate the number of refugees. Section 3 examines the distribution of nuclear refugees with respect to weather and release site. The distribution is asymmetric and fat-tailed: unfavorable weather can lead to the contamination of large areas of land; large cities have in turn a higher probability of being contaminated. - Highlights: • Number of refugees is a good indicator of the severity of radiological consequences. • It is a better measure of the long-term consequences than the number of fatalities. • A representative meteorological sample should be sufficiently large. • The number of refugees highly depends on the release site in a country like France.

  11. Decontamination process applied to radioactive solid wastes from nuclear power plants

    International Nuclear Information System (INIS)

    Franco, Milton B.; Kastner, Geraldo F.; Monteiro, Roberto Pellacani G.

    2009-01-01

    The process of decontamination is an important step in the economic operation of nuclear facilities. A large number of protective clothing, metallic parts and equipment get contaminated during the handling of radioactive materials in laboratory, plants and reactors. Safe and economic operation of these nuclear facilities will have a bearing on the extent to which these materials are reclaimed by the process of decontamination. The most common radioactive contaminants are fission products, corrosion products, uranium and thorium. The principles involved in decontamination are the same as those for an industrial cleaning process. However, the main difference is in the degree of cleaning required and at times special techniques have to be employed for removing even trace quantities of radioactive materials. This paper relate decontaminations experiences using acids and acids mixtures (HCl, HF, HNO 3 , KMnO 4 , C 2 H 2 O 4 , HBF 4 ) in several kinds of radioactive solid wastes from nuclear power plants. The result solutions were monitored by nuclear analytical techniques, in order to contribute for radiochemical characterization of these wastes. (author)

  12. Radioactive waste management and the nuclear renaissance

    International Nuclear Information System (INIS)

    McCombie, C.

    2006-01-01

    Full text: Full text: For many years, nuclear supporters have been talking of a possible nuclear power renaissance. Today there are definite signs that this is finally beginning to happen. New plants are being built or planned in China, Japan, Korea, Finland, France and even the USA. Phase-out policies are being rethought in countries like Sweden, Belgium and Germany. Countries like Vietnam, Indonesia, the Baltic States and even Australia are choosing or debating initiating a nuclear programme. Support for these nuclear power developments may be strongly influenced by the progress of waste management programmes, especially final disposal. Conversely, the growing realisation of the potential global benefits of nuclear power may well lead to increased support, effort and funding for initiatives to ensure that all nations have access to safe and secure waste management facilities. This implies that large nuclear programmes must make progress with implementation of treatment, storage and disposal facilities for all of their radioactive wastes. For small nuclear programmes (and for countries with nuclear applications other than power generation) such facilities are also necessary. For economic and other reasons, these small programmes may not be able to implement all of the required national facilities. Multinational cooperation is needed. This can be realised by large countries providing back-end services such as reprocessing and disposal, or by small countries forming regional or international partnerships to implement shared facilities for storage and/or disposal. This paper will trace through the past decades the mutual interactions between programmes in nuclear power and in waste management. The relevant issues of concern for both include radiological safety, environmental impacts and, most topically, non-proliferation and security. Debates on these issues have strongly affected national efforts to implement power plants and repositories, and also influenced the

  13. Studies of radioactivity from nuclear explosions for peaceful purposes

    Energy Technology Data Exchange (ETDEWEB)

    Siddons, R A [AWRE, Aldermaston (United Kingdom)

    1970-05-01

    Estimates are made of the extent and duration of hazards from radioactivity to the general public due to fallout from a cratering explosion. The nuclear explosive is assumed to be 'clean' in the sense that only a small fraction of the yield is derived from fission. Hypothetical examples take an explosive of total yield 100 kT, of which 10 kT, 1 kT and zero - the ultimate in cleanliness - are derived from fission. The maximum permitted level to the public is taken as 0.5 rem in a period of one year. Sources of activity considered are fission products, residual thermonuclear material (tritium), neutron induced activity in the device materials and neutron induced activity in the surrounding rock. Estimates of the production are made, and are associated with a distribution function derived from the Sedan fallout measurements. The hazards from radioactivity associated with the creation of a storage reservoir for natural gas have also been considered. In this case the main problem is contamination of the product by tritium left in the chimney. The possibility of flushing out this tritium with water is discussed. (author)

  14. Studies of radioactivity from nuclear explosions for peaceful purposes

    International Nuclear Information System (INIS)

    Siddons, R.A.

    1970-01-01

    Estimates are made of the extent and duration of hazards from radioactivity to the general public due to fallout from a cratering explosion. The nuclear explosive is assumed to be 'clean' in the sense that only a small fraction of the yield is derived from fission. Hypothetical examples take an explosive of total yield 100 kT, of which 10 kT, 1 kT and zero - the ultimate in cleanliness - are derived from fission. The maximum permitted level to the public is taken as 0.5 rem in a period of one year. Sources of activity considered are fission products, residual thermonuclear material (tritium), neutron induced activity in the device materials and neutron induced activity in the surrounding rock. Estimates of the production are made, and are associated with a distribution function derived from the Sedan fallout measurements. The hazards from radioactivity associated with the creation of a storage reservoir for natural gas have also been considered. In this case the main problem is contamination of the product by tritium left in the chimney. The possibility of flushing out this tritium with water is discussed. (author)

  15. Radioactive waste management and advanced nuclear fuel cycle technologies

    International Nuclear Information System (INIS)

    2007-01-01

    In 2007 ENEA's Department of Nuclear Fusion and Fission, and Related Technologies acted according to national policy and the role assigned to ENEA FPN by Law 257/2003 regarding radioactive waste management and advanced nuclear fuel cycle technologies

  16. Disposal and handling of nuclear steam generator chemical cleaning wastes

    International Nuclear Information System (INIS)

    Larrick, A.P.; Schneidmiller, D.

    1978-01-01

    A large number of pressurized water nuclear reactor electrical generating plants have experienced a corrosion-related problem with their steam generators known as denting. Denting is a mechanical deformation of the steam generator tubes that occurs at the tube support plates. Corrosion of the tube support plates occurs within the annuli through which the tubes pass and the resulting corrosion oxides, which are larger in volume than the original metal, compress and deform the tubes. In some cases, the induced stresses have been severe enough to cause tube and/or support cracking. The problem was so severe at the Turkey Point and Surrey plants that the tubing is being replaced. For less severe cases, chemical cleaning of the oxides, and other materials which deposit in the annuli from the water, is being considered. A Department of Energy-sponsored program was conducted by Consolidated Edison Co. of New York which identified several suitable cleaning solvents and led to in-plant chemical cleaning pilot demonstrations in the Indian Point Unit 1 steam generators. Current programs to improve the technology are being conducted by the Electric Power Research Institute, and the three PWR NSSS vendors with the assistance of numerous consultants, vendors, and laboratories. These programs are expected to result in more effective, less corrosive solvents. However, after a chemical cleaning is conducted, a large problem still remains- that of disposing of the spent wastes. The paper summarizes some of the methods currently available for handling and disposal of the wastes

  17. Nuclear astrophysics with radioactive beams: a TRIUMF perspective

    International Nuclear Information System (INIS)

    Shotter, A.C.

    2003-01-01

    Explosive nuclear burning in stellar environments involves reactions with a wide range of isotopes. For isotopes that are unstable, information on relevant reaction rates can only generally be obtained at radioactive beam facilities. The ISAC facility at TRIUMF is purpose built to provide a wide range of radioactive beams for nuclear astrophysics purposes as well as a range of other science

  18. Nuclear power and radioactive waste management

    International Nuclear Information System (INIS)

    Feates, F.S.

    1978-01-01

    The generation of electrical power by nuclear means leads to a very considerable reduction in the quantities of waste which would result from the use of any other fuel. The waste possess particular hazards which diminish with time. They are most dangerous during the first 500 years whilst fission products are decaying; subsequently their toxicity is comparable with that of many industrial chemicals which are currently in widespread use. There is no reason to believe that environmentally satisfactory disposal means cannot be found either on or under the ocean bed or below the surface of the earth. Nevertheless, since so little waste is involved considerable care can be devoted to ensure that whatever disposal method is selected is safe. The standards to be adopted are that any disposal method selected will, even in the worst conceivable situation, not lead to a significant increase in the exposure man already receives due to radioactivity arising from natural sources. (author)

  19. Qualification test of chemical cleaning for secondary side of steam generator in Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Zhang Mengqin; Zhang Shufeng; Yu Jinghua; Hou Shufeng

    1997-07-01

    The chemical cleaning technique for removing sludge on the secondary side in Qinshan Nuclear Power Plant has been qualified. The chemical cleaning process will carry out during shutdown refuelling. The qualification test has studied the effect of chemical cleaning agent component, cleaning time on dissolution effectiveness of sludge (Fe 3 O 4 ) and to evaluate corrosion situation of main materials of SG in the cleaning process. The main component of cleaning agent is EDTA. The cleaning temperature is 20∼30 degree C. It is determined that allowable remains amount of cleaning agent (EDTA). The technique of cleaning, rinse, passivation for the chemical cleaning in Qinshan Nuclear Power Plant has been made. The qualification test shown that the technique can dissolve Fe 3 O 4 >1 g/L, the corrosion of materials is in allowable value, the allowable remains of EDTA is <0.01%. The technique character is static, ambient temperature. (9 refs., 12 tabs.)

  20. Performance evaluation of air cleaning devices of an operating low level radioactive solid waste incinerator

    International Nuclear Information System (INIS)

    Subramanian, V.; Surya Narayana, D.S.; Sundararajan, A.R.; Satyasai, P.M.; Ahmed, Jaleel

    1997-01-01

    Particle removal efficiencies of a cyclone separator, baghouse filters and a high efficiency particulate activity (HEPA) filter bank of an incinerator have been determined during the incineration of combustible low level solid radioactive wastes with surface dose of 20 - 50 gy/h. Experimental runs have been carried out to collect the particulates in various aerodynamic size ranges using an eight stage Andersen sampler and a low pressure impactor (LPI) while the incinerator is in operation. The collection efficiencies of the cyclone, baghouse and HEPA filters have been found to be 100 per cent for particles of size greater than 4.7, 2.1 and 1.1 μm respectively. The results of our investigations indicate that the air cleaning devices of the incinerator are working according to their design criteria. The data will be useful in the design and operation of air cleaning devices for toxic gaseous effluents. (author). 3 refs., 2 figs., 1 tab

  1. Review of radioactive discharges from nuclear power stations

    International Nuclear Information System (INIS)

    1991-02-01

    HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report is a review of the arisings and concludes that suitable technologies exist, which if applied, could reduce discharges from nuclear power plants in England and Wales in line with the rest of Europe. (author)

  2. Off-gases cleaning and release from a radioactive waste incinerator protection and safety aspects

    International Nuclear Information System (INIS)

    Caramelle, D.; Chevalier, G.

    1985-01-01

    The function of an off-gas cleaning and release installation being environmental protection, the means allowing the installation operation and the quality control of this function must be available. The chief risk then in normal operation is occupational exposure in the vicinity of the points of radioactive products accumulation. The accidental risks are mainly related to an outage of the installation, or a tightness failure resulting from either internal perturbation (filter tear, exhauster failure, washing-column clogging) or external incidents (electricity cut off, furnace disarrangement, fire or explosion in the building, etc.). (orig.)

  3. Operational improvement to the flue gas cleaning system in radioactive waste incineration facilities

    International Nuclear Information System (INIS)

    Zheng Bowen; Li Xiaohai; Wang Peiyi

    2012-01-01

    After years of operation, some problems, such as corrosion and waste water treatment, have been found in the first domestic whole-scale radioactive waste incineration facility. According to the origin of the problems, the flue gas cleaning system has been optimized and improved in terms of technical process, material and structure. It improves the operational stability, extends the equipment life-time, and also reduces the amount of secondary waste. In addition, as major sources of problems, waste management, operational experiences and information exchange deserve more attention. (authors)

  4. Nuclear air cleaning: the need for a change in emphasis

    International Nuclear Information System (INIS)

    Carbaugh, E.H.

    1982-11-01

    The nuclear industry now has over 35 years of experience in nuclear air cleaning. This experience covers technology development, system design, operations, and maintenance. Much of the past experience has been directed towards technology development with particular emphasis on high efficiency particulate air (HEPA) filters. Implementation of this technology has lagged its development by a number of years. A recent study examines the cause and frequencies of HEPA filter changeouts and failures. These data lead to a conclusion that a shift in emphasis from technology development to the training of personnel and the designing and maintaining of such systems is needed. Some highlights of the data and a discussion of topics which should be addressed in training will be presented

  5. Nuclear air cleaning: the need for a change in emphasis

    International Nuclear Information System (INIS)

    Carbaugh, E.H.

    1983-01-01

    The nuclear industry now has over 35 years of experience in nuclear air cleaning. This experience covers technology development, system design, operations, and maintenance. Much of the past experience has been directed towards technology development with particular emphasis on high efficiency particulate air (HEPA) filters. Implementation of this technology has lagged its development by a number of years. A recent study examines the causes and frequencies of HEPA filter changeouts and failures. These data lead to a conclusion that a shift in emphasis from technology development to the training of personnel and the designing and maintaining of such systems is needed. Some highlights of the data and a discussion of topics which should be addressed in training will be presented. 7 references, 5 tables

  6. Licensing of nuclear and radioactive installations in Peru

    International Nuclear Information System (INIS)

    Medina Gironzini, E.

    1987-01-01

    In Peru, the Regulation for Ionizing Radiation Sources is applied, which establishes the norms and procedures to follow in the nuclear and radioactive installations of the country in order to assure their correct operation as concerns to the nuclear safety and radiological protection, allowing the emission of the respective licenses. As for the nuclear facilities, this authorization includes the Previous License, the Construction License and the Operation License (provisional and definitive) and for radioactive facilities and equipment generating ionizing radiations: the Construction License and the Operation License. The personnel also require a license that can be an operator license (as for nuclear reactors) or a supervisor license (for nuclear and radioactive facilities). In spite of the above mentioned regulation and its long enforcement period, less than 10% of radioactive facilities in this country are licensed, due to different problems which will be solved in the medium term. (Author)

  7. Nuclear power generation alternative for a clean energy future

    International Nuclear Information System (INIS)

    Simionov, V; Ibadula, R.; Popescu, Ion.; Bobric, Elena

    2001-01-01

    World Energy Council stated that to raise the efficiency in which energy is provided is a huge challenge for power engineering. Over 60% of primary energy is in effect, wasted. At present 63% of the world's electricity comes from thermal power (coal, oil and gas), 19% from hydro, 17% from nuclear, 0.5% from geothermal and 0.1% from solar, wind and biomass. Nuclear power almost completely avoids all the problems associated within fossil fuels: no greenhouse effect, no acid rain, no air pollution with sulfur dioxide, nitrogen oxides, no oil spills, etc. Its impact on health and environment is related to radiation and is relatively minor. Without pretending a high accuracy of numbers, if the first Romanian nuclear power reactor will be replaced by a coal plant of equivalent capacity, about 5 millions tons of CO 2 and large quantities of associated sulfur and nitrous oxides, would be discharged to the atmosphere each year. However, the acceptance of nuclear power is largely an emotional issue. Based on the environmental monitoring program this paper tries to demonstrate that the routine radioactive emissions of Cernavoda NPP, which are limited by competent national authority, constitutes an insignificant risk increase. The concept of sustainable development was elaborated in the late 1980s and defined as a development that fulfil the needs of the present, without compromising the ability of future generations to meet their own needs. Sustainable development incorporates equity within and across countries as well as across generations, and integrates economic growth, environmental protection and social welfare. To analyze nuclear energy from a sustainable development perspective it is necessary to consider its economic, environmental and social impacts characteristics, both positive and negative. It is obvious that the development of nuclear energy broadens the natural resource base usable for energy production, and increases human and man-made capital. There are also

  8. Measurement of nuclear cross sections using radioactive beams

    International Nuclear Information System (INIS)

    Lizcano, D.; Aguilera, E.F.; Martinez Q, E.

    1999-01-01

    One of the main applications of the production and use of nuclear radioactive beams is the measurement of nuclear cross sections. In this work is used a 6 He nuclear radioactive beam (β emitting with half life 806.7 ms) for the study of the reaction 6 + 209 Bi which could have several products. This investigation was realized in collaboration with the personnel of the Nuclear Structure laboratory at the University of Notre Dame (U.S.A.) and the National institute of Nuclear Research and CONACyT by Mexico. (Author)

  9. ASN guide project: complete cleaning-up modalities acceptable in nuclear base installations in France - ASN guide project nr 14 - Release of 21/06/2010

    International Nuclear Information System (INIS)

    2010-01-01

    As any nuclear base installation evolves during its exploitation, some premises or buildings may change of use or be destroyed. In the first case, a complete cleaning up might be necessary to get rid of radioactive products. In order to deal with this issue, after a brief recall of the regulatory context and references, and a recall of the general doctrine of waste management in nuclear base installations in France, this guide project presents the principles for a complete cleaning up of structures belonging to an area containing nuclear wastes. It describes the modalities of definition of three different and successive defence lines. It defines the requirements in performing cleaning-up operations, the requirements in terms of quality insurance, and the different administrative procedures (before, during and after cleaning-up works). Some particular cases are addressed

  10. Nuclear toxicology. To detect, to clean; Toxicologie nucleaire. Dectecter, depolluer

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, D. [CEA Cadarache (IBEB), Lab. de Bioenergetique Cellulaire, 13 - Saint-Paul-lez-Durance (France); Lecomte-Pradines, C. [Institut de Radioprotection et de Surete Nucleaire (IRSN/DEI), Lab. de Radioecologie et d' Ecotoxicologie, 13 - Saint-Paul-lez-Durance (France); Quemeneur, E. [CEA Valrho (IBEB), Lab. de Radioecologie et d' Ecotoxicologie Nucleaire, 30 - Marcoule (France); Petitot, F. [CEA Centre de Pierrelatte, Institut de Radioprotection et de Surete Nucleaire, (IRSN-DRPH-SRBE), Lab. de Radiotoxicologie Experimentale, 26 (France); Souidi, M.; Bertho, J.M. [CEA Fontenay-aux-Roses, Institut de Radioprotection et de Surete Nucleaire, (IRSN-DRPH-SRBE), Lab. de Radiotoxicologie Experimentale 92 (France); Junot, Ch. [CEA Saclay (iBiTec-S/SPI), Lab. d' Etude du Metabolisme des Medicaments, 91 - Gif-sur-Yvette (France); Malard, V. [CEA Valrho (IBEB-SBTN), Lab. de Biochimie des Systemes Perturbes, 30 - Marcoule (France); Berthomieu, C.; Chapon, V. [CEA Cadarache (IBEB), Lab. des Interactions Proteine Metal, 13 - Saint-Paul-lez-Durance (France); Gilbin, R.; Misson-Pons, J. [CEA Cadarache, Institut de Radioprotection et de Surete Nucleaire (IRSN/DEI), Lab. de Radioecologie et d' Ecotoxicologie, 13 - Saint-Paul-lez-Durance (France); Vavasseur, A. [CEA Cadarache (IBEB), Lab. des Echanges Membranaires et Signalisation, 13 - Saint-Paul-lez-Durance (France); Richaud, P. [CEA Cadarache (IBEB), Lab. de Bioenergetique et Biotechnologie des Basteries et Microalgues, 13 - Saint-Paul-lez-Durance (France); Ansoborlo, E.; Taran, F.; Benech, H.; Fattal, E.; Tsapis, N.; Menetrier, F.; Deverre, J.R.; Burgada, R. [CEA Marcoule (DEN/DRCP/CETAMA), 30 (France)

    2009-01-15

    This file shows two complementary parts: one aiming to a better detection of exposure for man and environment and and other one relative to the treatments to be used when there is a contamination. The development of biological captors is a research axis that could be very useful for nuclear toxicologists that wish to dispose of perceptible measurement tools. In the same idea biological markers could be an important help to determine the toxic quantity in organism in case of internal radioactive contamination. About remedial actions, bacteria are able to reduce, to oxide, to capture pollutants and then it is not insane to use them in efficient and low cost remediation for waters or contaminated lands, especially by trace metals or radioactive compounds. Next to them, plants can offer the same service it is the case for sunflower able to treat water loaded in uranium. This file ends with a review of the different treatments known nowadays as therapies for contamination by radioisotopes used in nuclear industry. (N.C.)

  11. Supply, operation and radioactive waste disposal of nuclear power plants

    International Nuclear Information System (INIS)

    Mohrhauer, H.; Krey, M.; Haag, G.; Wolters, J.; Merz, E.; Sauermann, P.F.

    1981-07-01

    The subject of 'Nuclear Fuel Cycle' is treated in 5 reports: 1. Uranium supply; 2. Fabrication and characteristics of fuel elements; 3. Design, operation and safety of nuclear power plants after Harrisburg; 4. Radioactive waste disposal of nuclear power plants - changed political scenery after 1979; 5. Shutdown and dismantling of LWR-KKW - state of knowledge and feasibility. (HP) [de

  12. Chapter 2. Peculiarities of radioactive particle formation and isotope fractionation resulted from underground nuclear explosions

    International Nuclear Information System (INIS)

    1996-01-01

    Radioactive particles, forming terrain fallouts from underground nuclear explosion differ sufficiently from radioactive particles, produced by atmospheric nuclear explosions. Patterns of underground nuclear explosion development, release of radioactivity to the atmosphere, formation of a cloud and base surge, peculiarities of formed radioactive particles, data on isotope fractionation in radioactive particles are presented. Scheme of particle activation, resulted from underground explosions is given

  13. Radioactive droplet moisture transfer from nuclear power plant spray pool

    International Nuclear Information System (INIS)

    Elokhin, A.P.

    1995-01-01

    Problem on transfer of radioactive droplet moisture with an account of its evaporation from the nuclear power plant spray pool (NPP coolant) is considered. Formulae enabling evaluation of droplet and radioactive water admixture lifetime as a whole, as well as the maximum distance (by wind), over which it can extend, are obtained. Recommendations for decrease in the droplet dispersed composition and reduction in scale of radioactive contamination of underlying surface are given. 10 refs.; 3 figs.; 1 tab

  14. Production and use of radioactive nuclear beams

    International Nuclear Information System (INIS)

    Tanihata, Isao

    1994-01-01

    Two different production method of radioactive nuclear beams (RNB) are reviewed, in this paper. One is the secondary beam method that use a high-energy heavy-ion reaction and a separator and the other is the reacceleration method. The RNB is also expected to have following properties that are useful to the application in wider research and technical usage; 1. any elements and isotopes can be used as a beam. 2. it is easy to control a position and a depth of the implantation. 3. an extremely sensitive detection is possible because they emit radiations. 4. one can select the lifetime among the isotopes suitable for a specific phenomenon. 5. one can select a spin among the isotopes for specific selectivity to the phenomenon. These useful properties of the RNB and a few recent examples of study are discussed. Among them are the discovery of the neutron skin and the neutron halo in nuclei near the limit of existence, the first determinations of reactions relevant to the synthesis of the heavy elements in the universe, and an application to the PET. (J.P.N.)

  15. Radioactive Effluents from Nuclear Power Plants Annual Report 2007

    International Nuclear Information System (INIS)

    2010-01-01

    This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2007. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

  16. Radioactive Effluents from Nuclear Power Plants Annual Report 2008

    International Nuclear Information System (INIS)

    2010-01-01

    This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2008. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

  17. Development of an air cleaning system for dissolving high explosives from nuclear warheads

    Energy Technology Data Exchange (ETDEWEB)

    Bergman, W.; Wilson, K.; Staggs, K.; Wapman, D. [Lawrence Livermore National Lab., CA (United States)

    1997-08-01

    The Department of Energy (DOE) has a major effort underway in dismantling nuclear weapons. In support of this effort we have been developing a workstation for removing the high explosive (HE) from nuclear warheads using hot sprays of dimethyl sulfoxide (DMSO) solvent to dissolve the HE. An important component of the workstation is the air cleaning system that is used to contain DMSO aerosols and vapor and radioactive aerosols. The air cleaning system consists of a condenser to liquefy the hot DMSO vapor, a demister pad to remove most of the DMSO aerosols, a high efficiency particulate air (HEPA) filter to remove the remaining aerosols, an activated carbon filter to remove the DMSO vapor, and a final HEPA filter to meet the redundancy requirement for HEPA filters in radioactive applications. The demister pad is a 4{double_prime} thick mat of glass and steel fibers and was selected after conducting screening tests on promising candidates. We also conducted screening tests on various activated carbons and found that all had a similar performance. The carbon breakthrough curves were fitted to a modified Wheeler`s equation and gave excellent predictions for the effect of different flow rates. After all of the components were assembled, we ran a series of performance tests on the components and system to determine the particle capture efficiency as a function of size for dioctyl sebacate (DOS) and DMSO aerosols using laser particle counters and filter samples. The pad had an efficiency greater than 990% for 0.1 {mu}m DMSO particles. Test results on the prototype carbon filter showed only 70% efficiency, instead of the 99.9% in small scale laboratory tests. Thus further work will be required to develop the prototype carbon filter. 7 refs., 18 figs., 10 tabs.

  18. Prospects of nuclear waste management and radioactive waste management

    International Nuclear Information System (INIS)

    Koprda, V.

    2015-01-01

    The policy of radioactive waste management in the Slovak Republic is based on the principles defined by law on the National Nuclear Fund (NJF) and sets basic objectives: 1 Safe and reliable nuclear decommissioning; 2 The minimization of radioactive waste; 3. Selection of a suitable fuel cycle; 4 Safe storage of radioactive waste (RAW) 5 Security chain management of radioactive waste and spent nuclear fuel (SNF); 6 Nuclear safety; 7 The application of a graduated approach; 8 Respect of the principle 'a polluter pays'; 9 Objective decision-making process; 10 Responsibility. In connection with the above objectives, it appears necessary to build required facilities that are listed in this article.

  19. Radioactive Semivolatiles in Nuclear Fuel Reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Jubin, R. T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Strachan, D. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ilas, G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Spencer, B. B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Soelberg, N. R. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    In nuclear fuel reprocessing, various radioactive elements enter the gas phase from the unit operations found in the reprocessing facility. In previous reports, the pathways and required removal were discussed for four radionuclides known to be volatile, 14C, 3H, 129I, and 85Kr. Other, less volatile isotopes can also report to the off-gas streams in a reprocessing facility. These were reported to be isotopes of Cs, Cd, Ru, Sb, Tc, and Te. In this report, an effort is made to determine which, if any, of 24 semivolatile radionuclides could be released from a reprocessing plant and, if so, what would be the likely quantities released. As part of this study of semivolatile elements, the amount of each generated during fission is included as part of the assessment for the need to control their emission. Also included in this study is the assessment of the cooling time (time out of reactor) before the fuel is processed. This aspect is important for the short-lived isotopes shown in the list, especially for cooling times approaching 10 y. The approach taken in this study was to determine if semivolatile radionuclides need to be included in a list of gas-phase radionuclides that might need to be removed to meet Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) regulations. A list of possible elements was developed through a literature search and through knowledge and literature on the chemical processes in typical aqueous processing of nuclear fuels. A long list of possible radionuclides present in irradiated fuel was generated and then trimmed by considering isotope half-life and calculating the dose from each to a maximum exposed individual with the US EPA airborne radiological dispersion and risk assessment code CAP88 (Rosnick 1992) to yield a short list of elements that actually need to be considered for control because they require high decontamination factors to meet a reasonable fraction of the regulated release. Each of these elements is

  20. The high efficiency steel filters for nuclear air cleaning

    International Nuclear Information System (INIS)

    Bergman, W.; Larsen, G.; Lopez, R.; Williams, K.; Violet, C.

    1990-08-01

    We have, in cooperation with industry, developed high-efficiency filters made from sintered stainless-steel fibers for use in several air-cleaning applications in the nuclear industry. These filters were developed to overcome the failure modes in present high-efficiency particulate air (HEPA) filters. HEPA filters are made from glass paper and glue, and they may fail when they get hot or wet and when they are overpressured. In developing our steel filters, we first evaluated the commercially available stainless-steel filter media made from sintered powder and sintered fiber. The sintered-fiber media performed much better than sintered-powder media, and the best media had the smallest fiber diameter. Using the best media, we then built prototype filters for venting compressed gases and evaluated them in our automated filter tester. 12 refs., 20 figs

  1. High efficiency steel filters for nuclear air cleaning

    International Nuclear Information System (INIS)

    Bergman, W.; Conner, J.; Larsen, G.; Lopez, R.; Turner, C.; Vahla, G.; Violet, C.; Williams, K.

    1991-01-01

    The authors have, in cooperation with industry, developed high-efficiency filters made from sintered stainless-steel fibers for use in several air-cleaning applications in the nuclear industry. These filters were developed to overcome the failure modes in present high-efficiently particulate air (HEPA) filters. HEPA filters are made from glass paper and glue, and they may fail when they get hot or wet and when they are overpressured. In developing steel filters, they first evaluated the commercially available stainless-steel filter media made from sintered powder and sintered fiber. The sintered-fiber media performed much better than sintered-powder media, and the best media had the smallest fiber diameter. Using the best media, prototype filters were then built for venting compressed gases and evaluated in their automated filter tester

  2. Radioactive waste management in the VS military nuclear industry

    International Nuclear Information System (INIS)

    Kobal'chuk, O.V.; Kruglov, A.K.; Sokolova, I.D.; Smirnov, Yu.V.

    1989-01-01

    Organization and plans of radioactive waste management in the US military nuclear industry, determining transition from the policy of temporal waste storage to their final and safe disposal are presented. Programs of long-term management of high-level, transuranium and low-level wastes, the problems of the work financing and the structure of management activities related to the radioactive waste processing military nuclear industry enterprises are considered

  3. Non-destructive nuclear forensics of radioactive samples

    Energy Technology Data Exchange (ETDEWEB)

    Rogge, R.B. [Canadian Neutron Beam Centre, Chalk River, ON (Canada); Alexander, Q.; Bentoumi, G.; Dimayuga, F. [Atomic Energy of Canada Limited, Chalk River, ON (Canada); Flacau, R. [Canadian Neutron Beam Centre, Chalk River, ON (Canada); Li, G.; Li, L.; Sur, B. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    It is a matter of public safety and security to be able to examine suspicious packages of unknown origin. If the package is radioactive and sealed (i.e., the radioactive materials contained in the package, including their chemical and physical forms, are unknown), there is a significant risk on how to handle the package and eventually safely dispose of its contents. Within the context of nuclear security, nuclear forensics helps address the key issue of identifying the nature and origin of radioactive and nuclear material in order to improve physical protection measures and prevent future theft or diversion of these materials. Nuclear forensics utilizes analytical techniques, destructive and non-destructive, developed for applications related to nuclear fuel cycles. This paper demonstrates the non-destructive examination techniques that can be used to inspect encapsulated radioactive samples. Results of γ spectroscopy, X-ray spectroscopy, neutron imaging, neutron diffraction, and delayed neutron analysis as applied to an examination of sealed capsules containing unknown radioactive materials are presented. The paper also highlights the value of these techniques to the overall nuclear forensic investigation to determine the origin of these unknown radioactive materials. (author)

  4. Proceedings of the 24. DOE/NRC nuclear air cleaning and treatment conference

    International Nuclear Information System (INIS)

    First, M.W.

    1997-08-01

    This report contains the papers presented at the 24th DOE/NRC Nuclear Air Cleaning and Treatment Conference and the associated discussions. Major topics are: (1) nuclear air cleaning issues, (2) waste management, (3) instrumentation and measurement, (4) testing air and gas cleaning systems, (5) progress and challenges in cleaning up Hanford, (6) international nuclear programs, (7) standardized test methods, (8) HVAC, (9) decommissioning, (10) computer modeling applications, (11) adsorption, (12) iodine treatment, (13) filters, and (14) codes and standards for filters and adsorbers. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

  5. Proceedings of the 24. DOE/NRC nuclear air cleaning and treatment conference

    Energy Technology Data Exchange (ETDEWEB)

    First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

    1997-08-01

    This report contains the papers presented at the 24th DOE/NRC Nuclear Air Cleaning and Treatment Conference and the associated discussions. Major topics are: (1) nuclear air cleaning issues, (2) waste management, (3) instrumentation and measurement, (4) testing air and gas cleaning systems, (5) progress and challenges in cleaning up Hanford, (6) international nuclear programs, (7) standardized test methods, (8) HVAC, (9) decommissioning, (10) computer modeling applications, (11) adsorption, (12) iodine treatment, (13) filters, and (14) codes and standards for filters and adsorbers. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  6. Proceedings of the 21st DOE/NRC nuclear air cleaning conference

    International Nuclear Information System (INIS)

    First, M.W.

    1991-02-01

    The 21st meeting of the Department of Energy/Nuclear Regulatory Commission (DOE/NRC) Nuclear Air Cleaning Conference was held in San Diego, CA on August 13--16, 1990. The proceedings have been published as a two volume set. Volume 2 contains sessions covering adsorbents, nuclear codes and standards, modelling, filters, safety, containment venting and a review of nuclear air cleaning programs around the world. Also included is the list of attendees and an index of authors and speakers

  7. Accountability of Radioactive Materials in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Noor Fadilla Ismail; Wan Saffiey Wan Abdullah; Khairuddin Mohamad Kontol; Azimawati Ahmad; Suzilawati Muhd Sarowi; Mohd Fazlie Abdul Rashid

    2016-01-01

    Radioactive materials possessed in Malaysian Nuclear Agency have many beneficial applications for research and development, calibration, tracer and irradiation. There are two types of radioactive materials which consist of sealed sourced and unsealed sourced shall be accounted for and secured at all the times by following the security aspect. The Health Physics Group in the Department of Radiation Safety and Health Division is responsible to manage the issues related to any accountability for all radioactive material purchased or received under the radioactive material protocol. The accountability of radioactive materials in Malaysian Nuclear Agency is very important to ensure the security and control the radioactive materials to not to be lost or fall into the hands of people who do not have permission to possess or use it. The accountability of radioactive materials considered as a mandatory to maintaining accountability by complying the requirements of the Atomic Energy Licensing Act 1984 (Act 304) and regulations made thereunder and the conditions of license LPTA / A / 724. In this report describes the important element of accountability of radioactive materials in order to enhances security standard by allowing tracking of the locations of sources and to reduce the risk of radioactive materials falling into the wrong hands. (author)

  8. Method and equipment of processing radioactive laundry wastes

    International Nuclear Information System (INIS)

    Shirai, Takamori; Suzuki, Takeo; Tabata, Masayuki; Takada, Takao; Yamaguchi, Shin-ichi; Noda, Tetsuya.

    1985-01-01

    Purpose: To effectively process radioactive laundry wastes generated due to water-washing after dry-cleaning of protective clothings which have been put on in nuclear facilities. Method: Dry cleaning soaps and ionic radioactive materials contained in radioactive laundry wastes are selectively adsorbed to decontaminate by adsorbents. Then, the adsorbents having adsorbed dry cleaning soaps and ionic radioactive materials are purified by being removed with these radioactive materials. The purified adsorbents are re-used. (Seki, T.)

  9. Provenance of nuclear radioactivity radiation and hazardous health risks

    International Nuclear Information System (INIS)

    Sakhuja, Geeta

    2016-01-01

    This assessment has an important consideration for nuclear energy upon the creation of radioactivity being generated and mobilized through various energy agencies. The term 'Radioactivity' or the rate of nuclear decay is measured in units called 'Becquerel' (Bq), where 1 Bq= 1 event (disintegration) per second. Another commonly used unit of radioactivity is the Curie (Ci), where 1 Ci = 3.70 x 10"1"0 Bq. Radiation is all around us. It is in our environment and has been since the earth was formed. As a result, life has evolved in the presence of significant levels of ionizing radiation. It comes from outer space (cosmic), ground (terrestrial) and even from within our own bodies. It is in the air we breathe, the food we eat, the water we drink, and the state of our wellbeing. However, the entire system is related to human and human-health issues. This paper examines the empirical evidence incorporated with human-made nuclear radioactivity from nuclear energy sources, especially while maintaining the viability of radioactive mechanisms, which may cause the uncontrolled highly dangerous harmful effects of radionuclides in human body and these radiations can even damage the DNA in the cells of people when exposed to it, because it is the DNA that passes on instructions for growth and development to the next generation. This, in turn, is the paradigm for the health risks of various sources of nuclear radioactivity. (author)

  10. Evaluation of radioactive inventory of nuclear ship MUTSU

    International Nuclear Information System (INIS)

    Adachi, M.

    1995-01-01

    The operation of the Nuclear Ship MUTSU was terminated in January 1992. Radioactivities and dose rates on the surfaces of reactor components were measured in order to estimate the residual radioactive inventory in the MUTSU. The predicted radioactive inventory due to neutron activation was calculated by using a computer code systems. The results show good correlation between predicted and measured values radioactivities in the core baffle plate. The radioactive inventory was estimated to be 8.4 x 10 14 Bq as of 1.5 years from the final shutdown of reactor operation. The contamination in reactor components was estimated from the contamination level measured in the Japan Power Demonstration Reactor (JPDR), from which the dose rates in the reactor room were calculated. The radioactive inventory due to contamination was estimated at 3.4 x 10 10 Bq. Some difference was found between these calculations and measurements. (Author)

  11. Testing and operation of nuclear air-cleaning systems in Qinshan NPP

    International Nuclear Information System (INIS)

    Yang Lin

    1993-01-01

    The components of nuclear air-cleaning system, system function, operational mode and the performance of cleaning components in Qinshan Nuclear Power Plant are described. The items, purpose, methods and results of in-place testing after the installation are also described in detail. The in-place testing verifies that nuclear air-cleaning systems in Qinshan Nuclear Power Plant are reliable and high effective. It also describes the points of the operational management. It is shown that the good operational management is the key which developed prescription function of nuclear air-cleaning systems. At present, Qinshan Nuclear Power Plant will be in full power, the normal operation of the system is satisfied with the demand of safe operation in Qinshan Nuclear Power Company

  12. Comparison of the performance, advantages and disadvantages of nuclear power generation compared to other clean sources of electricity

    International Nuclear Information System (INIS)

    Mata, Jônatas F.C. da; Neto, Rieder O.; Mesquita, Amir Z.

    2017-01-01

    Nowadays, there is an increase in the demand for electricity in emerging countries, such as India, China and Brazil. There are several alternatives to increase energy generation, and each country has followed certain strategies to achieve this goal. For a long time, developed countries, such as the United States, the United Kingdom and Germany, had focused their efforts on the use of thermoelectric generators through the combustion of non-renewable sources such as coal, natural gas and oil. These examples were followed, also, by the emerging countries. However, pollution levels, generated by these sources, have required the breakdown of this paradigm, and the consequent reversal of large investments in clean energy sources, such as hydraulics, solar and wind. Nucleo-electric energy is also considered a clean energy source, since it does not generate polluting gases during the processing of concentrated uranium in nuclear reactors. In addition, all radioactive waste occupying relatively small volumes and being stored in controlled deposits, in aspects of health, environment and safety. The objective of this article is to compare the performance, in economic, environmental and safety aspects, of nuclear power in relation to renewable energy sources. The results show that nuclear energy has become increasingly competitive in all these fields, justifying the growth of investments in new nuclear technologies. Therefore, the coexistence between the use of clean sources of electricity and the thermonuclear matrix will bring, for humanity, truly sustainable systems of energy generation. (author)

  13. Comparison of the performance, advantages and disadvantages of nuclear power generation compared to other clean sources of electricity

    Energy Technology Data Exchange (ETDEWEB)

    Mata, Jônatas F.C. da; Neto, Rieder O., E-mail: jonatasfmata@yahoo.com.br, E-mail: rieder.neto@gmail.com [Universidade do Estado de Minas Gerais (UEMG), João Monlevade, MG (Brazil); Mesquita, Amir Z., E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    Nowadays, there is an increase in the demand for electricity in emerging countries, such as India, China and Brazil. There are several alternatives to increase energy generation, and each country has followed certain strategies to achieve this goal. For a long time, developed countries, such as the United States, the United Kingdom and Germany, had focused their efforts on the use of thermoelectric generators through the combustion of non-renewable sources such as coal, natural gas and oil. These examples were followed, also, by the emerging countries. However, pollution levels, generated by these sources, have required the breakdown of this paradigm, and the consequent reversal of large investments in clean energy sources, such as hydraulics, solar and wind. Nucleo-electric energy is also considered a clean energy source, since it does not generate polluting gases during the processing of concentrated uranium in nuclear reactors. In addition, all radioactive waste occupying relatively small volumes and being stored in controlled deposits, in aspects of health, environment and safety. The objective of this article is to compare the performance, in economic, environmental and safety aspects, of nuclear power in relation to renewable energy sources. The results show that nuclear energy has become increasingly competitive in all these fields, justifying the growth of investments in new nuclear technologies. Therefore, the coexistence between the use of clean sources of electricity and the thermonuclear matrix will bring, for humanity, truly sustainable systems of energy generation. (author)

  14. Nuclear and x-ray spectroscopy with radioactive sources

    International Nuclear Information System (INIS)

    Fink, R.W.

    1977-01-01

    Research in nuclear chemistry for 1977 is reviewed. The greatest part of the effort was directed to nuclear spectroscopy (systematics, models, experimental studies), but some work was also done involving fast neutrons and x rays from radioactive sources. Isotopes of Tl, Hg, Au, and Eu were studied in particular. Personnel and publications lists are also included. 5 figures, 1 table

  15. Radioactive waste management at the Peruvian Nuclear Energy Institute

    International Nuclear Information System (INIS)

    Mallaupoma, M.

    1986-01-01

    A brief account of current radioactive liquid waste management practices at the Peruvian Nuclear Energy Institute (IPEN), is presented. The storage and disposal systems and facilities to be provided at the future Peruvian Nuclear Research Centre (CNIP) at Huarangal, 40 km to the North of Lima, are described. (Author) [pt

  16. Management of radioactive wastes at nuclear power plants

    International Nuclear Information System (INIS)

    2008-03-01

    This Regulation refers to the requirements of the Regulation CNEN-NE.1.26, 'Safety Operation of Nuclear Power Plants', as expressed in the section 13, specifically in the subsection 13.4, relatives to the management of radioactive wastes at nuclear power plants

  17. Fouling and cleaning of seawater reverse osmosis membranes in Kalpakkam Nuclear Desalination Plant

    International Nuclear Information System (INIS)

    Murugan, V.; Rajanbabu, K.; Tiwari, S.A.; Balasubramanian, C.; Yadav, Manoj Kumar; Dangore, A.Y.; Prabhakar, S.; Tewari, P.K.

    2005-01-01

    Seawater reverse osmosis plant of 1800 m 3 /day capacity is a part of 6300 m 3 /day capacity Nuclear Desalination Demonstration Project, at Kalpakkam. The plant was commissioned in October 2002 and is in continuous operation. This paper deals with types of foulants, membrane cleaning procedures and the improvement in the reverse osmosis system after cleaning. This paper also describes analysis of foulants which may consist of adsorbed organic compounds, particulate matter, microorganisms, metallic oxides and chemical cleaning procedure to be adopted, which is characteristics of sea water used as the membrane foulant is very much specific with respect to the sea water constituents. The cleaning of the membranes in Kalpakkam Nuclear Desalination plant were taken up as the quality of permeate deteriorated and differential pressure across membrane had gone-up. This paper essentially deals with selection of cleaning chemicals, the experience gained in cleaning procedure adopted and effects of cleaning for the membrane system. (author)

  18. Future spent nuclear fuel and radioactive waste infrastructure in Norway

    International Nuclear Information System (INIS)

    Soerlie, A.A.

    2002-01-01

    In Norway a Governmental Committee was appointed in 1991 to make an evaluation of the future steps that need to be taken in Norway to find a final solution for the spent nuclear fuel and for some other radioactive waste for which a disposal option does not exist today. The report from the Committee is now undergoing a formal hearing process. Based on the Committees recommendation and comments during the hearing the responsible Ministry will take a decision on future infrastructure in Norway for the spent nuclear fuel. This will be decisive for the future management of spent nuclear fuel and radioactive waste in Norway. (author)

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

    International Nuclear Information System (INIS)

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

    1982-05-01

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

  20. Nuclear incineration method for long life radioactive wastes

    International Nuclear Information System (INIS)

    Matsumoto, Takaaki; Uematsu, Kunihiko.

    1987-01-01

    Nuclear incineration method is the method of converting the long life radioactive nuclides in wastes to short life or stable nuclides by utilizing the nuclear reaction caused by radiation, unlike usual chemical incineration. By the nuclear incineration, the radioactivity of wastes increases in a short period, but the problems at the time of the disposal are reduced because of the decrease of long life radioactive nuclides. As the radiation used for the nuclear incineration, the neutron beam from fission and fusion reactors and accelerators, the proton beam and gamma ray from accelerators have been studied. The object of the nuclear incineration is actinide, Sr-90, Cs-137, I-129 and Tc-99. In particular, waste actinide emits alpha ray, and is strongly toxic, accordingly, the motive of attempting the nuclear incineration is strong. In Japan, about 24t of waste actinide will accumulate by 2000. The principle of the nuclear incineration, and the nuclear incineration using nuclear fission and fusion reactors and accelerators are described. The nuclear incineration using fission reactors was examined for the first time in 1972 in USA. It is most promising because it is feasible by the present technology without particular research and development. (Kako, I.)

  1. Safety aspects of the cleaning and conditioning of radioactive sludge from spent fuel storage pool on 'RA' Research reactor in the Vinca Institute

    International Nuclear Information System (INIS)

    Pavlovic, R; Pavlovic, S.; Plecas, I.

    1999-01-01

    Spent fuel elements from nuclear reactors in the Vinca Institute have been temporary stored in water filled storage pool. Due to the fact that the water in the spent fuel elements storage pool have not been purified for a long time, all metallic components submerged in the water have been hardly corroded and significant amount of the sludge has been settled on the bottom of the pool. As a first step in improving spent fuel elements storage conditions and slowing down corrosion in the storage spent fuel elements pool we have decided to remove the sludge from the bottom of the pool. Although not high, but slightly radioactive, this sludge had to be treated as radioactive waste material. Some safety aspects and radiation protection measures in the process of the spent fuel storage pool cleaning are presented in this paper

  2. Costs related to radioactive residues from nuclear power

    International Nuclear Information System (INIS)

    1988-06-01

    The nuclear power enterprises are responsible for proper actions for safe handling and final storage of spent nuclear fuel and radioactive waste from Swedish nuclear power facilities. The most important actions are to plan, build and operate necessary plants and systems. The nuclear power enterprises have designated Swedish Nuclear Fuel and Waste Management Co., (SKB), to perform these tasks. In this report calculations concerning costs to carry out these tasks are presented. The calculations are based upon a plan prepared by SKB. The plan is described in the report. As final storage of the long lived and highly radioactive waste is planned to take place in the 21st century continuing research and development may indicate new methods which may affect system design as well as costs in a simplifying way. Plants and systems already operational are: Transport systems for radioactive waste products; A central temporary storage for spent nuclear fuel, 'CLAB'; A final storage for radioactive waste from operating nuclear facilities, 'SFR 1'. (L.F.)

  3. Radioactive iodine releases from nuclear power plant, (1)

    International Nuclear Information System (INIS)

    Hashimoto, Tatsuya

    1974-01-01

    Concerning the release of radioactive iodine from nuclear power plants, the guidelines and data both in Japan and abroad are briefed, including those in the United States, Tsuruga nuclear power station and working Group of the Environmental Radiation Study Committee. In case of the Tsuruga nuclear power station, the radiation dose and other data for a few years are presented. Parameters and factors proposed by the working group cover such as the dose through food intake and respiration, concentration factor, etc. (Mori, K.)

  4. Radioactive waste management at Institute for Nuclear Research (ICN) - Pitesti

    International Nuclear Information System (INIS)

    Bujoreanu, C.

    2004-01-01

    The amounts of liquid and solid wastes accumulated at the Radioactive Wastes Treatment Plant are given. The technologies used for the treatment and conditioning of radioactive wastes are presented. The final product is metallic drum-concrete-radioactive wastes (type A package) for the final disposal at the National Repository Baita, Bihor. The facilities for radioactive waste management at ICN Pitesti are: Plant for treatment, with uranium recovery of liquid radioactive waste resulting from the fabrication of CANDU type nuclear fuel; Plant for treatment of low-active liquid wastes; Plant for conditioning in concrete of the radioactive concentrate obtained during the evaporation treatment of liquid radioactive waste; Plant for incineration of solid radioactive waste contaminated with natural uranium; Plant for treatment and conditioning of organic liquid radioactive waste with tritium content. This wastes are generated by Cernavoda-NPP operation; Plant for conditioning into bitumen of spent ion exchangers at TRIGA reactor. The existing Facility is Baita repository - with two rock cavities of an uranium mine and the total capacity of 21000 containers (200 l drums)

  5. Proceedings of the 23rd DOE/NRC nuclear air cleaning conference

    Energy Technology Data Exchange (ETDEWEB)

    First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

    1995-02-01

    The report contains the papers presented at the 23rd DOE/NRC Nuclear Air Cleaning Conference and the associated discussions. Major topics are: (1) nuclear air cleaning codes, (2) nuclear waste, (3) filters and filtration, (4) effluent stack monitoring, (5) gas processing, (6) adsorption, (7) air treatment systems, (8) source terms and accident analysis, and (9) fuel reprocessing. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  6. Radioactive iodine releases from nuclear power plant, (2)

    International Nuclear Information System (INIS)

    Naritomi, Mitsuo

    1974-01-01

    Internal radiation dose through the respiratory intake of fission products is predominantly due to radioactive iodine not only at the time of reactor accidents but also in normal operation of nuclear facilities. Technological studies in this field have thus been quite active to this day. With the rapid advance of nuclear power generation in recent years, the efforts to reduce environmental release of radioactive iodine and to enhance environmental safety are all the more emphasized. Experiences in the Japan Atomic Energy Research Institute during past about six years are described concerning the radioactive iodine release to the atmosphere in 131 I production and the measures taken to reduce the release. Then, problems are expounded regarding the radioactive iodine release at the time of reactor accidents and in spent fuel reprocessing. (Mori, K.)

  7. Studies on the radioactive contamination due to nuclear detonations II. Preliminary findings on the radioactive fallout due to nuclear detonations

    Energy Technology Data Exchange (ETDEWEB)

    Nishiwaki, Yasushi [Nuclear Reactor Laboratory, Tokyo Institute of Technology, Tokyo (Japan); Nuclear Reactor Laboratoroy, Kinki University, Fuse City, Osaka Precture (Japan)

    1961-11-25

    Since we have detected a considerable amount of artificial radioactivity in the rain in spring 1954, it has become one of the most important items, from the health physics point of view, to continue measurements of radioactivity in the rain and in the atmosphere. To watch out the radioactive contamination of our environment due to repeated nuclear weapons testings in other countries was also considered to be important from the nuclear engineering point of view, in the sense that the permissible allowances of the radioactivity for the peaceful uses of atomic energy might be lowered if the degree of radioactive contamination due to nuclear testings should continue to increase gradually and indefinitely. If the permissible level were lowered, the cost for radiation protection may be expected to increase at the peaceful uses of atomic energy and should the radioactive contamination increase seriously in the future, it was anticipated that we may have to face a very difficult situation in designing the atomic energy facilities for peaceful purposes in our country. From these points of views, we have been continuing measurements of the radioactivity in the rain in Osaka, Japan since the spring of 1954. Some of the preliminary findings are introduced in this paper.

  8. Studies on the radioactive contamination due to nuclear detonations II. Preliminary findings on the radioactive fallout due to nuclear detonations

    International Nuclear Information System (INIS)

    Nishiwaki, Yasushi

    1961-01-01

    Since we have detected a considerable amount of artificial radioactivity in the rain in spring 1954, it has become one of the most important items, from the health physics point of view, to continue measurements of radioactivity in the rain and in the atmosphere. To watch out the radioactive contamination of our environment due to repeated nuclear weapons testings in other countries was also considered to be important from the nuclear engineering point of view, in the sense that the permissible allowances of the radioactivity for the peaceful uses of atomic energy might be lowered if the degree of radioactive contamination due to nuclear testings should continue to increase gradually and indefinitely. If the permissible level were lowered, the cost for radiation protection may be expected to increase at the peaceful uses of atomic energy and should the radioactive contamination increase seriously in the future, it was anticipated that we may have to face a very difficult situation in designing the atomic energy facilities for peaceful purposes in our country. From these points of views, we have been continuing measurements of the radioactivity in the rain in Osaka, Japan since the spring of 1954. Some of the preliminary findings are introduced in this paper

  9. Radioactive waste management at nuclear power plant Cernavoda

    International Nuclear Information System (INIS)

    Raducea, D.

    2002-01-01

    Many human activities generate waste, but people are worried about wastes produced in nuclear power plants (NPPs). Their concern is an unjustified fear toward the hazards from radioactive waste, probably because in any country generating electric power by NPPs a lot of attention is paid to relevant parties involved in radioactive waste management. Significant attention is also given to the management of radioactive waste at the Cemavoda NPP. The general approach required for the collection, handling, conditioning and storage of radioactive wastes, while maintaining acceptable levels of safety for workers, members of the public and the environment, is conceptually established. The overall programme provides the necessary facilities to adequately manage solid radioactive waste from Cemavoda NPP Unit 1 and will be capable of expansion when other units are brought into service. (author)

  10. Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

    International Nuclear Information System (INIS)

    Jooho, W.; Baldwin, G.T.

    2005-01-01

    One critical aspect of any denuclearization of the Democratic People's Republic of Korea (DPRK) involves dismantlement of its nuclear facilities and management of their associated radioactive wastes. The decommissioning problem for its two principal operational plutonium facilities at Yongbyun, the 5MWe nuclear reactor and the Radiochemical Laboratory reprocessing facility, alone present a formidable challenge. Dismantling those facilities will create radioactive waste in addition to existing inventories of spent fuel and reprocessing wastes. Negotiations with the DPRK, such as the Six Party Talks, need to appreciate the enormous scale of the radioactive waste management problem resulting from dismantlement. The two operating plutonium facilities, along with their legacy wastes, will result in anywhere from 50 to 100 metric tons of uranium spent fuel, as much as 500,000 liters of liquid high-level waste, as well as miscellaneous high-level waste sources from the Radiochemical Laboratory. A substantial quantity of intermediate-level waste will result from disposing 600 metric tons of graphite from the reactor, an undetermined quantity of chemical decladding liquid waste from reprocessing, and hundreds of tons of contaminated concrete and metal from facility dismantlement. Various facilities for dismantlement, decontamination, waste treatment and packaging, and storage will be needed. The shipment of spent fuel and liquid high level waste out of the DPRK is also likely to be required. Nuclear facility dismantlement and radioactive waste management in the DPRK are all the more difficult because of nuclear nonproliferation constraints, including the call by the United States for 'complete, verifiable and irreversible dismantlement,' or 'CVID.' It is desirable to accomplish dismantlement quickly, but many aspects of the radioactive waste management cannot be achieved without careful assessment, planning and preparation, sustained commitment, and long completion times

  11. Radioactive rare gases emission at underground nuclear explosions

    International Nuclear Information System (INIS)

    Dubasov, Yu.V.

    2016-01-01

    The examples of radioactive rare gases emission at underground nuclear explosions conducted in the USSR on the Novaya Zemlya and Semipalatinsk test sites are considered. It is pointed out that in the case of evasive explosion in vertical wells without apparent radioactive gases emission the samples of subsurface gas must contain the traces of radioactive rare gases. Under the inspection of evasive explosion in horizontal workings of rock massif, one should guided by the analysis of atmospheric air samples in the inspected area [ru

  12. Education in radiation, radioactivity, and nuclear science

    Energy Technology Data Exchange (ETDEWEB)

    Faubert, I.; Wohrizek, J.; Donev, J., E-mail: Isaac.faubert@gmail.com [Univ. of Calgary, Alberta (Canada)

    2013-07-01

    Nuclear science and nuclear energy are not widely understood topics. A lack of understanding for a potentially dangerous technology can be the cause for avoidance and even fear. In order to break down the barriers of a misunderstood industry, high energy learning is an initiative to change the perspective of nuclear science and technology. Through explanation of the fundamental concepts surrounding nuclear science, we reconstruct a trust within the communities and cultures across the nation. Being able to change the perspective of uninformed and misinformed people may not only benefit the nuclear industry, but the state of our global environment. (author)

  13. Education in radiation, radioactivity, and nuclear science

    International Nuclear Information System (INIS)

    Faubert, I.; Wohrizek, J.; Donev, J.

    2013-01-01

    Nuclear science and nuclear energy are not widely understood topics. A lack of understanding for a potentially dangerous technology can be the cause for avoidance and even fear. In order to break down the barriers of a misunderstood industry, high energy learning is an initiative to change the perspective of nuclear science and technology. Through explanation of the fundamental concepts surrounding nuclear science, we reconstruct a trust within the communities and cultures across the nation. Being able to change the perspective of uninformed and misinformed people may not only benefit the nuclear industry, but the state of our global environment. (author)

  14. Radioactive Aerosol Size Distribution Measured in Nuclear Workplaces

    International Nuclear Information System (INIS)

    Kravchik, T.; Oved, S.; German, U.

    2002-01-01

    Inhalation is the main route for internal exposure of workers to radioactive aerosols in the nuclear industry.Aerosol's size distribution and in particular its activity median aerodynamic diameter (AMAD)is important for determining the fractional deposition of inhaled particles in the respiratory tract and the resulting doses. Respiratory tract models have been published by the International Commission on radiological Protection (ICRP).The former model has recommended a default AMAD of 1 micron for the calculation of dose coefficients for workers in the nuclear industry [1].The recent model recommends a 5 microns default diameter for occupational exposure which is considered to be more representative of workplace aerosols [2]. Several researches on radioactive aerosol's size distribution in nuclear workplaces has supported this recommendation [3,4].This paper presents the results of radioactive aerosols size distribution measurements taken at several workplaces of the uranium production process

  15. Certified training for nuclear and radioactive source security management

    International Nuclear Information System (INIS)

    Johnson, Daniel

    2017-01-01

    Radioactive sources are used by hospitals, research facilities and industry for such purposes as diagnosing and treating illnesses, sterilising equipment and inspecting welds. Unfortunately, many States, regulatory authorities and licensees may not appreciate how people with malevolent intentions could use radioactive sources, and statistics confirm that a number of security incidents happen around the globe. The adversary could be common thieves, activists, insiders, terrorists and organised crime groups. Mitigating this risk requires well trained and competent staff who have developed the knowledge, attributes and skills necessary to successfully discharge their security responsibilities. The International Atomic Energy Agency and the World Institute for Nuclear Security are leading international training efforts. The target audience is a multi-disciplinary group of professionals with management responsibilities for security at facilities with radioactive sources. These efforts to promote training and competence amongst practitioners have been recognised at the 2014 and 2016 Nuclear Security and Nuclear Industry Summits. (author)

  16. Transport of radioactive waste from nuclear facilities

    International Nuclear Information System (INIS)

    Keese, H.

    1976-01-01

    A transport system for spent fuel elements and radioactive waste is reported on. The construction of appropriate transport containers, safety regulations, as well as future developments in transport systems and transport containers are discussed in detail. The volume of the spent fuel elements to be moved and the number of transport containers needed is gone into, too. (HR/LN) [de

  17. Radioactive waste management of the nuclear medicine services

    International Nuclear Information System (INIS)

    Barboza, Alex

    2009-01-01

    Radioisotope applications in nuclear medicine services, for diagnosis and therapy, generate radioactive wastes. The general characteristics and the amount of wastes that are generated in each facility are function of the number of patients treated, the procedures adopted, and the radioisotopes used. The management of these wastes embraces every technical and administrative activity necessary to handle the wastes, from the moment of their generation, till their final disposal, must be planned before the nuclear medicine facility is commissioned, and aims at assuring people safety and environmental protection. The regulatory framework was established in 1985, when the National Commission on Nuclear Energy issued the regulation CNEN-NE-6.05 'Radioactive waste management in radioactive facilities'. Although the objective of that regulation was to set up the rules for the operation of a radioactive waste management system, many requirements were broadly or vaguely defined making it difficult to ascertain compliance in specific facilities. The objective of the present dissertation is to describe the radioactive waste management system in a nuclear medicine facility and provide guidance on how to comply with regulatory requirements. (author)

  18. Radioactive clearance discharge of effluent from nuclear and radiation facilities

    International Nuclear Information System (INIS)

    Liu Xinhua; Xu Chunyan

    2013-01-01

    On the basis of the basic concepts of radiation safety management system exemption, exclusion and clearance, we expound that the general industrial gaseous and liquid effluent discharges are exempted or excluded, gaseous and liquid effluent discharged from nuclear and radiation facilities are clearance, and non-radioactive. The main purpose of this paper is to clarify the concepts, reach a consensus that the gaseous and liquid effluent discharged from nuclear and radiation facilities are non-radioactive and have no hazard to human health and natural environment. (authors)

  19. Operating experience in cleaning sodium-wetted components at the KNK nuclear power plant

    International Nuclear Information System (INIS)

    Stade, K.Ch.

    1978-01-01

    Since 1969, components of the KNK facility, the first sodium cooled nuclear power plant in the Federal Republic of Germany, have been cleaned both by the alcohol and the wet gas techniques. This paper outlines the experience accumulated In the application of these methods, especially in cleaning steam generators and fuel elements. Some preliminary results are indicated of the attempt to clean a cold trap from the primary circuit of the KNK facility. (author)

  20. 17th DOE nuclear air cleaning conference: proceedings. Volume 2

    International Nuclear Information System (INIS)

    First, M.W.

    1983-02-01

    Volume 2 contains papers presented at the following sessions: adsorption; noble gas treatment; personnel education and training; filtration and filter testing; measurement and instrumentation; air cleaning equipment response to accident related stress; containment venting air cleaning; and an open end session. Twenty-eight papers were indexed separately for inclusion in the Energy Data Base. Ten papers had been entered earlier

  1. 17th DOE nuclear air cleaning conference: proceedings. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    First, M.W. (ed.)

    1983-02-01

    Volume 2 contains papers presented at the following sessions: adsorption; noble gas treatment; personnel education and training; filtration and filter testing; measurement and instrumentation; air cleaning equipment response to accident related stress; containment venting air cleaning; and an open end session. Twenty-eight papers were indexed separately for inclusion in the Energy Data Base. Ten papers had been entered earlier.

  2. Radioactive Waste as an Argument against Nuclear Energy

    International Nuclear Information System (INIS)

    Kowalski, E.

    1996-01-01

    The issue of safe radioactive waste is commonly regarded as the Achilles Heel of nuclear energy production. To add strength to the 'unsolved' waste problem as an argument in favour of abandoning nuclear energy production, anti-nuclear groups systematically seek to discredit waste management projects and stand in the way of progress in this field. The paradox in this situation is that it is exactly in the field of waste management that nuclear energy production allows ecologically sound procedures to be followed. (author)

  3. Risk Prevention for Nuclear Materials and Radioactive Sources

    International Nuclear Information System (INIS)

    Badawy, I.

    2008-01-01

    The present paper investigates the parameters which may have effects on the safety of nuclear materials and other radioactive sources used in peaceful applications of atomic energy. The emergency response planning in such situations are also indicated. In synergy with nuclear safety measures, an approach is developed in this study for risk prevention. It takes into consideration the collective implementation of measures of nuclear material accounting and control, physical protection and monitoring of such strategic and dangerous materials in an integrated and coordinated real-time mode at a nuclear or radiation facility and in any time

  4. Measurement of nuclear cross sections using radioactive beams; Medicion de secciones eficaces nucleares usando haces radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Lizcano, D.; Aguilera, E.F.; Martinez Q, E. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2000-07-01

    One of the main applications of the production and use of nuclear radioactive beams is the measurement of nuclear cross sections. In this work is used a {sup 6} He nuclear radioactive beam ({beta} emitting with half life 806.7 ms) for the study of the reaction {sup 6} + {sup 209} Bi which could have several products. This investigation was realized in collaboration with the personnel of the Nuclear Structure laboratory at the University of Notre Dame (U.S.A.) and the National institute of Nuclear Research and CONACyT by Mexico. (Author)

  5. Formation of nuclear molecules in cluster radioactivity. On interpretation of the cluster radioactivity mechanism

    International Nuclear Information System (INIS)

    Volkov, V.V.; Cherepanov, E.A.

    2012-01-01

    The basis for cluster radioactivity is the property of nuclei of light isotopes of elements heavier than lead to spontaneously form clusters - nuclei of light elements - from valence nucleons, which gives rise to asymmetric nuclear molecules. The cluster formation proceeds through successive excitation-free transfer of valence nucleons to the particle and to subsequent light nuclei. Nuclear molecule formation is accompanied by a considerable amount of released energy, which allows quantum-mechanical penetration of the cluster through the exit Coulomb barrier

  6. Radioactive residues at nuclear sites in the United States of America

    International Nuclear Information System (INIS)

    Fiore, J.; Rampertaap, A.; Greeves, J.; MacKinney, J.; Raguso, M.; Selstrom, J.

    2000-01-01

    The United States of America has a large number of sites where radioactive materials have been mined, processed, produced, or used. Upon completion of activities at these sites, some will be cleaned up completely and released for unrestricted future use. However, at other sites, contamination will remain on the site following cleanup, requiring long term institutional controls. Depending on the purpose or the activity conducted at a specific site, these locations are generally under the jurisdiction of a federal agency: the United States Department of Energy, the United States Nuclear Regulatory Commission, the United States Environmental Protection Agency, or the United States Department of Defense. However, under certain conditions, the Nuclear Regulatory Commission relinquishes regulatory authority to individual states to regulate the commercial uses of radioactive materials (except for nuclear reactors), so some locations with radioactive materials are under the jurisdiction of individual states. Other sites with naturally occurring radioactive contamination may also be controlled by individual states. One or two sites under the jurisdiction of each agency are discussed where radioactive materials either existed in the past or exist today, and the source of contamination, the anticipated end state, and the process by which the responsible agency did or will conduct cleanup and site closure are described. Several issues are reviewed that must be addressed in order to design and implement remediations that will ensure long term protection for the environment and future inhabitants. The role of citizens in environmental cleanups is examined, and how institutional controls may be applied to ensure long term protection of remediations that leave some contaminants in place. (author)

  7. Sample and injection manifolds used to in-place test of nuclear air-cleaning system

    International Nuclear Information System (INIS)

    Qiu Dangui; Li Xinzhi; Hou Jianrong; Qiao Taifei; Wu Tao; Zhang Jirong; Han Lihong

    2012-01-01

    Objective: According to the regulations of nuclear safety rules and related standards, in-place test of the nuclear air-cleaning systems should be carried out before and during operation of the nuclear facilities, which ensure them to be in good condition. In some special conditions, the use of sample and injection manifolds is required to make the test tracer and ventilating duct air fully mixed, so as to get the on-spot typical sample. Methods: This paper introduces the technology and application of the sample and injection manifolds in nuclear air-cleaning system. Results: Multi point injection and multi point sampling technology as an effective experimental method, has been used in a of domestic and international nuclear facilities. Conclusion: The technology solved the problem of uniformly of on-spot injection and sampling,which plays an important role in objectively evaluating the function of nuclear air-cleaning system. (authors)

  8. Radioactive waste: the poisoned legacy of the nuclear industry; Dechets radioactifs: l'heritage empoisonne du nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Rousselet, Y. [Campagne Climat/Energie - Greenpeace (France)

    2011-02-15

    The nuclear industry produces a huge amount of radioactive waste from one end to the other of the nuclear cycle: i.e. from mining uranium to uranium enrichment through reactor operating, waste reprocessing and dismantling nuclear power plants. Nuclear power is now being 'sold' to political leaders and citizens as an effective way to deal with climate change and ensure security of energy supplies. Nonetheless, nuclear energy is not a viable solution and is thus a major obstacle to the development of clean energy for the future. In addition to safety and security issues, the nuclear industry is, above all, faced with the huge problem of how to deal with the waste it produces and for which it has no solution. This ought to put a brake on the nuclear industry, but instead, against all expectations, its development continues to gather pace. (author)

  9. Radioactive waste management perspectives in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Nurul Wahida Ahmad Khairuddin; Nik Marzukee Nik Ibrahim; Mat Bakar Mahusin; Mohamad Hakiman Mohamad Yusoff; Muhammad Zahid Azrmi

    2009-01-01

    Waste Technology Development Centre (WasTeC) has been mandated to carry out radioactive waste management activities since 1984. The main objective of WasTeC is to deal with radioactive waste in a manner that protects health and the environment now and in the future, without imposing undue burdens on the future generations. This centre provides services for waste generators within Nuclear Malaysia and also for external waste generators. Services provided include transportation of radioactive waste, decontamination, treatment and storage. This paper will discuss on procedure for applying for services, responsibility of waste generator, responsibility of waste operator, need to comply with waste acceptance criteria and regulations related to management of radioactive waste. (Author)

  10. The new context for transport of radioactive and nuclear material

    International Nuclear Information System (INIS)

    Anne, C.; Galtier, J.

    2002-01-01

    The transportation of radioactive and nuclear materials involves all modes of transportation with a predominance for road and for air. It is but a minute fraction dangerous good transportation. Around 10 millions of radioactive packages are shipped annually all over the world of which ninety percent total corresponds to shipments of radioisotopes. In spite of the small volume transported, experience, evolution of transport means and technologies, the trend to constantly improve security and safety and public acceptance have modified the transport environment. During the last few years, new evolutions have applied to the transport of radioactive and nuclear materials in various fields and especially: - Safety - Security - Logistics means - Public acceptance - Quality Assurance. We propose to examine the evolution of these different fields and their impact on transportation methods and means. (authors)

  11. Proceedings of the fifteenth DOE nuclear air cleaning conference

    Energy Technology Data Exchange (ETDEWEB)

    First, M.W. (ed.)

    1979-02-01

    Papers presented are grouped under the following topics: noble gas separation, damage control, aerosols, test methods, new air cleaning technology from Europe, open-end, and filtration. A separate abstract was prepared for each paper.

  12. Chemical cleaning the service water system at a nuclear power plant

    International Nuclear Information System (INIS)

    Brice, T.O.; Glover, W.A.

    1994-01-01

    Chemical cleaning a large cooling water system in a nuclear power plant presented many unique problems. The selection, qualification, and performance of the cleaning process were done using a phased approach. The piping was inspected to determine the extent of the problem. Deposit samples were removed from the service water system pipe and tested in the laboratory to determine the most effective cleaning solvent for deposit removal. An engineering study was performed to define the design parameters required to implement the system-wide chemical cleaning

  13. The new context for transport of radioactive nuclear material

    International Nuclear Information System (INIS)

    Anne, Catherine; Galtier, Jerome

    2001-01-01

    The transportation of radioactive and nuclear materials, involves all modes of transportation (road, air, sea, rail) with predominance for road and for air (air for radioisotopes). In this paper we examine the impact of new evolutions in the fields of safety, security, logistics means, public acceptance and quality assurance

  14. Management of radioactive wastes from nuclear power plants

    International Nuclear Information System (INIS)

    1985-01-01

    This Code of Practice defines the minimum requirements for the design and operation of structures, systems and components important for the management of radioactive wastes from thermal neutron nuclear power plants. The topics covered include design and operation of gaseous, liquid and solid waste systems, waste transport, storage and disposal, decommissioning wastes and wastes from unplanned events

  15. Radioactive wastes database at Brazilian Nuclear Technology Development Center - CDTN

    International Nuclear Information System (INIS)

    Reis, L.C.A.; Silva, F.

    1994-01-01

    Development and implementation of a radioactive waste management data base are being carried out at Centro de Desenvolvimento da Tecnologia Nuclear - CDTN. The objectives are to treat and retrieve information about wastes generated and received at the Centre in order to facilitate the waste management. (author)

  16. Nuclear chemistry fifty years after the discovery of artificial radioactivity

    International Nuclear Information System (INIS)

    Lefort, M.

    1984-01-01

    In January 1934, the observation and the chemical identification of radiophosphorus as a reaction product in the bombardment of Aluminium by alpha particles have been the first step of a new scientific branch: Nuclear Chemistry. We describe here how this discovery in itself contains the frame of all the development which has followed. It consisted in four stages, each of them being a crucial starting point. The first one is the possibility for a total balance of the nuclear reaction in the exit channels, so that reaction mechanisms can be studied. The second, the most important perhaps, is the opening of nuclear synthesis. Nuclear chemists can now interfere into nuclear matter and instead of staying as observers of the radioactive decays of natural isotopes, they were able to build up a numerous chart of various nuclear species, going step by step further and further away from the nuclear stability conditions. The third aspect of the discovery was the appearance of a new mode of radioactive decay with the production of the first particle an antimater. 50 years later, the instability due to a much larger excess of protons is known to induce the proton emission radioactivity for new species like 109 I or 115 Cs, in the vicinity of proton unstability. Finally, the last point, so fertile for the future, was the observation of a neutron in the exit channel, so that neutron fluxes could result from alpha induced nuclear reactions and became such a strong tool for the production of transuranium elements and for nuclear fission. In the present survey, the wide interest of the second point, i.e. the nuclear synthesis, is emphasized, as well as the huge change in the technical methods

  17. Radioactivity

    International Nuclear Information System (INIS)

    Chelet, Y.

    2006-01-01

    The beginning of this book explains the why and how of the radioactivity, with a presentation of the different modes of disintegration. Are tackled the reports between radioactivity and time before explaining how the mass-energy equivalence appears during disintegrations. Two chapters treat natural radioisotopes and artificial ones. This book makes an important part to the use of radioisotopes in medicine (scintigraphy, radiotherapy), in archaeology and earth sciences (dating) before giving an inventory of radioactive products that form in the nuclear power plants. (N.C.)

  18. Design of Radioactive Waste Management Systems at Nuclear Power Plants

    International Nuclear Information System (INIS)

    1986-01-01

    This Safety Guide is addressed to the administrative and technical authorities and specialists dealing with the design, construction and operation of nuclear power plants, and in particular waste management facilities at nuclear power plants. This Guide has been prepared as part of the IAEA Waste Handling, Treatment and Storage programme. It is a follow-up document to the Code of Practice on Management of Radioactive Wastes from Nuclear Power Plants published in 1985 in the IAEA Safety Standards, Safety Series No. 69, in which basic principles for management of radioactive wastes at nuclear power plants are set out. The IAEA has established wide ranging programmes to provide Member States with guidance on different aspects of safety and technology related to thermal neutron power reactors and associated nuclear fuel cycle operations, including those for management of radioactive wastes. There are many IAEA publications related to various technical and safety aspects of different nuclear energy applications. All these publications are issued by the Agency for the use of Member States in connection with their own nuclear technological safety requirements. They are based on national experience contributed by experts from different countries and relate to common features in approaches to the problems discussed. However, the final decision and legal responsibility in any regulatory procedure always rest with the Member State. This particular Guide aims to provide general and detailed principles for the design of waste management facilities at nuclear power plants. It emphasizes what and how specific safety requirements for the management of radioactive wastes from nuclear power plants can be met in the design and construction stage. The safety requirements for operation of such facilities will be considered in the Agency's next Safety Series publication, Safety Guide 50-SG-011, Operational Management for Radioactive Effluents and Wastes Arising in Nuclear Power Plants

  19. Proceedings of the 19th DOE/NRC nuclear air cleaning conference

    International Nuclear Information System (INIS)

    First, M.W.

    1987-05-01

    This document contains the papers and the associated discussions of the 19 DOE/NRC Nuclear Air Cleaning Conference. Sessions were devoted to (1) fire, explosion and accident analysis, (2) adsorption and iodine retention, (3) filters and filter testing, (4) standards and regulation, (5) treatment of radon, krypton, tritium and carbon-14, (6) ventilation and air cleaning in reactor operations, (7) dissolver off-gas cleaning, (8) adsorber fires, (9) nuclear grade carbon testing, (10) sampling and monitoring, and (11) field test experience. Individual papers were processed separately for the data base

  20. AEC Regulatory view of the reliability of air cleaning systems in nuclear facilities

    International Nuclear Information System (INIS)

    Bellamy, R.R.; Zavadoski, R.W.

    1975-01-01

    Air cleaning systems in nuclear facilities can be divided into three categories: ventilation exhaust systems, containment atmosphere cleanup systems, and process offgas systems. These systems have been the subject of numerous reports, regulatory guides, discussions, and meetings. Some of the analyses have been critical of the operation and design of these air cleaning systems--in particular, the engineered safety features containment atmosphere cleanup systems. Although for the most part the criticism is applicable, and recognizing that there are a number of unresolved issues pertaining to gaseous waste management systems, there are data to show that air cleaning systems in use in nuclear facilities are performing their intended function. (U.S.)

  1. Nuclear criticality safety evaluation of large cylinder cleaning operations in X-705, Portsmouth Gaseous diffusion Plant

    International Nuclear Information System (INIS)

    Sheaffer, M.K.; Keeton, S.C.; Lutz, H.F.

    1995-06-01

    This report evaluates nuclear criticality safety for large cylinder cleaning operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current cleaning procedures and required hardware/equipment is presented, and documentation for large cylinder cleaning operations is identified and described. Control parameters, design features, administrative controls, and safety systems relevant to nuclear criticality are discussed individually, followed by an overall assessment based on the Double Contingency Principle. Recommendations for enhanced safety are suggested, and issues for increased efficiency are presented

  2. Aerosol challenges to air cleaning systems during severe accidents in nuclear plants

    International Nuclear Information System (INIS)

    Gieseke, J.A.

    1985-01-01

    A variety of air cleaning systems may be operating in nuclear power plants and under severe accident conditions, these systems may be treating airborne concentrations of aerosols which are very high. Predictions of airborne aerosol concentrations in nuclear power plant containments under severe accident conditions are reviewed to provide a basis for evaluating the potential effects on the air cleaning systems. The air cleaning systems include filters, absorber beds, sprays, water pools, ice beds, and condensers. Not all of these were intended to operate as air cleaners but will in fact be good aerosol collectors. Knowledge of expected airborne concentrations will allow better evaluation of system performances

  3. Nuclear waste: our radioactive hot potato

    International Nuclear Information System (INIS)

    Conselman, F.B.

    1984-01-01

    Nuclear industry inevitably produces nuclear waste, whose prudent, prompt and economic disposal is important to the national welfare. Technological problems of containment and isolation have apparently been solved. Underground or geologic disposal sites have the potential form permanent isolation, with salt, basalt, granite, shale, and tuff currently receiving principal attention as repository host rocks. Bedded salt deposits may offer the principal mechanical advantages, but in the northwestern United States the abundance of basalt at existing test sites has made it the subject of experimentation. However, psychological, political, and allegedly environmental obstructionism have stalled the process and virtually immobilized current construction. A program is suggested with the purpose of satisfying technical requirements for public protection while allaying the exaggerated fears of anti-nuclear factions

  4. The risk of storing radioactive wastes from nuclear power plants

    International Nuclear Information System (INIS)

    Gruemm, H.

    1976-09-01

    Serious bottle-necks exist in the nuclear fuel cycle and will continue for the next decade. A total of 800 nuclear reactors are now in operation. 153 nuclear power plants represent an installed capacity of 70 GVe. Until 1985 five hundred nuclear power plants will be in operation from which up to this date 53.000 t uranium will have been discharged. Part of this will have to be reprocessed. Associated with the above mentioned amount are 500 t plutonium and 1.500 t highly radioactive wastes. Two risks for the population have to be considered: firstly, the effect of small amounts of radioactive substances released during normal operation of nuclear power plants (the annual dose is about 1 mrem per person). Secondly, the possibility of the release of great amounts of radioactivity during heavy accidents (the probability for which is extremely small). A series of feasible possibilities for conditioning are shown. Firstly, the wastes are packed in substances which are insoluble in water. Secondly, for low and medium wastes these can be mixed with concrete or bitumen and filled into stable containers. Thirdly, the wastes could also be solidified. Fourthly, the wastes could be enclosed in small glass spheres which are embedded in a metal matrix. (H.G.)

  5. Management of commercial radioactive nuclear wastes. A status report

    International Nuclear Information System (INIS)

    1976-01-01

    The President's Energy Resources Council (ERC) has the responsibility for coordination of Administration policies and programs relating to energy. Because of the important role envisioned for nuclear power in the next decade and beyond, the ERC established a nuclear sub-committee to coordinate Federal nuclear policy and programs to assure that issues which arise are treated via an integrated Government effort. This paper was prepared by those Federal agencies which are ERC members and have the technical, economic, and environmental expertise to provide a brief review of the nature of radioactive wastes and our ability to dispose of them safely

  6. Evaluation of bitumens for nuclear facilities radioactive waste immobilization

    International Nuclear Information System (INIS)

    Guzella, Marcia F.R.; Silva, Tania V. da; Loiola, Roberto; Monte, Lauro J.B.

    2000-01-01

    The activities developed at the Nuclear Technology Development Centre, Centro de Desenvolvimento da Tecnologia Nuclear - CDTN/CNEN, include the research and development work of the radioactive wastes immobilization in different kind of bitumen. The present work describes the bituminization of simulated low level wastes of evaporator concentrates.Two types of bitumen are used for incorporation of the simulated wastes generated by nuclear power plants. Studies on rheological properties, leaching data, differential thermoanalysis and water content of the waste-products have been carried out. (author)

  7. Treatment and storage of radioactive gases from nuclear facilities

    International Nuclear Information System (INIS)

    Johannsen, K.H.; Schwarzbach, R.

    1980-01-01

    Treatment of exhaust air from nuclear facilities aimed at retaining or separating the radionuclides of iodine, xenon, and krypton as well as of tritium and carbon-14 and their storage are of special interest in connection with increasing utilization of nuclear power in order to reduce releases of radioactive materials to the atmosphere. The state of the art and applicability of potential processes of separating volatile fission and activation products from nuclear power stations and reprocessing plants are reviewed. Possibilities of ultimate storage are presented. An evaluation of the current stage of development shows that processes for effective separation of radioactive gases are available. Recent works are focused on economy and safety optimization. Long-term storage, in particular of extremely long-lived radionuclides, needs further investigation. (author)

  8. The French nuclear safety authority's experience with radioactive transport inspection

    International Nuclear Information System (INIS)

    Jacob, E.; Aguilar, J.

    2004-01-01

    About 300,000 radioactive material packages are transported annually in France. Most consist of radioisotopes for medical, pharmaceutical or industrial use. On the other hand, the nuclear industry deals with the transport of fuel cycle materials (uranium, fuel assemblies, etc.) and waste from power plants, reprocessing plants and research centers. France is also a transit country for shipments such as spent fuel packages from Switzerland or Germany, which are bound for Sellafield in Great Britain. The French nuclear safety authority (DGSNR: Directorate General for Nuclear Safety and Radioprotection) has been responsible since 1997 for the safety of radioactive material transport. This paper presents DGNSR's experience with transport inspection: a feedback of key points based on 300 inspections achieved during the past five years is given

  9. First report of the Civil Nuclear Power Working Group to the Technical Comittee of the National Society for Clean Air -Summer 1988

    International Nuclear Information System (INIS)

    1988-01-01

    The accident at the Chernobyl reactor in April 1986 had serious consequences, not just for Russia but for many countries in Europe. Following the accident, the National Society for Clean Air formed a Working Group to look at the Society's policy on civil nuclear power. Its finding and recommendations are presented in this first report. The subject was considered under several headings - radioactivity (public education in measurement and dose evaluation), emergency procedures in the event of incidents overseas, radiation monitoring, a national monitoring and information service, plant safety, nuclear materials handling and radioactive waste disposal, energy policy and conservation. Four main recommendations are made on public education, risk assessment and radiation monitoring, radioactive waste disposal and energy policy. (U.K.)

  10. Radioactive decays at limits of nuclear stability

    DEFF Research Database (Denmark)

    Pfützner, M.; Karny, M.; Grigorenko, L. V.

    2012-01-01

    , and their relative probabilities. When approaching limits of nuclear stability, new decay modes set in. First, beta decays are accompanied by emission of nucleons from highly excited states of daughter nuclei. Second, when the nucleon separation energy becomes negative, nucleons start being emitted from the ground...

  11. ISOL based radioactive nuclear beam facilities

    International Nuclear Information System (INIS)

    Nomura, T.

    1991-07-01

    High-intensity and high-quality unstable nuclear beams can be realized by coupling an isotope separator on-line and a proper post accelerator in various primary beams. Some technical features and problems in the production of such beams are discussed. A brief description is given on 'Exotic Nuclei Arena' in Japanese Hadron Project. (author)

  12. Evaluation of early phase nuclear accident clean-up procedures for Nordic residential areas

    International Nuclear Information System (INIS)

    Andersson, K.G.

    1996-12-01

    The work reported was carried out as a part of the EKO-5 project under the framework of the Nordic co-operative NKS programme. The project is aimed at giving guidelines relating to Nordic conditions for the reduction of external doses in the early phase of a major accidental airborne nuclear contamination (essentially with 137 Cs) situation in urban areas. The material in this report describes the expected effects, in terms of immediate dose rate reduction and of reduction of the integrated doses over 70 years, of implementation of the methods which were considered to be feasible for early phase treatment of contaminated urban surfaces. Also given are estimates of the integrated doses if no action were taken. The given estimates were based on the experience obtained through large amounts of in situ measurements on different types of surface, mainly since the Chernobyl accident in 1986. The computer model URGENT, was used to apply the information on the migration of the radioactive material with time, together with the results of Monte Carlo photon transport calculations, for the time-integrated dose estimates. 66 data sheets describe the beneficial effects, costs and disadvantages of application of a feasible method for cleaning in the early phase of a specific type of surface in one of five different urban or suburban environments. These data form the foundation for the recommendations on guidelines, which are the ultimate goal of the EKO-5 project. References are given to recommended supplementary reading. (EG)

  13. Radioactive release during nuclear accidents in Chernobyl and Fukushima

    Science.gov (United States)

    Nur Ain Sulaiman, Siti; Mohamed, Faizal; Rahim, Ahmad Nabil Ab

    2018-01-01

    Nuclear accidents that occurred in Chernobyl and Fukushima have initiated many research interests to understand the cause and mechanism of radioactive release within reactor compound and to the environment. Common types of radionuclide release are the fission products from the irradiated fuel rod itself. In case of nuclear accident, the focus of monitoring will be mostly on the release of noble gases, I-131 and Cs-137. As these are the only accidents have been rated within International Nuclear Events Scale (INES) Level 7, the radioactive release to the environment was one of the critical insights to be monitored. It was estimated that the release of radioactive material to the atmosphere due to Fukushima accident was approximately 10% of the Chernobyl accident. By referring to the previous reports using computational code systems to model the release rate, the release activity of I-131 and Cs-137 in Chernobyl was significantly higher compare to Fukushima. The simulation code also showed that Chernobyl had higher release rate of both radionuclides on the day of accident. Other factors affecting the radioactive release for Fukushima and Chernobyl accidents such as the current reactor technology and safety measures are also compared for discussion.

  14. Measures for prevention illicit trafficking of nuclear and radioactive materials

    International Nuclear Information System (INIS)

    Strezov, A.

    2002-01-01

    Full text: In the early 1990ies the number of illicit trafficking cases with nuclear material and radioactive sources began to appear in the press more often than before. This fact became of great concern among international organizations and different states that the nuclear material subjected to trafficking might become in possession of rogue states and be implicated in weapons production or that stolen radioactive sources may cause health and safety effects to the population or to the environment. The creation and proposition of a model scheme procedure for the developing countries is important for starting the initial process of preventing and combating the illicit traffic of nuclear materials. Particular efforts have been directed for the protection of fissile materials. The reported incidents for diversion of nuclear materials have raised the problem of potential nuclear terrorism and also for countries of proliferation to take a short cut to the bomb. There is a need of rapid implementation of comprehensive, mutually reinforcing strategy to control the existing stockpiles of fissile material and to lower the future production and use of such materials. The illicit traffic of nuclear materials is a new threat, which requires new efforts, new approaches and coordination of services and institutions and even new legislation. The propositions of a model-procedure will allow better and quicker upgrade of developing countries capabilities for combating illicit nuclear trafficking. (author)

  15. Cost of the radioactive residues of nuclear power

    International Nuclear Information System (INIS)

    1986-06-01

    The calculation of cost for the management and final storage of spent nuclear fuel and radioactive waste is presented. The continuing Research and Development activities are judged to render simplified designs. The existing and planned systems and and plans are as follows: - transport system for radioactive residues - central intermediate storage of spent fuel, CLAB - processing of spent fuel - final storing of long-lived waste - final storing of reactor waste and decommissioning waste, SFR. The total future cost of the Swedish waste management is calculated to be 39 billion SEK from 1987 and 60 years onwards. 5.3 billion SEK have been spent up to the year 1986. (G.B.)

  16. Management of radioactive wastes from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1976-01-01

    The increased emphasis in many countries on the development and utilization of nuclear power is leading to an expansion of all sectors of the nuclear fuel cycle, giving rise to important policy issues and radioactive-waste management requirements. Consequently, the IAEA and the Nuclear Energy Agency of OECD felt that it would be timely to review latest technology for the management of the radioactive wastes arising from nuclear fuel cycle facilities, to identify where important advances have been made, and to indicate those areas where further technological development is needed. Beginning in 1959, the IAEA, either by itself or jointly with OECD/NEA has held seven international symposia on the management of radioactive wastes. The last symposium, on the management of radioactive wastes from fuel reprocessing, was held jointly by the IAEA and OECD/NEA in Paris in November 1972. An objective of the 1976 symposium was to update the information presented at the previous symposia with the latest technological developments and thinking regarding the management and disposal of all categories of radioactive wastes. Consequently, although the scope of the symposium was rather broad, attention was focussed on operational experience and progress in unresolved areas of radioactive waste management. The programme dealt primarily with the solidification of liquid radioactive wastes and disposal of the products, especially the high-level fission products and actinide-containing waste from fuel reprocessing. Other topics covered policy and planning, treatment of hulls and solvent, management of plutonium-contaminated waste, and removal of gaseous radionuclides. The major topic of interest was the current state of the technology for the reduction and incorporation of the high-level radioactive liquid from fuel reprocessing into solid forms, such as calcines, glasses or ceramics, for safe interim storage and eventual disposal. The approaches to vitrification ranged from two stage

  17. Radioactive survey of the environment of the nuclear sites of French Nuclear Board: an overview

    International Nuclear Information System (INIS)

    Robeau, D.; Montjoie, M.; Sauve, A.M.; Laporte, J.; Rahaplen, A.; Alphonse, L.; Huc, C.; Bensimon, C.; Cissoko, G.

    1992-01-01

    C.E.A. has set up a network of radioactive survey around its nuclear sites. This network involves terrestrial, atmospheric and marine results of radioactive measurements. This survey is structured in four levels. The level 0 homogenizes stations of measurements, level 1 centralizes real-time measurements of gross α and β measurements of atmospheric radioactivity, level 2 and 3 centralizes postponed α-β spectrometric measurements of radioactivity on water, deposition, grass, vegetables. People can have a squint at these results of measurements using popular MINITEL telephonic network. (author)

  18. Nuclear physics with radioactive ion beams

    Energy Technology Data Exchange (ETDEWEB)

    Kozub, Raymond L. [Tennessee Technological Univ., Cookeville, TN (United States)

    2015-07-23

    This is a final report on DOE Grant No. DE FG02 96ER40955, which was active at Tennessee Technological University (TTU) from 1 March 1996 to 29 May 2015. Generally, this report will provide an overall summary of the more detailed activities presented in the progress reports, numbered DOE/ER/40955-1 through DOE/ER/40955-18, which were submitted annually to the DOE Office of Nuclear Physics.

  19. Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jooho, W.; Baldwin, G. T.

    2005-04-01

    One critical aspect of any denuclearization of the Democratic People’s Republic of Korea (DPRK) involves dismantlement of its nuclear facilities and management of their associated radioactive wastes. The decommissioning problem for its two principal operational plutonium facilities at Yongbyun, the 5MWe nuclear reactor and the Radiochemical Laboratory reprocessing facility, alone present a formidable challenge. Dismantling those facilities will create radioactive waste in addition to existing inventories of spent fuel and reprocessing wastes. Negotiations with the DPRK, such as the Six Party Talks, need to appreciate the enormous scale of the radioactive waste management problem resulting from dismantlement. The two operating plutonium facilities, along with their legacy wastes, will result in anywhere from 50 to 100 metric tons of uranium spent fuel, as much as 500,000 liters of liquid high-level waste, as well as miscellaneous high-level waste sources from the Radiochemical Laboratory. A substantial quantity of intermediate-level waste will result from disposing 600 metric tons of graphite from the reactor, an undetermined quantity of chemical decladding liquid waste from reprocessing, and hundreds of tons of contaminated concrete and metal from facility dismantlement. Various facilities for dismantlement, decontamination, waste treatment and packaging, and storage will be needed. The shipment of spent fuel and liquid high level waste out of the DPRK is also likely to be required. Nuclear facility dismantlement and radioactive waste management in the DPRK are all the more difficult because of nuclear nonproliferation constraints, including the call by the United States for “complete, verifiable and irreversible dismantlement,” or “CVID.” It is desirable to accomplish dismantlement quickly, but many aspects of the radioactive waste management cannot be achieved without careful assessment, planning and preparation, sustained commitment, and long

  20. A comparative analysis of managing radioactive waste in the Canadian nuclear and non-nuclear industries

    Energy Technology Data Exchange (ETDEWEB)

    Batters, S.; Benovich, I.; Gerchikov, M. [AMEC NSS Ltd., Toronto, ON (Canada)

    2011-07-01

    Management of radioactive waste in nuclear industries in Canada is tightly regulated. The regulated nuclear industries include nuclear power generation, uranium mining and milling, nuclear medicine, radiation research and education and industrial users of nuclear material (e.g. radiography, thickness gauges, etc). In contrast, management of Naturally Occurring Radioactive Material (NORM) waste is not regulated by the Canadian Nuclear Safety Commission (CNSC), with the exception of transport above specified concentrations. Although these are radioactive materials that have always been present in various concentrations in the environment and in the tissues of every living animal, including humans, the hazards of similar quantities of NORM radionuclides are identical to those of the same or other radionuclides from regulated industries. The concentration of NORM in most natural substances is so low that the associated risk is generally regarded as negligible, however higher concentrations may arise as the result of industrial operations such as: oil and gas production, mineral extraction and processing (e.g. phosphate fertilizer production), metal recycling, thermal electric power generation, water treatment facilities. Health Canada has published the Canadian Guidelines for the Management of Naturally Occurring Radioactive Materials (NORM). This paper presents a comparative analysis of the requirements for management of radioactive waste in the regulated nuclear industries and of the guidelines for management of NORM waste. (author)

  1. A comparative analysis of managing radioactive waste in the Canadian nuclear and non-nuclear industries

    International Nuclear Information System (INIS)

    Batters, S.; Benovich, I.; Gerchikov, M.

    2011-01-01

    Management of radioactive waste in nuclear industries in Canada is tightly regulated. The regulated nuclear industries include nuclear power generation, uranium mining and milling, nuclear medicine, radiation research and education and industrial users of nuclear material (e.g. radiography, thickness gauges, etc). In contrast, management of Naturally Occurring Radioactive Material (NORM) waste is not regulated by the Canadian Nuclear Safety Commission (CNSC), with the exception of transport above specified concentrations. Although these are radioactive materials that have always been present in various concentrations in the environment and in the tissues of every living animal, including humans, the hazards of similar quantities of NORM radionuclides are identical to those of the same or other radionuclides from regulated industries. The concentration of NORM in most natural substances is so low that the associated risk is generally regarded as negligible, however higher concentrations may arise as the result of industrial operations such as: oil and gas production, mineral extraction and processing (e.g. phosphate fertilizer production), metal recycling, thermal electric power generation, water treatment facilities. Health Canada has published the Canadian Guidelines for the Management of Naturally Occurring Radioactive Materials (NORM). This paper presents a comparative analysis of the requirements for management of radioactive waste in the regulated nuclear industries and of the guidelines for management of NORM waste. (author)

  2. Factor of radioactive waste on nuclear power program

    International Nuclear Information System (INIS)

    Syed Abdul Malik Syed Zain

    2009-01-01

    Global warming phenomena and rising oil prices have brought the excitement of open space use of nuclear power. Arguments in favor of this technology range in terms of more environmentally friendly, energy diversification and cost efficiency has prompted the government to widen the choice of nuclear power be considered as a serious alternative. Despite the attractive factors to the use of these powers, there are also factors that stem from the continued development of nuclear power. These include the factor of safety, security, security of fuel supply, and public attention is often associated with radioactive waste management. This article attempts to debate specific to radioactive waste management factors that impact on public acceptance of a country's nuclear power program, especially in Malaysia. Starting from the absence of radioactive waste management policy to model uncertainty of the landfill and complications in selecting a repository site shows the basic infrastructure is still lacking. In addition, previous experience handling thorium waste has not reached a final settlement after several years of implementation. It reinforced the perception about the level of public confidence in the competence and attitude of local workers who are not very encouraging to pursue this advanced.

  3. Nuclear imperatives and public trust: Dealing with radioactive waste

    International Nuclear Information System (INIS)

    Carter, L.J.

    1987-01-01

    What should be done with the radioactive wastes that are accumulating from nuclear power plants throughout the world? Should spent nuclear fuel be reprocessed despite complications surrounding the containment of radioactivity despite complications surrounding the containment of radioactivity and the safeguarding of explosive plutonium from terrorists? Or is there another solution to this pressing problem? The author advocates treating spent nuclear fuel as waste -- rather than as recyclable material -- and burying it in deep geologic repositories. Moreover, he contends that because of its size, geologic diversity, and technical sophistication, the United States should be able to establish a system of nuclear waste isolation that is technically and politically robust enough to be a model for the rest of the world. The key to a successful repository siting effort is to select a relatively small number of carefully screened deep geologic repositories for intensive investigation, the author maintains. Potential risk can be further minimized by harnessing technology to develop engineered barriers that complement natural geologic barriers. Emphasizing that geology and technology are not the only factors that stand in the way of success, the author calls for a carefully mapped strategy. Policies should incorporate means to avoid environmental conflict, the locality eventually chosen should receive meaningful benefits, and the door should be kept open for eventual retrieval of spent fuel if the reprocessing of plutonium ever becomes safe enough to make economic and political sense

  4. Proceedings of the fifteenth DOE nuclear air cleaning conference

    Energy Technology Data Exchange (ETDEWEB)

    First, M.W. (ed.)

    1979-02-01

    Papers presented are grouped under the following topics: air cleaning; waste volume reduction and preparation for storage; tritium, carbon-14, ozone; containment of accidental releases; adsorbents and absorbents; and off-gas treatment. A separate abstract was prepared for each paper.

  5. Global risk of radioactive fallout after major nuclear reactor accidents

    International Nuclear Information System (INIS)

    Lelieveld, J.; Kunkel, D.; Lawrence, M.G.

    2012-01-01

    Major reactor accidents of nuclear power plants are rare, yet the consequences are catastrophic. But what is meant by ''rare''? And what can be learned from the Chernobyl and Fukushima incidents? Here we assess the cumulative, global risk of exposure to radioactivity due to atmospheric dispersion of gases and particles following severe nuclear accidents (the most severe ones on the International Nuclear Event Scale, INES 7), using particulate "1"3"7Cs and gaseous "1"3"1I as proxies for the fallout. Our results indicate that previously the occurrence of INES 7 major accidents and the risks of radioactive contamination have been underestimated. Using a global model of the atmosphere we compute that on average, in the event of a major reactor accident of any nuclear power plant worldwide, more than 90% of emitted "1"3"7Cs would be transported beyond 50 km and about 50% beyond 1000 km distance before being deposited. This corroborates that such accidents have large-scale and trans-boundary impacts. Although the emission strengths and atmospheric removal processes of "1"3"7Cs and "1"3"1I are quite different, the radioactive contamination patterns over land and the human exposure due to deposition are computed to be similar. High human exposure risks occur around reactors in densely populated regions, notably in West Europe and South Asia, where a major reactor accident can subject around 30 million people to radioactive contamination. The recent decision by Germany to phase out its nuclear reactors will reduce the national risk, though a large risk will still remain from the reactors in neighbouring countries.

  6. Application of clearance principles to radioactive waste from the decommissioning of nuclear reactors

    International Nuclear Information System (INIS)

    Lin Xiaoling; Feng Dingsheng; Dong Yonghe

    2010-01-01

    The definition of clearance is introduced. The principles and dose criterion of clearance are also clarified. The main radionuclides in radioactivity waste and the radioactivity waste which can be cleared are investigated. The techniques for the measurement of radioactivity waste from the decommissioning of nuclear reactors are summarized. This paper provides the scientific criterion and methods for the management of radioactive waste, and lays the foundation for the treatment of radioactive waste from the decommissioning of nuclear reactor. (authors)

  7. Nuclear astrophysics at the Holifield Radioactive Ion Beam Facility

    International Nuclear Information System (INIS)

    Smith, M.S.

    1994-01-01

    The potential for understanding spectacular stellar explosions such as novae, supernovae, and X-ray bursts will be greatly enhanced by the availability of the low-energy, high-intensity, accelerated beams of proton-rich radioactive nuclei currently being developed at the Holifield Radioactive Ion Beam Facility (HRIBF) at Oak Ridge National Laboratory. These beams will be utilized in absolute cross section measurements of crucial (p, γ) capture reactions in efforts to resolve the substantial qualitative uncertainties in current models of explosive stellar hydrogen burning outbursts. Details of the nuclear astrophysics research program with the unique HRIBF radioactive beams and a dedicated experimental endstation--centered on the Daresbury Recoil Separator--will be presented

  8. Advanced nuclear fuel cycles and radioactive waste management

    International Nuclear Information System (INIS)

    2006-01-01

    This study analyses a range of advanced nuclear fuel cycle options from the perspective of their effect on radioactive waste management policies. It presents various fuel cycle options which illustrate differences between alternative technologies, but does not purport to cover all foreseeable future fuel cycles. The analysis extends the work carried out in previous studies, assesses the fuel cycles as a whole, including all radioactive waste generated at each step of the cycles, and covers high-level waste repository performance for the different fuel cycles considered. The estimates of quantities and types of waste arising from advanced fuel cycles are based on best available data and experts' judgement. The effects of various advanced fuel cycles on the management of radioactive waste are assessed relative to current technologies and options, using tools such as repository performance analysis and cost studies. (author)

  9. Clinical aspects of the health disturbances in Chernobyl Nuclear Power Plant accident clean-up workers (liquidators) from Latvia.

    Science.gov (United States)

    Eglite, M E; Zvagule, T J; Rainsford, K D; Reste, J D; Curbakova, E V; Kurjane, N N

    2009-06-01

    The health status of some 6,000 workers from Latvia who went to clean-up the Chernobyl Nuclear Power Plant (CNPP) site following the explosion on 26 April 1986 has been analyzed. The data on these workers have been recorded in the Latvian State Register of Occupational disease patients and people exposed to ionizing radiation due to Chernobyl NPP accident (Latvian State Register) that was established in 1994. From these data, estimates have been made of external ionizing radiation to which these workers were exposed together with observations on the impact of exposure to heavy metals (especially lead and zinc) and radioactive isotopes released during the reactor 'meltdown'. These factors along with psycho-emotional and social-economic stresses account for a marked excess of mortality and morbidity in the group of CNPP accident clean-up workers compared with that of the non-exposed normal Latvian population adjusted for age and sex. The number of diseases or conditions in the CNPP accident clean-up workers has progressively risen from an average of 1.3 in 1986 to 10.9 in 2007. This exceeds for the Latvian population when adjusted for age and sex. The most serious conditions affect the nervous, digestive, respiratory, cardiovascular, endocrine (especially thyroid) and immunological systems. While the morbidity associated with diseases of the respiratory and digestive systems has decreased in recent years that in the other systems is increasing. In recent years, there has been an increased occurrence of cancers affecting the thyroid, prostate and stomach. Clinical and laboratory investigations suggest that surviving CNPP accident clean-up workers exhibit signs of immuno-inflammatory reactions causing premature aging with evidence of autoimmune diseases and immunological deficiencies or abnormalities. It is suggested that the CNPP accident clean-up workers may have a specific syndrome, the 'Chernobyl post-radiation neurosomatic polypathy', due to sustained oxidant

  10. Rutherford, Radioactivity and the Origins of Nuclear Physics

    International Nuclear Information System (INIS)

    Hughes, J

    2012-01-01

    When Ernest Rutherford became Professor of Physics at Manchester University in 1907, he brought with him the research field in which he had played a leading role over the previous few years: radioactivity. Rutherford turned the Manchester physics lab over to studies of radioactivity and radiation, and through his own work and that of his many collaborators and students, established Manchester as a major international centre in atomic physics. It was out of this powerhouse that the nuclear theory of the atom emerged in 1911. In 1917, Rutherford 'disintegrated' the nitrogen nucleus using α-particles, opening up the possibility of nuclear structure. At Cambridge's Cavendish Laboratory from 1919, Rutherford and his co-workers began to explore the constitution of the nucleus. With Chadwick, Aston and others, Rutherford turned his research school to the emergent field of nuclear physics – a field he dominated (though not without controversy) until his death in 1937. Exploring the intellectual, material and institutional cultures of early twentieth century physics, this paper will outline the background to Rutherford's career and work, the experimental and theoretical origins of nuclear theory of the atom and the early development of nuclear physics. (rutherford centennial conference on nuclear physics university of manchester 8-12 august 2011)

  11. Illicit trafficking of nuclear material and other radioactive sources

    International Nuclear Information System (INIS)

    Yilmazer, A.; Yuecel, A.; Yavuz, U.

    2001-01-01

    As it is known, for the fact that the illicit trafficking and trading of nuclear materials are being increased over the past few years because of the huge demand of third world states. Nuclear materials like uranium, plutonium, and thorium are used in nuclear explosives that have very attractive features for crime groups, terrorist groups and, the states that are willing to have this power. Crime groups that make illegal trade of nuclear material are also trying to market strategic radioactive sources like red mercury and Osmium. This kind of illegal trade threats public safety, human health, environment also it brings significant threat on world peace and world public health. For these reasons, both states and international organizations should take a role in dealing with illicit trafficking. An important precondition for preventing this kind of incidents is the existence of a strengthened national system for control of all nuclear materials and other radioactive sources. Further, Governments are responsible for law enforcement within their borders for prevention of illegal trading and trafficking of nuclear materials and radiation sources

  12. Nuclear reactor structural material forming less radioactive corrosion product

    International Nuclear Information System (INIS)

    Nakazawa, Hiroshi.

    1988-01-01

    Purpose: To provide nuclear reactor structural materials forming less radioactive corrosion products. Constitution: Ni-based alloys such as inconel alloy 718, 600 or inconel alloy 750 and 690 having excellent corrosion resistance and mechanical property even in coolants at high temperature and high pressure have generally been used as nuclear reactor structural materials. However, even such materials yield corrosion products being attacked by coolants circulating in the nuclear reactor, which produce by neutron irradiation radioactive corrosion products, that are deposited in primary circuit pipeways to constitute exposure sources. The present invention dissolves dissolves this problems by providing less activating nuclear reactor structural materials. That is, taking notice on the fact that Ni-58 contained generally by 68 % in Ni changes into Co-58 under irradiation of neutron thereby causing activation, the surface of nuclear reactor structural materials is applied with Ni plating by using Ni with a reduced content of Ni-58 isotopes. Accordingly, increase in the radiation level of the nuclear reactor structural materials can be inhibited. (K.M.)

  13. An introduction to the design, commissioning and operation of nuclear air cleaning systems for Qinshan Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Xinliang Chen; Jiangang Qu; Minqi Shi [Shanghai Nuclear Engineering Research and Design Institute (China)] [and others

    1995-02-01

    This paper introduces the design evolution, system schemes and design and construction of main nuclear air cleaning components such as HEPA filter, charcoal adsorber and concrete housing etc. for Qinshan 300MW PWR Nuclear Power Plant (QNPP), the first indigenously designed and constructed nuclear power plant in China. The field test results and in-service test results, since the air cleaning systems were put into operation 18 months ago, are presented and evaluated. These results demonstrate that the design and construction of the air cleaning systems and equipment manufacturing for QNPP are successful and the American codes and standards invoked in design, construction and testing of nuclear air cleaning systems for QNPP are applicable in China. The paper explains that the leakage rate of concrete air cleaning housings can also be assured if sealing measures are taken properly and embedded parts are designed carefully in the penetration areas of the housing and that the uniformity of the airflow distribution upstream the HEPA filters can be achieved generally no matter how inlet and outlet ducts of air cleaning unit are arranged.

  14. Index to the 1st through 16th AEC/ERDA/DOE nuclear air cleaning conferences

    International Nuclear Information System (INIS)

    Burchsted, C.A.

    1981-02-01

    The Proceedings of the sixteen conferences comprise a vertible encyclopedia on the technology of nuclear air and gas treatment and the control of airborne nuclear waste. These Proceedings cover the history of the technology; describe most of the research and developments in the field, worldwide, since the early 1950's; describe the problems that have been encountered and the solutions found to those problems; and summarize experience with equipment and systems developed for the control of airborne radioactive wastes in laboratory, radiochemical, and reactor operations, both government and commercial. The problem with this encyclopedia is that there has been no index to it; there has been no easy way for searching it to find what was available. This index fills the gap. The first conference was an informal meeting of a number of interested parties from among the then AEC contractors. Consequently, there were no proceedings for that meeting. The subsequent conferences, with their years, locations, and Proceedings numbers, are listed. This index consists of three parts: a tabulation of papers and their authors by paper number (Part I); a tabulation of papers and their paper numbers by author (Part II); and a key-word-in context (KWIC) index of papers. The paper number is a two-part designation consisting of the number of the conference (2, 3...16) followed by the page number of the paper in the corresponding Proceedings. The author index lists each author who has participated in the air cleaning conferences over the years, and the paper index lists all authors of the respective papers. The KWIC index is, in effect, a comprehensive subject cross index; each paper is listed as many times, by keyword, as there are major terms (i.e., keywords) in its title. Although this multiple listing results in a lengthy list, it provides a very deep cross-indexing of the papers

  15. Management of radioactive waste generated in nuclear medicine; Gestion de los residuos radiactivos generados en medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lorenz Perez, P.

    2015-07-01

    Nuclear medicine is a clinical specialty in which radioactive material is used in non-encapsulated form, for the diagnosis and treatment of patients. Nuclear medicine involves administering to a patient a radioactive substance, usually liquid, both diagnostic and therapeutic purposes. This process generates solid radioactive waste (syringes, vials, gloves) and liquid (mainly the patient's urine). (Author)

  16. Nuclear fuel cycle waste recycling technology deverlopment - Radioactive metal waste recycling technology development

    International Nuclear Information System (INIS)

    Oh, Won Zin; Moon, Jei Kwon; Jung, Chong Hun; Park, Sang Yoon

    1998-08-01

    With relation to recycling of the radioactive metal wastes which are generated during operation and decommissioning of nuclear facilities, the following were described in this report. 1. Analysis of the state of the art on the radioactive metal waste recycling technologies. 2. Economical assessment on the radioactive metal waste recycling. 3. Process development for radioactive metal waste recycling, A. Decontamination technologies for radioactive metal waste recycling. B. Decontamination waste treatment technologies, C. Residual radioactivity evaluation technologies. (author). 238 refs., 60 tabs., 79 figs

  17. Method of reducing radioactivity in nuclear reactors

    International Nuclear Information System (INIS)

    Koshino, Yasuo

    1987-01-01

    Purpose: To prevent increase of radiation dose ratio in primary coolant circuit pipeways of nuclear reactor and reduce operators' exposure dose upon periodical inspection, etc. Method: β-diketone such as acetylacetone is added in a predetermined amount to reactor cooling water. β-diketone dissolves to catch metal ions and iron oxides as the main ingredient of cruds. The resultant β-diketone complex of metals is slightly water soluble neutron molecule, and the total metal amount in the reactor coolant is at a concentration of less than 10 ppb and completely dissolved in water. Accordingly, deposition of clads in the coolant to pipeways can be prevented thereby enabling to prevent the increase in the radiation dose ratio in the pipeways and thus reduce the operators' exposure dose. (Takahashi, M.)

  18. Border Control of Nuclear and Other Radioactive Materials

    International Nuclear Information System (INIS)

    Medakovic, S.; Cizmek, A.; Prah, M.

    2007-01-01

    In the second half of year 2006, stationary detection systems for nuclear and other radioactive materials were installed on Border Crossing Bregana, Croatia. Yantar 2U, which is the commercial name of the system, is integrated automatic system capable of detection of nuclear and other radioactive materials prepared for fixed-site customs applications (Russian origin). Installed system contains portal monitors, camera, communication lines and communication boxes and server. Two fully functional separate systems has been installed on BC Bregana, one on truck entrance and another one on car entrance. In this article the operational experience of installed system is presented. This includes statistical analysis of recorded alarms, evaluation of procedures for operational stuff and maintenance and typical malfunction experience, as well as some of the recommendation for future use of detection systems.(author)

  19. Decontamination and disposal of radioactive wastes from nuclear facilities

    International Nuclear Information System (INIS)

    Dlouhy, Z.

    1978-01-01

    A survey and characteristics are given of the main sources of wastes from the operation of nuclear installations. The amounts are compared of liquid and gaseous wastes from PWR and BWR reactors. The main trends of radioactive waste processing in the world are described. In Czechoslovakia, two methods of waste fixation have been developed: vacuum cementation and bituminization. The demands are summed up on radioactive waste storage sites and it is stated that there are a number of suitable localities, namely abolished granite quarries with a very deep ground water level and a low-permeable overburden and exhausted quarries of kaolinitic clays, which meet all criteria and secure the safe disposal of wastes from Czechoslovak nuclear power plants up to the year 2020. (Z.M.)

  20. Environmental radioactivity levels, Sequoyah Nuclear Plant. Annual report, 1983

    International Nuclear Information System (INIS)

    1984-04-01

    This report describes the environmental radiological monitoring of the Sequoyah Nuclear Plant (SQN) located in Hamilton County, Tennessee, conducted in 1983. Dose estimates were calculated from concentrations of radioactivity found in samples of air, milk, water, and fish. It was concluded there were no significant increases in the exposure to members of the general public attributable to the operation of SQN. 11 figures, 34 tables

  1. Radioactive materials released from nuclear power plants: Annual report, 1984

    Energy Technology Data Exchange (ETDEWEB)

    Tichler, J.; Norden, K.; Congemi, J.

    1987-08-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1984 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1984 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

  2. Regulatory control of radioactivity and nuclear fuel cycle in Canada

    International Nuclear Information System (INIS)

    Hamel, P.E.; Jennekens, J.H.

    1977-05-01

    Legislation and regulations giving birth to the Atomic Energy Control Board (AECB) are outlined, as well as current licencing procedures. The AECB bases its health and safety criteria on ICRP recommendations. R and D is funded to aid regulatory activity. Licencing activities cover uranium resource management, uranium mining and milling, nuclear generating stations, heavy water plants, and radioactive waste management. Safeguards, physical security, and international controls are also concerns of the AECB. (E.C.B.)

  3. Method for removing radioactive waste from a nuclear power plant

    International Nuclear Information System (INIS)

    1978-01-01

    By using the existing safety and auxiliary systems in a nuclear power plant a bunker-type building is to be linked up with the region of the main airlock, in which the radioactive material to be disposed of may pass through the necessary mechanical and chemical process while being handled in mobile containers. The constructional and engineering measures are described by a design example. (TK) [de

  4. From radioactivity to nuclear physics. Marie Curie and Lise Meitner

    International Nuclear Information System (INIS)

    Sime, R. L.

    1996-01-01

    In the first part of this century, at a time when few women obtained a higher education and even fewer entered the scientific professions, two exceptional women achieved great prominence in physics: Marie Curie in radioactivity and Lise Meitner in nuclear physics. In this article I outline the scientific work of meitner and Curie, in the context of their backgrounds and career paths that permitted them to overcome many of the obstacles faced by women in science. (author). 20 refs

  5. Radioactive materials released from nuclear power plants (1976)

    International Nuclear Information System (INIS)

    Decker, T.R.

    1978-11-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1976 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1976 release data are compared with previous year releases in tabular form. Data covering specific radionuclides are summarized

  6. Radioactive materials released from nuclear power plants. Annual report 1977

    International Nuclear Information System (INIS)

    Decker, T.R.

    1978-11-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1977 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1977 release data are compared with previous years releases in tabular form. Data covering specific radionuclides are summarized

  7. Risk assessment for transportation of radioactive materials and nuclear explosives

    International Nuclear Information System (INIS)

    Clauss, D.B.; Wilson, R.K.; Hartman, W.F.

    1991-01-01

    Sandia National Laboratories has the lead technical role for probabilistic risk assessments of transportation of nuclear weapons, components, and special nuclear material in support of the US Department of Energy. The emphasis of the risk assessments is on evaluating the probability of inadvertent disposal of radioactive material and the consequences of such a release. This paper will provide an overview of the methodology being developed for the risk assessment and will discuss the interpretation and use of the results. The advantages and disadvantages of using risk assessment as an alternative to performance-based criteria for packaging will be described. 2 refs., 1 fig

  8. Application of Nuclear Forensics in Combating Illicit Trafficking of Nuclear and Other Radioactive Material

    International Nuclear Information System (INIS)

    2014-01-01

    As a scientific discipline, nuclear forensics poses formidable scientific challenges with regard to extracting information on the history, origin, movement and processing of nuclear and other radioactive material found to be out of regulatory control. Research into optimized techniques is being pursued by leading nuclear forensic research groups around the world. This research encompasses areas including evidence collection, analytical measurements for rapid and reliable categorization and characterization of nuclear and radioactive material, and interpretation using diverse data characteristics or the 'science of signatures' from throughout the nuclear fuel cycle. In this regard, the IAEA recently concluded the Coordinated Research Project (CRP) entitled Application of Nuclear Forensics in Illicit Trafficking of Nuclear and Other Radioactive Material. The CRP seeks to improve the ability of Member States to provide robust categorization and characterization of seized material, reliable techniques for the collection and preservation of nuclear forensic evidence, and the ability to interpret the results for law enforcement and other purposes. In accordance with broader IAEA objectives, the CRP provides a technical forum for participating institutes from Member States to exchange technical information to benefit national confidence building as well as to advance the international discipline of nuclear forensics. This CRP was initially planned in 2006, commenced in 2008 and was completed in 2012. Three research coordination meetings (RCM) were convened at the IAEA in Vienna to review progress. The leadership of the chairpersons was essential to establishing the technical viability of nuclear forensics at the IAEA and with the Member States

  9. Management of radioactive wastes from nuclear power plants

    International Nuclear Information System (INIS)

    Krause, H.

    1984-01-01

    The importance of radioactive wastes from nuclear power plants (NPPs) results primarily from their large amounts. In NPPs more radioactive wastes arise than in all other plants of the nuclear fuel cycle, with the exception of uranium mills. Although the volume is great, NPP wastes are relatively low in activity and radiotoxicity and short in half-life. Several methods for treatment of NPP wastes are available that meet all the relevant requirements and they have attained high technical standards and are highly reliable. Consequently, the discharge of radionuclides with liquid and gaseous effluents and the resulting dose commitment to the general public are far below established limits. The quality of the conditioned wastes conforms to the requirements for ultimate disposal. The final disposal of NPP wastes has already been demonstrated successfully in several places and the feasibility of NPP decommissioning and management of the wastes arising in this process have been proved. The problems associated with the management of radioactive wastes from NPPs have been solved both scientifically and technically; there is no urgent need for improvement. This is why for new developments cost-benefit aspects must be considered, including the dose commitment to the operating staff and general aspects such as public acceptance and socio-ethical questions. Spectacular new developments are not to be expected in the near future. However, by continuous improvement of details and optimization of the whole system useful contributions can still be made to develop nuclear technology further. (author)

  10. Certified Training for Nuclear and Radioactive Source Security Management.

    Science.gov (United States)

    Johnson, Daniel

    2017-04-01

    Radioactive sources are used by hospitals, research facilities and industry for such purposes as diagnosing and treating illnesses, sterilising equipment and inspecting welds. Unfortunately, many States, regulatory authorities and licensees may not appreciate how people with malevolent intentions could use radioactive sources, and statistics confirm that a number of security incidents happen around the globe. The adversary could be common thieves, activists, insiders, terrorists and organised crime groups. Mitigating this risk requires well trained and competent staff who have developed the knowledge, attributes and skills necessary to successfully discharge their security responsibilities. The International Atomic Energy Agency and the World Institute for Nuclear Security are leading international training efforts. The target audience is a multi-disciplinary group of professionals with management responsibilities for security at facilities with radioactive sources. These efforts to promote training and competence amongst practitioners have been recognised at the 2014 and 2016 Nuclear Security and Nuclear Industry Summits. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  11. Radioactive Waste Generation in Pyro-SFR Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Gao, Fanxing; Park, Byung Heung; Ko, Won Il

    2011-01-01

    Which nuclear fuel cycle option to deploy is of great importance in the sustainability of nuclear power. SFR fuel cycle employing pyroprocessing (named as Pyro- SFR Cycle) is one promising fuel cycle option in the near future. Radioactive waste generation is a key criterion in nuclear fuel cycle system analysis, which considerably affects the future development of nuclear power. High population with small territory is one special characteristic of ROK, which makes the waste management pretty important. In this study, particularly the amount of waste generation with regard to the promising advanced fuel cycle option was evaluated, because the difficulty of deploying an underground repository for HLW disposal requires a longer time especially in ROK

  12. Some applications of radioactivity and of nuclear reactions

    International Nuclear Information System (INIS)

    2007-01-01

    This document presents various applications of radioactivity. It first addresses the medical field with applications in imagery (principles, used compounds, positron emission tomography, tumour detection, study of brain operation), applications in therapy (biological effects of radiations, principles of radiotherapy, struggle against cancer, notably by proton therapy), and applications in sterilisation and microbiological decontamination of instruments and medical products. It evokes applications in agriculture (irradiation of fruits and vegetables, vegetable conservation), in industry (production of new and stronger materials by irradiation, analysis by activation, thickness, density or homogeneity gauges), in arts (analysis of statues, use of gamma-graphy on dense objects, decontamination by irradiation), and in science (carbon 14 dating). It presents nuclear fission and ways to control it, recalls the main scientific discoveries and their consequences. It describes energy production based on nuclear fission (description of nuclear reactor core, of waste processing), and on nuclear fusion (principle, Tokamak examples with JET and ITER, brief presentation of laser fusion)

  13. Nuclear Security Recommendations on Nuclear and other Radioactive Material out of Regulatory Control: Recommendations (Spanish Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication presents recommendations for the nuclear security of nuclear and other radioactive material that is out of regulatory control. It is based on national experiences and practices and guidance publications in the field of security as well as the nuclear security related international instruments. The recommendations include guidance for States with regard to the nuclear security of nuclear and other radioactive material that has been reported as being out of regulatory control as well as for material that is lost, missing or stolen but has not been reported as such, or has been otherwise discovered. In addition, these recommendations adhere to the detection and assessment of alarms and alerts and to a graded response to criminal or unauthorized acts with nuclear security implications.

  14. Nuclear Security Recommendations on Nuclear and Other Radioactive Material out of Regulatory Control: Recommendations (Arabic Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication presents recommendations for the nuclear security of nuclear and other radioactive material that is out of regulatory control. It is based on national experiences and practices and guidance publications in the ? field of security as well as the nuclear security related international instruments. The recommendations include guidance for States with regard to the nuclear security of nuclear and other radioactive material that has been reported as being out of regulatory control as well as for material that is lost, missing or stolen but has not been reported as such, or has been otherwise discovered. In addition, these recommendations adhere to the detection and assessment of alarms and alerts and to a graded response to criminal or unauthorized acts with nuclear security implications.

  15. Nuclear security recommendations on nuclear and other radioactive material out of regulatory control: Recommendations

    International Nuclear Information System (INIS)

    2011-01-01

    The purpose of this publication is to provide guidance to States in strengthening their nuclear security regimes, and thereby contributing to an effective global nuclear security framework, by providing: - Recommendations to States and their competent authorities on the establishment or improvement of the capabilities of their nuclear security regimes, for carrying out effective strategies to deter, detect and respond to a criminal act, or an unauthorized act, with nuclear security implications, involving nuclear or other radioactive material that is out of regulatory control; - Recommendations to States in support of international cooperation aimed at ensuring that any nuclear or other radioactive material that is out of regulatory control, whether originating from within the State or from outside that State, is placed under regulatory control and the alleged offenders are, as appropriate, prosecuted or extradited

  16. Nuclear Security Recommendations on Nuclear and Other Radioactive Material out of Regulatory Control: Recommendations

    International Nuclear Information System (INIS)

    2011-01-01

    This publication presents recommendations for the nuclear security of nuclear and other radioactive material that is out of regulatory control. It is based on national experiences and practices and guidance publications in the field of security as well as the nuclear security related international instruments. The recommendations include guidance for States with regard to the nuclear security of nuclear and other radioactive material that has been reported as being out of regulatory control as well as for material that is lost, missing or stolen but has not been reported as such, or has been otherwise discovered. In addition, these recommendations adhere to the detection and assessment of alarms and alerts and to a graded response to criminal or unauthorized acts with nuclear security implications

  17. Nuclear Security Recommendations on Nuclear and Other Radioactive Material out of Regulatory Control: Recommendations (Russian Edition)

    International Nuclear Information System (INIS)

    2011-01-01

    This publication presents recommendations for the nuclear security of nuclear and other radioactive material that is out of regulatory control. It is based on national experiences and practices and guidance publications in the field of security as well as the nuclear security related international instruments. The recommendations include guidance for States with regard to the nuclear security of nuclear and other radioactive material that has been reported as being out of regulatory control as well as for material that is lost, missing or stolen but has not been reported as such, or has been otherwise discovered. In addition, these recommendations adhere to the detection and assessment of alarms and alerts and to a graded response to criminal or unauthorized acts with nuclear security implications.

  18. A DEVICE TO MEASURE LOW LEVELS OF RADIOACTIVE CONTAMINANTS IN ULTRA-CLEAN MATERIALS

    International Nuclear Information System (INIS)

    James H Reeves; Matthew Kauer

    2006-01-01

    The purpose of this research was to develop a radiation detection device so sensitive that a decay rate of only one atom per 11.57 days per kilogram of material could be detected. Such a detector is needed for screening materials that will be used in exotic high energy physics experiments currently being planned for the near future. The research was performed deep underground at the Underground Mine State Park in Soudan, Minnesota. The overburden there is ∼1800 meters water equivalent. The reason for performing the research at such depth was to vastly reduce the effects of cosmic radiation. The flux of muons and fast neutrons is about 100,000 times lower than at the surface. A small clean room quality lab building was constructed so that work could be performed in such a manner that radioactive contamination could be kept at a minimum. Glove boxes filled with dry nitrogen gas were used to further reduce contamination from dirt and also help reduce the concentration of the radioactive gas 222Ra and daughter radionuclides which are normally present in air. A massive lead shield (about 20 tons) was constructed in such a manner that an eight inch cube of space in the center was available for the sample and detector. The innermost 4 inch thick lead walls were made of ∼460 year old lead previously used in double beta decay experiments and known to be virtually free of 210Pb. A one and one half inch thick shell of active plastic scintillator was imbedded in the center of the 16 inch thick lead walls, ceiling, and floor of the shield and is used to help reduce activity due to the few muons and fast neutrons seen at this depth. The thick lead shielding was necessary to shield the detector from gamma rays emitted by radionuclides in the rock walls of the mine. A sealable chamber was constructed and located on top of the shield that included a device for raising and lowering the detector and samples into and out of the center chamber of the shield. A plastic scintillator

  19. A simple dynamic rising nuclear cloud based model of ground radioactive fallout for atmospheric nuclear explosion

    International Nuclear Information System (INIS)

    Zheng Yi

    2008-01-01

    A simple dynamic rising nuclear cloud based model for atmospheric nuclear explosion radioactive prediction was presented. The deposition of particles and initial cloud radius changing with time before the cloud stabilization was considered. Large-scale relative diffusion theory was used after cloud stabilization. The model was considered reasonable and dependable in comparison with four U.S. nuclear test cases and DELFIC model results. (authors)

  20. Regulations for the safe management of radioactive wastes and spent nuclear fuel

    International Nuclear Information System (INIS)

    Voica, Anca

    2007-01-01

    The paper presents the national, international and European regulations regarding radioactive waste management. ANDRAD is the national authority charged with nation wide coordination of safe management of spent fuel and radioactive waste including their final disposal. ANDRAD's main objectives are the following: - establishing the National Strategy concerning the safety management of radioactive waste and spent nuclear fuel; - establishing the national repositories for the final disposal of the spent nuclear fuel and radioactive waste; - developing the technical procedures and establishing norms for all stages of management of spent nuclear fuel and radioactive waste, including the disposal and the decommissioning of the nuclear and radiologic facilities

  1. Early phase clean-up actions after nuclear accidents. Guidelines for the planner. Final report

    International Nuclear Information System (INIS)

    Ulvsand, T.

    1997-06-01

    The work reported has been performed with the purpose of working out a guide for planners of early clean-up actions in nuclear fallout situations and for decision makers in the Nordic countries. The actions considered are hosing of roofs, walls and paved areas, lawn mowing, removal of snow, pruning of trees and bushes and vacuum cleaning of streets. The expected effects, mainly as life time dose reduction, and consequences regarding practicability, waste produced, staffing and protection are presented for urban, suburban and rural living environments. The work has been performed within the fram work of the Nordic Nuclear Safety Research Program 1994-97 (Statens Raeddningsverk). (au)

  2. Accelerator driven radiation clean nuclear power system conceptual research symposium

    International Nuclear Information System (INIS)

    Zhao Zhixiang

    2000-06-01

    The R and D of ADS (Accelerators Driven Subcritical System) in China introduced. 31 theses are presented. It includes the basic principle of ADS, accelerators, sub-critical reactors, neutron physics, nuclear data, partitioning and transmutation

  3. Radioactivity And Nuclear Themes In Croatian Popular Culture

    International Nuclear Information System (INIS)

    Franic, Z.; Franic, S.

    2015-01-01

    Popular culture refers to the entirety of ideas, perspectives, attitudes, behaviours, ways of communication, cultural and artistic products, (visual, auditory, written, etc.) as well as other phenomena in the real or virtual world within mainstream culture. Heavily influenced by mass media, this collection of ideas permeates the everyday lives of society. In the so-called atomic age, which corresponds to the cold war period, stylistic coloration and application of the concepts of radiation that have persisted in everyday life to this day can be classified into four main groups of radiological-nuclear themes: monsters and mutants associated with radiation, nuclear accidents, nuclear terrorism and nuclear optimism. This paper discusses some examples relating to radioactivity, radiation and nuclear topics in Croatian popular culture, with special reference to the mass media, including some Internet portals. In Croatian mass media, like in other cultures, radiation and nuclear metaphors symbolize something scary and completely incomprehensible. However, further systematic research would be needed to analyse and explain all of the stereotypes in more detail. Results would be useful in creating a more effective way for informing the general public about the effects and use of radiation and nuclear technology, which is expected to play a far greater role in solving numerous problems dealing with energy supply, medicine, etc. in the near future. It should be noted that nowadays the collective public fears shift from radiation to other global threats such as climate change, genetically modified organisms, global terrorism and others. (author).

  4. Basic approach to the disposal of low level radioactive waste generated from nuclear reactors containing comparatively high radioactivity

    International Nuclear Information System (INIS)

    Moriyama, Yoshinori

    1998-01-01

    Low level radioactive wastes (LLW) generated from nuclear reactors are classified into three categories: LLW containing comparatively high radioactivity; low level radioactive waste; very low level radioactive waste. Spent control rods, part of ion exchange resin and parts of core internals are examples of LLW containing comparatively high radioactivity. The Advisory Committee of Atomic Energy Commission published the report 'Basic Approach to the Disposal of LLW from Nuclear Reactors Containing Comparatively High Radioactivity' in October 1998. The main points of the proposed concept of disposal are as follows: dispose of underground deep enough not be disturb common land use (e.g. 50 to 100 m deep); dispose of underground where radionuclides migrate very slowly; dispose of with artificial engineered barrier which has the same function as the concrete pit; control human activities such as land use of disposal site for a few hundreds years. (author)

  5. Biological considerations in nuclear decommissioning, and radioactive waste management

    International Nuclear Information System (INIS)

    Rees, J.F.

    1991-01-01

    The importance of natural processes such as microbial action in waste management has recently been recognised. Although it is often difficult to predict the effects because the interactive processes are complex, human intervention can optimize the process. This paper highlights some of the fundamental stages in the management of low- and intermediate-level radioactive wastes where particular uncertainties exist and which might benefit from controlled microbial intervention. The areas considered are the use of biodegradable surfactants for cleaning surfaces before disposal, microbial adsorption and concentration of intermediate-level wastes from solution, microbial transformation of intermediate-level wastes organic fractions, enhancement of radionuclide transfer to the atmosphere, enhancement of transfer into vadose zone and ground water and the microbial treatment of any oily residues. (UK)

  6. Nuclear spectroscopy with Geant4: Proton and neutron emission & radioactivity

    Energy Technology Data Exchange (ETDEWEB)

    Sarmiento, L. G., E-mail: Luis.Sarmiento@nuclear.lu.se; Rudolph, D. [Department of Physics, Lund University, 22100 Lund (Sweden)

    2016-07-07

    With the aid of a novel combination of existing equipment – JYFLTRAP and the TASISpec decay station – it is possible to perform very clean quantum-state selective, high-resolution particle-γ decay spectroscopy. We intend to study the determination of the branching ratio of the ℓ = 9 proton emission from the I{sup π} = 19/2{sup −}, 3174-keV isomer in the N = Z − 1 nucleus {sup 53}Co. The study aims to initiate a series of similar experiments along the proton dripline, thereby providing unique insights into “open quantum systems”. The technique has been pioneered in case studies using SHIPTRAP and TASISpec at GSI. Newly available radioactive decay modes in Geant4 simulations are going to corroborate the anticipated experimental results.

  7. Nuclear spectroscopy with Geant4: Proton and neutron emission & radioactivity

    Science.gov (United States)

    Sarmiento, L. G.; Rudolph, D.

    2016-07-01

    With the aid of a novel combination of existing equipment - JYFLTRAP and the TASISpec decay station - it is possible to perform very clean quantum-state selective, high-resolution particle-γ decay spectroscopy. We intend to study the determination of the branching ratio of the ℓ = 9 proton emission from the Iπ = 19/2-, 3174-keV isomer in the N = Z - 1 nucleus 53Co. The study aims to initiate a series of similar experiments along the proton dripline, thereby providing unique insights into "open quantum systems". The technique has been pioneered in case studies using SHIPTRAP and TASISpec at GSI. Newly available radioactive decay modes in Geant4 simulations are going to corroborate the anticipated experimental results.

  8. CEA - Nuclear Energy Division. Report on Sustainable Radioactive Waste Management

    International Nuclear Information System (INIS)

    2012-12-01

    The Sustainable Radioactive Waste Management Act of June 28, 2006, specified clear guidelines for spent nuclear fuel management. It states two complementary principles: - The policy of treating and recycling spent nuclear fuel is valid for reducing the quantity and toxicity of suitably packaged ultimate radioactive waste-forms. - The reference process for high-activity and long-lived ultimate waste is deep geological disposal. The report prepared by the CEA in response to these requirements was completed after several years of work in cooperation with the other French actors in this field (EDF, AREVA) and with contribution of the CNRS and Andra. It addresses the following topics in several volumes: n guidelines for research on 4. generation systems, and a description of the various systems examined; - the results of research coordinated by the CEA on partitioning and transmutation of long-lived radioactive elements; - choices proposed for the Astrid integrated technology demonstrator - a sodium-cooled fast reactor (SFR) - and a reasonable timetable for its construction; - a review of research conducted around the world on 4. generation systems based on fast neutron reactors (FNRs). The principal results and findings compiled by the CEA from these studies are summarized in this document

  9. Marine environmental radioactivity surveys at nuclear submarine berths 2001

    International Nuclear Information System (INIS)

    Cowling, E.; Ball, R.; Simpson, C.

    2002-01-01

    This report presents the results of the marine environmental radioactivity monitoring surveys of intertidal and underwater areas around nuclear submarine berths which were carried out by DRPS during 2001. Also included are results of smaller scale intertidal surveys carried out by local staff but co-ordinated by DRPS. Cobalt-60, the nuclide of major importance in naval discharges, was detected in a number of samples but in many cases was attributable to discharges by other operators. Concentrations in any case were found to be low, and at no survey location did the calculated annual radiation dose commitment to the most exposed members of the general public due to the presence of cobalt-60 exceed 1% of the ICRP principal dose limit for members of the public (1000μSv). These results are consistent with those obtained in the independent monitoring programmes as reported in the Radioactivity in Food and the Environment (RIFE) annual reports. It is concluded that existing discharge arrangements are providing effective control over environmental levels of radioactivity, and that there has been no radiological hazard to any member of the general public during 2001 from the operation of nuclear powered submarines. (author)

  10. The potential of nuclear energy to generate clean electric power in Brazil

    International Nuclear Information System (INIS)

    Stecher, Luiza C.; Sabundjian, Gaiane; Menzel, Francine; Giarola, Rodrigo S.; Coelho, Talita S.

    2013-01-01

    The generation of electricity in Brazil is concentrated in hydroelectric generation, renewable and clean source, but that does not satisfy all the demand and leads to necessity of a supplementary thermal sources portion. Considering the predictions of increase in demand for electricity in the next years, it becomes necessary to insert new sources to complement the production taking into account both the volume being produced and the needs of environmental preservation. Thus, nuclear power can be considered a potential supplementary source for electricity generation in Brazil as well as the country has large reserves of fissile material, the generation emits no greenhouse gases, the country has technological mastery of the fuel cycle and it enables the production of large volumes of clean energy. The objective of this study is to demonstrate the potential of nuclear energy in electricity production in Brazil cleanly and safely, ensuring the supplies necessary to maintain the country's economic growth and the increased demand sustainable. For this, will be made an analysis of economic and social indicators of the characteristics of our energy matrix and the availability of our sources, as well as a description of the nuclear source and arguments that justify a higher share of nuclear energy in the matrix of the country. Then, after these analysis, will notice that the generation of electricity from nuclear source has all the conditions to supplement safely and clean supply of electricity in Brazil. (author)

  11. Environmental radioactivity levels, Browns Ferry Nuclear Plant: Annual report, 1986

    International Nuclear Information System (INIS)

    1986-04-01

    The report presents data gathered during radiological monitoring program conducted in the environs of the Browns Ferry Nuclear Plant. Dose estimates were made from concentrations of radioactivity found in samples of media including air, milk, food products, drinking water, and fish. Inhalation and ingestion doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations. Greater than 95% of those doses were contributed by the naturally occurring K-40 and by Sr-90 and Cs-137 which are long-lived radioisotopes found in fallout from nuclear weapons testing. Increased levels of I-131 were reported in air, milk, and rainwater following the accident at the Chernobyl nuclear power station. In addition, Ru-103, Cs-137, and Cs-134 were identified in air particulates, and traces of Ru-103 were found in rainwater

  12. Recent advances in nuclear techniques for environmental radioactivity monitoring

    International Nuclear Information System (INIS)

    Kumar, Ajay; Tripathi, R.M.

    2016-01-01

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

  13. Disposal of slightly contaminated radioactive wastes from nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Minns, J.L. [Nuclear Regulatory Commission, Washington, DC (United States)

    1995-02-01

    With regard to the disposal of solid wastes, nuclear power plants basically have two options, disposal in a Part 61 licensed low-level waste site, or receive approval pursuant to 20.2002 for disposal in a manner not otherwise authorized by the NRC. Since 1981, the staff has reviewed and approved 30 requests for disposal of slightly contaminated radioactive materials pursuant to Section 20.2002 (formerly 20.302) for nuclear power plants located in non-Agreement States. NRC Agreement States have been delegated the authority for reviewing and approving such disposals (whether onsite or offsite) for nuclear power plants within their borders. This paper describes the characteristics of the waste disposed of, the review process, and the staff`s guidelines.

  14. Session 1984-85. Radioactive waste. Minutes of evidence, Monday 17 June 1985. Nuclear Industry Radioactive Waste Executive

    International Nuclear Information System (INIS)

    1985-01-01

    The Environment Select Committee of the House of Commons received a memorandum from the Nuclear Industry Radioactive Waste Executive, on the management and disposal of radioactive waste arising in the UK, under the headings: introduction; the structure of NIREX; the nature of radioactive waste; plans for the disposal of low and intermediate level wastes. Representatives of NIREX were examined on the subject of the memorandum and the minutes of evidence are recorded. (U.K.)

  15. Cleaning and extraction apparatus in a nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Nakamura, Yoshiaki.

    1983-01-01

    Purpose : To eliminate the requirement for the decomposition and cleaning of a centrifugal extractor upon re-processing of FBR type reactor fuels, by preventing solid fission products from depositing on a rotary body of the centrifugal extractor. Constitution : A cleaning and extraction apparatus comprising a combination of a centrifugal cleaner and a centrifugal extractor is used for shortening the contact time between the process liquid and the extraction solvent in FBR type reactor fuel re-processing, and variable parameters are adjusted so that the following equation can be satisfied for avoiding the deposition of solids onto the rotary body of the centrifugal extractor: lsub(e). (rsub(le) 2 + rsub(2r) 2 ) . Nsub(e) . Qsub(c)/ lsub(c) (rsub(lc) 2 + rsub(2c) 2 ) . Nsub(c) . Qsub(e) < 0.8 where Qsub(c) : flow rate to be processed in a centrifugal cleaner, lsub(c) : length of the rotary body, rsub(2c) : radius of a rotary body, rsub(le) : distance from the center to the liquid-extracting hole of the rotary body center to the liquid-extraction hole, Nsub(c) : number of revolution of the rotary body, Qsub(e) : amount of flowrate to be treated in the centrifugal extractor, lsub(e) : length of the rotary body, rsub(2e) : radius for the rotary body, rsub(le) : distance from the center of the rotary body to the liquid discharging aperture and Nsub(e) : number of rotation of the rotary body. (Ikeda, J.)

  16. Nuclear knowledge management in radioactive waste management programmes

    International Nuclear Information System (INIS)

    Vetere, Claudia L.; Gomiz, Pablo R.; Lavalle, Myriam; Masset, Elvira

    2015-01-01

    In late 2007, the Nuclear Knowledge Management (NKM) group of the Argentine Atomic Energy Commission (CNEA), understanding the need to preserve knowledge related with radioactive waste, formulated the CONRRaD Project with the aim of developing and implementing a sustainable knowledge management system. The CONRRaD Project was highly focused on minimising the loss of radioactive waste management knowledge related to processes and facilities as a consequence of staff ageing and retiring, promoting transfer and preservation so as to ensure that future generations interpret and improve the management of waste, protecting the environment and people's health. The National Programme for Radioactive Waste Management (NPRWM) has the responsibility of maintaining a documented record system to preserve the knowledge that is available and relates to the facilities for radioactive wastes treatment, conditioning, packaging, storing and disposal of low-level radioactive wastes. The STOReR system has been designed with the aim of ensuring traceability through all the steps of radioactive waste management from generation to storage or disposal. Apart from upgrading an application in use since 2001, the new software includes improvements in the inventory calculations according to the current regulations. Basically, the system consists of two applications. One application called PAGE is on the Net and it is available for the producers. These producers are the facilities that generate radioactive waste as a consequence of their normal operation. PAGE enables the producers to access all the services provided by AGE more easily. Not only are producers the users of PAGE, but there are also authorised owners of radioactive sources and devices because AGE provides transitory or permanent storage of these elements. The other application called STOReR is the main one which provides the capabilities needed to support the whole system, such as the databases storage and management. STORe

  17. Present and future radioactive nuclear beam developments at Argonne

    International Nuclear Information System (INIS)

    Decrock, P.

    1996-01-01

    A scheme for building an ISOL-based radioactive nuclear beam facility at the Argonne Physics Division, is currently evaluated. The feasibility and efficiency of the different steps in the proposed production- and acceleration cycles are being tested. At the Dynamitron Facility of the ANL Physics Division, stripping yields of Kr, Xe and Ph beams in a windowless gas cell have been measured and the study of fission of 238 U induced by fast neutrons from the 9 Be(dn) reaction is in progress. Different aspects of the post-acceleration procedure are currently being investigated. In parallel with this work, energetic radioactive beams such as 17 F, 18 F and 56 Ni have recently been developed at Argonne using the present ATLAS facility

  18. Support of the radioactive waste treatment nuclear fuel fabrication facility

    International Nuclear Information System (INIS)

    Park, H.H.; Han, K.W.; Lee, B.J.; Shim, G.S.; Chung, M.S.

    1982-01-01

    Technical service of radioactive waste treatment in Daeduck Engineering Center includes; 1) Treatment of radioactive wastes from the nuclear fuel fabrication facility and from laboratories. 2) Establishing a process for intermediate treatment necessary till the time when RWTF is in completion. 3) Technical evaluation of unit processes and equipments concerning RWTF. About 35 drums (8 m 3 ) of solid wastes were treated and stored while more than 130 m 3 of liquid wastes were disposed or stored. A process with evaporators of 10 1/hr in capacity, a four-stage solvent washer, storage tanks and disposal system was designed and some of the equipments were manufactured. Concerning RWTF, its process was reviewed technically and emphasis were made on stability of the bituminization process against explosion, function of PAAC pump, decontamination, and finally on problems to be solved in the comming years. (Author)

  19. Cost for the radioactive wastes from nuclear power

    International Nuclear Information System (INIS)

    1992-06-01

    The future cost for handling, storing and disposing of radioactive wastes from the Swedish nuclear power plants are calculated in this report. The following plants and systems are already operating: * Transport system for radioactive wastes, * A control spent fuel intermediate storage plant, * A repository for low and medium level wastes. These are planned: * A treatment plant for used fuels, * A repository for high-level wastes, and * Repository for decommissioning wastes. The costs include R and D and decommissioning. Total future costs from 1993 are estimated to be 46.4 billion SEK (8.3 billion USD), during 60 years. Up to 1992 8.7 billion SEK (1.6 billion USD) have been spent

  20. Cost for the radioactive wastes from nuclear power

    International Nuclear Information System (INIS)

    1989-06-01

    The future cost for handling, storing and disposing of radioactive wastes from the Swedish nuclear power plants are calculated in this report. The following plants and systems are already operating: - Transportsystem for radioactive wastes. - A control spent fuel intermediate storage plant. - A repository for low and medium level wastes. These are planned: - A treatment plant for used fuels. A repository for high-level wastes and repository for decommissioning wastes. The costs include Rand D and decommissioning. Total future costs from 1990 are estimated to be 43 billion SEK (6,5 billion dollars), during 60 years. Up to 1990 7,4 billion SEK (1,1 billion dollars) have been spent. (L.E.)

  1. Aspects of nuclear safety in the management of the radioactive wastes

    International Nuclear Information System (INIS)

    Popescu, D.; Iliescu, E.

    1997-01-01

    The paper reviews aspects of nuclear safety which should be taken into account in the management of the radioactive wastes. The paper considers underlying criteria concerning the management, collecting, sorting transportation and treatment of radioactive wastes as well as safety engineering measures taken when designing a facility for the treatment of radioactive wastes. The paper also brings forward the removal radioactive wastes and some points on the policy of radioactive wastes management in Romania. (authors)

  2. Radiological pathways analysis for spent solvents from the boiler chemical cleaning at the Pickering Nuclear Site

    International Nuclear Information System (INIS)

    Garisto, N.C.; Eslami, Z.; Hodgins, S.; Beaman, T.; Von Svoboda, S.; Marczak, J.

    2006-01-01

    Spent solvents are generated as a result of Boiler Chemical Cleanings (BCC) at CANDU reactor sites. These solutions contain small amount of radioactivity from a number of different sources including: Cut tubes - short sections of boiler tubes are infrequently removed from the boilers for a detailed characterization. These tubes are typically only plugged at the tubesheet allowing the primary side deposits to be exposed to BCC solvents. Tube leaks - primary to secondary side leaks also occur infrequently as a result of tube degradation. Radioactivity from the leaking fluid can consequently be deposited in the sludge on the secondary side of the tubes. Diffusion of tritium - during normal operation of the reactor units, tritium slowly diffuses from the heavy water in the primary heat-transfer system to the light-water coolant on the secondary side. Some of this tritium is retained in the secondary side deposits. The Pickering Nuclear Generating Station (PNGS) would like the flexibility to have several options for handling the spent solvent waste and associated rinse water from BCC. To this end, a radiological pathways analysis was undertaken to determine dose consequences associated with each option. Sample results from this study are included in this paper. The pathways analysis is used in this study to calculate dose to hypothetical receptors including individuals such as truck drivers, incinerator workers, residue (ash) handlers, residents who live near the landfill, inadvertent intruders into the landfill after closure and residents who live near the outfall. This dose is compared to a de minimis dose. A de minimis dose or dose rate represents a level of risk, which is generally accepted as being of no significance. Shipments of spent solvents and rinse water with corresponding doses below de minimis can be sent to conventional (i.e., non-radioactive) landfills for incineration and disposal as the radioactive dose associated with them is much less than natural

  3. Analysis of occupational doses in radioactive and nuclear facilities

    International Nuclear Information System (INIS)

    Curti, A.; Gomez P, I.; Pardo, G.; Thomasz, E.

    1996-01-01

    Occupational doses were analyzed in the most important nuclear and radioactive facilities in Argentina, on the period 1988-1994. The areas associated with uranium mining and milling, and medical uses of radiation facilities were excluded from this analysis. The ICRP publication 60 recommendations, adopted in 1990, and enforced in Argentine in 1994, keep the basic criteria of dose limitation system and recommend a substantial reduction in the dose limits. The reduction of the dose limits will affect the individual dose distributions, principally in those installations with occupational doses close to 50 mSv. It were analyzed Occupational doses, principally in the following facilities: Atucha-I and Embalse Nuclear Power Plants, radioisotope production plants, research reactors and radioactive waste management plants. The highest doses were identified in each facility, as well as the task associated with them. Trends in the individual dose distribution and collective and average doses were analyzed. It is concluded, that no relevant difficulties should appear in accomplishing with the basic standards for radiological safety, except for the Atucha-I Nuclear Power Plant. In this NPP a significant effort for the optimization of radiological safety procedures in order to diminish the occupational doses, and a change of the fuel channels by new ones free of cobalt are being carried out. (authors). 4 refs., 3 figs., 3 tabs

  4. Characterization of radioactive waste from nuclear power reactors

    International Nuclear Information System (INIS)

    Piumetti, Elsa H.; Medici, Marcela A.

    2007-01-01

    Different kinds of radioactive waste are generated as result of the operation of nuclear power reactors and in all cases the activity concentration of several radionuclides had to be determined in order to optimize resources, particularly when dealing with final disposal or long-term storage. This paper describes the three basic approaches usually employed for characterizing nuclear power reactor wastes, namely the direct methods, the semi-empirical methods and the analytical methods. For some radionuclides or kind of waste, the more suitable method or combination of methods applicable is indicated, stressing that these methods shall be developed and applied during the waste generation step, i.e. during the operation of the reactor. In addition, after remarking the long time span expected from waste generation to their final disposal, the importance of an appropriate record system is pointed out and some basic requirements that should be fulfilled for such system are presented. It is concluded that the tools for a proper characterization of nuclear reactor radioactive waste are available though such tools should be tailored to each specific reactor and their history. (author) [es

  5. Proceedings of the 21st DOE/NRC nuclear air cleaning conference; Volume 2, Sessions 9--16

    Energy Technology Data Exchange (ETDEWEB)

    First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

    1991-02-01

    The 21st meeting of the Department of Energy/Nuclear Regulatory Commission (DOE/NRC) Nuclear Air Cleaning Conference was held in San Diego, CA on August 13--16, 1990. The proceedings have been published as a two volume set. Volume 2 contains sessions covering adsorbents, nuclear codes and standards, modelling, filters, safety, containment venting and a review of nuclear air cleaning programs around the world. Also included is the list of attendees and an index of authors and speakers. (MHB)

  6. Radioactive waste generation in the nuclear reactors in Romania

    International Nuclear Information System (INIS)

    Popescu, I.V.

    2002-01-01

    The successful use of nuclear fission as major source of energy for this century is based upon the technological capabilities acquired to face the issue of radioactive waste and spent fuel. The management of radioactive waste is complex and implies solving the following major problems: - isolation of the radioisotopes from the complex of effluents released in the environment; - processing the separated radioisotopes for subsequent storing and final disposal; - transport of processed and conditioned wastes towards disposal repository; - selecting the sites for storage and final disposal. During reactor operation liquid and gaseous effluents are released to the environment as well as radioactive materials. All these may have an dangerous impact upon the environment when the international regulations, i.e. the ALARA principle are not strictly observed. The maximal values for the radioactive release are established by national regulations which are concordant with the IAEA principles. The amount of radioactive materials released depends of the reactor type and the measures adopted to reduce these releases. The average values of these releases during the normal operation of the reactor constitute the 'source term'. Its calculation implies several factors such as: the reactor type; the radionuclide concentration in the primary cooling systems; the transport mechanisms and leaks resulting in liquid and gaseous radionuclide emissions; the efficiency of the barriers and engineered safety systems built to reduce the amounts of radionuclide in the effluents. The concentration of radionuclides in the primary cooling circuit depends on the reactor power level, fuel burnup, fuel sheath type, tightness of the fuel cans, impurity concentration, chemical additives in the fluid of the primary cooling system, the total volume of this fluid, as well as its purification system. The methods applied to facilitate the calculation of the source term are described. In 1998 the spent fuel

  7. Off-gas and air cleaning systems for accident conditions in nuclear power plants

    International Nuclear Information System (INIS)

    1993-01-01

    This report surveys the design principles and strategies for mitigating the consequences of abnormal events in nuclear power plants by the use of air cleaning systems. Equipment intended for use in design basis accident and severe accident conditions is reviewed, with reference to designs used in IAEA Member States. 93 refs, 48 figs, 23 tabs

  8. Radioactive fallout from the Chernobyl nuclear reactor accident

    International Nuclear Information System (INIS)

    Beiriger, J.M.; Failor, R.A.; Marsh, K.V.; Shaw, G.E.

    1987-01-01

    Following the accident at the nuclear reactor at Chernobyl, in the Soviet Union on April 26, 1986, we performed a variety of measurements to determine the level of the radioactive fallout on the western United States. We used gamma-spectroscopy to analyze air filters from the areas around Lawrence Livermore National Laboratory (LLNL), California, and Barrow and Fairbanks, Alaska. Milk from California and imported vegetables were also analyzed. The levels of the various fission products detected were far below the maximum permissible concentration levels

  9. Science seeks [nuclear] weapons clean-up role

    International Nuclear Information System (INIS)

    Macilwain, Colin.

    1996-01-01

    US scientists argue for funding to support basic research which would make the decommissioning of one of the world's nuclear stockpiles cheaper and more effective. This runs contrary to current popular and political thought, from citizens' groups and state governments, that the stockpile should be dismantled immediately and publicly due to their suspicion of scientists and fear that stockpiled weapons could still be used. This article examines the debate between the two opposing views. (UK)

  10. Future prospects for radioactive nuclear beams in North America

    International Nuclear Information System (INIS)

    Nitschke, J.M.

    1993-05-01

    In 1989 this author proposed the construction of a dedicated, flexible, radioactive nuclear beams facility that would provide intense beams of nearly all elements for a program of scientific studies in nuclear structure, nuclear reaction dynamics, astrophysics, high-spin physics, nuclei far from stability, material- and surface science, and atomic- and hyperfine-interaction physics. The initial name proposed for the new facility was ''IsoSpin Factory'' to underscore the key feature of this new physics tool; it was later changed to ''IsoSpin Laboratory'' (ISL). The ISL is now supported by a broad base of nuclear scientists and has been identified in the US Long Range Plan on Nuclear Science as one of the new potential construction projects for the second part of this decade. Since 1989 a number of conferences and workshops has been held in which the scientific and technical case for RNB facilities has been made. The purpose of this paper is to focus on the North American plan for the ISL, which was initially summarized in a ''White Paper'' but has since evolved in its scientific and technical scop

  11. Public perception on nuclear energy and radioactive waste storage

    International Nuclear Information System (INIS)

    Ferreira, Vinicius V.M.; Mourao, Rogerio P.; Fleming, Peter M.; Soares, Wellington A.; Braga, Leticia T.P.; Santos, Rosana A.M.

    2009-01-01

    The final destination of the waste generated in a nuclear power plant remains a big challenge. The question is not only the radiation emitted by the sources, in some cases for many years, but also the public acceptance of this theme. In many countries where a nuclear waste storage facility has to be built, the local population of the chosen site did not accept it at first, and the whole process had to restart including this variable. In the past, the population opinion was considered not relevant but several international experiences showed that in fact it can not be forgotten. Statistical data show that a significant fraction of the population of the world has many concerns about nuclear energy and its potential impacts. Although many experts state that it has environmental advantages, such as the absence of greenhouse gases emissions, the subject is still the target of never ending discussions. But it is a concrete fact that the sector is growing in many countries. The objective of this article is to summarize several experiences in many countries associated with nuclear energy, mainly those ones that involve nuclear storage facilities, and its acceptance by the public. This task can help CNEN in the studies associated with the RMBN project - Repository for Radioactive Waste with Low and Medium Levels of Radiation. (author)

  12. Occupational radiation exposures at radioactive and nuclear facilities in Argentina

    International Nuclear Information System (INIS)

    Curti, A.; Pardo, G.; Melis, H.

    1998-01-01

    This paper presents an evaluation of occupational radiation exposures at relevant radioactive and nuclear facilities in Argentina, for 1996. The facilities send this information to the Nuclear Regulatory Authority due to the requirements included in their operation licenses and authorizations. Dose distributions of 1891 workers and their parameters are presented. The analysis is performed for each type of the following practices: nuclear power plants, research reactors, radioisotope production, fuel fabrication, industrial irradiation and research in the nuclear fuel cycle. Trends of occupational exposure in different practices are analysed and the highest doses have been identified. Following the 1990 recommendations of the International Commission on Radiological Protection (ICRP 60), the Nuclear Regulatory Authority of Argentina updated the dose limits for workers in 1995. The individual dose limits are 20 mSv per year averaged over five consecutive years (100 mSv in 5 years), not exceeding 50 mSv in a single year. To evaluate the occupational radiation exposure trend, without taking into account practices, an analysis of the distribution of individual doses accumulated in the period 1995/96, for all workers, is performed. Individual doses received during 1996 were all below 50 mSv and doses accumulated in the period 1995/96 were below 100 mSv. (author). 7 refs., 16 figs., 5 tabs

  13. Incidents of illicit trafficking and other unauthorized activities involving nuclear and other radioactive materials (1993-2005)

    International Nuclear Information System (INIS)

    2010-01-01

    The confirmed incidents of illicit trafficking and other unauthorized activities involving nuclear and other radioactive materials between 1993-2005 shows that, 27% involved nuclear materials, 62% radioactive materials,7% involved both nuclear and other radioactive materials while the remainder involved other radioactive and non radioactive materials.Also 80% of nuclear material which was recovered during the same period was not reported as stolen or lost.

  14. Management of radioactive waste from nuclear power plants: An overview

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1994-01-01

    The nuclear power industry, which accounts for about 20% of the total electricity supply, is a vital part of the nation's energy resource. While it generates approximately one-third of the commercial low-level radioactive waste produced in the country, it has achieved one of the most successful examples in waste minimization. On the other hand, progress on development of new disposal facilities by the state compacts is currently stalled. The milestones have been repeatedly postponed, and the various Acts passed by Congress on nuclear waste disposal have not accomplished what they were intended to do. With dwindling access to waste disposal sites and with escalating disposal costs, the power plant utilities are forced to store wastes onsite as an interim measure. However, such temporary measures are not a permanent solution. A national will is sorely needed to break out of the current impasse

  15. Regulatory control of radioactivity and nuclear fuel cycle in Canada

    International Nuclear Information System (INIS)

    Hamel, P.E.; Jennekens, J.H.

    1977-01-01

    The mining of pitchblende for the extraction of radium some four decades ago resulted in a largely unwanted by-product, uranium, which set the stage for Canada to be one of the first countires in the world to embark upon a nuclear energy program. From this somewhat unusual beginning, the Canadian program expanded beyond mining of uranium-bearing ores to include extensive research and development in the field of radio-isotope applications, research and power reactors, nuclear-fuel conversion and fabrication facilities, heavy-water production plants and facilities for the management of radioactive wastes. As in the case of any major technological development, nuclear energy poses certain risks on the part of those directly engaged in the industry and on the part of the general public. What characterizes these risks is not so much their physical nature as the absence of long-term experience and the confidence resulting from it. The early development of regulatory controls in the nuclear field in Canada was very much influenced by security considerations but subsequently evolved to include radiological protection and safety requirements commensurate with the expanding application of nuclear energy to a wide spectrum of peaceful uses. A review of Canadian nuclear regulatory experience will reveal that the risks posed by the peaceful uses of nuclear energy can be controlled in such a manner as to ensure a high level of safety. Recent events and development have shown however that emphasis on the risks associated with low-probability, high-consequence events must not be allowed to mask the importance of health and safety measures covering the entire fuel cycle

  16. Improvements of radioactive waste management at WWER nuclear power plants

    International Nuclear Information System (INIS)

    2006-04-01

    This report is part of a systematic IAEA effort to improve waste management practices at WWER plants and to make them consistent with the current requirements and standards for safe and reliable operation of nuclear power plants. The report reviews the wet and dry solid waste management practices at the various types of WWER nuclear power plants (NPP) and describes approaches and recent achievements in waste minimization. Waste minimization practices in use at western PWRs are reviewed and compared, and their applicability at WWER plants is evaluated. Radioactive waste volume reduction issues and waste management practices are reflected in many IAEA publications. However, aspects of waste minimization specific to individual WWER nuclear power plant designs and WWER waste management policies are not addressed extensively in those publications. This report covers the important aspects applicable to the improvement of waste management at WWER NPP, including both plant-level and country-level considerations. It is recognized that most WWER plants are already implementing many of these concepts and recommendations with varying degrees of success; others will benefit from the included considerations. The major issues addressed are: - Review of current waste management policies and practices related to WWERs and western PWRs, including the influence of the original design concepts and significant modifications, liquid waste discharge limits and dry solid waste clearance levels applied in individual countries, national policies and laws, and other relevant aspects affecting the nature and quantities of waste arisings; - Identification of strategies and methods for improving the radioactive waste management generated in normal operation and maintenance at WWERs. This report is a composite (combination) of the two separate initiatives mentioned above. The first draft report was prepared at the meeting 26-30 May 1997 by five consultants. The draft was improved during an

  17. Twenty-second DOE/NRC nuclear air cleaning and treatment conference

    International Nuclear Information System (INIS)

    Bellamy, R.R.; Moeller, D.W.; First, M.W.

    1992-01-01

    The Twenty-Second Department of Energy/Nuclear Regulatory Commission Nuclear Air Cleaning and Treatment Conference was held Aug. 24-27, 1992, in Denver, Colo. A total of 224 air-cleaning specialists attended the conference. The United States and 12 foreign countries were represented, and the specialists were affiliated with government agencies, educational institutions, and all aspects of the nuclear industry, including utilities, architect engineers, equipment suppliers, and consultants. Several major topics were discussed, similar to areas covered at previous conferences: chemical processing off-gas cleaning; particulate filler developments, including filter testing, performance, and response to physical stress,adsorber testing and performance, including laboratory and in-place testing; waste management; system operation; codes and standards; and advanced nuclear power plants. The conference continued to provide an effective forum for direct interchange of information of both a practical and theoretical nature. International participation and interest continues, as evidenced by over 40% of the papers being sponsored by foreign interests and almost 20% of the attendees being from outside the United States. The potential for new, safer nuclear plants of an advanced design was an optimistic note during the conference. Regulatory authorities are playing a major role in providing guidance in the development of safety goals and other technical criteria for these new installations

  18. Multi-criteria planning of nuclear contribution to the goals of clean electricity in Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Martin-del-Campo, C., E-mail: cecilia.martin.del.campo@gmail.com [Universidad Nacional Autonoma de Mexico, Departamento de Sistemas Energeticos, Facultad de Ingenieria (Mexico)

    2014-07-01

    Three scenarios of electricity expansion planning were developed to analyze nuclear technology's contributions to the socioeconomic development, mitigation of global climate change and energy security. The scenarios were developed based on minimal cost optimization satisfying the energy demand and the non-fossil electricity targets established by the Mexican National Energy Strategy (MexNES) of no more than 65% of annual electricity production using fossil fuels by 2024 and drop down to 60% by 2035. Special attention was paid to wind and nuclear as clean energy options to produce electricity. An analysis decision based on the Position Vector of Minimum Regret was applied to rank the different plans in terms of the criteria. Results showed that nuclear power must definitely participate in the Mexican electricity expansion in order to meet the goals of clean energy set by the MexNES. (author)

  19. Releases of radioactive substances from Swedish nuclear power plants (RAKU)

    Energy Technology Data Exchange (ETDEWEB)

    Ingemansson, T.; Bergstroem, C. [ALARA Engineering AB, Skultuna (Sweden)

    1997-04-01

    Releases of radioactivity to air and water from Swedish nuclear power plants have been studied and compared with those from foreign reactors. Averaged over the years from commissioning of the reactors to the last year data are available, the release of radioactive noble gas from the Swedish BWRs has been about the same as from comparable foreign reactors. The oldest Swedish BWRs, Oskarshamn 1 and 2 (O1 and O2) and Ringhals 1 (R1), have simple off-gas systems with only one delay volume. All BWRs in US, Germany, Japan and Switzerland are equipped with more sophisticated off-gas systems. It can be expected that O1, O2 and R1 therefore will have the highest release of noble gas activity at an international comparison if they do not modernize their off-gas system. BWRs in US, Germany and Japan are today equipped with recombiners and with one exception also charcoal columns. Japanese BWRs report zero releases to air. Releases of radioactivity to water after commissioning was about the same for most of the studied reactors. Some of the newest German plants have had low annual releases already at commissioning. Improvements of the treatment systems at old German, Swiss and US reactors have significantly lowered the releases. For most of the Swedish plants the annual releases to water have remained at the initial level. Forsmark 3 has succeeded in decreasing the release of radionuclides to water by a factor of almost one hundred compared to other Swedish reactors. Also O3 has managed to decrease the liquid effluents. Japanese plants have zero release of radioactivity excluding tritium to water. The release of tritium is about the same for all reactors of the same type in the world. 35 refs, 31 figs, 24 tabs.

  20. Method of reducing the radioactivity in nuclear power plants

    International Nuclear Information System (INIS)

    Ohashi, Kenya; Honda, Takashi; Furutani, Yasumasa; Kashimura, Eiji; Minato, Akira; Osumi, Katsumi.

    1986-01-01

    Purpose: To reduce the radioactivity in nuclear power plants in contact with pure water at high temperature and high pressure. Method: For suppressing the deposition of radioactive materials in nuclear reactor coolants to the structural materials, oxide layers which are relatively porous but have a sufficient layer thickness are formed as the primary treatment and then thin but dense layers are formed as the secondary treatment. Oxidization is applied by means of heated water or steams with less oxidizing property in the first treatment, while oxidizing treatment is applied with heated water and steams at high oxidizing property in the second treatment, because the effect of suppressing corrosion is insufficient only by means of the membranes in the primary treatment, while the layers formed by the secondary treatment alone are liable to be injured and degraded. Since coolants for use in BWR type reactors usually contain about 200 ppb of dissolved oxygen, it is desirably from 40 to 100 ppb for the primary treatment and from 400 ppb to 8 ppb for the secondary treatment, and non-oxidating heated gases at high purity such as Ar, N 2 , He may be used in addition to heated water and steams. (Kawakami, Y.)

  1. Experience with radioactive waste incineration at Chalk River Nuclear Laboratories

    International Nuclear Information System (INIS)

    Le, V.T.; Beamer, N.V.; Buckley, L.P.

    1988-06-01

    Chalk River Nuclear Laboratories is a nuclear research centre operated by Atomic Energy of Canada Limited. A full-scale waste treatment centre has been constructed to process low- and intermediate-level radioactive wastes generated on-site. A batch-loaded, two-stage, starved-air incinerator for solid combustible waste is one of the processes installed in this facility. The incinerator has been operating since 1982. It has consistently reduced combustible wastes to an inert ash product, with an average volume reduction factor of about 150:1. The incinerator ash is stored in 200 L drums awaiting solidification in bitumen. The incinerator and a 50-ton hydraulic baler have provided treatment for a combined volume of about 1300 m 3 /a of solid low-level radioactive waste. This paper presents a review of the performance of the incinerator during its six years of operation. In addition to presenting operational experience, an assessment of the starved-air incineration technique will also be discussed

  2. Changing methodology for measuring airborne radioactive discharges from nuclear facilities

    International Nuclear Information System (INIS)

    Glissmeyer, J.A.; Ligotke, M.W.

    1995-05-01

    The US Environmental Protection Agency (USEPA) requires that measurements of airborne radioactive discharges from nuclear facilities be performed following outdated methods contained in the American National Standards Institute (ANSI) N13.1-1969 Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities. Improved methods are being introduced via two paths. First, the ANSI standard is being revised, and second, EPA's equivalency granting process is being used to implement new technology on a case-by-case or broad basis. The ANSI standard is being revised by a working group under the auspices of the Health Physics Society Standards Committee. The revised standard includes updated methods based on current technology and a performance-based approach to design. The performance-based standard will present new challenges, especially in the area of performance validation. Progress in revising the standard is discussed. The US Department of Energy recently received approval from the USEPA for an alternate approach to complying with air-sampling regulations. The alternate approach is similar to the revised ANSI standard. New design tools include new types of sample extraction probes and a model for estimating line-losses for particles and radioiodine. Wind tunnel tests are being performed on various sample extraction probes for use at small stacks. The data show that single-point sampling probes are superior to ANSI-Nl3.1-1969 style multiple-point sample extraction probes

  3. National audit of radioactivity measurements in Nuclear Medicine Centres

    International Nuclear Information System (INIS)

    Ravindra, Anuradha; Kulkarni, D.B.; Joseph, Leena; Babu, D.A.R.

    2014-01-01

    Routine activity measurements of radiopharmaceutical solutions in Nuclear Medicine Centres (NMC) are carried out with the help of radionuclide calibrators (RC). These solutions are either ingested or injected to the patient for diagnosis or therapy. However, for the realization of an optimized examination, the activity of these radiopharmaceuticals must be determined accurately before administering it to patients. The primary standards are maintained by Radiation Standards Section, Radiological Physics and Advisory Division. National audit programmes of Iodine -131 activity measurements with RCs are conducted biannually to establish traceability to national standards and to check the status of nuclear medicine practice followed at the NMC. The results of fifteenth audit of 131 I activity measurements with RC are presented in this paper. Questionnaires were sent to two hundred and thirty three NMCs in-the country. One hundred and nine NMC's agreed for participation and accordingly, glass vials containing radioactive 131 I solution of nominal activity of 100 MBq were procured from Board of Radiation and Isotope Technology, Mumbai. The radioactivity in each vial was determined with high pressure re-entrant gamma ionisation chamber (GIC), a secondary standard maintained by this laboratory. The sensitivity coefficient of GIC is traceable to the primary standard. The standardized radioactive solution of 131 I in glass vial was sent to each participant. Measurements results were reported in the reporting form sent. This audit was conducted in four schedules in Jan 2013. One hundred and sixty six results were received from one hundred and nine participants as many participants took measurements on more than one isotope calibrator

  4. Incineration plant for radioactive waste at the Nuclear Research Center Karlsruhe

    International Nuclear Information System (INIS)

    Baehr, W.; Hempelmann, W.; Krause, H.

    1977-02-01

    In 1971 a large incineration plant started operation in the Nuclear Research Center Karlsruhe. This plant is serving for routine incineration of up to 100 kg of combustible radioactive solids or 40 l of contaminated organic liquids and oils per hour. A dry off-gas cleaning system has been developed for this installation in which the flue gases are cleaned by ceramic filter candles. After passing the filtering system and cooling the off-gas is discharged directly through a stack. The activity concentration in the off-gas is measured by a continuous monitoring system. The ashes arising from the incineration are mixed with cement grout and filled into 200 ldrums. By this way approximately one drum of fixed ashes results from 100 drums of combustible wastes. During the first four years of operation, more than 4,000 m 3 of combustible solids and about 60 m 3 organic solvents have been incinerated in the plant. The operating experiences are presented. (orig.) [de

  5. Nuclear structure and radioactive decay resources at the US National Nuclear Data Center

    International Nuclear Information System (INIS)

    Sonzogni, A.A.; Burrows, T.W.; Pritychenko, B.; Tuli, J.K.; Winchell, D.F.

    2008-01-01

    The National Nuclear Data Center has a long tradition of evaluating nuclear structure and decay data as well as offering tools to assist in nuclear science research and applications. With these tools, users can obtain recommended values for nuclear structure and radioactive decay observables as well as links to the relevant articles. The main databases or tools are ENSDF, NSR, NuDat and the new Endf decay data library. The Evaluated Nuclear Structure Data File (ENSDF) stores recommended nuclear structure and decay data for all nuclei. ENSDF deals with properties such as: -) nuclear level energies, spin and parity, half-life and decay modes, -) nuclear radiation energy and intensity for different types, -) nuclear decay modes and their probabilities. The Nuclear Science References (NSR) is a bibliographic database containing nearly 200.000 nuclear sciences articles indexed according to content. About 4000 are added each year covering 80 journals as well as conference proceedings and laboratory reports. NuDat is a software product with 2 main goals, to present nuclear structure and decay information from ENSDF in a user-friendly way and to allow users to execute complex search operations in the wealth of data contained in ENSDF. The recently released Endf-B7.0 contains a decay data sub-library which has been derived from ENSDF. The way all these databases and tools have been offered to the public has undergone a drastic improvement due to advancements in information technology

  6. Incinerators for radioactive wastes in Japanese nuclear power stations

    International Nuclear Information System (INIS)

    Karita, Yoichi

    1983-01-01

    As the measures of treatment and disposal of radioactive wastes in nuclear power stations, the development of the techniques to decrease wastes, to reduce the volume of wastes, to treat wastes by solidification and to dispose wastes has been advanced energetically. In particular, efforts have been exerted on the volume reduction treatment from the viewpoint of the improvement of storage efficiency and the reduction of transport and disposal costs. Incineration as one of the volume reduction techniques has been regarded as the most effective method with large reduction ratio, but it was not included in waste treatment system. NGK Insulators Ltd. developed NGK type miscellaneous solid incinerators, and seven incinerators were installed in nuclear power stations. These incinerators have been operated smoothly, and the construction is in progress in six more plants. The necessity of incinerators in nuclear power stations and the problems in their adoption, the circumstance of the development of NGK type miscellaneous solid incinerators, the outline of the incinerator of Karlsruhe nuclear power station and the problems, the contents of the technical development in NGK, the outline of NGK type incinerators and the features, the outline of the pretreatment system, incinerator system, exhaust gas treatment system, ash taking out system and accessory equipment, the operational results and the performance are described. (Kako, I.)

  7. Laser enhanced radioactive decay and selective transmutation of nuclear waste

    International Nuclear Information System (INIS)

    Saloman, R.; Aarnio, P.; Ala-Heikkila, J.; Hakola, A.; Santala, M.

    2007-01-01

    We have investigated narrow-band coherent laser radiation - ranging from visible to X- and to gamma-ray wave length region - and their interactions both directly with photon-nuclear couplings and indirectly through the photon-electron and electron-nucleus interactions. In particular we discuss various means of selective excitation of nuclear resonance states by narrowband lasers. During the relaxation process the active nucleus may return to its initial ground-state or find another final state. In the latter case the nucleus is transmuted into a state which may have beneficial properties for instance concerning radioactivity. One ideal case would be the destruction of long-lived nuclear waste isotopes into faster decaying ones. The essential presumption is that the excitation process is selective and efficient as regards background processes due to unwanted excitation channels of the primary isotope and due to other surrounding nuclides. The paper consists of 1) a short review of generating short-wave length coherent light sources, 2) a survey of potential photon-induced nuclear states and their decay channels, and 3) a determination of the selectivity of the transmutation process

  8. New Horizon in Nuclear Physics and Astrophysics Using Radioactive Nuclear Beams

    Science.gov (United States)

    Tanihata, Isao

    Beams of β- radioactive nuclei, having a lifetime as short as 1 ms have been used for studies of the nuclear structure and reaction relevant to nucleosynthesis in the universe. In nuclear-structure studies, decoupling of the proton and neutron distributions in nuclei has been discovered. The decoupling appeared as neutron halos and neutron skins on the surface of neutron-rich unstable nuclei. In astrophysics, reaction cross sections have been determined for many key reactions of nucleosynthesis involving short-lived nuclei in the initial and final states. One such important reaction, 13N+p → 14O +γ, has been studied using beams of unstable 13N nuclei. Such studies became possible after the invention of beams of radioactive nuclei in the mid-80's. Before that, the available ion beams were restricted to ions of stable nuclei for obvious reasons. In the next section the production method of radioactive beams is presented, then a few selected studies using radioactive beams are discussed in the following sections. In the last section, some useful properties of radioactive nuclei for other applications is shown.

  9. Radioactive waste: the Nuclear Industry's response to the Environment Committee's report

    International Nuclear Information System (INIS)

    1986-07-01

    This paper represents the nuclear industry's response to the Environmental Committee's report on the handling and disposal of radioactive wastes. Topics covered include the historical aspects of the management of radioactive wastes, technical problems, comparisons with overseas management methods, liquid effluents, reprocessing problems, and public attitudes and perceptions of radioactive waste. Responses to the Environmental Committee's recommendations form an appendix. (U.K.)

  10. Management of radioactive waste at INR-technical support for processing of radioactive waste from nuclear facilities

    International Nuclear Information System (INIS)

    Bujoreanu, D.; Popescu, I.V.; Bujoreanu, L.

    2009-01-01

    The Institute for nuclear research (INR) subsidiary of the Romanian authority for nuclear activities has its own radwaste treatment plant (STDR). STDR is supposed to treat and condition radioactive waste from the nuclear fuel facility, the TRIGA reactor, post irradiation examination laboratories and other research laboratories of NRI. The main steps of waste processing are: pretreatment (collection, characterization, segregation, decontamination)., treatment (waste volume reduction, radionuclide removal, compositional change), conditioning (immobilization and containerization), interim storage of the packages in compliance with safety requirements for the protection of human health and environmental protection, transport of the packages containing radioactive waste, disposal.

  11. Quality assurance for radioactive measurement in nuclear medicine

    International Nuclear Information System (INIS)

    2006-01-01

    The field of nuclear medicine continues to grow around the world, owing in part to a number of successful programmes carried out by the IAEA to enhance the use of nuclear medicine techniques in Member States. The implementation of quality assurance (QA) programmes to ensure the safe application of radiopharmaceuticals has, however, been variable in many Member States. One possible reason is the lack of a unified set of principles regarding the establishment of such programmes. This publication addresses the issue of QA programmes for radioactivity measurement in nuclear medicine. A group of experts consulted by the IAEA recommended in 2002 that unified principles concerning QA and quality control (QC) procedures for the measurement of radioactivity in nuclear medicine be developed because of its importance in controlling the safety and effectiveness of the use of radiopharmaceuticals. This publication is the result of advice provided to the IAEA by experts in the fields of radionuclide metrology, medical physics and radiopharmacy. This report can be considered to be a more detailed and updated version of IAEA-TECDOC-602, Quality Control of Nuclear Medicine Instruments, published in 1991. Advances in the field of nuclear instrumentation since that report was published, particularly in imaging, and the increased emphasis on QA and QC prompted the need for an update. Moreover, it was realized that the activity measurement and imaging aspects had each become so specialized as to be better treated in separate publications. The present report focuses on the factors affecting radioactivity measurement and the implementation of QA and QC programmes to ensure accurate and consistent results. The IAEA has developed a safety standard on The Management System for Facilities and Activities (IAEA Safety Standards Series No. GS-R-3), which replaces the IAEA publications on QA issued as Safety Series No. 50-C/SG-Q (1996). In GS-R-3, the management system is described as a set of

  12. What are Spent Nuclear Fuel and High-Level Radioactive Waste?

    International Nuclear Information System (INIS)

    2002-01-01

    Spent nuclear fuel and high-level radioactive waste are materials from nuclear power plants and government defense programs. These materials contain highly radioactive elements, such as cesium, strontium, technetium, and neptunium. Some of these elements will remain radioactive for a few years, while others will be radioactive for millions of years. Exposure to such radioactive materials can cause human health problems. Scientists worldwide agree that the safest way to manage these materials is to dispose of them deep underground in what is called a geologic repository

  13. Storage, handling and internal transport of radioactive materials (fuel elements excepted) in nuclear power plants

    International Nuclear Information System (INIS)

    1983-06-01

    The rule applies to storage and handling as well as to transport within the plant and to the exchange of - solid radioactive wastes, - liquid radioactive wastes, except for those covered by the rule KTA 3603, - radioactive components and parts which are planned to be mounted and dismounted until shutdown of the plant, - radioactive-contaminated tools and appliances, - radioactive preparations. The rule is to be applied within the fenced-in sites of stationary nuclear power plants with LWR or HTR including their transport load halls, as fas as these are situated so as to be approachable from the nuclear power station by local transport systems. (orig./HP) [de

  14. SCOPE-RADTEST: Radioactivity from nuclear test explosions

    International Nuclear Information System (INIS)

    Shapiro, C.S.; Tsaturov, Y.

    1993-10-01

    The SCOPE-RADTEST program consists of an international collaborative study involving Russia, the USA, China, and Kazakhstan. It will focus on the releases of radioactivity that resulted from nuclear test explosions that have taken place at various test sites around the world for peaceful and military purposes. RADTEST will focus on these principal tasks: (1) To inventory data on measurements of radionuclide deposition densities, and identify gaps in these data. (2) To compare old and develop new models of radioactive transport to better understand the deposition densities of radionuclides both on and near the nuclear test sites, including areas downwind where potentially significant episodes of fallout have occurred (such as the Altaj Region of Russia). (3) To study the migration of the radionuclides through the biosphere, including all pathways to humans. This will include the study of the effects on other biota that have impacts on humans. The main focus will be to characterize the nature and magnitude of the dose to humans. This will include dose reconstructions from past events, and also an increased capability for dose prediction from possible future accidental or deliberate explosions. (4)To analyze the data on the effects of these doses (including low doses) on human health. The test sites to be studied would include the Nevada Test Site (USA), South Pacific Islands (USA), Novaja Zemla (Russia), Semipalatinsk (Kazakhstan) and Luc Bu Pu (Lop Nor) (China). Tests at these sites include most of the total of nuclear explosions that have been conducted. Other sites, (including the sites of the U.K. and France), as appropriate, may also be included where tests were conducted for peaceful or military purposes

  15. Air-cleaning philosophy in a nuclear-materials fabrication plant

    International Nuclear Information System (INIS)

    Ward, F.Y.; Yoder, R.E.

    1982-01-01

    At the Department of Energy's Rocky Flats Plant there is a major ventilation improvement project underway. To achieve the desired goals of ALARA regarding radioactivity and toxic material releases and natural phenomena insults, a comprehensive air-cleaning philosophy and policy statement was developed. Design of the upgraded systems were evaluated against these statements and we believe that upon completion of the projects that an efficient system will be demonstrated. the design permits reuse and heat recovery of ventilation air, the optimization of sampling points to reduce analytical laboratory services. This paper discusses the basis of the philosophy and the engineering features incorporated to meet this stated objective. Points of compromise are noted

  16. Radioactivity monitoring programme of Krsko nuclear power plant

    International Nuclear Information System (INIS)

    Miklavzic, U.; Martincic, R.; Kanduc, M.; Lulic, S.; Kovac, J.; Breznik, B.

    1996-01-01

    As a successor to the preoperational surveillance programme, the regular offsite radioactivity monitoring programme (RMP) of the Krsko Nuclear Power Plant (NPP) was implemented in 1982, when the power plant formally commenced operating. Observations collected during the first years of its operation were later also the basis for setting up the official 'Regulatory guide on monitoring of nuclear installations', issued not earlier than in 1986. The basic criterion which governed the selection of measuring methods, sampling techniques and locations, was the extent to which the data obtained could serve for the realistic assessment of the committed dose to a member of the population, and later on to members of a representative (critical) group. To be able to differentiate the radioactivity released through the liquid and gaseous effluents of the NPP from other radiation sources (natural radioactivity, global contamination), and especially because of the varying radiotoxicity of different radionuclides, in principle monitoring in the environment, as at the source, had to provide activity data for each individual radionuclide appearing in the effluents. Therefore, as early as 1982 the programme attributed the main weight to high resolution gamma spectrometry, combined with specific radiochemical analytical methods (e.g. 90 Sr/ 89 Sr, 3 H, 14 C, alpha spectrometry of Pu isotopes) which together made feasible determination of individual specific activities of the most significant man-made and natural radionuclides. By weighting the specific activities of the radionuclides identified and measured in the media surveyed by dose factors for intake, the quantity 'B' - the so-called 'radiological burden', was calculated and introduced in the yearly-summary tables. Expressed in relative units, from which the committed dose could be readily calculated, the burden B very lucidly disclosed the relative importance of different artificial pollutants and natural radioactivity present in

  17. Intake of radioactivity by inhalation, in buildings after nuclear incidents

    International Nuclear Information System (INIS)

    Brenk, H.D.

    1987-01-01

    Risk studies so far assumed that in case of a nuclear incident, the exposure of persons through inhalation proceeds in free air by direct intake of contaminated ambient air. In reality, however, about 80 p.c. of the population is indoors, and there is a considerable delay of room air contamination in comparison with free air contamination. The radionuclides are deposited on indoor surfaces (such as walls, windows, furniture, etc.), and in air-conditioning systems on the filters. This contamination is somewhat regularly removed through cleaning or filter exchange, which reduces the contamination of room air, and then also the radiation exposure by inhalation. The reducing effect can be enhanced by such simple measures as closing doors and windows in time, and switching the air-conditioning system to recirculating regime, followed by enhanced fresh air supply at a later time. (orig./HP) [de

  18. A comparative study on laser induced shock cleaning of radioactive contaminants in air and water

    Science.gov (United States)

    Kumar, Aniruddha; Prasad, Manisha; Bhatt, R. B.; Behere, P. G.; Biswas, D. J.

    2018-03-01

    Efficient removal of Uranium-di-oxide (UO2) particulates from stainless steel surface was effected by Nd-YAG laser induced plasma shock waves in air as well as in water environment. The propagation velocity of the generated shock wave was measured by employing the photo-acoustic probe deflection method. Monitoring of the alpha activity of the sample with a ZnS (Ag) scintillation detector before and after the laser exposure allowed the estimation of decontamination efficiency defined as the percentage removal of the initial activity. Experiments were carried out to study the effect of laser pulse energy, number of laser exposures, orientation of the sample, the separation between the substrate surface and the onset point of the shock wave on the de-contamination efficiency. The most optimised cleaning was found to occur when the laser beam impinged normally on the sample that was immersed in water and placed at a distance of ∼0.7 mm from the laser focal spot. Analysis of the cleaned surface by optical microscopes established that laser induced shock cleaning in no way altered the surface property. The shock force generated in both air and water has been estimated theoretically and has been found to exceed the Van der Waal's binding force for spherical contaminant particulate.

  19. Chemical mode control in nuclear power plant decommissioning during operation of technologies in individual radioactive waste processing plants

    International Nuclear Information System (INIS)

    Horvath, J.; Dugovic, L.

    1999-01-01

    Sewage treatment of nuclear power plant decommissioning is performed by system of sewage concentration in evaporator with formation of condensed rest, it means radioactive waste concentrate and breeding steam. During sewage treatment plant operation department of chemical mode performs chemical and radiochemical analysis of sewage set for treatment, chemical and radiochemical analysis of breeding steam condensate which is after final cleaning on ionization filter and fulfilling the limiting conditions released to environment; chemical and radiochemical analysis of heating steam condensate which is also after fulfilling the limiting conditions released to environment. Condensed radioactive concentrate is stored in stainless tanks and later converted into easy transportable and chemically stable matrix from the long term storage point of view in republic storage Mochovce. The article also refer to bituminous plant, vitrification plant, swimming pool decontamination plant of long term storage and operation of waste processing plant Bohunice

  20. Disposal of radioactive wastes from Czechoslovak nuclear power plants

    International Nuclear Information System (INIS)

    Neumann, L.

    In gaseous radioactive waste disposal, aerosol particles are filtered and gaseous wastes are discharged in the environment. The filters and filter materials used are stored on solid radioactive waste storage sites in the individual power plants. Liquid radioactive wastes are concentrated and the concentrates are stored. Distillates and low-level radioactive waste water are discharged into the hydrosphere. Solid radioactive wastes are stored without treatment in power plant bunkers. Bituminization and cementation of liquid radioactive wastes are discussed. (H.S.)

  1. Institutional radioactive waste management in the Nuclear Research Institute Rez plc

    International Nuclear Information System (INIS)

    Kovarik, P.; Svoboda, K.; Podlaha, J.

    2008-01-01

    Nuclear research institute Rez, plc. (mentioned below as NRI) has had a dominant position in the area of the nuclear research and development in the Czech Republic, the Central and the Eastern Europe. Naturally, the radioactive waste management is an integral part of the nuclear industry, research and development. For that reason, there is Centre of the radioactive waste management (mentioned below as Centre) in the NRI. This Centre is engaged in the radioactive waste treatment, decontamination, characterisation, decommissioning and other relevant activities. This paper describes the system of technology and other information about institutional radioactive waste management in the NRI. (authors)

  2. International guidance on the establishment of quality assurance programmes for radioactivity measurement in nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Zimmerman, B.E. [Dosimetry and Medical Radiation Physics Section, Division of Human Health, International Atomic Energy Agency, Wagramer Strasse 5, P.O. Box 200, A-1400 Vienna (Austria)]. E-mail: b.zimmerman@iaea.org; Herbst, C. [Department of Medical Physics, University of the Free State, Geneeskundige Fisika G 68, Bloemfontein 9300 (South Africa); Norenberg, J.P. [College of Pharmacy, 2502 Marble, NE MSC09 5360, University of New Mexico, Albuquerque 87131 (United States); Woods, M.J. [Ionizing Radiation Consultants, Ltd., 152 Broom Road, Teddington, Middlesex TW11 9PQ (United Kingdom)

    2006-10-15

    A new guidance document for the implementation of quality assurance (QA) programmes for nuclear medicine radioactivity measurement, produced by the International Atomic Energy Agency, is described. The proposed programme is based on the principles of ISO 17025 and will enable laboratories, particularly in developing countries, to provide consistent, safe and effective radioactivity measurement services to the nuclear medicine community.

  3. International guidance on the establishment of quality assurance programmes for radioactivity measurement in nuclear medicine

    International Nuclear Information System (INIS)

    Zimmerman, B.E.; Herbst, C.; Norenberg, J.P.; Woods, M.J.

    2006-01-01

    A new guidance document for the implementation of quality assurance (QA) programmes for nuclear medicine radioactivity measurement, produced by the International Atomic Energy Agency, is described. The proposed programme is based on the principles of ISO 17025 and will enable laboratories, particularly in developing countries, to provide consistent, safe and effective radioactivity measurement services to the nuclear medicine community

  4. Manual of use and accounting of radioactive material and procedures of radiological protection for nuclear medicine

    International Nuclear Information System (INIS)

    Chavez, Miguel

    1997-03-01

    This manual of use and accounting of material radioactive and procedures of radiological safety tries to facilitate workings of protection of material radioactive in services of medicine nuclear, during diagnosis (examinations with x-rays, or those that are made in nuclear medicine), or during the processing of diseases, mainly of the carcinomas (x-ray)

  5. Establishment of a clean laboratory for ultra trace analysis of nuclear materials in safeguards environmental samples

    International Nuclear Information System (INIS)

    Hanzawa, Yukiko; Magara, Masaaki; Watanabe, Kazuo

    2003-01-01

    The Japan Atomic Energy Research Institute has established a cleanroom facility with cleanliness of ISO Class 5: the Clean Laboratory for Environmental Analysis and Research (CLEAR). It was designed to be used for the analysis of nuclear materials in environmental samples mainly for the safeguards, in addition to the Comprehensive Nuclear-Test-Ban Treaty verification and research on environmental sciences. The CLEAR facility was designed to meet conflicting requirements of a cleanroom and for handling of nuclear materials according to Japanese regulations, i.e., to avoid contamination from outside and to contain nuclear materials inside the facility. This facility has been intended to be used for wet chemical treatment, instrumental analysis and particle handling. A fume-hood to provide a clean work surface for handling of nuclear materials was specially designed. Much attention was paid to the selection of construction materials for use to corrosive acids. The performance of the cleanroom and analytical background in the laboratory are discussed. This facility has satisfactory specification required for joining the International Atomic Energy Agency Network of Analytical Laboratories. It can be concluded that the CLEAR facility enables analysis of ultra trace amounts of nuclear materials at sub-pictogram level in environmental samples. (author)

  6. Underground Nuclear Explosions and Release of Radioactive Noble Gases

    Science.gov (United States)

    Dubasov, Yuri V.

    2010-05-01

    Over a period in 1961-1990 496 underground nuclear tests and explosions of different purpose and in different rocks were conducted in the Soviet Union at Semipalatinsk and anovaya Zemlya Test Sites. A total of 340 underground nuclear tests were conducted at the Semipalatinsk Test Site. One hundred seventy-nine explosions (52.6%) among them were classified as these of complete containment, 145 explosions (42.6%) as explosions with weak release of radioactive noble gases (RNG), 12 explosions (3.5%) as explosions with nonstandard radiation situation, and four excavation explosions with ground ejection (1.1%). Thirty-nine nuclear tests had been conducted at the Novaya Zemlya Test Site; six of them - in shafts. In 14 tests (36%) there were no RNG release. Twenty-three tests have been accompanied by RNG release into the atmosphere without sedimental contamination. Nonstandard radiation situation occurred in two tests. In incomplete containment explosions both early-time RNG release (up to ~1 h) and late-time release from 1 to 28 h after the explosion were observed. Sometimes gas release took place for several days, and it occurred either through tunnel portal or epicentral zone, depending on atmospheric air temperature.

  7. High-spin nuclear structure studies with radioactive ion beams

    International Nuclear Information System (INIS)

    Baktash, C.

    1992-01-01

    Two important developments in the sixties, namely the advent of heavy-ion accelerators and fabrication of Ge detectors, opened the way for the experimental studies of nuclear properties at high angular momentum. Addition of a new degree of freedom, namely spin, made it possible to observe such fascinating phenomena as occurrences and coexistence of a variety of novel shapes, rise, fall and occasionally rebirth of nuclear collectivity, and disappearance of pairing correlations. Today, with the promise of development of radioactive ion beams (RIB) and construction of the third-generation Ge-detection systems (GAMMASPHERE and EUROBALL), nuclear physicists are poised to explore new and equally fascinating phenomena that have been hitherto inaccessible. With the addition of yet another dimension, namely the isospin, they will be able to observe and verify predictions for exotic shapes as varied as rigid triaxiality, hyperdeformation and triaxial-octupole shapes, or to investigate the T=O pairing correlations. In this paper, the author reviews, separately for neutron-deficient and neutron-rich nuclei, these and a few other new high-spin physics opportunities that may be realized with RIB. Following this discussion, a list of the beam species, intensities and energies that are needed to fulfill these goals is presented. The paper concludes with a description of the experimental techniques and instrumentations that are required for these studies

  8. Radioactive contamination of oil produced from nuclear-broken shale

    International Nuclear Information System (INIS)

    Arnold, W.D.; Crouse, D.J.

    1970-01-01

    The results of small-scale exposure and retorting tests indicate that oil recovered from shale that has been broken with nuclear explosives will be contaminated with tritium. When oil shale was heated in sealed flasks with tritiated water vapor or with tritiated hydrogen, both the shale and the oil subsequently retorted from the shale contained tritium. There was much less contamination of the shale or oil, however, when the shale was exposed to tritiated methane and ethane. Contamination of shale and oil with tritium, as the result, of exposure to tritiated water, increased as the exposure temperature, exposure pressure, and the tritium concentration in the water were increased. This contamination also increased as the exposure time was increased up to 25 days, but not significantly thereafter. More than 90% of the tritium was removed from contaminated shale by treating the shale with moist air at elevated temperatures. Only small amounts of the tritium were removed from crude oil by contacting it with solid drying agents or with water. When tritium-contaminated shale oil was distilled, the tritium contents of the recovered fractions were found to be approximately equal. After being heated with a sample of underground test-shot debris, liquid shale oil became contaminated with radioactive fission products. Most of the radioactivity of the oil was due to finely dispersed solids rather than to dissolved radionuclides. Filtration of the oil removed a major fraction of the radioactive material. When the contaminated oil was distilled, more than 99% of the radionuclides remained in the pot residue. (author)

  9. The liquidation of liquid radioactive waste on nuclear medicine departments

    International Nuclear Information System (INIS)

    Fueriova, A.

    1995-01-01

    The most serious problems for Clinic of Nuclear Medicine of National Oncological Institute, Bratislava (CNM) is the localization of CNM in the downtown, inside the hospital area with the dilution water deficit. This department is the only one in Slovak Republic performing therapeutical applications. To be able to perform the necessary amount of therapies and also to introduce a new therapeutical methods, in 1992-1994 the old liquidation waste disposal station (LWDS) was reconstructed with the aim to satisfy the newest requirements of radiation hygiene. LWDS is the 5-floor object partly underground which satisfied the requirements for liquidation of radioactive liquid waste from diagnostic procedures(annually 5000 patients) and also from 200 therapeutical applications annually (15 beds, 720 GBq iodine-131). The capacity of LWDS is able to store about 90 m 3 liquid radioactive waste. Part of the underground spaces are used for the storage of solid radioactive trash. The liquid waste from CNM is collected through isolated metal sewage system to the storage with continuous observation of water specific activity. According to the activity, the liquid waste is placed to the 5 decay storages with the volume about 15 m 3 . The six one serves for the case of technical accident. When the activity declines, the liquid waste is diluted with non active medical trash to the level which is acceptable by low about radiation hygiene protection. The storage walls are made from barium-concrete 25-50 cm thick which is enough for sufficient protection of operation staff and also for walking around persons. Double-layer high quality chemical material prevents the water leak and diffusion of radionuclides into the concrete. Technology consists of cast-iron drains, powerful slush pumps, operation valves, regulation technology from dosimetric system for continuous monitoring of specific activity, for managing system with powerful industrial computer

  10. The liquidation of liquid radioactive waste on nuclear medicine departments

    Energy Technology Data Exchange (ETDEWEB)

    Fueriova, A [National Oncological Institue, Bratislava (Slovakia). Hospital St. Elis, Clinic of Nuclear Medicine

    1996-12-31

    The most serious problems for Clinic of Nuclear Medicine of National Oncological Institute, Bratislava (CNM) is the localization of CNM in the downtown, inside the hospital area with the dilution water deficit. This department is the only one in Slovak Republic performing therapeutical applications. To be able to perform the necessary amount of therapies and also to introduce a new therapeutical methods, in 1992-1994 the old liquidation waste disposal station (LWDS) was reconstructed with the aim to satisfy the newest requirements of radiation hygiene. LWDS is the 5-floor object partly underground which satisfied the requirements for liquidation of radioactive liquid waste from diagnostic procedures(annually 5000 patients) and also from 200 therapeutical applications annually (15 beds, 720 GBq iodine-131). The capacity of LWDS is able to store about 90 m{sup 3} liquid radioactive waste. Part of the underground spaces are used for the storage of solid radioactive trash. The liquid waste from CNM is collected through isolated metal sewage system to the storage with continuous observation of water specific activity. According to the activity, the liquid waste is placed to the 5 decay storages with the volume about 15 m{sup 3}. The six one serves for the case of technical accident. When the activity declines, the liquid waste is diluted with non active medical trash to the level which is acceptable by low about radiation hygiene protection. The storage walls are made from barium-concrete 25-50 cm thick which is enough for sufficient protection of operation staff and also for walking around persons. Double-layer high quality chemical material prevents the water leak and diffusion of radionuclides into the concrete. Technology consists of cast-iron drains, powerful slush pumps, operation valves, regulation technology from dosimetric system for continuous monitoring of specific activity, for managing system with powerful industrial computer.

  11. Radioactive contamination of oil produced from nuclear-broken shale

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, W D; Crouse, D J

    1970-05-15

    The results of small-scale exposure and retorting tests indicate that oil recovered from shale that has been broken with nuclear explosives will be contaminated with tritium. When oil shale was heated in sealed flasks with tritiated water vapor or with tritiated hydrogen, both the shale and the oil subsequently retorted from the shale contained tritium. There was much less contamination of the shale or oil, however, when the shale was exposed to tritiated methane and ethane. Contamination of shale and oil with tritium, as the result, of exposure to tritiated water, increased as the exposure temperature, exposure pressure, and the tritium concentration in the water were increased. This contamination also increased as the exposure time was increased up to 25 days, but not significantly thereafter. More than 90% of the tritium was removed from contaminated shale by treating the shale with moist air at elevated temperatures. Only small amounts of the tritium were removed from crude oil by contacting it with solid drying agents or with water. When tritium-contaminated shale oil was distilled, the tritium contents of the recovered fractions were found to be approximately equal. After being heated with a sample of underground test-shot debris, liquid shale oil became contaminated with radioactive fission products. Most of the radioactivity of the oil was due to finely dispersed solids rather than to dissolved radionuclides. Filtration of the oil removed a major fraction of the radioactive material. When the contaminated oil was distilled, more than 99% of the radionuclides remained in the pot residue. (author)

  12. Environmental radioactivity at the National Nuclear Research Centre, Pelindaba

    International Nuclear Information System (INIS)

    Brits, R.J.N.; Van der Westhuizen, G.S.H.; Annandale, J.

    1983-06-01

    The revised environmental survey program, introduced during 1970 with the emphasis on monitoring of the critical paths of exposure of the general public, was continued in 1982. Results of determinations of both gross radioactivity and individual nuclides in samples of fish and water (which are critical materials for liquid-effluent releases) from the Hartebeespoort Dam and from the Crocodile River, are given and discussed. Results of 131 I, 90 Sr and gamma-spectrometric analyses of milk, the critical material for releases to the atmosphere, are presented. Results are given of regular investigations of the composition of airborne releases to the atmosphere and liquid-effluent releases to the Crocodile River, performed in order to detect other possible critical nuclides. Levels of deposited and airborne activity from nuclear-bomb tests are reported. Due to absence of fresh fallout material the levels for most fission products have fallen below the limit of detection. No environmental radioactivity due to releases from the Pelindaba site could be detected above the natural background or accumulated fallout levels. Unplanned releases of UF 6 occur sometimes. Accordingly, some of the environmental samples were also analysed for uranium. The results obtained so far do not indicate an increase in uranium levels in the environment

  13. Mapping the radioactive contamination in urban environments after nuclear emergencies

    International Nuclear Information System (INIS)

    Kaiser, Jan Christian; Proehl, Gerhard; Woda, Clemens

    2008-01-01

    Full text: In the event of a nuclear emergency in an urban environment a reliable overview on the radioactive contamination is crucial for decision making. To assess the radiological situation both measurements of the gamma dose or dose rate (GDR) and results from urban dispersion and deposition models are used. Measurements may arrive from various sources like car-borne detectors or man-borne radiation-sensitive materials embedded in cell phones, flash memory devices or RFID chips. The measurements depend strongly on the detector environment. To account for this dependence each signal is multiplied by a location factor, which quantifies the deviation of the recorded signal from the hypothetical signal of a reference surface of infinitely extended lawn. Furthermore, the data originate from geo-referenced points or lines but do not provide full spatial information. We present here two approaches to produce maps of the reference GDR or surface contamination in urban areas, which are implemented in the Inhabited Areas Monitoring Module (IAMM) as part of the European decision support systems RODOS and ARGOS. Immediately after the accident, a few measurements are combined with the predictions of urban models using data assimilation. If enough measurements are available they are regionalised with geo-statistical interpolation algorithms like inverse distance weighting or kriging. Both approaches are demonstrated in hypothetical scenarios based on the explosion of a radioactive dispersion device. (author)

  14. Environmental radioactivity at the National Nuclear Research Centre, Pelindaba

    International Nuclear Information System (INIS)

    Brits, R.J.N; Prinsloo, L.; De Jesus, A.S.M.

    1981-07-01

    The revised environmental survey program, introduced during 1970 with the emphasis on monitoring of the critical paths of exposure of the general public, was continued in 1980. Results of determinations of both gross radioactivity and individual nuclides in samples of fish and water (which are critical materials for liquid-effluent releases) from the Hartbeespoort Dam and from the Crocodile River, are given and discussed. Results of 131 I, 0 Sr and gamma-spectrometric analyses of milk, the critical material for releases to the atmosphere, are presented. Results are given of regular investigations of the composition of airborne releases to the atmosphere and liquid-effluent releases to the Crocodile River, performed in order to detect other possible critical nuclides. Levels of deposited and airborn activity from nuclear-bomb tests are reported. Due to the absence of fresh fallout, the levels for most fission products have fallen below the limit of detection. No environmental radioactivity resulting from NNRC releases could be detected above the natural background or accumulated fallout levels [af

  15. Radioactive contamination of copper produced using nuclear explosives

    Energy Technology Data Exchange (ETDEWEB)

    Crouse, D J; Arnold, W D; Hurst, F J

    1970-05-15

    Laboratory tests simulating the processing of copper ore after fracturing with nuclear explosives indicate that only very small fractions of the radioactive fission products will be dissolved on leaching with dilute sulfuric acid. Tritium (as tritiated water) will be by far the dominant radionuclide in the circulating leach liquor, assuming use of a fusion device. Only 106Ru appears of significant importance with respect to contamination of the cement copper. It is rejected effectively in electrolytic purification and, therefore, the final copper product should be very low in radiocontamination and not hazardous to the customer. The activity level may be high enough, however, to make the copper unsuitable for some specific uses. If necessary, solvent extraction can be used as an alternative to the cementation process to reduce the radioactivity of the copper products. The tritium in the circulating liquor and the 106Ru in the cement copper are potential hazards at the plant site and must be given consideration in designing and operating the facility. However since the activity levels will be low, the protection necessary to ensure safety of the operating personnel should be neither difficult nor costly to provide. (author)

  16. 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...

  17. Management of effluents and radioactive wastes from nuclear power plants

    International Nuclear Information System (INIS)

    2005-01-01

    Management of effluents and radioactive waste from nuclear power plants, from the viewpoint of radiological protection, basically consists of three main themes: 1) developing and implementing actions that minimize, or where possible, eliminate generation. These actions ranging from simple awareness of people involved with the work on project modifications; 2) maintain a system of accounting and control that allows to know the characteristics of effluents and wastes, charting indicators that reveal the performance and trends of plant, and supplying data proving the compliance of national regulatory body standards; 3) Storing the solid waste generated in a safe manner, ensuring that the physical integrity of the packaged is maintained and that there is no impact to the population and the environment

  18. Radiation doses to the personnel at insertion of gynaecological implants and cleaning of radioactive applicators

    International Nuclear Information System (INIS)

    Lax, I.

    1975-11-01

    The measurements of the radiation doses to the personnel consisted of dose measurements on the fingers and on the body. The radiation doses to the fingers and to different parts of the body at on one hand the insertion of gynecological implanta and on the other the cleaning of them have been measured before at the wards of gynecological application at the department of oncology (Radiumhemmet), the Caroline Institute. Thermoluminescent dosemeters were used to measure the radiation doses to the finger tips. The dimensions of these dosemeters are nowadays so small that they are no hindrance to the work. (M.S.)

  19. Radiation doses to the personnel at insertion of gynaecological implants and cleaning of radioactive applicators

    Energy Technology Data Exchange (ETDEWEB)

    Lax, I

    1975-11-01

    The measurements of the radiation doses to the personnel consisted of dose measurements on the fingers and on the body. The radiation doses to the fingers and to different parts of the body at on one hand the insertion of gynecological implanta and on the other the cleaning of them have been measured before at the wards of gynecological application at the department of oncology (Radiumhemmet), the Caroline Institute. Thermoluminescent dosemeters were used to measure the radiation doses to the finger tips. The dimensions of these dosemeters are nowadays so small that they are no hindrance to the work.

  20. Recycling of Organic Wastes to Achieve the Clean Agriculture Approach with Aid of Nuclear Techniques

    International Nuclear Information System (INIS)

    Moursy, A.A.A.

    2012-01-01

    The Objective of this current work is to study Organic matter decomposition under clean agriculture system in sandy soil using nuclear technique. This desirtatation has the following targets: - Amendment and improving sandy soil properties - Utilization of farm wastes (Recycling) in safe mode -Benefits form organic matter decomposition. - Follow up the fate of same nutrients (Nitrogen) released in soil media after organic matter (O.M) decomposition and Impact on plant nutrition status.-saving the environment on short and long run.

  1. Polypropilene nuclear track membranes - a new type of membranes for cleaning and analysis of agressive media

    International Nuclear Information System (INIS)

    Apel', P.Yu.; Shirkova, V.V.; Soboleva, T.I.; Kuznetsov, V.I.; Shestakov, V.D.

    1988-01-01

    The brief description of the polypropylene nuclear track membranes is given. The membranes are obtained from biaxially oriented polypropylene films 10μm thick by means of irradiation with accelerated heavy ions and following chemical etching. The data on pore shape, pore size dispersion, the permeability of membranes and on the content of impurities in membrane matrix are given. It is noted that the polypropylene membranes can be used for cleaning and analysis of agressive chemical species. 9 refs.; 2 figs

  2. Clean energy proposals are chance for nuclear to have rightful place at policy table

    Energy Technology Data Exchange (ETDEWEB)

    Shepherd, John [nuclear 24, Redditch (United Kingdom)

    2017-06-15

    Foratom, the Brussels based trade association for the nuclear industry in Europe, published a position paper on the European Commission's 'Clean Energy for All Europeans' package of EU legislative proposals. The proposals seek to improve the functioning of the energy market and ensure all energy technologies can compete on a level-playing field without jeopardising climate and energy targets. If Europe seeks to have a coherent and inclusive energy policy, which encompasses all lowcarbon contributors, nuclear must be allowed a place at the policy table.

  3. Method to determine the radioactivity of radioactive waste packages. Basic procedure of the method used to determine the radioactivity of low-level radioactive waste packages generated at nuclear power plants: 2007

    International Nuclear Information System (INIS)

    2008-03-01

    This document describes the procedures adopted in order to determine the radioactivity of low-level radioactive waste packages generated at nuclear power plants in Japan. The standards applied have been approved by the Atomic Energy Society of Japan after deliberations by the Subcommittee on the Radioactivity Verification Method for Waste Packages, the Nuclear Cycle Technical Committee, and the Standards Committee. The method for determining the radioactivity of the low-level radioactive waste packages was based on procedures approved by the Nuclear Safety Commission in 1992. The scaling factor method and other methods of determining radioactivity were then developed on the basis of various investigations conducted, drawing on extensive accumulated knowledge. Moreover, the international standards applied as common guidelines for the scaling factor method were developed by Technical Committee ISO/TC 85, Nuclear Energy, Subcommittee SC 5, Nuclear Fuel Technology. Since the application of accumulated knowledge to future radioactive waste disposal is considered to be rational and justified, such body of knowledge has been documented in a standardized form. The background to this standardization effort, the reasoning behind the determination method as applied to the measurement of radioactivity, as well as other related information, are given in the Annexes hereto. This document includes the following Annexes. Annex 1: (reference) Recorded items related to the determination of the scaling factor. Annex 2 (reference): Principles applied to the determining the radioactivity of waste packages. (author)

  4. Prevention of illicit trafficking of nuclear material and radioactive sources

    International Nuclear Information System (INIS)

    Kravchenko, N.

    2001-01-01

    Full text: Countries like Russia, which have a large nuclear industry, export a significant number of radioactive sources and substances. Some of them are nuclear material. In general, it is the task of the customs inspectors to verify that the content of the shipment is in agreement with the declaration (as safeguards inspectors verify operators declarations). In case of other goods, this is easy. The consignment can be opened and the content can be seen and compared with the declaration. In the case of radioactive shipments this cannot be done. The radioactive substance is in a shielded container and opening is often only possible in a hot cell. Opening of the package and measurement of the removed source in presence of the customs inspector is impossible because the customs inspector is impossible because the customs control begins only after the declaration has been registered. Therefore, the Russian customs authorities have contracted a company to develop a gamma spectrometer, which can be used to verify the source, even if inside the shielded shipping container. Throughout the country - near the where many shipments or receivables take place - there are 18 customs offices, equipped with gamma spectrometers and special software. If a container arrives for customs inspection, its design is called from a database. Then the gamma spectrum outside the container is measured and the measured gamma peak energy and intensity is compared with the expected, which is calculated by software based on the design information of the container. This approach works well. Several cases were already discovered in Russia, where there were attempts to use legal shipments for smuggling radioactive sources. I would like to mention some technical problems concerning control of legal export and import of radioactive sources: a) There are not enough commercial suppliers, which offer the needed equipment; because of lack of competition prices for the equipment are too high b) Presently

  5. Nuclear Security Systems and Measures for the Detection of Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide

    International Nuclear Information System (INIS)

    2013-01-01

    Nuclear terrorism and the illicit trafficking of nuclear and other radioactive material threaten the security of all States. There are large quantities of diverse radioactive material in existence, which are used in areas such as health, the environment, agriculture and industry. The possibility that nuclear and other radioactive material may be used for terrorist acts cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material, and to establish capabilities for detection and response to nuclear and other radioactive material out of regulatory control. Through its nuclear security programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This approach recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in nuclear and other radioactive material; national response plans; and contingency measures. Within its nuclear security programme, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. Each State carries the full responsibility for nuclear security, specifically: to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; to combat illicit trafficking; and to detect and respond to nuclear security events. This is an Implementing Guide on nuclear security systems and measures for the detection of nuclear and other radioactive material out of regulatory control. The objective of the publication is to provide guidance to Member States for the

  6. Radioactive releases of nuclear power plants: the code ASTEC

    International Nuclear Information System (INIS)

    Sdouz, G.; Pachole, M.

    1999-11-01

    In order to adopt potential countermeasures to protect the population during the course of an accident in a nuclear power plant a fast prediction of the radiation exposure is necessary. The basic input value for such a dispersion calculation is the source term, which is the description of the physical and chemical behavior of the released radioactive nuclides. Based on a source term data base a pilot system has been developed to determine a relevant source term and to generate the input file for the dispersion code TAMOS of the Zentralanstalt fuer Meteorologie und Geodynamik (ZAMG). This file can be sent directly as an attachment of e-mail to the TAMOS user for further processing. The source terms for 56 European nuclear power plant units are included in the pilot version of the code ASTEC (Austrian Source Term Estimation Code). The use of the system is demonstrated in an example based on an accident in the unit TEMELIN-1. In order to calculate typical core inventories for the data bank the international computer code OBIGEN 2.1 was installed and applied. The report has been completed with a discussion on the optimal data transfer. (author)

  7. Earthquake resistant design of nuclear facilities with limited radioactive inventory

    International Nuclear Information System (INIS)

    1985-10-01

    This document comprises the essential elements of an earthquake resistant design code for nuclear facilities with limited radioactive inventory. The purpose of the document is the enhancement of seismic safety for such facilities without the necessity to resort to complicated and sophisticated methodologies which are often associated with and borrowed from nuclear power plant analysis and design. The first two sections are concerned with the type of facility for which the document is applicable and the radiological consideration for accident conditions. The principles of facility classification and item categorization as a function of the potential radiological consequences of failure are given in section 3. The design basis ground motion is evaluated in sections 4-6 using a simplified but conservative approach which also includes considerations for the underlying soil characteristics. Sections 7 and 8 specify the principles of seismic design of building structures and equipment using two methods, called the equivalent static and simplified dynamic approach. Considerations for the detailing of equipment and piping and those other than for lateral load calculations, such as sloshing effects, are given in the subsequent sections. Several appendices are given for illustration of the principles presented in the text. Finally, a design tree diagram is included to facilitate the user's task of making the appropriate selections. (author)

  8. Liquid radioactive waste processing improvement of PWR nuclear power plants

    International Nuclear Information System (INIS)

    Nery, Renata Wolter dos Reis; Martinez, Aquilino Senra; Monteiro, Jose Luiz Fontes

    2005-01-01

    The study evaluate an inorganic ion exchange to process the low level liquid radwaste of PWR nuclear plants, so that the level of the radioactivity in the effluents and the solid waste produced during the treatment of these liquid radwaste can be reduced. The work compares two types of ion exchange materials, a strong acid cation exchange resin, that is the material typically used to remove radionuclides from PWR nuclear plants wastes, and a mordenite zeolite. These exchange material were used to remove cesium from a synthetic effluent containing only this ion and another effluent containing cesium and cobalt. The breakthrough curves of the zeolite and resin using a fix bed reactor were compared. The results demonstrated that the zeolite is more efficient than the resin in removing cesium from a solution containing cesium and cobalt. The results also showed that a bed combining zeolite and resin can process more volume of an effluent containing cesium and cobalt than a bed resin alone. (author)

  9. Selected problems of minimization and management of radioactive wastes from nuclear power plant decommissioning. Part 2

    International Nuclear Information System (INIS)

    Kyrs, M.; Moravec, A.

    1988-06-01

    The processing prior to storage of radioactive wastes produced in nuclear power plant decommissioning is described as are the types of containers employed for waste transport and/or disposal. Data are summarized on exposure of personnel to radioactivity resulting from nuclear power plant decommissioning activities, and accessible data are collected on the costs of nuclear power plant decommissioning and of waste management. Potential directions of research in this field under Czechoslovak conditions are specified. (author)

  10. Deployment of Radioactive Waste Disposal Facility with the Introduction of Nuclear Power Plants in Kenya

    Energy Technology Data Exchange (ETDEWEB)

    Shadrack, Antoony; Kim, Changlak [KEPCO International Nuclear Graduate School, Uljin (Korea, Republic of)

    2013-07-01

    The nuclear power program will inevitably generate radioactive wastes including low-and intermediate radioactive waste and spent fuel. These wastes are hazardous to human health and the environment and therefore, a reliable radioactive waste disposal facility becomes a necessity. This paper describes Kenya's basic plans for the disposal of radioactive wastes expected from the nuclear program. This plan is important as an initial implementation of a national Low to intermediate level wastes storage facility in Kenya. In Kenya, radioactive waste is generated from the use of radioactive materials in medicine, industry, education and research and development. Future radioactive waste is expected to arise from nuclear reactors, oil exploration, radioisotope and fuel production, and research reactors as shown in table 1. The best strategy is to store the LILW and spent fuel temporarily within reactor sites pending construction of a centralized interim storage facility or final disposal facility. The best philosophy is to introduce both repository and nuclear power programs concurrently. Research and development on volume reduction technology and conceptual design of disposal facility of LILW should be pursued. Safe management of radioactive waste is a national responsibility for sustainable generation of nuclear power. The republic of Kenya is set to become the second African nuclear power generation country after South Africa.

  11. Limitation of releases of radioactive effluents for nuclear power plants in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Tolksdorf, P.; Buehling, A.

    1981-01-01

    Empirical values relating to the effluents of nuclear power plants in the Federal Republic of Germany are now available. These values cover a period of several years of operation. The measured emissions of radioactive substances are often very much below the maximum permissible values, based on the dose limits for the environment stipulated in the legal regulations. Extensive technical and administrative measures contribute to the reduction of radioactive effluents. Furthermore, additional possibilities for improvement are mentioned which may lead to a further reduction of radioactive effluents. These are derived from investigations into the release of radioactive substances in nuclear power plants. The licensing procedure in the Federal Republic of Germany in fixing discharge limits is outlined. Proposals are made concerning licence values which may be determined for the radioactive effluents in modern standardized nuclear power plants with light-water reactors. The resulting radiation exposures are quoted for a typical nuclear power plant site. (author)

  12. Nuclear plant refurbishment calls for patience. [Construction of radioactive effluent plant

    Energy Technology Data Exchange (ETDEWEB)

    Henly, Anna

    1989-08-01

    All nuclear power plants produce a small quantity of liquid effluent from wash hand basins, showers and surface drains on the site. The effluent is termed low-level radioactive waste and under the 'Radioactive Substances Act' can be discharged into estuaries or the sea. Before a controlled discharge can be made the effluent has to be chemically treated and have any radioactive particulate matter removed. The replacing of the radioactive effluent plant at the Berkeley nuclear power station in the United Kingdom is described, with particular reference to the vigorous safety standards and quality assurance programme operated by the Central Electricity Generating Board. (author).

  13. Management of Radioactive Waste after a Nuclear Power Plant Accident

    International Nuclear Information System (INIS)

    Strand, Per; Laurent, Gerard; Rindo, Hiroshi; Georges, Christine; Ito, Eiichiro; Yamada, Norikazu; Iablokov, Iuri; Kilochytska, Tatiana; Jefferies, Nick; Byrne, Jim; Siemann, Michael; Koganeya, Toshiyuki; Aoki, Hiroomi

    2016-01-01

    The NEA Expert Group on Fukushima Waste Management and Decommissioning R and D (EGFWMD) was established in 2014 to offer advice to the authorities in Japan on the management of large quantities of on-site waste with complex properties and to share experiences with the international community and NEA member countries on ongoing work at the Fukushima Daiichi site. The group was formed with specialists from around the world who had gained experience in waste management, radiological contamination or decommissioning and waste management R and D after the Three Mile Island and Chernobyl accidents. This report provides technical opinions and ideas from these experts on post-accident waste management and R and D at the Fukushima Daiichi site, as well as information on decommissioning challenges. Chapter 1 provides general descriptions and a short introduction to nuclear accidents or radiological contaminations; for instance the Chernobyl NPP accident, the Three Mile Island Unit 2 accident and the Windscale fire accident. Chapter 2 provides experiences on regulator-implementer interaction in both normal and abnormal situations, including after a nuclear accident. Chapter 3 provides experiences on stakeholder involvement after accidents. These two chapters focus on human aspects after an accident and provide recommendations on how to improve communication between stakeholders so as to resolve issues arising after unexpected nuclear accidents. Chapters 4, 5 and 6 provide information on technical issues related to waste management after accidents. Chapter 4 focuses on the physical and chemical nature of the waste, Chapter 5 on radiological characterisation, and Chapter 6 on waste classification and categorisation. The persons involved in waste management after an accident should address these issues as soon as possible after the accident. Chapters 7 and 8 also focus on technical issues but with a long-term perspective of the waste direction in the future. Chapter 7 relates

  14. Reactor, radioactive isotopes and nuclear energy: their avatars in Venezuela

    Energy Technology Data Exchange (ETDEWEB)

    Roche, M

    1981-03-01

    The decision to bring a fair sized (3MW) research reactor to Venezuela, made in 1954 by a single, ambitious and prestige seeking individual working with a dictatorial government, is a clear case of cargo cult, an implicit desire to import industralized countries' science and technology by purchasing key in hand their expensive machine. The reactor has never ceased to experience difficulties since then, not so much of a physical or mechanical, but rather of a human nature and due to the almost grotesque distance between the machine's potentialities and the quantity and quality of personnel available. Demand and motivation have been scarce, because fossil and hydro energy have been so far plentiful. Military motivation was in theory absent. Perspectives have apparently improved, not that a scientific community has been trained and an infrastructure exists. Radioactive isotopes have been widely used in Venezuela, beginning in 1953, for medical practice and biological research. At present about 2.5 million bolivars worth of radioisotopes are imported annually, mostly from the US and to a lesser extent, from UK. Steps are being taken to train nuclear engineers, since most studies thus far indicate the last few years of the century as the time when nuclear energy will begin to enter the picture, and since a period of at least ten years is needed between the decision to build an atomic power plant and the time it goes into operation. Choice of technique has not been made, but an active, although still small, uranium prospecting program has been initiated. It seems as if, by the end of the century, either nuclear energy will have to supplement other sources, or standard of living of Venezuelans - at least that relative minority who can afford to live well - will drop. 2 figures, 2 tables.

  15. Monitoring for radioactive materials releasing to environment in M310 reformatived nuclear power plant

    International Nuclear Information System (INIS)

    Yin Zhenyu; Yang Guangli; Xu Guang

    2012-01-01

    Airborne radioactive materials of nuclear power plant (NPP) releases to the environment from the stack of NPP. Radioactive liquid waste releases of the ocean, the fluvial and the lake through the liquid waste letdyke of NPP. Further more, a few radioactive waste may be taken out of the NPP by vehicle or personnel. For the purpose of strict management and control above-mentioned waste, we use detect equipment monitoring radioactive waste of NPP. Management and control for the releasing of radioactive material to the environment in M310 reformatived NPP is strict and safety. (authors)

  16. Radioactive waste treatment system for Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    Taniguchi, Takashi; Takeshima, Masaki; Saito, Toru; Kikkawa, Ryozo

    1978-01-01

    The augmentation of the radioactive waste treatment system in the Tsuruga Nuclear Power Station was planned in 1973, and this enlarged facility was completed in June, 1977. The object of this augmentation is to increase the storage capacity for wastes and to enlarge the treating capacity utilizing the newly installed facility. The operating experience in the facility having been already constructed was fed back for the engineering of this new facility. This new facility contains the newly developed vacuum forced circulation type concentrator, the exclusive storage pool for solid wastes, etc. At the design stage of this new system, the pilot plant test of slurry transportation and the corrosion test of long hours were carried out as the research and developmental works for the confirmation of correct design condition. The measures for augmenting this radioactive waste treatment system are the installation of a long time storage tank with the capacity of 350 m 3 , the sit bunker facility and the drum storage as the storage facility, and the vacuum forced circulation type concentrator with the circulating flow rate more than 200 times as much as the treating flow rate and vacuum level of 0.255 ata. The augmented system is shown with the flow sheet of whole waste disposal system. The flow sheet of the concentrator is separately shown, and the relating research and developmental works, for example, the test of the cause of corrosion, the surface finishing test, the material test, the blockage test for heat transfer tubes and the inhibiter test, are explained with the test results. The ion exchange resin is transported by air and water as the slurry state, and the long distance transport of about 250 m is required in this new system. As clogging has to be avoided in this transportation, the experimental work was conducted to obtain the flow characteristics of slurry, and the test result is outlined. (Nakai, Y.)

  17. The possibility of clean development mechanism in a nuclear power expansion in Brazil

    International Nuclear Information System (INIS)

    Paris, Alexandre G.; Oliveira, Wagner S.

    2009-01-01

    The nuclear power expansion is a very controversial topic in Brazil, which needs to be carefully addressed, especially because the national energy supply system is becoming more carbon-intensive. Although most of the electricity generated in Brazil is by hydropower plants, the country's electricity matrix expansion is moving towards a larger participation of fossil fuel thermo power generation which is contrarily the global objects of climate change mitigation. Climate change is a reality and the choice facing this problem is between action and delay. There will be needed a huge international mobilization, associated with a great amount of financial, political and engineering resources interested for preventing the aggravation of the greenhouse effect. This article analyses, in the possibility of including nuclear power in the Clean Development Mechanism (CDM) criteria, the revenue that could be generated from the trading of Certified Emission Reduction (CER) in different scenarios of nuclear power expansion in Brazil. (author)

  18. Separation techniques for the clean-up of radioactive mixed waste for ICP-AES/ICP-MS analysis

    International Nuclear Information System (INIS)

    Swafford, A.M.; Keller, J.M.

    1993-01-01

    Two separation techniques were investigated for the clean-up of typical radioactive mixed waste samples requiring elemental analysis by Inductively Coupled Plasma-Atomic Emission Spectroscopy (ICP-AES) or Inductively Coupled Plasma-Mass Spectrometry (ICP-MS). These measurements frequently involve regulatory or compliance criteria which include the determination of elements on the EPA Target Analyte List (TAL). These samples usually consist of both an aqueous phase and a solid phase which is mostly an inorganic sludge. Frequently, samples taken from the waste tanks contain high levels of uranium and thorium which can cause spectral interferences in ICP-AES or ICP-MS analysis. The removal of these interferences is necessary to determine the presence of the EPA TAL elements in the sample. Two clean-up methods were studied on simulated aqueous waste samples containing the EPA TAL elements. The first method studied was a classical procedure based upon liquid-liquid extraction using tri-n- octylphosphine oxide (TOPO) dissolved in cyclohexane. The second method investigated was based on more recently developed techniques using extraction chromatography; specifically the use of a commercially available Eichrom TRU·Spec trademark column. Literature on these two methods indicates the efficient removal of uranium and thorium from properly prepared samples and provides considerable qualitative information on the extraction behavior of many other elements. However, there is a lack of quantitative data on the extraction behavior of elements on the EPA Target Analyte List. Experimental studies on these two methods consisted of determining whether any of the analytes were extracted by these methods and the recoveries obtained. Both methods produced similar results; the EPA target analytes were only slightly or not extracted. Advantages and disadvantages of each method were evaluated and found to be comparable

  19. Data for radioactive waste management and nuclear applications

    International Nuclear Information System (INIS)

    Stewart, D.C.

    1985-01-01

    This book is a specialized handbook on the management of radioactive waste, including information applicable to related applications. It consolidates information from many sources to develop techniques for dealing with radioactive waste management and features reports and other specialized data not available in libraries. It covers physical data, chemical data, types of radioactive wastes, and data for different operations

  20. Modelling of radioactive fallout in the vicinity of Chernobyl nuclear power plant accident

    International Nuclear Information System (INIS)

    Israel, Y.A.; Petrov, V.N.; Severov, D.A.

    1988-03-01

    Deposition of radioactive products escaping into the atmosphere for a long time from the Chernobylsk-4 reactor resulting in residual radioactive contamination of the region at a distance of up to 100 km from the nuclear power plant is considered. The suggested model may be used for estimation of the possible scope of nuclear danger in the regions of nuclear power plants and creation of conditions ensuring safety of the population at possible accidents. The following topics are developed: height of elevation and conditions of radionuclide transfer in the atmosphere; dynamics of release and dispersive composition of radioactive products; calculations of radiation levels at a close trace [fr

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-11-01

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

  2. Measures Against-Illicit Trafficking of Nuclear Materials and Other Radioactive Sources

    International Nuclear Information System (INIS)

    Barakat, M.B.; Nassef, M.H.; El Mongy, S.A.

    2008-01-01

    Since the early nineties, illicit trafficking (IT) of nuclear materials and radioactive sources appeared as a new trend which raised the concern of the international community due to the grave consequences that would merge if these materials or radioactive sources fell into the hands of terrorist groups. However, by the end of the last century illicit trafficking of nuclear materials and radioactive sources lost its considerable salience, in spite of seizure of considerable amounts of 2 '3'5U (76% enrichment) in Bulgaria (May 1999) and also 235 U (30% enrichment) in Georgia (April 2000). Nevertheless, IT should be always considered as a continued and viable threat to the international community. Awareness of the problem should be developed and maintained among concerned circles as the first step towards combating illicit trafficking of nuclear materials and radioactive sources. Illicit trafficking of nuclear and radioactive materials needs serious consideration and proper attention by the governmental law enforcement authorities. Measures to combat with IT of nuclear material or radioactive sources should be effective in recovery, of stolen, removed or lost nuclear materials or radioactive sources due to the failure of the physical protection system or the State System Accounting and Control (SSAC) system which are normally applied for protecting these materials against illegal actions. Measures such as use of modern and efficient radiation monitoring equipment at the borders inspection points, is an important step in preventing the illicit trafficking of nuclear and radioactive materials across the borders. Also providing radiological training to specific personnel and workers in this field will minimize the consequences of a radiological attack in case of its occurrence. There is a real need to start to enter into cooperative agreements to strengthen borders security under the umbrella of IAEA to faster as an international cooperation in the illicit trafficking

  3. The concept of radioactive waste and spent nuclear fuel management in the Czech Republic

    International Nuclear Information System (INIS)

    Suransky, F.; Duda, V.

    2003-01-01

    The article briefly comments on the status of nuclear waste and spent nuclear fuel management in the Czech Republic in the context of the document entitled 'The Concept of Radioactive Waste and Spent Nuclear Fuel Management in the Czech Republic', which was adopted by the Czech Government in May 2002 as a national strategy in this field. (author)

  4. Classification of radioactive wastes produced by the nuclear industry

    International Nuclear Information System (INIS)

    2013-01-01

    This document first indicates the origins of radioactive wastes (mainly electronuclear industry), and the composition of spent fuel, and that only fission products and minor actinides are considered as radioactive wastes whereas uranium and plutonium can be used as new fuel after recycling. The classification of radioactive wastes is indicated in terms of radioactivity level and radionuclide half-life: high level (0.2 per cent of the total waste volume but 96 per cent of total waste radioactivity), medium level long life (3 per cent of volume, 4 per cent of radioactivity), low level long life (7 per cent of volume, 0.1 per cent of radioactivity), low and medium level and short life (63 per cent of volume and 0.02 per cent of radioactivity), very low level (27 per cent of volume and less than 0.01 per cent of radioactivity). An overview of radioactive waste processing and storage in France is presented for each category. Current and predicted volumes are indicated for each category. The main challenges are briefly addressed: spent fuel recycling, waste valorisation by fourth-generation reactors. Processing locations in France and in the World are indicated. Some key figures are provided: 2 kg of radioactive waste are produced per inhabitant and per year, and waste management costs represent 5 per cent of the total cost of produced electricity

  5. IAEA expert review mission completes assessment of fuel cleaning incident at Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    2003-01-01

    Full text: The IAEA today completed its expert review mission to investigate the 10 April fuel cleaning incident at the Paks nuclear power plant in Hungary. The mission was requested by the Hungarian Government to provide an independent assessment of the causes and actions taken by the plant and Hungarian authorities. The team was composed of nuclear and radiation experts from the IAEA, Austria, Canada, Finland, Slovakia, the United Kingdom and the United States. In a press conference, team leader Miroslav Lipar highlighted the team's findings in five areas: On management, the team concluded that the Hungarian Atomic Energy Authority and Paks are committed to improving the safety of the plant. They noted that as a result of steam generator decontamination in previous years, deposits became attached to the fuel assemblies. A decision was made to clean the fuel and contract an outside company to develop and operate a fuel cleaning process. The team found that the design and operation of the fuel cleaning tank and system was not accomplished in the manner prescribed by the IAEA Safety Standards. Neither the Hungarian Atomic Energy Authority nor Paks used conservative decision-making in their safety assessments for this unproven fuel cleaning system. The team determined that there was an over-reliance on the contractor that had been selected for the design, management and operation of the fuel cleaning system. Time pressure related to a prescribed fuel outage schedule, combined with confidence generated by previous successful fuel cleaning operations, contributed to a weak assessment of a new design and operation, which involved fuel directly removed from the reactor following a planned shutdown. On regulatory oversight, the IAEA team concluded that the Hungarian Atomic Energy Authority underestimated the safety significance of the proposed designs for the fuel cleaning system, which resulted in a less than rigorous review and assessment than should have been necessary

  6. Astrophysical r- and rp-processes, and radioactive nuclear beams

    International Nuclear Information System (INIS)

    Boyd, Richard N.

    1998-01-01

    The modern description of the r-process follows naturally from α-rich freezeout, thought to occur in the hot neutrino wind just beyond the nascent neutron star in a type II supernova. Initially, all pre-existing nuclei are reduced to α-particles and neutrons. As the environment cools, nuclei up to about mass 90 to 100 u are synthesized, in nuclear statistical equilibrium, in about 1 s. In the next few seconds, the remaining neutrons are captured to form the r-process progenitors, which then decay to the r-process nuclides. The rp-process occurs in a high-temperature H-rich environment. It is one of the processes that synthesize the p-process nuclei, the most neutron-poor nuclei in the periodic table. It is thought to occur during the explosion of a C-O white dwarf in a type Ia supernova or in a binary system during accretion onto a white dwarf or a neutron star. It appears to be capable of forming the p-nuclei up to about mass 90 u. Both processes pass through nuclei that are far from stability. Thus, their description requires the masses, half-lives, decay modes, and structure of these nuclei. The next generation of radioactive beam facilities promises to allow the study of many such nuclei. (author)

  7. Radioactive targets for nuclear astrophysics research at LANSCE

    International Nuclear Information System (INIS)

    Koehler, P.E.; O'Brien, H.A.; Gursky, J.C.

    1990-01-01

    During the past few years we have made measurements of (n,p) and (n,α) cross sections on several radioactive nuclei of importance to nuclear astrophysics. The measurements were made at the Manuel Lujan, Jr., Neutron Scattering Center (LANSCE) from thermal neutron energy to approximately 100 keV. Successful measurements have been completed on the radioisotopes 7 Be, 22 Na and 36 Cl while preliminary data have been taken on targets of 54 Mn and 55 Fe. Similar measurements have also been made on the stable isotopes 14 N, 17 O and 35 Cl. We are currently assembling a 4π barium fluoride (BaF 2 ) detector which will allow us to expand our program to (n,γ) measurements. The (n,γ) (and in some cases future (n,p)) measurements will require targets with higher specific activity and greater chemical purity than we have so far been able to use. We discuss the fabrication techniques used for the samples produced so far, the requirements the future (n,γ) targets must meet and our current plans for producing them, and the physics motivations for the measurements

  8. Guide to sampling airborne radioactive materials in nuclear facilities

    International Nuclear Information System (INIS)

    Glissmeyer, J.A.

    1995-01-01

    The ANSI N13.1-1969 Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities is currently being revised. The revision is being drafted by a working group under the auspices of the Health Physics Society Standards Committee. The main differences between the original standard and the proposed revision are a narrowed scope, a greater emphasis on the design process, and the verification of meeting performance criteria. Compliance with the revised standard will present new challenges, especially in the area of performance validation. The progress made in the revision and key portions of the standard are discussed. The DOE has recently petitioned EPA for alternate approaches to complying with air-sampling regulations. Dealing with compliance issues until the revised standard is adopted will be a challenge for both designers and regulators. The objective of this paper is to briefly describe the content of the proposed revision in order to point out significant differences from the old standard and to describe the new challenges that the proposed revision will present

  9. Guide to sampling airborne radioactive materials in nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Glissmeyer, J.A. [Pacific Northwest Laboratory, Richland, WA (United States)

    1995-02-01

    The ANSI N13.1-1969 Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities is currently being revised. The revision is being drafted by a working group under the auspices of the Health Physics Society Standards Committee. The main differences between the original standard and the proposed revision are a narrowed scope, a greater emphasis on the design process, and the verification of meeting performance criteria. Compliance with the revised standard will present new challenges, especially in the area of performance validation. The progress made in the revision and key portions of the standard are discussed. The DOE has recently petitioned EPA for alternate approaches to complying with air-sampling regulations. Dealing with compliance issues until the revised standard is adopted will be a challenge for both designers and regulators. The objective of this paper is to briefly describe the content of the proposed revision in order to point out significant differences from the old standard and to describe the new challenges that the proposed revision will present.

  10. PAVAN, Atmospheric Dispersion of Radioactive Releases from Nuclear Power Plants

    International Nuclear Information System (INIS)

    2001-01-01

    1 - Description of program or function: PAVAN estimates down-wind ground-level air concentrations for potential accidental releases of radioactive material from nuclear facilities. Options can account for variation in the location of release points, additional plume dispersion due to building wakes, plume meander under low wind speed conditions, and adjustments to consider non-straight trajectories. It computes an effective plume height using the physical release height which can be reduced by inputted terrain features. 2 - Method of solution: Using joint frequency distributions of wind direction and wind speed by atmospheric stability, the program provides relative air concentration (X/Q) values as functions of direction for various time periods at the exclusion area boundary (EAB) and the outer boundary of the low population zone (LPZ). Calculations of X/Q values can be made for assumed ground-level releases or evaluated releases from free-standing stacks. The X/Q calculations are based on the theory that material released to the atmosphere will be normally distributed (Gaussian) about the plume centerline. A straight-line trajectory is assumed between the point of release and all distances for which X/Q values are calculated. 3 - Restrictions on the complexity of the problem: - The code cannot handle multiple emission sources

  11. Monitoring of radioactivity at the Russian nuclear submarine Kursk

    International Nuclear Information System (INIS)

    Amundsen, I.; Lind, B.

    2002-01-01

    In the morning of August 12th 2000, a Russian submarine accident occurred in international waters east of Rybatschi Peninsula in the Barents Sea about 250 km from Norway. The submarine, a Russian Oscar class II attack submarine, sunk to 116 meters depth at the position 69 deg. 36,99N, 37 deg. 34,50E. The submarine 'Kursk' is 154 meters long, equipped with two pressurised water reactors and the submerged displacement is 24000 tons. Each reactor has a thermal effect or 190 megawatt, or less than 10% of a typical nuclear power plant reactor. The submarines in Oscar-II class is one of the largest and most capable in the Russian Northern Fleet. No indications of leakage from the submarine have so far been observed during the monitoring expeditions. Elevated levels of radioactivity have note been detected in any dose-rate readings or at any of the measurements of environmental samples taken close to Kursk. Furthermore, no increased levels were measured on bits and pieces from the submarine or from water sampled inside the submarine. A more comprehensive report covering experience and monitoring results from the two expeditions term and impact assessments of possible future releases from Kursk. (LN)

  12. Dependence of two-proton radioactivity on nuclear pairing models

    Science.gov (United States)

    Oishi, Tomohiro; Kortelainen, Markus; Pastore, Alessandro

    2017-10-01

    Sensitivity of two-proton emitting decay to nuclear pairing correlation is discussed within a time-dependent three-body model. We focus on the 6Be nucleus assuming α +p +p configuration, and its decay process is described as a time evolution of the three-body resonance state. For a proton-proton subsystem, a schematic density-dependent contact (SDDC) pairing model is employed. From the time-dependent calculation, we observed the exponential decay rule of a two-proton emission. It is shown that the density dependence does not play a major role in determining the decay width, which can be controlled only by the asymptotic strength of the pairing interaction. This asymptotic pairing sensitivity can be understood in terms of the dynamics of the wave function driven by the three-body Hamiltonian, by monitoring the time-dependent density distribution. With this simple SDDC pairing model, there remains an impossible trinity problem: it cannot simultaneously reproduce the empirical Q value, decay width, and the nucleon-nucleon scattering length. This problem suggests that a further sophistication of the theoretical pairing model is necessary, utilizing the two-proton radioactivity data as the reference quantities.

  13. The possible transmutation of radioactive waste from nuclear reactors

    International Nuclear Information System (INIS)

    Harries, J.R.

    1974-01-01

    A nuclear reactor power program produces high level and long lived radioactive wastes. The high level activity is associated with fission products, but beyond 400 years the principal waste hazard is from transuranic elements produced in the reactor. Several schemes have been proposed for the transmutation of the problem isotopes into more easily handled isotopes. The neutron flux in a thermal reactor is not high enough to significantly reduce the longer lived fission product isotopes 90 Sr and 132 Gs, but the transuranic elements can be reduced by recycling through power reactors. The limitation on recycling of the transuranic elements is the separation process to remove trace quantities from the waste stream. In fast reactors the transuranic elements are the principal fuel and fast reactor waste contains only half as much 90 Sr as thermal reactors. However, the overall waste hazard is similar to thermal reactors. A sufficiently intense neutron flux for fission product transmutation could perhaps be produced by a spallation reactor driven by a proton linear accelerator or a controlled thermonuclear reactor. However, both concepts are still some years in the future. Transmutation by accelerator sources of protons, electrons of gammas tend to require more energy than neutron transmutation. (author)

  14. Monitoring device for radioactive leakage from steam system in nuclear power plant

    International Nuclear Information System (INIS)

    Ogawa, Tateo; Sato, Kohei

    1988-01-01

    Purpose: To improve the reliability for the monitor of radio-active leakage by accumulating small quantity of radioactivities each lower than the detectable level and increasing their dose rate. Constitution: Even if the steam system radiation monitor in the nuclear power plant is disposed for the detection of in-leak radioactivity, radioactive leakage can be monitored at high reliability by increasing the small quantity of radioactivities in the drains to a detectable sensitivity range of the monitor upon detection. In view of the above, in the present invention, radioactive material catching medium is incorporated to a radio-activity monitor spool piece for accumulating small quantity of radioactivities. Specifically as the catching medium, an ion exchange resin is used for the leakage of ionic radioactive material, while an ion exchange resin increased with the mixing ratio of a cationic resin or hollow thread membrane filter is used for crud-like radioactive material leakage. These catching media are incorporated into the spool piece, thereby enabling to catch even small quantity of radioactive leakage lower than the detectable sensitivity of the radiation monitor, if should occur, in the spool piece and enabling radioactive detection for the accumulated dose rate. (Horiuchi, T.)

  15. Radioactive cesium deposition on rice, wheat, peach tree and soil after nuclear accident in Fukushima

    International Nuclear Information System (INIS)

    Nakanishi, T.M.; Kobayashi, N.I.; Tanoi, K.

    2013-01-01

    We present how radioactive Cs was deposited on wheat, rice, peach tree and soil after nuclear accident in Fukushima. The deposition of radioactive Cs was found as spots at the surface of the leaves, branch or trunk of the trees, as well as in soil using one of the imaging method, autoradiography. The deposited radioactive Cs was not easily washed out, even with the treatment of acid solution. When the wheat was harvested 2 months after the accident, high radioactivity of Cs was found only on the leaves developed and expanded at the time of the accident. In the case of the rice grain, most of the radioactivity was found in bran and the radioactivity was drastically reduced in milled rice. Most of the radioactive Cs accumulation in rice plants was estimated from the absorption of the Cs ion dissolved in water, rather than Cs adsorbed in soil. (author)

  16. Low activation material design methodology for reduction of radio-active wastes of nuclear power plant

    International Nuclear Information System (INIS)

    Hasegawa, A.; Satou, M.; Nogami, S.; Kakinuma, N.; Kinno, M.; Hayashi, K.

    2007-01-01

    Most of the concrete shielding walls and pipes around a reactor pressure vessel of a light water reactor become low level radioactive waste at decommission phase because they contain radioactive nuclides by thermal-neutron irradiation during its operation. The radioactivity of some low level radioactive wastes is close to the clearance level. It is very desirable in terms of life cycle cost reduction that the radioactivity of those low level radioactive wastes is decreased below clearance level. In case of light water reactors, however, methodology of low activation design of a nuclear plant has not been established yet because the reactor is a large-scale facility and has various structural materials. The Objectives of this work are to develop low activation material design methodology and material fabrication for reduction of radio-active wastes of nuclear power plant such as reinforced concrete. To realize fabrication of reduced radioactive concrete, it is necessary to develop (1) the database of the chemical composition of raw materials to select low activation materials, (2) the tool for calculation of the neutron flux and the spectrum distribution of nuclear plants to evaluate radioactivity of reactor components, (3) optimization of material process conditions to produce the low activation cement and the low activation steels. Results of the data base development, calculation tools and trial production of low activation cements will be presented. (authors)

  17. A summary and historical review of the radioactive clean-up in Port Hope, Ontario

    International Nuclear Information System (INIS)

    Case, G.

    1980-01-01

    In 1976 several buildings and other areas of the town of Port Hope were found to be contaminated by radium and radon from residues produced by a local uranium refining plant and from materials salvaged from old refinery buildings. In the spring of 1976 the entire town was surveyed and 550 houses were found to have elevated radon gas levels or background radiation levels. Of these, 500 properties were classified as sites requiring remedial work. Large amounts of contaminated soil and fill were removed, as well as other building materials. Demolition was necessary in some cases. For the first three years contaminated materials were stored at the Chalk River Nuclear Laboratories, but finally the waste disposal site there was filled with over 104 000 tons of contaminated soil. By the end of 1979 work had been completed on 441 properties. Work on smaller sites was continuing, but progress on the cleanup of of larger areas depended on another disposal area being found

  18. Radioactive waste management in Centre for nuclear technologies and investigations, Institute VINCA

    International Nuclear Information System (INIS)

    Avramovic, I.

    2007-01-01

    Responsible radioactive waste management requires the implementation of measures that will afford protection of human health and the environment. Radioactive waste management system was improved in Center for Nuclear Technology and Research, Institute VINCA, during 2006 and 2007 regarding the activities of spent fuel removal and R-A research reactor decommissioning [sr

  19. Management of radioactive waste generated from nuclear power reactors in Korea

    International Nuclear Information System (INIS)

    Jeong-Mook Kim

    2000-01-01

    Fundamental objectives and efforts to safely manage radioactive wastes generating from the expanding nuclear power industry in the Republic of Korea are described. Management, treatment and storage of radioactive wastes arising in different form are addressed. A long tern plan to reduce the volume of solid waste is outlined. (author)

  20. Trends for minimization of radioactive waste arising from spent nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Polyakov, A.S.; Koltunov, V.S.; Marchenko, V.I.; Ilozhev, A.P.; Mukhin, I.V.

    2000-01-01

    Research and development of technologies for radioactive waste (RAW) minimization arising from spent nuclear fuel reprocessing are discussed. Novel reductants of Pu and Np ions, reagents of purification recycled extractant, possibility of the electrochemical methods are studied. The partitioning of high activity level waste are considered. Examples of microbiological methods decomposition of radioactive waste presented. (authors)

  1. Estimation of radioactive effluents dispersion from the nuclear power plants in Yugoslavia surrounding

    International Nuclear Information System (INIS)

    Vehauc, A.

    1997-01-01

    The computational method for atmospheric dispersion of radioactive effluents is applied to the nuclear power plants in Yugoslavia surrounding. On the basis of computation results, ground level concentrations and washout of radioactive nuclides on exposed Yugoslav territories during unfavourable meteorological conditions are estimated. (author)

  2. Nuclear energy's dilemma: disposing of hazardous radioactive waste safely. Report to the congress

    International Nuclear Information System (INIS)

    1977-01-01

    The unsolved problem of radioactive waste disposal threatens the future of nuclear power in the United States. Nuclear critics, the public, business leaders, and Government officials concur that a solution to the disposal problem is critical to the continued growth of nuclear energy. The Energy Research and Development Administration has begun a program to demonstrate by the mid-1980s the feasibility and safety of placing radioactive wastes in deep geological formations. GAO points out that not only has progress been negligible to date, but that future program goals are overly optimistic because the Energy Research and Development Administration faces many unsolved social, regulatory, and geological obstacles. GAO also discusses the progress and problems the Energy Research and Development Administration faces in managing its radioactive waste and how the Nuclear Regulatory Commission is handling the problem of large amounts of spent nuclear fuel now accumulating at nuclear power plants, and makes a number of recommendations for regulatory and program management changes

  3. The radioactive waste regulation in the new Czech Nuclear Energy Act

    International Nuclear Information System (INIS)

    Kucerka, M.

    1995-01-01

    Recently, in the Czech Republic, there is in the phase of development the Act on Peaceful Use of Nuclear Energy and Ionizing Radiation, so called the Nuclear Energy Act. This Act has to replace existing regulations and fulfill some not yet covered fields of that area. The act is developed as so called ''umbrella act'' and has to cover all aspects of the nuclear energy and ionizing radiation use, from uranium mining or isotopes use in medicine, to the power generation in nuclear power plants. It will include among others also provisions on registration and licensing, liability for nuclear damage, decommissioning and radioactive waste management funding, and some other topics, that were missing in the regulations up to today. The paper describes recent state policy in the field of radioactive waste management and the main provisions of proposed Nuclear Energy Act, concerning the radioactive waste management

  4. Real and alleged hazard of radioactive contamination of seas caused by activities of Russian nuclear fleets

    International Nuclear Information System (INIS)

    Lavkovsky, S.A.

    1999-01-01

    The current paper addresses the assessment results of the degree of danger caused by radioactive contamination of seas by wastes from activities of nuclear fleets compared to the results obtained in other works, specifically, in the IASAP program

  5. Radioactive materials and nuclear fuel transport requirements in Poland in the light of international regulations

    International Nuclear Information System (INIS)

    Musialowicz, T.

    1977-01-01

    National regulations for the transport of radioactive materials and nuclear fuel in Poland are discussed. Basic transport requirements and regulations, transport experience including transport accidents and emergency service are described. The comparison with international regulations is given

  6. Radiation Detection System for Prevention of Illicit Trafficking of Nuclear and Radioactive Materials

    International Nuclear Information System (INIS)

    Kwak, Sung Woo; Chang, Sung Soon; Yoo, Ho Sik

    2010-01-01

    Fixed radiation portal monitors (RPMs) deployed at border, seaport, airport and key traffic checkpoints have played an important role in preventing the illicit trafficking and transport of nuclear and radioactive materials. However, the RPM is usually large and heavy and can't easily be moved to different locations. These reasons motivate us to develop a mobile radiation detection system. The objective of this paper is to report our experience on developing the mobile radiation detection system for search and detection of nuclear and radioactive materials during road transport. Field tests to characterize the developed detection system were performed at various speeds and distances between the radioactive isotope (RI) transporting car and the measurement car. Results of measurements and detection limits of our system are described in this paper. The mobile radiation detection system developed should contribute to defending public's health and safety and the environment against nuclear and radiological terrorism by detecting nuclear or radioactive material hidden illegally in a vehicle

  7. Structural radioactive waste from 'retubing/refurbishment' of Embalse nuclear power plant. Regulatory perspective

    International Nuclear Information System (INIS)

    Alvarez, Daniela E.; Lee Gonzales, Horacio M.; Medici, Marcela A.; Piumetti, Elsa H.

    2009-01-01

    Unlike the building of a new nuclear reactor, the 'retubing / refurbishment' of nuclear reactors that have been in operation for many years, involves the replacement of components in a radioactive environment. This requires a carefully planned radiation protection program to ensure protection of workers, the public and the environment as well as a radioactive waste management program for those radioactive waste generated during the process, which go beyond those generated during the normal operation and maintenance of the plant. Nucleoelectrica Argentina Sociedad Anonima (NA-SA) is scheduled to conduct the Life Extension Process of Embalse Nuclear Power Plant (CNE) which essentially consist of 'retubing / refurbishment' of the installation. The Nuclear Regulatory Authority (ARN) will then have an important activity related to the above process. In particular, this paper will describe some points of interest related to the generation and management of radioactive waste during the 'retubing / refurbishment' of the CNE, from the regulatory point of view. (author)

  8. Six Decades of Nuclear Accidents, Nuclear Compensation, and Issues of Radioactive Waste Management

    International Nuclear Information System (INIS)

    Boonsuwan, P.; Songjakkeaw, A.

    2011-11-01

    Thailand has made a serious aim to employ nuclear power by adopting five 1,000 MWt in the 2010 national Power Development Plan (PDP 2010) with the first NPP coming online in 2020. However, after the Fukushima nuclear disaster in March 2011, the National Energy Policy Committee had made the resolution to postpone the plan by 3 years. The post-Fukushima atmosphere does not bode well for the public sentiment towards the proposed programme, especially with regards to safety of an NPP. Nonetheless, during the six decades that NPPs have been in operation in 32 countries worldwide, there are only 19 serious accidents involving fatalities and/or damage to properties in excess of 100 million USD. Out of the three significant accidents - Fukushima nuclear accident (2011), Chernobyl nuclear accident (1986), and Three Miles Island nuclear accident (1979) - only the accident at Three Miles Island occurs during normal operation. Such can be implied that the operation of NPPs does maintain a high level of safety. The current technology on nuclear safety has been advancing greatly to the point that the new NPP design claims to render the possibility of a severe accident resulting in core melting insignificant. Along with the technical improvements, laws and regulations have also be progressing in parallel to adequately compensate and limit the liability of operators in case of a nuclear accident. The international agreements such as the Vienna Convention on Civil Liability for Nuclear Damage and the Convention of the Third Party Liability in the Field of Nuclear Energy had also been established and also the national laws of countries such as the United States and Japan have been implemented to address such issues to the point that victims of a nuclear accidents are adequately and justly compensated. In addition to the issues of nuclear accident, the dilemma in nuclear waste management, especially with regards to the High Level Waste which is highly radioactive while having very

  9. Selected works of basic research on the physics and technology of accelerator driven clean nuclear power system

    International Nuclear Information System (INIS)

    Zhao Zhixiang

    2002-01-01

    38 theses are presented in this selected works of basic research on the physics and technology of accelerator driven clean nuclear power system. It includes reactor physics and experiment, accelerators physics and technology, nuclear physics, material research and partitioning. 13 abstracts, which has been presented on magazines home and abroad, are collected in the appendix

  10. Design of off-gas and air cleaning systems at nuclear power plants

    International Nuclear Information System (INIS)

    1987-01-01

    The primary purpose of this report is to describe the current design of air and process off-gas cleaning technologies used in nuclear power plants (NPPs). Because of the large inventory of fission products that are produced in the fuel (i.e. in the range of 5x10 19 Bq per GW(e)·a) and the highly restrictive airborne radionuclide release limits being established by Member States, air and process off-gas cleaning technologies are constantly being improved to provide higher airborne radionuclide recovery efficiencies and a smaller probability of malfunction. For various technologies considered an attempt has been made to provide the following information: (a) Process description in terms of principles of off-gas and air cleaning, operating parameters and system performance; (b) Design for normal and accident situations; (c) Design of components with regard to construction materials, size, shape and geometry of the system, resistance to chemical and physical degradation from the operational environment, safety and quality assurance requirements

  11. New research discovery may mean less radioactive contamination, safer nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Murph, S. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-06-20

    Murph has now made another nanoparticle breakthrough that could benefit various work environments such as nuclear power plants. Murph and her team have created nanoparticle treated stainless steel filters that are capable to capturing radioactive vapor materials. Just like air filters capture dust and dirt, these filters are capable of capturing large amounts of radioactive vapors. The new research may one day mean that nuclear power plant workers, and other workers in related fields, will have a safer working environment.

  12. Forecast of energy demand in China and introduction of nuclear power using the clean development mechanism

    International Nuclear Information System (INIS)

    Ikemoto, Ichiro

    2003-01-01

    As an economic energy source with low greenhouse gas emissions and essentially no resource limitations, nuclear power is a promising option for meeting the rapidly growing energy demands of China that is being driven by rapid population and economic growth. This paper examines an introduction scenario for nuclear power in China by using the clean development mechanism, based on quantitative evaluation of energy demand forecasts and the nuclear fuel cycle through 2100. The results of the case study concluded that in the short to mid term, large-scale light water reactors will primarily be sited in coastal areas where infrastructure development is advanced. In the future, as dispersed power sources in inland areas, small scale FBRs will be preferred due to their promising safety, operation and maintenance characteristics, ease of transportation of plant equipment and plant construction and the possibility of on-site nuclear fuel cycle. Evaluation of nuclear fuel cycle showed that this introduction scenario is feasible considering natural Uranium demand, Uranium enrichment capacity and reprocessing capacity. (author)

  13. Ukrainian efforts in preventing illicit trafficking in nuclear materials and other radioactive sources

    International Nuclear Information System (INIS)

    Kondratov, S.I.

    1998-01-01

    The Ukrainian efforts in preventing illicit trafficking in nuclear materials and other radioactive sources are described. Attention is paid for Ukrainian Government's Decree intended, in particular, to facilitate in establishing well-coordinated activities of the Ukrainian law enforcement bodies and other agencies involved, assigning the status of the main expert organization on illicit trafficking in nuclear materials to the Scientific Center 'Institute for Nuclear Research', in developing the three-years Program on prevention illicit trafficking in nuclear materials and other radioactive sources on the Ukrainian territory as well as measures at the State and customs borders. The main directions provided by the draft Program mentioned are presented as well. (author)

  14. Nuclear safety requirements for upgrading the National Repository for Radioactive Wastes-Baita Bihor

    International Nuclear Information System (INIS)

    Vladescu, Gabriela; Necula, Daniela

    2000-01-01

    The upgrading project of National Repository for Radioactive Wastes-Baita Bihor is based on the integrated concept of nuclear safety. Its ingredients are the following: A. The principles of nuclear safety regarding the management of radioactive wastes and radioprotection; B. Safety objectives for final disposal of low- and intermediate-level radioactive wastes; C. Safety criteria for final disposal of low- and intermediate-level radioactive wastes; D. Assessment of safety criteria fulfillment for final disposal of low- and intermediate-level radioactive wastes. Concerning the nuclear safety in radioactive waste management the following issues are considered: population health protection, preventing transfrontier contamination, future generation radiation protection, national legislation, control of radioactive waste production, interplay between radioactive waste production and management, radioactive waste repository safety. The safety criteria of final disposal of low- and intermediate-level radioactive wastes are discussed by taking into account the geological and hydrogeological configuration, the physico-chemical and geochemical characteristics, the tectonics and seismicity conditions, extreme climatic potential events at the mine location. Concerning the requirements upon the repository, the following aspects are analyzed: the impact on environment, the safety system reliability, the criticality control, the filling composition to prevent radioactive leakage, the repository final sealing, the surveillance. Concerning the radioactive waste, specific criteria taken into account are the radionuclide content, the chemical composition and stability, waste material endurance to heat and radiation. The waste packaging criteria discussed are the mechanical endurance, materials toughness and types as related to deterioration caused by handling, transportation, storing or accidents. Fulfillment of safety criteria is assessed by scenarios analyses and analyses of

  15. Review of failures in nuclear air cleaning systems (1975--1978)

    International Nuclear Information System (INIS)

    Moeller, D.W.

    1979-01-01

    During the period from January 1, 1975 through June 30, 1978, over 9,000 Licensee Event Reports (LERs) pertaining to the operation of commercial light water nuclear power plants in the US were reported to the Nuclear Regulatory Commission. Of these reports, over 1,200 (approximately 13%) pertained to failures in air monitoring, ventilating and cleaning systems. For BWR installations, over half of the reported events related to failures in equipment for monitoring the performance of air cleaning systems as contrasted to failures in the systems themselves. In PWR installations, failures in monitoring equipment amounted to about 32% of the total. Reported problem areas in BWR installations included the primary containment and standby gas treatment and off-gas systems, as well as the High Pressure Coolant Injection and Reactor Core Isolation Systems. For PWR installations, reported problem areas included primary containment and associated spray systems and waste processing equipment. Although data on reported failures in power reactor installations can be interpreted in a variety of ways, one message is clear. There is a need for research on the development of more reliable equipment for sampling and monitoring air systems. Equipment that provides inaccurate data on the performance of such systems can lead to as many problems as inadequacies in the systems themselves

  16. Predicting the radioactive contamination of the surroundings near a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Khristova, M; Paskalev, Z

    1975-01-01

    Predicting the radioactive contamination requires determining the concentration of radioactive material emitted from the stack of a nuclear power plant into the air and deposited on the earth's surface. The main factors determining the degree of contamination are the distance from the stack, the wind velocity and air turbulence. Formulas are presented for predicting the amount of radioactivity as a function of the initial concentration of activity, the distance from the stack and the meteorological condition. Formulas are given for the maximum deposition of radioactive aerosols at a distance R from the stack under wet and dry condtions. 2 refs. (SJR)

  17. Problems and management of radioactive sources and measures against illicit trafficking of nuclear materials in Bulgaria

    International Nuclear Information System (INIS)

    Strezov, A.

    1998-01-01

    Illicit trafficking of nuclear materials continues to pose a danger to public health and safety and to nuclear non proliferation efforts. The majority of cases so far have involved only small amounts of fissile materials or mainly radioactive sources in Bulgaria. A proper scheme for analysis of seized nuclear materials will be developed based on existing equipment for NDA analysis of nuclear materials supplemented by new system through PHARE project assistance by EU experts. (author)

  18. Public perception on nuclear energy and radioactive waste - The second opinion poll

    International Nuclear Information System (INIS)

    Diaconu, Stela; Covreag Ilinca

    2009-01-01

    In 2008 ANDRAD started the second national opinion poll which had the purpose to identify the support of Romanian citizen for energy production by nuclear power stations, which is perceived as a less expensive energy, that could reduces the oil dependence of our country. The questionnaire consisted in 22 questions aiming to assess: the level of information about radioactive waste, the actual knowledge about radioactive waste management, the support and the opinion on nuclear energy, the public attitude regarding radioactive waste disposal, the trust in information sources and the public involvement in the decision-making process. (authors)

  19. In-situ measurement of environment radioactivity by mobile nuclear field laboratory (MNFL)

    International Nuclear Information System (INIS)

    Gopalani, Deepak; Mathur, A.P.; Rawat, D.K.; Barala, S.S.; Singhal, K.P.; Singh, G.P.; Samant, R.P.

    2008-01-01

    In-situ measurement of environment radioactivity is useful tool for determine the unusual increase of radioactivity at any place due to any nuclear eventuality take place. A mobile nuclear field laboratory has been designed and developed for in-situ measurement of environment radioactivity at any desired location. This vehicle is equipped with different monitoring and analysis instruments. These equipment can be operated while vehicle is moving. The measured data can be stored in computer. This vehicle has the space for storage of various environmental matrices of affected area and these can analysis in laboratory. (author)

  20. Experiments with radioactive nuclear beams II; Experimentos con haces nucleares radiactivos II

    Energy Technology Data Exchange (ETDEWEB)

    Aguilera R, E.F.; Martinez Q, E.; Gomez C, A.; Lizcano C, D.; Garcia M, H.; Rosales M, P. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2001-12-15

    The studies of nuclear reactions with heavy ions have been carried out for years for the group of heavy ions of the laboratory of the Accelerator of the ININ. Especially in the last years the group has intruded in the studies of nuclear reactions with radioactive beams, frontier theme at world level. Presently Technical Report is presented in detailed form the experimental methods and the analysis procedures of the research activities carried out by the group. The chpater II is dedicated to the procedures used in the analysis of the last two experiments with radioactive beams carried out by the group. In the chapter III is presented the procedure followed to carrying out an extended analysis with the CCDEF code, to consider the transfer channel of nucleons in the description of the fusion excitation functions of a good number of previously measured systems by the group. Finally, in the chapter IV the more important steps to continue in the study of the reaction {sup 12}C + {sup 12}C experiment drifted to be carried out using the available resources of the Tandem Accelerator Laboratory of the ININ are described. At the end of each chapter some of the more representative results obtained in the analysis are presented and emphasis on the scientific production generated by the group for each case is made. (Author)

  1. Use of fixation techniques in processing radioactive wastes from nuclear power plants in Czechoslovakia

    International Nuclear Information System (INIS)

    Seliga, M.

    1977-01-01

    The current state of radioactive waste disposal from the Bohunice nuclear power plant is described. The method of vacuum cementation was chosen for solidifying liquid radioactive wastes. This method makes it possible to obtain a product whose properties, namely strength, leachability, and radiation stability allow for the production of blocks without packing material. Also solved was the fixation of liquid radioactive waste using bituminization based on mixing liquid radioactive waste with aqueous bitumen emulsion in a film evaporator in which the mixture of liquid radioactive wastes and bitumen emulsion evaporate producing solid bitumen. The parameters are given of the cementation and bituminization lines which are designed for use in nuclear power plants with WWER type reactors. (J.B.)

  2. Development of RadRob15, A Robot for Detecting Radioactive Contamination in Nuclear Medicine Departments

    Directory of Open Access Journals (Sweden)

    Shafe A.

    2016-09-01

    Full Text Available Accidental or intentional release of radioactive materials into the living or working environment may cause radioactive contamination. In nuclear medicine departments, radioactive contamination is usually due to radionuclides which emit high energy gamma photons and particles. These radionuclides have a broad range of energies and penetration capabilities. Rapid detection of radioactive contamination is very important for efficient removing of the contamination without spreading the radionuclides. A quick scan of the contaminated area helps health physicists locate the contaminated area and assess the level of activity. Studies performed in IR Iran shows that in some nuclear medicine departments, areas with relatively high levels of activity can be found. The highest contamination level was detected in corridors which are usually used by patients. To monitor radioactive contamination in nuclear medicine departments, RadRob15, a contamination detecting robot was developed in the Ionizing and Non-ionizing Radiation Protection Research Center (INIRPRC. The motor vehicle scanner and the gas radiation detector are the main components of this robot. The detection limit of this robot has enabled it to detect low levels of radioactive contamination. Our preliminary tests show that RadRob15 can be easily used in nuclear medicine departments as a device for quick surveys which identifies the presence or absence of radioactive contamination.

  3. Illicit trafficking of nuclear and other radioactive material in Paraguay

    Energy Technology Data Exchange (ETDEWEB)

    Facetti, J.F. [Institute of Strategic Studies, Asuncion (Paraguay)], E-mail: jfacetti@yahoo.com

    2009-07-01

    ratifying the inexistence of terrorist groups operating in these areas, but confirming the existence of strong evidence of the remittance of foreign currency to extremist Arab groups. Illegal activities in this area are notorious: weapons trafficking, money laundering, drug trafficking, and other types of traffic (nuclear and radioactive materials) cannot be dismissed. The problem is that authorities from no country would wish to have nuclear or radiological materials stolen or misplaced in them and then used to fabricate a 'dirty' bomb to perpetrate attacks. This document analyzes the situation of sector policies (international binding and non-binding agreements legal instruments, internal security policies, defence programs and plans, etc.); global and national threats; the nature of actions taken by the Paraguayan Government through effective mechanisms for coordination including planning, implementation and monitoring, and relevant collaborative actions implemented with the International Atomic Energy Agency - IAEA. (author)

  4. Illicit trafficking of nuclear and other radioactive material in Paraguay

    International Nuclear Information System (INIS)

    Facetti, J.F.

    2009-01-01

    ratifying the inexistence of terrorist groups operating in these areas, but confirming the existence of strong evidence of the remittance of foreign currency to extremist Arab groups. Illegal activities in this area are notorious: weapons trafficking, money laundering, drug trafficking, and other types of traffic (nuclear and radioactive materials) cannot be dismissed. The problem is that authorities from no country would wish to have nuclear or radiological materials stolen or misplaced in them and then used to fabricate a 'dirty' bomb to perpetrate attacks. This document analyzes the situation of sector policies (international binding and non-binding agreements legal instruments, internal security policies, defence programs and plans, etc.); global and national threats; the nature of actions taken by the Paraguayan Government through effective mechanisms for coordination including planning, implementation and monitoring, and relevant collaborative actions implemented with the International Atomic Energy Agency - IAEA. (author)

  5. Challenges in ensuring radiological safety and nuclear forensic for malicious acts involving nuclear and other radioactive material

    International Nuclear Information System (INIS)

    Sharma, Ranjit; Chatterjee, M.K.; Singh, Rajvir; Pradeepkumar, K.S.

    2010-01-01

    Nuclear and other radioactive materials may get smuggled into the country aimed at malicious acts. Radioactive material detected accidentally or during inspection at the entry points/national borders may indicate illicit trafficking for the purpose of nuclear/radiological terrorism. As country requires prevention and preparedness for response to these malicious acts, nuclear forensic techniques are to be developed incorporating radiological safety aspects. Nuclear forensics helps in determining the origin, intended use, legal owner and the smuggled route etc. by using fingerprinting as well as comparison with reference data. The suggested sequence of methods for analysis of radioactive material/samples will be radiological assessment, physical characterization, traditional forensic analysis, isotope analysis along with elemental/chemical analysis

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

    International Nuclear Information System (INIS)

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

    2017-05-01

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

  7. Emulsion type dry cleaning system

    International Nuclear Information System (INIS)

    Kohanawa, Osamu; Matsumoto, Hiroyo.

    1988-01-01

    Protective clothing against radioactive contamination used in the radiation controlled areas of nuclear plants has been washed by the same wet washing as used for underwear washing, but recently dry cleaning is getting used in place of wet washing, which generates a large quantity of laundry drain. However, it was required to use wet washing once every five to ten dry cleanings for washing protective clothing, because conventional dry cleaning is less effective in removing water-soluble soils. Therefore, in order to eliminate wet washing, and to decrease the quantity of laundry drains, the emulsion type dry cleaning system capable of removing both oil-soluble and water-soluble soils at a time has been developed. The results of developmental experiments and actual application are presented in this paper. (author)

  8. Nuclear power for greenhouse gas mitigation under the Kyoto protocol: The Clean Development Mechanism (CDM)

    International Nuclear Information System (INIS)

    Rogner, H.-H.

    2000-01-01

    At the 43rd regular session of the IAEA General Conference, Member States requested the IAEA to help countries in assessing nuclear power's role in light of global environmental challenges and energy needs. Such assistance should include support for implementing national case studies, and facilitating access to relevant information about nuclear power's role in achieving sustainable development in developing countries and in mitigating GHG emissions. The dissemination of information on CDM is of particular importance to developing countries, so as to enable Member States interested in the mechanism to take an active and informed role in the debate regarding the Kyoto Protocol and eligible CDM technologies. Therefore, the Secretariat organized a series of information seminars, workshops and training courses for Member States on the Kyoto Protocol, the Clean Development Mechanism, Joint Implementation and Emissions Trading with particular emphasis on the potential role of nuclear power for GHG mitigation. On request, the Secretariat also provided training and assistance to several Member States in the preparation of national case studies that explore the potential role of nuclear power as a CDM technology. These case studies will be presented by the respective national study teams during this side event at the 44th IAEA General Conference. Within the general criteria included in the Kyoto Protocol, the decision on which technologies are eligible for GHG mitigation under the flexibility mechanisms is a sovereign decision of each country

  9. Accumulation of radioactive cesium released from Fukushima Daiichi Nuclear Power Plant in terrestrial cyanobacteria Nostoc commune.

    Science.gov (United States)

    Sasaki, Hideaki; Shirato, Susumu; Tahara, Tomoya; Sato, Kenji; Takenaka, Hiroyuki

    2013-01-01

    The Fukushima Daiichi Nuclear Power Plant accident released large amounts of radioactive substances into the environment and contaminated the soil of Tohoku and Kanto districts in Japan. Removal of radioactive material from the environment is an urgent problem, and soil purification using plants is being considered. In this study, we investigated the ability of 12 seed plant species and a cyanobacterium to accumulate radioactive material. The plants did not accumulate radioactive material at high levels, but high accumulation was observed in the terrestrial cyanobacterium Nostoc commune. In Nihonmatsu City, Fukushima Prefecture, N. commune accumulated 415,000 Bq/kg dry weight (134)Cs and 607,000 Bq kg(-1) dry weight (137)Cs. The concentration of cesium in N. commune tended to be high in areas where soil radioactivity was high. A cultivation experiment confirmed that N. commune absorbed radioactive cesium from polluted soil. These data demonstrated that radiological absorption using N. commune might be suitable for decontaminating polluted soil.

  10. Risk Informed Approach for Nuclear Security Measures for Nuclear and Other Radioactive Material out of Regulatory Control. Implementing Guide

    International Nuclear Information System (INIS)

    2015-01-01

    This publication provides guidance to States for developing a risk informed approach and for conducting threat and risk assessments as the basis for the design and implementation of sustainable nuclear security systems and measures for prevention of, detection of, and response to criminal and intentional unauthorised acts involving nuclear and other radioactive material out of regulatory control. It describes concepts and methodologies for a risk informed approach, including identification and assessment of threats, targets, and potential consequences; threat and risk assessment methodologies, and the use of risk informed approaches as the basis for informing the development and implementation of nuclear security systems and measures. The publication is an Implementing Guide within the IAEA Nuclear Security Series and is intended for use by national policy makers, law enforcement agencies and experts from competent authorities and other relevant organizations involved in the establishment, implementation, maintenance or sustainability of nuclear security systems and measures related to nuclear and other radioactive material out of regulatory control

  11. Prevention of the inadvertent movement and illicit trafficking of radioactive and nuclear materials in Argentine border

    International Nuclear Information System (INIS)

    Bonet Duran, Stella M.; Canibano, Javier A.; Menossi, Sergio A.; Rodriguez, Carlos E.

    2004-01-01

    The inadvertent and illegal movements of radioactive and nuclear materials are issues of increased national and international awareness. States are progressively becoming more conscious of the need to adequately respond to these events. As regards the States' regulatory infrastructure, the design and enforcement of control and verification measures to maintain the continuity of knowledge about possession, use and movements of radioactive and nuclear materials is of critical importance. The existence of an appropriate legislative framework and a regulatory authority empowered to establish effective safety and security measures are essential to prevent inadvertent and illegal movements of nuclear materials and other radioactive materials. The events of Sep. 11, 2001 in the US have increased the States' awareness on the need to review their national infrastructure to identify additional measures against inadvertent and illegal movements of radioactive and nuclear materials as well as against sabotage of nuclear facilities. Argentina has more than a half- century- old tradition regarding the control and supervision of all activities involving the use of nuclear and radioactive materials. The Nuclear Regulatory Authority (ARN) of Argentina is the organization with federal competence in radiation protection, nuclear safety, safeguards and physical protection. It is responsible for issuing licenses and permits to any activity involving radioactive materials and for controlling and verifying that these activities are performed in full compliance with ARN standards and requirements. In the region, Argentina has been playing an important role in the prevention of illicit traffic of nuclear and radioactive materials for the last years within the framework of Security Commission of MERCOSUR. The last goals of this initiative are to define and coordinate actions and to establish a set of common operational procedures in the countries participating in the mentioned multilateral

  12. Experimentation of nuclear weapons, releases and storages of radioactive wastes in the Kara sea and in New Zemble

    International Nuclear Information System (INIS)

    Charmasson, S.

    1996-01-01

    132 nuclear weapons were tested from 1955 to 1990 in New Zemble. From 1959 to 1993, low level liquid radioactive wastes, low and medium level solid radioactive wastes, reactor core and fuel of submarine and nuclear propelled ships were released in the Kara and the Barentz seas. For these two seas, a recapitulation of the different radioactive sources and the found level of radioactivity of the marine environment are presented. (A.B.). 22 refs. 4 figs., 6 tabs

  13. Safety Aspects of Radioactive Waste Management in Different Nuclear Fuel Cycle Policies, a Comparative Study

    International Nuclear Information System (INIS)

    Gad Allah, A.A.

    2009-01-01

    With the increasing demand of energy worldwide, and due to the depletion of conventional natural energy resources, energy policies in many countries have been devoted to nuclear energy option. On the other hand, adopting a safe and reliable nuclear fuel cycle concept guarantees future nuclear energy sustain ability is a vital request from environmental and economic point of views. The safety aspects of radioactive waste management in the nuclear fuel cycle is a topic of great importance relevant to public acceptance of nuclear energy and the development of nuclear technology. As a part of nuclear fuel cycle safety evaluation studies in the department of nuclear fuel cycle safety, National Center for Nuclear Safety and Radiation Control (NCNSRC), this study evaluates the radioactive waste management policies and radiological safety aspects of three different nuclear fuel cycle policies. The once-through fuel cycle (OT- fuel cycle) or the direct spent fuel disposal concept for both pressurized light water reactor ( PWR) and pressurized heavy water reactor (PHWR or CANDU) systems and the s elf-generated o r recycling fuel cycle concept in PWR have been considered in the assessment. The environmental radiological safety aspects of different nuclear fuel cycle options have been evaluated and discussed throughout the estimation of radioactive waste generated from spent fuel from these fuel cycle options. The decay heat stored in the spent fuel was estimated and a comparative safety study between the three fuel cycle policies has been implemented

  14. Transportation of radioactive wastes from nuclear fuel cycles

    International Nuclear Information System (INIS)

    1979-09-01

    This paper discusses current and foreseen radioactive waste transportation systems as they apply to the INFCE Working Group 7 study. The types of wastes considered include spent fuel, which is treated as a waste in once-through fuel cycles; high-, medium-, and low-level waste; and gaseous waste. Regulatory classification of waste quantities and containers applicable to these classifications are discussed. Radioactive wastes are presently being transported in a safe and satisfactory manner. None of the INFCE candidate fuel cycles pose any extraordinary problems to future radioactive waste transportation and such transportation will not constitute a decisive factor in the choice of a preferred fuel cycle

  15. Radioactive particles after different nuclear events in the USSR (overview and modern data)

    Energy Technology Data Exchange (ETDEWEB)

    Gordeev, S.K.; Stukin, E.D.; Kvasnikova, E.V. [Institute of Global Climate and Ecology, Moscow (Russian Federation)

    2004-07-01

    Institute of Global Climate and Ecology participated in all stages of investigations concerning spreading of the radioactive particles formed after nuclear explosions. Since 1963 the radioactive particles from the surface nuclear explosions on the Semipalatinsk Test Site were investigated. Since 1964 the study of the environmental contamination from the underground nuclear explosions (including the cratering nuclear explosions) was carried out. Simultaneously the secondary radioactive aerosols released into the atmosphere from ventilated underground explosions were investigated. Since 1986 the forming and spreading of the radioactive aerosols from Chernobyl accident was studied. An overview of retrospective data will be presented. For example, the fragmentation radionuclides {sup 90}Sr, {sup 137}Cs and {sup 155}Eu, radionuclides induced by neutrons {sup 60}Co, {sup 152}Eu, {sup 154}Eu and transuranium radionuclides {sup 238}Pu, {sup 239+240}Pu and {sup 241}Am were estimated in 15 particles of August, 29, 1949 explosion using the semiconductor spectrometry and radiochemical analysis. Data collection include the samples taken on local traces of ground and underground excavation nuclear explosions, this information will be added by the modern data from soil samples near '1004' explosion (lake Chagan), October 2003. The results of comparison of radionuclide fractionation in the radioactive particles in slag from cratering nuclear explosions and in melt samples will be presented. Main results obtained under the IAEA Research Contract no. 11468. (author)

  16. Recommended parameters for effect assessment of radioactive airborne effluents under normal condition of nuclear facilities

    International Nuclear Information System (INIS)

    Li Hong; Fang Dong; Sun Chengzhi; Xiao Naihong

    2003-01-01

    A set of models and default parameters are recommended for effect assessment of radioactive airborne effluents under normal condition of nuclear facilities in order to standardize the environmental effect assessment of nuclear facilities, and to simplify the observation and investigation in early phase. The paper introduces the input data and default parameters used in the model

  17. Significance of iodine radioactive isotopes in the problem of radiation safety of nuclear fuel cycle

    International Nuclear Information System (INIS)

    Malenchenko, A.F.; Mironov, V.P.

    1979-01-01

    The data on actual wastes of nuclear-power plants, environmental distribution and biological effects of iodine radioactive isotopes have been analyzed. Dose-response relationship is estimated as well as its significance for struma maligna development under ionizing radiation and the contribution of iodine radionuclides resulted from nuclear power engineering to this process

  18. Nuclear Technology Series. Course 25: Radioactive Material Handling Techniques.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  19. Natural radioactivity measurements at the proposed nuclear power plant site

    International Nuclear Information System (INIS)

    Cojuangco, J.G.; Salomon, A.Ph.

    1976-01-01

    Natural radioactivity measurement in the Philippines aims to establish baseline radioactivity levels in the environment of items essential to man. In this article, results of the environmental surveillance conducted in Bagac, Bataan from 1973 to 1974 are presented. Analyses were made on air parti-culates, sea and fresh water, grass, and soil samples for gross beta-gamma activities. Results obtained showed activity levels below the maximum permissible concentration recommended by the International Committee on Radiation Protection (ICRP)

  20. Radioactivity of air caused by nuclear bomb tests

    Energy Technology Data Exchange (ETDEWEB)

    Aron, A; Gross, B

    1957-01-01

    Daily checks of radioactive fallout at the above institute (Instituto Nacional de Tecnologia, Rio de Janeiro) gave an activity 10 times as high as the average on June 25, 1957. By applying the decay law for fallout of Way and Wigner the origin could be traced to the British H-bomb test at Christmas Island on May 15, 1957. By autoradiography of the filter it was shown that the high activity was caused by only one highly radioactive particle.

  1. Removing radioactive noble gases from nuclear process off-gases

    International Nuclear Information System (INIS)

    Lofredo, A.

    1977-01-01

    A system is claimed for separating, concentrating and storing radioactive krypton and xenon in the off-gases from a boiling water reactor, wherein adsorption and cryogenic distillation are both efficiently used for rapid and positive separation and removal of the radioactive noble gases, and for limiting such gases in circulation in the system to low inventory at all times, and wherein the system is self-regulating to eliminate operator options or attention

  2. Low radioactivities '85. (The 7th Nuclear Science Colloquium)

    International Nuclear Information System (INIS)

    1985-01-01

    The conference proceedings contain 108 papers. The following topics are dealt with: accelerator mass spectroscopy, rare decays, underground laboratories, low level counting and spectroscopy, double beta-decay experiments, low level detectors, cosmogenic radionuclides and rare events, 14 C counting and applications, 3 H counting and hydrology appllications, natural radioactivity in the environment, gaseous detectors, anthropogenic radionuclides and radioactivity in the environment. (J.P.)

  3. Safe operation of existing radioactive waste management facilities at Dalat Nuclear Research Institute

    International Nuclear Information System (INIS)

    Pham Van Lam; Ong Van Ngoc; Nguyen Thi Nang

    2000-01-01

    The Dalat Nuclear Research Reactor was reconstructed from the former TRIGA MARK-II in 1982 and put into operation in March 1984. The combined technology for radioactive waste management was newly designed and put into operation in 1984. The system for radioactive waste management at the Dalat Nuclear Research Institute (DNRI) consists of radioactive liquid waste treatment station and disposal facilities. The treatment methods used for radioactive liquid waste are coagulation and precipitation, mechanical filtering and ion- exchange. Near-surface disposal of radioactive wastes is practiced at DNRI In the disposal facilities eight concrete pits are constructed for solidification and disposal of low level radioactive waste. Many types of waste generated in DNRI and in some Nuclear Medicine Departments in the South of Vietnam are stored in the disposal facilities. The solidification of sludge has been done by cementation. Hydraulic compactor has done volume reduction of compatible waste. This paper presents fifteen-years of safe operation of radioactive waste management facilities at DNRI. (author)

  4. Verification of radioactive waste management of nuclear medicine clinics in the city of Recife

    International Nuclear Information System (INIS)

    Silva, V.C.B.; Lopes-Filho, F.J.; Passos, R.S.; Lira, R.F.; Santos, M.A.P.; Belo, I.B.; Lima, F.R.A.; Vieira, J.W.; Ferreira-Filho, A.

    2010-01-01

    The increasing use of ionizing radiation in various areas can not be dissociated from the concerns of safety and radiation security. In Nuclear Medicine, this concern becomes higher, because of the radionuclides used in diagnosis and therapy of radiation sources are not sealed. Their use inevitably produces radioactive waste that must be controlled through proper management, according to the normative standards established in Brazil by the National Commission of Nuclear Energy (CNEN). The management of radioactive waste seeks to lower the occupational doses besides the environmental preservation. In the work carried out by the Regional Center of Nuclear Sciences Northeast (CRCN-NE) and the Federal Office for Education, Science and Technology (OPSI), we see the systems management of radioactive waste from Nuclear Medicine in the city of Recife. The results were obtained from the preparation of a sheet of compliance and its implementation in eight clinics. (author)

  5. UK safety and standards for radioactive waste management and decommissioning on nuclear licensed sites

    International Nuclear Information System (INIS)

    Mason, D.J.

    2001-01-01

    This paper discusses the regulation of radioactive waste and decommissioning in the United Kingdom and identifies the factors considered by HM Nuclear Installations Inspectorate in examining the adequacy arrangements for their management on nuclear licensed sites. The principal requirements are for decommissioning to be undertaken as soon as reasonably practicable and that radioactive wastes should be minimised, disposed of or contained and controlled by storage in a passively safe form. However, these requirements have to be considered in the context of major organisational changes in the UK nuclear industry and the non-availability of disposal routes for some decommissioning wastes. The legislative framework used to regulate decommissioning of nuclear facilities in the UK is described. Reference is made to radioactive waste and decommissioning strategies, quinquennial reviews criteria for delicensing and the forthcoming Environmental Impact Assessment Regulations. (author)

  6. Evaluation of nuclear data for emergency preparedness system of nuclear power plants. Comparison of radioactivity inventories by newest nuclear data and rather older nuclear data

    International Nuclear Information System (INIS)

    Yoshida, Yoshitaka; Kimura, Itsuro

    2004-01-01

    The radioactivity inventories for emergency preparedness systems of nuclear power plants calculated by the combination of the generally-used in Japan (general-version), the INSS used by the present authors (INSS-version) and the newest nuclear data library and codes (newest-version) were compared, and the maintaining of conservativeness of the general-version and the INSS-version against the newest-version was examined. And the influences of the radioactivity inventories by the difference between the nuclear cross section and fission yield data, decay data and calculation codes were investigated. As a result, (1) the radioactivity inventories calculated by general-version and INSS-version were not confirmed the conservativeness to the newest-version. But the difference was less than 10%, and it would not give large influence to the calculation of the emergency preparedness system of nuclear plants. (2) The influence of the radioactivity inventories such as 135 Xe build-up were observed by the difference of neutron flux level in an operation of reactors that occurred by the variety of nuclear cross section and fission yield data. (3) Little influence by the variety of decay data was confirmed. (4) The ORIGEN2.1 code underestimated the amount of fission products generated by fission of minor actinides. From these result, the radioactivity inventories for the emergency preparedness system of nuclear power plants are recommended to use the calculation results by the combination of the library for ORIGEN2 based on JENDL3.3 and the ORIGEN2.2 code. (author)

  7. Reactor, radioactive isotopes and nuclear energy: their avatars in Venezuela

    International Nuclear Information System (INIS)

    Roche, M.

    1981-01-01

    A brief history of nuclear affairs in Venezuela, since the decision to bring a research reactor (3MW) to Venezuela (1954) to current situation, is presented. Since the establishment of the National Council for Nuclear Affairs (CONAN) and then of the National Council for the Development of Nuclear Industry (CONADIN), steps are being taken to train nuclear engineers, since most studies thus far indicate the last few years of the Century as the time when nuclear energy will have to supplement other sources

  8. New safety and security requirements for the transport of nuclear and other radioactive materials in Hungary

    International Nuclear Information System (INIS)

    Katona, T.; Horvath, K.; Safar, J.

    2016-01-01

    In addition to the promulgation of mode-specific regulations of international transport of dangerous goods, some Hungarian governmental and ministerial decrees impose further conditions upon the transport of nuclear and other radioactive materials. One of these ministerial decrees on the transport, carriage and packaging of radioactive materials is under revision and it will require • approval of emergency response plan (including security and safety contingency plan); • report on transport incidents and accidents for classifying them in accordance with the INES scale; • the competent authority to request experts’ support for the approval of package designs, radioactive material designs and shipments. Regarding the security of the transport of nuclear and other radioactive materials a new Hungarian governmental decree and a related guidance are about to be published which will supply additional requirements in the field of the transport security especially concerning radioactive materials, implementing - among others - IAEA recommendations of the NSS No9 and No14. The main and relevant features of the Hungarian nuclear regulatory system and the details of both new decrees regarding the safety and security issues of transport of nuclear and other radioactive materials will be discussed. (author)

  9. Terrain and building effects on the transport of radioactive material at a nuclear site

    International Nuclear Information System (INIS)

    Jeong, Hyojoon; Park, Misun; Jeong, Haesun; Hwang, Wontae; Kim, Eunhan; Han, Moonhee

    2014-01-01

    Highlights: • This study is to quantify the building and terrain effects on the atmospheric dispersion. • Statistical methods with AERMOD-PRIME and CFD were used. • To assess the risk in nuclear power plants, terrain and building effects have to be considered. - Abstract: This study identified the terrain and building effects on the atmospheric dispersion of radioactive materials at the Wolsong Nuclear Site. To analyze the atmospheric dispersion of radioactive materials, the AERMOD-PRIME model, CFD model and meteorological data from 2010 were used. The terrain and building effects on the atmospheric dispersion of radioactive materials within a 1 km radius of the site were statistically significant. The maximum concentration of the radioactive material increased by 7 times compared to the concentration when the terrain and building effects were not considered. It was found that the terrain and building influenced the decrease in the concentration of radioactive material in a concentric circle with a 914 m radius from the center of the site. The concentration of radioactive material in a concentric circle with a 350 m radius was two-times higher than the concentration estimated at the backside of the building, which is the downwind side, without any consideration of the terrain and building effects. In consideration of the Korean situation, in which multiple nuclear reactors are built on the same nuclear site, it is necessary to evaluate the risk that may affect workers and nearby residents by reflecting the terrain and building effects

  10. Method of and apparatus for cleaning garments and soft goods contaminated with nuclear, chemical and/or biological contaminants

    International Nuclear Information System (INIS)

    Fowler, D.E.

    1989-01-01

    A method is described for decontaminating garments, soft good or mixtures thereof contaminated with radioactive particulates, toxin, chemical, and biological contaminants comprising the steps of: (a) depositing contaminated garments, soft goods or mixtures thereof in a cleaning drum; (b) charging the drum with a cleaning solvent in which the chemical contaminants are soluble; (c) agitating the drum during a wash cycle to separate radioactive, toxin, biological particulate matter of mixtures thereof from the garments; (d) draining the drum of the dry cleaning solvent which contains suspended particulate contaminants and dissolved chemical contaminants; (e) contacting the drained solvent with both a neutralizing agent and an oxidizing agent, the neutralizing agent being selected from the group consisting of sodium hydroxide, potassium hydroxide and mixtures thereof and having a concentration greater than one (1.0) normal; (f) rinsing the garments, soft goods or mixtures thereof by circulating clean solvent from a solvent tank through the drum thereby effecting additional removal and flushing of particulate and chemical contaminants; (g) filtering the circulated solvent to remove the particulate material suspended in the solvent prior to addition to the drum; and (h) preferentially adsorbing the chemical contaminants dissolved in the circulated solvent prior to addition to the drum

  11. Illicit trafficking of nuclear and other radioactive material: The 'net' security threat

    International Nuclear Information System (INIS)

    Zaitseva, L.; Steinhausler, F.

    2006-01-01

    Illicit trafficking in nuclear and other radioactive material, which could be used for building a nuclear weapon or a radiological dispersal device, has been a subject of concern for more than a decade. A major obstacle to assessing the actual security threat due to nuclear trafficking is the inclusion in the analysis of incidents that do not represent a security threat, in the sense of being a possible pre-stage to a clandestine nuclear weapons programme or a terrorist operation involving a crude nuclear device or a radiological dispersal device. International transport of contaminated scrap metal, or discovery of lost or abandoned radioactive sources are examples of such incidents, which have little or no security relevance. This paper analyses the global data contained in the Database on Nuclear Smuggling, Theft and Orphan Radiation Sources (DSO) using special filters to discriminate between incidents that are of security relevance and those that are not. (author)

  12. Underwater cleaning techniqued used for removal of zebra mussels at the FitzPatrick Nuclear Power Plant

    International Nuclear Information System (INIS)

    Hobbs, B.; Kahabka, J.

    1995-01-01

    This paper discusses the use of a mechanical brush cleaning technology recently used to remove biofouling from the Circulating Water (CW) System at New York Power Authority's James A. FitzPatrick Nuclear Power Plant. The FitzPatrick plant had previously used chemical molluscicide to treat zebra mussels in the CW system. Full system treatment was performed in 1992 with limited forebay/screenwell treatment in 1993. The New York Power Authority (NYPA) decided to conduct a mechanical cleaning of the intake system in 1994. Specific project objectives included: (1) Achieve a level of surface cleaniness greater than 98%; (2) Remove 100% of debris, both existing sediment and debris generated as a result of cleaning; (3) Inspect all surfaces and components, identifying any problem areas; (4) Complete the task in a time frame within the 1994-95 refueling outage schedule window, and; (5) Determine if underwater mechanical cleaning is a cost-effective zebra mussel control method suitable for future application at FitzPatrick. A pre-cleaning inspection, including underwater video photography, was conducted of each area. Cleaning was accomplished using diver-controlled, multi-brush equipment included the electro-hydraulic powered Submersible Cleaning and Maintenance Platform (SCAMP), and several designs of hand-held machines. The brushes swept all zebra mussels off surfaces, restoring concrete and metal substrates to their original condition. Sensitive areas including pump housings, standpipes, sensor piping and chlorine injection tubing, were cleaned without degradation. Submersible vortex vacuum pumps were used to remove debris from the cavity. More than 46,000 ft 2 of surface area was cleaned and over 460 cubic yards of dewatered debris were removed. As each area was completed, a post-clean inspection with photos and video was performed

  13. Preventive acid chemical cleaning operation (PACCO) on steam generator in French nuclear power plants

    International Nuclear Information System (INIS)

    Traino, Jules; Ruiz Martinez, Jose Thomas; Rottner, Bernard; Vedova, Eric

    2014-01-01

    Steam Generators (SG) usually present important deposit loading and Tube Support Blockage, resulting from Secondary Side corrosion products. These phenomena modify SG behavior which can lead to safety, heat exchange performance and lifetime problems. In this context, a Chemical Cleaning Process (PACCO) was designed to solve the issue. After almost two years of intensive lab tests, pilot simulation and mock-ups, the chemical process was finally qualified by EDF. The aim of the work was firstly the development in laboratory of a chemical process that could eliminate partially the deposit loading, respecting the integrity of materials and gas emission limits. Secondly, the objective was the design and the implementation of the process on-site. The process has been applied successfully in 3 SG in Dampierre nuclear power plant in France on July 2013. The main results were: - Corrosion < 100 μm. - 40% of the initial deposit loading, removed by SG. (authors)

  14. Nuclear Structure Studies On Exotic Nuclei With Radioactive Beams - Present Status And Future Perspectives At FAIR

    International Nuclear Information System (INIS)

    Peter Egelhof

    2011-01-01

    The investigation of nuclear reactions using radioactive beams in inverse kinematics gives access to a wide field of nuclear structure studies in the region far off stability. The basic concept and the methods involved are briefly discussed, and an overview including some selected examples of recent results obtained with radioactive beams from the present fragment separator at GSI Darmstadt is presented. The experimental conditions expected at the future international facility FAIR will, among others, allow for a substantial improvement in intensity and quality of radioactive beams as compared to present facilities. Therefore, it is expected that FAIR will provide unique opportunities for nuclear structure studies on nuclei far off stability, and will allow to explore new regions in the chart of nuclides of high interest for nuclear structure and nuclear astrophysics. A brief overview on the new facility, and on the experimental setups planned for nuclear structure research with radioactive beams is given. For nuclear reaction studies several complex, highly efficient, high resolution, and universal detection systems such as R 3 B, EXL, ELISe, etc. are presently under design and construction. A brief overview on the research objectives and the technical realization will be presented. (author)

  15. Radioactive waste management of the nuclear medicine services; Gestao de rejeitos radioativos em servicos de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Barboza, Alex

    2009-07-01

    Radioisotope applications in nuclear medicine services, for diagnosis and therapy, generate radioactive wastes. The general characteristics and the amount of wastes that are generated in each facility are function of the number of patients treated, the procedures adopted, and the radioisotopes used. The management of these wastes embraces every technical and administrative activity necessary to handle the wastes, from the moment of their generation, till their final disposal, must be planned before the nuclear medicine facility is commissioned, and aims at assuring people safety and environmental protection. The regulatory framework was established in 1985, when the National Commission on Nuclear Energy issued the regulation CNEN-NE-6.05 'Radioactive waste management in radioactive facilities'. Although the objective of that regulation was to set up the rules for the operation of a radioactive waste management system, many requirements were broadly or vaguely defined making it difficult to ascertain compliance in specific facilities. The objective of the present dissertation is to describe the radioactive waste management system in a nuclear medicine facility and provide guidance on how to comply with regulatory requirements. (author)

  16. Radioactive waste management of the nuclear medicine services; Gestao de rejeitos radioativos em servicos de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Barboza, Alex

    2009-07-01

    Radioisotope applications in nuclear medicine services, for diagnosis and therapy, generate radioactive wastes. The general characteristics and the amount of wastes that are generated in each facility are function of the number of patients treated, the procedures adopted, and the radioisotopes used. The management of these wastes embraces every technical and administrative activity necessary to handle the wastes, from the moment of their generation, till their final disposal, must be planned before the nuclear medicine facility is commissioned, and aims at assuring people safety and environmental protection. The regulatory framework was established in 1985, when the National Commission on Nuclear Energy issued the regulation CNEN-NE-6.05 'Radioactive waste management in radioactive facilities'. Although the objective of that regulation was to set up the rules for the operation of a radioactive waste management system, many requirements were broadly or vaguely defined making it difficult to ascertain compliance in specific facilities. The objective of the present dissertation is to describe the radioactive waste management system in a nuclear medicine facility and provide guidance on how to comply with regulatory requirements. (author)

  17. Interactive information system on the nuclear physics properties of nuclides and radioactive decay chains

    International Nuclear Information System (INIS)

    Plyaskin, V.I.; Kosilov, R.A.; Manturov, G.N.

    2001-01-01

    A brief review is given of a computerized information system on the nuclear physics properties of nuclides and radioactive decay chains. The main difference between the system presented here and those already in existence is that these evaluated databases of nuclear physics constants are linked to a set of programs, thus enabling analysis of a wide range of problems regarding various nuclear physics applications. (author)

  18. Extended-life nuclear air cleaning filters via dynamic exclusion prefilters

    Energy Technology Data Exchange (ETDEWEB)

    Wright, S.R.; Crouch, H.S.; Bond, J.H. [Micro Composite Materials Corp., Durham, NC (United States)

    1997-08-01

    The primary objective of this investigation was to ascertain if a dynamic, self-cleaning particulate exclusion precleaner, designed for relatively large dust removal (2 to 100+ {mu}m diameter particles) from helicopter turbine inlets, could be extended to submicron filtration. The improved device could be used as a prefilter for HEPA filtration systems, significantly increasing service life. In nuclear air cleaning, its use would reduce the amount of nuclear particulate matter that would otherwise be entrapped in the HEPA filter cartridge/panel, causing fouling and increased back pressure, as well as requiring subsequent disposal of the contaminated media at considerable expense. A unique (patent-pending) mechanical separation device has recently been developed to extract particulate matter from fluid process streams based on a proprietary concept called Boundary Layer Momentum Transfer (BLMT). The device creates multiple boundary layers that actively exclude particles from entering the perimeter of the device, while allowing air to traverse the boundaries relatively unimpeded. A modified two-dimensional (2-D) computerized flow simulation model was used to assist in the prototype design. Empirical results are presented from particle breakthrough and AP experiments obtained from a reduced-scale prototype filter. Particles larger than 0.23 {mu}m were actively excluded by the prototype, but at a higher pressure drop than anticipated. Experimental data collected indicates that the filter housing and the inlet flow configuration may contribute significantly to improvements in device particle separation capabilities. Furthermore, preliminary experiments have shown that other downstream pressure drop considerations (besides those just across the spinning filtration disks) must be included to accurately portray the AP across the device. Further detailed quantitative investigations on a larger scale (1,000 CFM) prototype are warranted. 3 refs., 5 figs., 2 tabs.

  19. The Activities of Nuclear Training Centre Ljubljana in the Area of Radioactive Waste Management

    International Nuclear Information System (INIS)

    Jencic, I.

    2006-01-01

    Nuclear Training Centre Ljubljana has several activities related to radioactive waste management. These activities include training of professionals in the area of nuclear physics and nuclear technology, radiation protection courses, organization of international courses and workshops in the area of radioactive waste management, and public information on radioactivity and waste management. The paper will describe the specifics and the extent of training related to radioactive waste. Recently we have participated in a European coordination action CETRAD and an overview of the results of this project will also be presented. Very important component of our activity is public information that is based on an information centre and live lectures to organized groups of visitors, mostly schoolchildren. About one half of one school generation of Slovenia visits the Information centre every year. A poll is conducted among visitors every year and its results are a very useful tool to follow the evolution of public opinion on nuclear energy and radioactive waste disposal. The latter is, at least in Slovenia, still considered as the major obstacle against the use of nuclear energy. (authors)

  20. Forecasting of the radioactive material transport demand for the Brazilian Nuclear Program and the security aspects

    International Nuclear Information System (INIS)

    Meldonian, Nelson Leon

    1979-01-01

    In the nuclear fuel cycle, a lot of radioactive materials are produced. These radioactive materials must be transported in order to promote the integration of the fuel cycle units. Considerations about the transport characteristics of radioactive material were made for each section of the fuel cycle. These considerations were based on the experience of several countries and in accordance with the International Atomic Energy Agency regulations. A prediction of transport demands for the Brazilian Nuclear Program until year 2.010 was made. The prediction refers mainly to the quantity of radioactive material produced in each section of the cycle the quantity of vehicles needed for the transport of these materials. Several safety aspects were considered specially, the accidents predictions for years 2.000 and 2.010. The accident probability in Brazilian railroads and highways was compared with that of the USA. (author)

  1. Method and apparatus for removing radioactive gases from a nuclear reactor

    International Nuclear Information System (INIS)

    Frumerman, R.; Brown, W.W.

    1975-01-01

    A description is given of a method for removing radioactive gases from a nuclear reactor including the steps of draining coolant from a nuclear reactor to a level just below the coolant inlet and outlet nozzles to form a vapor space and then charging the space with an inert gas, circulating coolant through the reactor to assist the release of radioactive gases from the coolant into the vapor space, withdrawing the radioactive gases from the vapor space by a vacuum pump which then condenses and separates water from gases carried forward by the vacuum pump, discharging the water to a storage tank and supplying the separated gases to a gas compressor which pumps the gases to gas decay tanks. After the gases in the decay tanks lose their radioactive characteristics, the gases may be discharged to the atmosphere or returned to the reactor for further use

  2. Master Training in Radiological Protection Facilities Radioactive and Nuclear

    International Nuclear Information System (INIS)

    Verdu, G.; Mayo, P.; Campayo, J. M.

    2011-01-01

    The master includes general aspects of radiation protection in nuclear facilities. also an advanced module to acquire a high level training highlights as nuclear decommissioning, shielding calculation using advanced codes, particle accelerators, international law, etc.

  3. Interim report to the Nuclear Regulatory Commission on radioactive waste classification

    International Nuclear Information System (INIS)

    King, W.C.; Cohen, J.J.

    1977-01-01

    The Lawrence Livermore Laboratory assisted the Nuclear Regulatory Commission in the development of a radioactive waste classification system that will satisfy technical, environmental, and societal concerns. This is an interim report to the NRC on work accomplished to date. It describes a proposed waste-classification system that is based on the final disposition of waste material. The system consists of three classes of radioactive waste. The classification of any radioactive waste will depend primarily on its hazard potential. Other characteristics such as longevity (half-size) will be considered also. The levels of hazard that differentiate the three classes of radioactive waste will be determined by ongoing work. This report describes other work to be completed before a suitable radioactive waste-classificaion system is established

  4. Radioactivity around Fukushima Daiichi Nuclear Power Plant 9 months after the disaster

    International Nuclear Information System (INIS)

    Shozugawa, Katsumi

    2012-01-01

    We have measured radioactivities around Fukushima Daiichi Nuclear Power Plant in December, 2011, 9 months after the disaster, to compare with measurements in April, 2011. The radioactivity originated by radioactive iodine should have disappeared before December due to its comparatively short lifetime. At the point 1.5km apart from the Plant, the dose rate 1m above the earth was 78 μ Sv/h in April whereas it was 56 μ Sv/h in December, which was higher than anticipation. The measured radioactivities of the soil of fields and forests around the Plant in December were even four times higher than those in April. These phenomena may be resulted with the movement of soil particles attached with radioactive cesium by rainwater or wind. (author)

  5. Radioactive nuclear beam facilities based on projectile fragmentation

    International Nuclear Information System (INIS)

    Sherrill, B.M.

    1992-01-01

    The production of radioactive beams using direct separation techniques is discussed. The reaction mechanisms which can be used to produce radioactive beams with these techniques can be broadly divided into three groups, projectile fragmentation, nucleon transfer, and Coulomb disassociation. Radioactive nuclei produced in these ways have large forward momenta with relatively sharp angular distributions peaked near zero degrees which are suitable for collection with magnetic devices. Secondary beam intensities of up to a few percent of the primary beam intensity are possible, although depending on the production mechanism the beam emittance may be poor. Further beam purification can be achieved using atomic processes with profiled energy degraders. The features of the production reaction mechanism, separation techniques, and a review of world wide efforts are presented. The advantages and disadvantages of the method are presented, with discussion of techniques to overcome some of the disadvantages. (Author)

  6. Radioactive waste management research at CEGB Berkeley nuclear laboratories

    International Nuclear Information System (INIS)

    Bradbury, D.

    1988-01-01

    The CEGB is the major electric utility in the United Kingdom. This paper discusses how, at the research laboratories at Berkeley (BNL), several programs of work are currently taking place in the radioactive waste management area. The theme running through all this work is the safe isolation of radionuclides from the environment. Normally this means disposal of waste in solid form, but it may also be desirable to segregate and release nonradioactive material from the waste to reduce volume or improve the solid waste characteristics (e.g., the release of liquid or gaseous effluents after treatment to convert the radioactivity to solid form). The fuel cycle and radioactive waste section at BNL has a research program into these aspects for wastes arising from the operation or decommissioning of power stations. The work is done both in-house and on contract, with primarily the UKAEA

  7. Radioactive wastes: a reason to go against nuclear?

    International Nuclear Information System (INIS)

    Dupont, Jean-Francois

    2013-01-01

    In this note, the author aims at explaining the nature of the risk related to radioactive wastes, how these wastes are managed, and precautions which are taken for them not to be ever dangerous for mankind or for the environment. He discusses the safety aspects of separation of wastes from the biosphere, describes how radioactive wastes are separated from the biosphere, compares with the case of special wastes. Then he discusses and denies the various objections which are made regarding wastes and their management, i.e.: it is not acceptable nor ethical to pass on toxic wastes to several generations, there is no solution to the problem of radioactive wastes, the solution is bad or its reliability is not certain, the waste issue has been neglected from the start by people who do not care of humanist or ethical issues, people are afraid of deep geological storage

  8. Transmutation of radioactive nuclear waste – present status and ...

    Indian Academy of Sciences (India)

    Transmutation of long-lived actinides and fission products becomes an important issue of the overall nuclear fuel cycle assessment, both for existing and future reactor systems. Reliable nuclear data are required for analysis of associated neutronics. The present paper gives a review of the status of nuclear data analysis ...

  9. Report on radioactivity monitoring during the visits of nuclear powered ships

    International Nuclear Information System (INIS)

    1977-01-01

    The National Radiation Laboratory of the Department of Health is required under NZAEC Report 500 'New Zealand Code for Nuclear Powered Shipping' (June 1976) to monitor for release of radioactivity during the stay of such a ship in a New Zealand port and to provide technical assistance to Civil Defence organisations charged with dealing with any emergency arising from an accidental release of radioactive materials. This report outlines the activities undertaken for the two visits which took place in 1976

  10. Low-level radioactive waste management in EDF nuclear power plants (FRANCE)

    International Nuclear Information System (INIS)

    Boussard, C.

    1991-01-01

    This paper shows some recent examples of Low-level radioactive waste management in EDF nuclear power plants: - Radioactive liquid wastes proceeding from steam generators leaching (NOGENT SUR SEINE-1 REACTOR) - Thermal insulation proceeding from heat exchanger and blower (CHINON-2 REACTOR) - Old iron from reactor dismantling (CHINON-3 REACTOR, MARCOULE G1 REACTOR, MARCOULE G2-G3 REACTORS) - fresh air filter and fire detector - CHINON-2 REACTOR breaker chambers

  11. What about radioactive waste management in the reorganization of the Russian nuclear industry?

    International Nuclear Information System (INIS)

    Krone, Juergen

    2008-01-01

    Even in the light of rising government revenues, the expansion of the Russian nuclear industry cannot be considered on safe grounds as far as funding is concerned. Decisions about new investments depend on proof that nuclear power is by far more profitable than investments into the development of new gas fields. For a long time, the way in which the unsolved issues of radioactive waste management were to be integrated into the reorganization of the Russian nuclear industry was an open question. Current developments demonstrate the efforts made by the Rosatom management to establish a sound basis for the sustainable management of radioactive waste. In late June 2008, the committees of the Russian parliament started deliberations of the draft legislation introduced by Rosatom about the management of radioactive waste, which includes the legal prerequisites for a sustainable national waste management system. The government-operated waste management company, FGUP 'RosRAO' (Sole Federal Government Enterprise, 'Russian Radioactive Waste'), was founded as a Rosatom subsidiary henceforth to be responsible also for the final storage of radioactive waste. Mainly recommendations of the R4.04/04, 'Strategy Definition for Russian Federation NPP Back End Radioactive Waste Management, including Draft Legislation and Institutional Framework', Tacis project were taken up, which had been elaborated by a consortium of 6 West European waste management organizations in close cooperation with Russian experts from Rosatom. The analysis conducted is described in an outline of the present situation of radioactive waste management in Russia and the recommendations derived from it. In addition, the most recent steps towards building a sustainable government-operated management system for radioactive waste of the Russian nuclear industry are explained. (orig.)

  12. Combating illicit trafficking in nuclear and other radioactive material. Technical guidance. Reference manual. (Chinese Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication is intended for individuals and organizations that may be called upon to deal with the detection of and response to criminal or unauthorized acts involving nuclear or other radioactive material. It will also be useful for legislators, law enforcement agencies, government officials, technical experts, lawyers, diplomats and users of nuclear technology. This manual emphasizes the international initiatives for improving the security of nuclear and other radioactive material. However, it is recognized that effective measures for controlling the transfer of equipment, non-nuclear material, technology or information that may assist in the development of nuclear explosive devices, improvised nuclear devices (INDs) or other radiological dispersal devices (RDDs) are important elements of an effective nuclear security system. In addition, issues of personal integrity, inspection and investigative procedures are not discussed in this manual, all of which are essential elements for an effective overall security system. The manual considers a variety of elements that are recognized as being essential for dealing with incidents of criminal or unauthorized acts involving nuclear and other radioactive material. Depending on conditions in a specific State, including its legal and governmental infrastructure, some of the measures discussed will need to be adapted to suit that State's circumstances. However, much of the material can be applied directly in the context of other national programmes. This manual is divided into four main parts. Section 2 discusses the threat posed by criminal or unauthorized acts involving nuclear and other radioactive material, as well as the policy and legal bases underlying the international effort to restrain such activities. Sections 3 and 4 summarize the major international undertakings in the field. Sections 5-8 provide some basic technical information on radiation, radioactive material, the health consequences of radiation

  13. Combating illicit trafficking in nuclear and other radioactive material. Reference material

    International Nuclear Information System (INIS)

    2007-01-01

    This publication is intended for individuals and organizations that may be called upon to deal with the detection of and response to criminal or unauthorized acts involving nuclear or other radioactive material. It will also be useful for legislators, law enforcement agencies, government officials, technical experts, lawyers, diplomats and users of nuclear technology. This manual emphasizes the international initiatives for improving the security of nuclear and other radioactive material. However, it is recognized that effective measures for controlling the transfer of equipment, non-nuclear material, technology or information that may assist in the development of nuclear explosive devices, improvised nuclear devices (INDs) or other radiological dispersal devices (RDDs) are important elements of an effective nuclear security system. In addition, issues of personal integrity, inspection and investigative procedures are not discussed in this manual, all of which are essential elements for an effective overall security system. The manual considers a variety of elements that are recognized as being essential for dealing with incidents of criminal or unauthorized acts involving nuclear and other radioactive material. Depending on conditions in a specific State, including its legal and governmental infrastructure, some of the measures discussed will need to be adapted to suit that State's circumstances. However, much of the material can be applied directly in the context of other national programmes. This manual is divided into four main parts. Section 2 discusses the threat posed by criminal or unauthorized acts involving nuclear and other radioactive material, as well as the policy and legal bases underlying the international effort to restrain such activities. Sections 3 and 4 summarize the major international undertakings in the field. Sections 5-8 provide some basic technical information on radiation, radioactive material, the health consequences of radiation

  14. Process of liquid radioactive waste treatment in nuclear power plant and development trend

    International Nuclear Information System (INIS)

    Liu Jiean; Wang Xin; Liu Dan; Zhu Laiye; Chen Bin

    2014-01-01

    The popular liquid radioactive waste treatment methods in nuclear power plants (NPP) are Chemical precipitation, evaporation, ion exchange, membrane treatment, chemical coagulation and activated carbon absorption and so on. 'Filter + activated carbon absorption (Chemical coagulation) + ion exchange' has a good prospect for development, as its simple process, high decontamination factor, low energy consumption and smaller secondary wastes. Also the process is used in Sanmen and Haiyang Projects. The severe incident in NPP set an even higher demand on liquid radioactive waste treatment. The new type treatment materials, optimization of the existed treatment, combination of treatment and the mobile treatment facility is the development trend in liquid radioactive waste treatment in NPP. (authors)

  15. Mining of Radioactive Raw Materials as an Origin of the Nuclear Fuel Chain

    Directory of Open Access Journals (Sweden)

    Bedřich Michálek

    2007-01-01

    Full Text Available The mining of radioactive raw materials may be considered as an origin of the nuclear fuel chain and thus determines the amount of radioactive wastes which have to be stored safety in the final stage of the fuel chain. The paper informs about the existing trends in mining of radioactive raw materials in the world, provides an overview of development in mining in the Czech Republic and of possibilities of future exploiting some uranium deposits. It points a possibility of non-traditional obtaining uranium from mine waters from underground uranium mines closed and flooded earlier.

  16. Levels of surface contamination with radioactive materials at workplaces of nuclear research centre at Rez

    International Nuclear Information System (INIS)

    Hoelgye, Z.; Nemcova, I.; Kasikova, M.; Popper, J.; Chysky, J.

    1983-01-01

    A hygiene supervision unit at workplaces of the nuclear Research Institute in Rez monitored on a long-term basis surface contamination with radioactive substances. Surface contamination was found at workplaces with open sources. Of the 4343 monitored places action levels were only exceeded in 13 cases. The obtained data were used for typifying workplaces with the highest level of surface contamination, to determine in certain instances the mechanism of the escape of radioactive substances from insulating facilities and to determine the rate of the spread of the radioactive substance into adjacent non-active workplaces. (author)

  17. Radioactive fallout from Chinese nuclear weapons test of March 15, 1978

    International Nuclear Information System (INIS)

    Thomas, C.W.

    1979-01-01

    Pacific Northwest Laboratory (PNL) has measured the radionuclide concentration of short-lived debris from a radioactive cloud, produced by a nuclear weapons test conducted by the People's Republic of China on March 15, 1978. Analysis with a 40 cfm Sierra impactor showed that a large portion of the radioactivity was associated with relatively large particles. Surface air samples showed significant concentrations of 124 Sb. Samples of rain water from New York State showed that radioactivity arrived on the east coast at about the same time as peak debris levels were observed on the west coast. Highest concentrations of 131 I occurred along the Washington State--Canadian border

  18. Radioactive waste and the back part of fuel cycle of nuclear installations in Slovakia

    International Nuclear Information System (INIS)

    Koprda, V.

    2004-01-01

    This article is devoted to radioactive waste (RAW) management, an integrated system starting with collection and sorting of RAW through its storage, treatment, conditioning, handling and transport up to its disposal. Some notes will touch also the near surface depository of low level and intermediate level radioactive waste in Mochovce, and the long-term storage of waste improper for such type of disposal, and also some words will be addressed to the development and research of a deep geological depository for disposal spent fuel from nuclear power plant and long-lived radioactive waste. (author)

  19. Nuclear Astrophysics Data from Radioactive Beam Facilities. Final report

    International Nuclear Information System (INIS)

    Chen, Alan A.

    2008-01-01

    The scientific aims of this project have been the evaluation and dissemination of key nuclear reactions in nuclear astrophysics, with a focus on ones to be studied at new radioactive beam facilities worldwide. These aims were maintained during the entire funding period from 2003 - 2006. In the following, a summary of the reactions evaluated during this period is provided. Year 1 (2003-04): 21 Na(p,γ) 22 Mg and 18 Ne(α,p) 21 Na - The importance of the 21 Na(p,γ) 22 Mg and the 18 Ne(α,p) 21 Na reactions in models of exploding stars has been well documented: the first is connected to the production of the radioisotope 22 Na in nova nucleosynthesis, while the second is a key bridge between the Hot-CNO cycles and the rp-process in X-ray bursts. By the end of Summer 2004, our group had updated these reaction rates to include all published data up to September 2004, and cast the reaction rates into standard analytical and tabular formats with the assistance of Oak Ridge National Laboratory's computational infrastructure for reaction rates. Since September 2004, ongoing experiments on these two reactions have been completed, with our group's participation in both: 21 Na(p,γ) 22 Mg at the TRIUMF-ISAC laboratory (DRAGON collaboration), and 18Ne(α,p) 21 Na at Argonne National Laboratory (collaboration with Ernst Rehm, Argonne). The data from the former was subsequently published and included in our evaluation. Publication from the latter still awaits independent confirmation of the experimental results. Year 2 (2004-05): The 25Al(p,γ) 26 Si and 13 N(p,γ)14O reactions - For Year 2, we worked on evaluations of the 25 Al(p,γ) 26 Si and 13 N(p,γ) 14 O reactions, in accordance with our proposed deliverables and following similar standard procedures to those used in Year 1. The 25 Al(p,γ) 26 Si reaction is a key uncertainty in the understanding the origin of galactic 26 Al, a target radioisotope for gamma ray astronomy; the 13 N(p,γ) 14 O reaction in turn is the trigger

  20. Technical aspects regarding the management of radioactive waste from decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Dragolici, F.; Turcanu, C.N.; Rotarescu, Gh.; Paunica, I.

    2002-01-01

    The proper application of the nuclear techniques and technologies in Romania started in 1957 with the commissioning of the VVR-S Research Reactor at IFIN-HH-Magurele. During the past 40 years, this reactor was used for thousands of nuclear applications with extremely diverse profiles (research, biology, medicine, education, agriculture, transport, all types of industry) which used radioactive sources in their activity and produced radioactive waste. The Radioactive Waste Treatment Plant (STDR) at IFIN-HH was constructed in collaboration with companies from the United Kingdom and became operational in 1975. It was the only authorized and specialized institution for the management of non-fuel cycle radioactive waste in Romania. Using the concepts existing in the 1980's concerning the final disposal of the low and intermediate level radioactive wastes, and applying internal standards and international recommendations, the National Repository for Low and Intermediate Radioactive Waste (DNDR) was built in 1985 in Baita, Bihor county and placed into operation. Therefore, through the construction and operation of the treatment and final disposal capabilities, Romania has solved the management of the low and intermediate level radioactive waste while providing for the protection of the people and environment. (author)

  1. Calculation of radioactive inventory of activated parts for nuclear power unit and analysis of influence factors

    International Nuclear Information System (INIS)

    Liu Yang; Cai Qi; Lin Xiaoling

    2011-01-01

    Based on the operation characteristics of the nuclear power unit, the radioactive inventory of activated parts was calculated by ORIGEN2, and the effects of bum-up, operation mode and power change on the radioactive inventory for activated parts were analyzed. The results indicated that the radioactive inventory grew with the increasing of burn-up, and when the actual operation time was longer than the effective operation time, the increasing rate of nuclide activity approximated the burn-up increasing; Radioactive inventory of activated parts was influenced directly by the operation modes of the nuclear power unit, and under same reactor load, operation power and bum-up, the radioactive inventory for non-continuous operation mode is less than that for the continuous operation mode. Effects of operation modes on radioactive inventory reversed with half life of nuclides. Under same bum-up and longer operation time, the effect of operation power change on the radioactive inventory is not obvious, (authors)

  2. Radiological protection and radioactive waste management aspects of the decommissioning of redundant nuclear facilities at the Rosyth Dockyard, UK

    International Nuclear Information System (INIS)

    Kerr, Robert W.; Murdo Murray; Hunter Common

    2008-01-01

    The Rosyth Dockyard is located near the city of Edinburgh in Scotland. The dockyard's nuclear activities centred around the refuelling and refitting of submarines, as well as some submarine decommissioning. In 1993, submarine refitting work was transferred to Devonport in Southern England. This meant that there were a number of facilities at the Rosyth Dockyard that were now redundant. In accordance with UK government policy a programme of works was instigated to allow for the decommissioning of these nuclear liabilities. This paper provides a brief overview of work activities performed to allow physical decommissioning to take place. Topics covered include radiological characterisation activities, development of monitoring protocols for decommissioning, obtaining relevant environmental authorisations, developing a decommissioning safety case, gaining the UK's Nuclear Installations Inspectorate approval to proceed with decommissioning and an overview of some of the post operative clean out (POCO) activities performed. Edmund Nuttall Ltd were contracted to perform the physical decommissioning of the redundant nuclear facilities, that have been subject to POCO, and this work commenced in February 2006. As part of this contract they were to provide a radiological protection infrastructure including dosimetry and health physics monitoring. This paper discusses the radiological protection infrastructure established by the decommissioning contractor, the radiological protection aspects of the decommissioning work, some of the tools and techniques utilised to date during the nuclear decommissioning, and the radioactive waste management processes established for the project. All activities are referenced to relevant aspects of UK nuclear industry best practice and to the Scottish, UK and European regulatory framework. The progress to date is discussed and lessons that have been learnt are highlighted. (author)

  3. Transport of radioactive droplet moisture from a source in a nuclear power plant spray pond

    International Nuclear Information System (INIS)

    Elokhin, A.P.

    1995-01-01

    In addition to a change in the microclimate in the region surrounding a nuclear power plant resulting from the emission of vapor form a cooling tower, evaporation of water from the water surface of a cooling pond or a spray pond, in the latter case direct radioactive contamination of the underlying surface around the nuclear power plant can also occur due to discharge of process water (radioactive) into the pond and its transport in the air over a certain distance in the form of droplet moisture. A typical example may be the situation at the Zaporozhe nuclear power plant in 1986 when accidental discharge of process water into the cooling pond occurred. Below we present a solution for the problem of transport of droplet moisture taking into account its evaporation, which may be used to estimate the scale of radioactive contamination of the locality

  4. Security of material: Preventing criminal activities involving nuclear and other radioactive materials

    International Nuclear Information System (INIS)

    Nilsson, A.

    2001-01-01

    The report emphasizes the need for national regulatory authorities to include in the regulatory systems, measures to control and protect nuclear materials from being used in illegal activities, as well as aspects of relevance for detecting and responding to illegal activities involving nuclear and other radioactive materials. The report will give an overview of the international treaties and agreements that underpin the establishment of a regulatory structure necessary for States to meet their non-proliferation policy and undertakings. Ongoing work to strengthen the protection of nuclear material and to detect and respond to illegal activities involving nuclear and other radioactive material will be included. The focus of the paper is on the need for standards and national regulation in the nuclear security area. (author)

  5. The treatment of radioactive waste in Institute of Nuclear Physics of Uzbekistan

    International Nuclear Information System (INIS)

    Radyuk, R.I.

    2001-01-01

    Full text: The main purpose of radioactive waste treatment is security of humanity and environment for future. The formation of radioactive waste in Institute of Nuclear Physics connects with scientific and research works on reactor and cyclotron. There are works in the field of radiochemistry, activation analysis, research of material. It is connected with some different materials used in practical work: mountain rock, food-stuffs, biological materials and other. The Institute of Nuclear Physics has enterprise, making radioactive isotopes. In consequence of this work radioactive wastes form. Average annual volume of liquid radioactive waste is 2000 m 3 in year. During normal work of nuclear reactor and enterprise of radioactive isotope small part of radionuclides with gaseous waste gets in environment. The content of inert gas does not exceed 2% of permissible level . Value of radionuclides fall out in area from 0.5 Km to 10 Km does not differ global fall out and changes from 1.1.10 6 Bq/km 2 to 1.6.10 7 Bq/km 2 month (permissible doze - 5.6.10 8 Bq/km 2 .month). The solid radioactive waste of medium and low activity are burying on Republic point of radioactive waste storage. Annual volume of solid radioactive waste is 60 m 3 in year and total radioactivity is 10 11 Bk. The solid radioactive waste of high activity are going to of Chelyabinsk. The liquid radioactive waste belong to second and third group of radioactive waste (classification of IAEA). The decontamination of liquid radioactive waste are made on the station of liquid radioactive waste treatment by method of sedimentation and distillation. The productivity of this plant is 15m 3 in day. Before treatment liquid radioactive waste is analyzed to determine chemical and radiochemical composition. It is solution with content of salt from 0.8 g/l to 15 g/l, salt Ca 2+ and Mg 2+ - 20 mg-eqv/l, oxygen - 100 mg O 2 /l , activity from 10 2 Bq/l to 10 4 Bq/l. The radionuclides composition of liquid radioactive

  6. Radioactivity

    International Nuclear Information System (INIS)

    2002-01-01

    This pedagogical document presents the origin, effects and uses of radioactivity: where does radioactivity comes from, effects on the body, measurement, protection against radiations, uses in the medical field, in the electric power industry, in the food (ionization, radio-mutagenesis, irradiations) and other industries (radiography, gauges, detectors, irradiations, tracers), and in research activities (dating, preservation of cultural objects). The document ends with some examples of irradiation levels (examples of natural radioactivity, distribution of the various sources of exposure in France). (J.S.)

  7. Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1995-09-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions

  8. Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

  9. The role of national regulatory authority in monitoring of radioactivity and in case of seizure of radioactive or nuclear material

    International Nuclear Information System (INIS)

    Morkunas, G.

    2002-01-01

    Full text: The Radiation Protection Centre is a regulatory authority in radiation protection in Lithuania. Its main tasks are licensing of practices, supervision, control and enforcement of radiation protection requirements, dosimetric, radiometric and spectrometric measurements, evaluation of exposure and its sources, expertise and advice on optimization of radiation protection. Its activities may be divided into two main parts -- regulatory and analytical ones. Food, drinking water, environmental, wipe and other samples are monitored, the appropriate evaluation of doses is done. The data on concentrations of artificial radionuclides in different bodies are available. The laboratory is to be accredited according to the ISO 17025 standard in the framework of Phare Twinning Project. In case of seized radioactive or nuclear material the Radiation Protection Centre has to identify the necessary radiation protection means for members of public and emergency workers, perform measurements of dose rate and radioactive contamination, and, if necessary, evaluate doses received due to the seized radioactive or nuclear material. Since the Radiation Protection Centre has its departments in the largest cities of Lithuania the above mentioned measures can be taken very urgently, especially the ones connected with primary evaluation of situation and identification of optimized radiation protection measures. The Radiation Protection Centre has its own possibilities of identification of radionuclides in the seized material. Such installations as HpGe spectrometers (Oxford and Canberra), equipment for radiochemical separation of U, Pu and actinides, alpha spectrometer, liquid scintillation spectrometer and neutron rem counter are available. There were a few cases when seized material had to be analyzed also. Different sources were found in different places of Lithuania, and it was necessary to define the activity and isotopic content of these sources. The following scheme is used in

  10. Terminating Safeguards on Excess Special Nuclear Material: Defense TRU Waste Clean-up and Nonproliferation - 12426

    Energy Technology Data Exchange (ETDEWEB)

    Hayes, Timothy [Los Alamos National Laboratory, Carlsbad Operations Group (United States); Nelson, Roger [Department Of Energy, Carlsbad Operations Office (United States)

    2012-07-01

    The Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) manages defense nuclear material that has been determined to be excess to programmatic needs and declared waste. When these wastes contain plutonium, they almost always meet the definition of defense transuranic (TRU) waste and are thus eligible for disposal at the Waste Isolation Pilot Plant (WIPP). The DOE operates the WIPP in a manner that physical protections for attractiveness level D or higher special nuclear material (SNM) are not the normal operating condition. Therefore, there is currently a requirement to terminate safeguards before disposal of these wastes at the WIPP. Presented are the processes used to terminate safeguards, lessons learned during the termination process, and how these approaches might be useful for future defense TRU waste needing safeguards termination prior to shipment and disposal at the WIPP. Also described is a new criticality control container, which will increase the amount of fissile material that can be loaded per container, and how it will save significant taxpayer dollars. Retrieval, compliant packaging and shipment of retrievably stored legacy TRU waste has dominated disposal operations at WIPP since it began operations 12 years ago. But because most of this legacy waste has successfully been emplaced in WIPP, the TRU waste clean-up focus is turning to newly-generated TRU materials. A major component will be transuranic SNM, currently managed in safeguards-protected vaults around the weapons complex. As DOE and NNSA continue to consolidate and shrink the weapons complex footprint, it is expected that significant quantities of transuranic SNM will be declared surplus to the nation's needs. Safeguards termination of SNM varies due to the wide range of attractiveness level of the potential material that may be directly discarded as waste. To enhance the efficiency of shipping waste with high TRU fissile content to WIPP, DOE designed an

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

    International Nuclear Information System (INIS)

    Bachmann, Udo; Biederbick, Walter; Derakshani, Nahid

    2010-01-01

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

  12. Emerging Environmental Justice Issues in Nuclear Power and Radioactive Contamination

    Directory of Open Access Journals (Sweden)

    Dean Kyne

    2016-07-01

    Full Text Available Nuclear hazards, linked to both U.S. weapons programs and civilian nuclear power, pose substantial environment justice issues. Nuclear power plant (NPP reactors produce low-level ionizing radiation, high level nuclear waste, and are subject to catastrophic contamination events. Justice concerns include plant locations and the large potentially exposed populations, as well as issues in siting, nuclear safety, and barriers to public participation. Other justice issues relate to extensive contamination in the U.S. nuclear weapons complex, and the mining and processing industries that have supported it. To approach the topic, first we discuss distributional justice issues of NPP sites in the U.S. and related procedural injustices in siting, operation, and emergency preparedness. Then we discuss justice concerns involving the U.S. nuclear weapons complex and the ways that uranium mining, processing, and weapons development have affected those living downwind, including a substantial American Indian population. Next we examine the problem of high-level nuclear waste and the risk implications of the lack of secure long-term storage. The handling and deposition of toxic nuclear wastes pose new transgenerational justice issues of unprecedented duration, in comparison to any other industry. Finally, we discuss the persistent risks of nuclear technologies and renewable energy alternatives.

  13. Emerging Environmental Justice Issues in Nuclear Power and Radioactive Contamination.

    Science.gov (United States)

    Kyne, Dean; Bolin, Bob

    2016-07-12

    Nuclear hazards, linked to both U.S. weapons programs and civilian nuclear power, pose substantial environment justice issues. Nuclear power plant (NPP) reactors produce low-level ionizing radiation, high level nuclear waste, and are subject to catastrophic contamination events. Justice concerns include plant locations and the large potentially exposed populations, as well as issues in siting, nuclear safety, and barriers to public participation. Other justice issues relate to extensive contamination in the U.S. nuclear weapons complex, and the mining and processing industries that have supported it. To approach the topic, first we discuss distributional justice issues of NPP sites in the U.S. and related procedural injustices in siting, operation, and emergency preparedness. Then we discuss justice concerns involving the U.S. nuclear weapons complex and the ways that uranium mining, processing, and weapons development have affected those living downwind, including a substantial American Indian population. Next we examine the problem of high-level nuclear waste and the risk implications of the lack of secure long-term storage. The handling and deposition of toxic nuclear wastes pose new transgenerational justice issues of unprecedented duration, in comparison to any other industry. Finally, we discuss the persistent risks of nuclear technologies and renewable energy alternatives.

  14. Chemical cleaning for sludge in steam generator of nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Mengqin; Lu Yucheng; Zhang Binyong; Yu Jinghua

    2002-01-01

    The sludge induced corrosion damage to secondary side of tubes of Steam Generator (SG), effect of chemical cleaning technique on maintenance integrity of tubes of SG NPP and use of chemical cleaning technique in SG NPP have been summarized. The engineering technique of chemical cleaning for removing sludge in secondary side of SG NPP has been studied and qualified by CIAE (China Institute of Atomic Energy). Chemical cleaning engineering technique is introduced (main agent is EDTA, temp. <100 degree C), including chemical cleaning technology for tube plate and full tube nest of secondary side of SG, the monitoring technique of chemical cleaning process (effectiveness and safety), the disposal method of wastage of chemical cleaning, the system of chemical cleaning. The method for preventing sludge deposition in secondary side and the research on advanced water chemistry of secondary loop are introduced

  15. Summary of personnel doses and discharge of radioactivity at Swedish nuclear power plants 1971-1975

    International Nuclear Information System (INIS)

    Malmqvist, L.; Persson, Aa.

    1977-01-01

    The report is a summary of personnel doses and activity discharges from Swedish nuclear power plants during the first five years of electric power production by nuclear plants. The personnel doses for the Sweedish plants are lower than the corresponding values for American plants. The highest Swedish value is o,13 manrem per MWE and year. The discharge of radioactivity to the atmosphere from the Swedish plants has been for below the maximum permissible limits. The discharge of radioactivity to the water recipients was less than 1 % of what is permissible

  16. Clean-up and dismantling, Dismantling - legacy of the past, prospects for the future: CEA, a pioneer in the dismantling process, nuclear dismantling, research and innovation dedicated to dismantling

    International Nuclear Information System (INIS)

    Lorec, Amelie

    2016-01-01

    France - a world leader in the whole nuclear power cycle - is also responsible for the clean-up and dismantling of its end-of-life nuclear facilities. Here, the CEA is considered to be a pioneer both in the project ownership of work sites and in the R and D for optimising the timescales, costs and safety of those work sites. Its responsibilities range from defining the most appropriate scenario, characterising the radiological state of equipment and decontaminating premises, carrying out dismantling and optimising the resulting waste. With this wide range of skills and the diversity of its facilities, the CEA Nuclear Energy Division is developing innovative solutions which are already the subject of industrial transfers. Two-thirds of France's end-of-life nuclear facilities belong to the CEA - a situation connected with its history. This implies setting up clean-up and dismantling work sites which have unprecedented scientific, human and financial challenges. Every regulated nuclear installation (INB) (nuclear reactors, laboratories, etc.) has a limited operating life. When it stops being used, it is first cleaned up (removal of radioactive substances), then dismantled (disassembly of components) in accordance with the baseline safety requirements, and finally decommissioned so that it can be used for other purposes or be demolished. Cleanup and dismantling operations concern all the facility's components, such as hot (shielded) cells which can be found in some laboratories. As the owner of its clean-up and dismantling projects, the CEA also devotes a significant amount of R and D to reducing the timescales, costs and waste from current and future programmes, while improving their safety. The resulting innovations often lead to industrial transfers. (authors)

  17. Control of radioactive waste in dismantling of a nuclear facility; Control de residuos radiactivos en desmantelamiento de una instalacion nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Campayo, E.

    2014-07-01

    In the dismantling of a nuclear facility are generated radioactive waste that must be suitably processed. The overall process, in a simplified manner, contemplates the characterization in origin, their segregation on the basis of physical, mechanical, and radiological characteristics and their packaging. (Author)

  18. Reduction and resource recycling of high-level radioactive wastes through nuclear transmutation with PHITS code

    International Nuclear Information System (INIS)

    Fujita, Reiko

    2017-01-01

    In the ImPACT program of the Cabinet Office, programs are underway to reduce long-lived fission products (LLFP) contained in high-level radioactive waste through nuclear transmutation, or to recycle/utilize useful nuclear species. This paper outlines this program and describes recent achievements. This program consists of five projects: (1) separation/recovery technology, (2) acquisition of nuclear transmutation data, (3) nuclear reaction theory model and simulation, (4) novel nuclear reaction control and development of elemental technology, and (5) discussions on process concept. The project (1) develops a technology for dissolving vitrified solid, a technology for recovering LLFP from high-level waste liquid, and a technology for separating odd and even lasers. Project (2) acquires the new nuclear reaction data of Pd-107, Zr-93, Se-79, and Cs-135 using RIKEN's RIBF or JAEA's J-PARC. Project (3) improves new nuclear reaction theory and structural model using the nuclear reaction data measured in (2), improves/upgrades nuclear reaction simulation code PHITS, and proposes a promising nuclear transmutation pathway. Project (4) develops an accelerator that realizes the proposed transmutation route and its elemental technology. Project (5) performs the conceptual design of the process to realize (1) to (4), and constructs the scenario of reducing/utilizing high-level radioactive waste to realize this design. (A.O.)

  19. Safety transport of radioactive waste in the nuclear power area

    Directory of Open Access Journals (Sweden)

    Tureková Ivana

    2017-01-01

    Full Text Available Radioactive wastes require strict rules for manipulation with them due to the hazards for the human health and environment, not excluding the hazards during their internal transport. The article deals with the transport of packing unit inside of the company and it proposes the possible alternatives so that meet the limit conditions and reduce the manipulation time with the radioactive material in the packing unit. The packing unite isolates fixated liquid waste from the environment while it also serves as protection. There are also important external radiation characteristics of package unit, which consist of measurable values of the scratch contamination surface and dose power on the surface of package unit. Thus, the paper is aimed to point out the necessity of the logistics during manipulation with the package unit in the process of internal transport so that the dose power of exposed employees would achieve the lowest possible level and meet the strict limits in a full extent.

  20. Radioactivity appearing at landfills in household trash of nuclear medicine patients: much ado about nothing?

    Science.gov (United States)

    Siegel, Jeffry A; Sparks, Richard B

    2002-03-01

    The U.S. NRC in 1997 removed its arbitrary 1.11 GBq (30 mCi) rule, which had been in existence for almost 50 y, and now many more patients receiving radionuclide therapy in nuclear medicine can be treated as outpatients. However, another problem has the potential to limit the short-lived reality of outpatient treatment unless nuclear medicine practitioners and the health physics community gets involved. Radioactive articles in the household trash of nuclear medicine patients are appearing at solid waste landfills that have installed radiation monitors to prevent the entry of any detectable radioactivity, and alarms are going off around the country. These monitors are set to alarm at extremely low activity levels. Some states may actually hold licensees responsible if a patient's radioactive household trash is discovered in a solid waste stream; this is another major reason [along with continued use of the 1.11 GBq (30 mCi) rule] why many licensees are still not releasing their radionuclide therapy patients. This is in spite of the fact that the radioactivity contained in released nuclear medicine therapy patients, let alone the much lower activity level contained in their potentially radioactive household wastes, poses a minimal hazard to the public health and safety or to the environment. Currently, there are no regulations governing the disposal of low-activity, rapidly-decaying radioactive materials found in the household trash of nuclear medicine patients, the performance of landfill radiation monitors, or the necessity of spectrometry equipment. Resources are, therefore, being unnecessarily expended by regulators and licensees in responding to radiation monitor alarms that are caused by these unregulated short-lived materials that may be mixed with municipal trash. Recommendations are presented that would have the effect of modifying the existing landfill regulations and practices so as to allow the immediate disposal of such wastes.

  1. Studies on the radioactive contamination due to nuclear detonations I. Studies on the Radioactive dust due to nuclear detonation in Bikini on March 1, 1954

    Energy Technology Data Exchange (ETDEWEB)

    Nishiwaki, Yasushi [Nuclear Reactor Laboratory, Tokyo Institute of Technology, Tokyo (Japan); Nuclear Reactor Laboratoroy, Kinki University, Fuse City, Osaka Precture (Japan)

    1961-11-25

    A study has been made, from the health physics standpoint, of the radioactivity emitted from the dust collected from No. 5 Fukuryu Maru, which was showered by the strong radioactive ash at about 0-90 miles east of Bikini on March 1, 1954. The probable dose of external gamma radiation the crew might have received during their two weeks voyage may be estimated roughly about 500-800 rad. However,, judging from the strong radioactive contamination of the boat, it may be inferred that the crew might have received a considerable-degree of internal irradiation besides the external whole body gamma irradiation and the local beta irradiation on the skin where the radioactive dust directly contacted, The specific activity of the dust when it fell on the boat a few hours after the nuclear detonation may be estimated to be roughly about one curie per gram. From the radiochemical analysis and the beta-ray analysis, the major part of the radioactivity included in-the dust was found to be due to a mixture of various fission products, while the main chemical component of the dust (Bikini ash) itself consisted of a calcium compound. The alpha-ray was also detected by the use of an ionization chamber in that portion where transuranium elements, if present, were collected. The tuna fish and the shark fins which were brought back to Japan by No.5 Fukuryu Maru in the middle of March, 1954 were most strongly contaminated on the skin, but the fish caught later in the South Pacific were found to be contaminated more strongly in the internal organs rather than on the skin. The area in the Pacific where the radioactive contaminated fish were caught seemed to expand gradually with time. In the latter half of 1954, besides the ordinary fission products, the radioactive Zn{sup 65} which was not found in appreciable amount in the original Bikini ash has been detected from the internal organs of the contaminated fish. A possible production of Zn{sup 65} by the neutron activation of some metallic

  2. Studies on the radioactive contamination due to nuclear detonations I. Studies on the Radioactive dust due to nuclear detonation in Bikini on March 1, 1954

    International Nuclear Information System (INIS)

    Nishiwaki, Yasushi

    1961-01-01

    A study has been made, from the health physics standpoint, of the radioactivity emitted from the dust collected from No. 5 Fukuryu Maru, which was showered by the strong radioactive ash at about 0-90 miles east of Bikini on March 1, 1954. The probable dose of external gamma radiation the crew might have received during their two weeks voyage may be estimated roughly about 500-800 rad. However,, judging from the strong radioactive contamination of the boat, it may be inferred that the crew might have received a considerable-degree of internal irradiation besides the external whole body gamma irradiation and the local beta irradiation on the skin where the radioactive dust directly contacted, The specific activity of the dust when it fell on the boat a few hours after the nuclear detonation may be estimated to be roughly about one curie per gram. From the radiochemical analysis and the beta-ray analysis, the major part of the radioactivity included in-the dust was found to be due to a mixture of various fission products, while the main chemical component of the dust (Bikini ash) itself consisted of a calcium compound. The alpha-ray was also detected by the use of an ionization chamber in that portion where transuranium elements, if present, were collected. The tuna fish and the shark fins which were brought back to Japan by No.5 Fukuryu Maru in the middle of March, 1954 were most strongly contaminated on the skin, but the fish caught later in the South Pacific were found to be contaminated more strongly in the internal organs rather than on the skin. The area in the Pacific where the radioactive contaminated fish were caught seemed to expand gradually with time. In the latter half of 1954, besides the ordinary fission products, the radioactive Zn 65 which was not found in appreciable amount in the original Bikini ash has been detected from the internal organs of the contaminated fish. A possible production of Zn 65 by the neutron activation of some metallic part of

  3. Three-gradual pilot unit of JP3RO for cleanings and concentration of radioactive sewage by method of upturned osmosis

    International Nuclear Information System (INIS)

    Chmielewski, A.G.; Harasimowicz, M.; Tyminski, B.; Zakrzewska-Trznadel, G.

    2001-01-01

    For many years the Institute of Nuclear Chemistry and Technology has worked on the application of different membrane processes to nuclear technology. The experiments with ultrafiltration, ultrafiltration combined with chemical complexation, membrane distillation and reverse osmosis were conducted. Reverse osmosis (RO) as a method for liquid radioactive waste treatment has been examined at laboratory and pilot plant installations. Thr purification of radioactive model solutions as well as liquid low and medium level radioactive waste samples has been examined with various reverse osmotic modules equipped with thin composite polymeric membranes. The experience with the process led to design and construction of the JP3RO industrial plant, 1 m 3 capacity, composed of three RO stages. On the basis of earlier investigations, membrane modules were selected for the plant. The installation is described in this paper, and the results of experiments are presented. The JP3RO installation was included into the system of liquid low and medium-level radioactive wastes treatment at Institute of Nuclear Energy in Swierk. (author)

  4. Radioactive waste management in the Chernobyl exclusion zone: 25 years since the Chernobyl nuclear power plant accident.

    Science.gov (United States)

    Oskolkov, Boris Y; Bondarkov, Mikhail D; Zinkevich, Lubov I; Proskura, Nikolai I; Farfán, Eduardo B; Jannik, G Timothy

    2011-10-01

    Radioactive waste management is an important component of the Chernobyl Nuclear Power Plant accident mitigation and remediation activities in the so-called Chernobyl Exclusion Zone. This article describes the localization and characteristics of the radioactive waste present in the Chernobyl Exclusion Zone and summarizes the pathways and strategy for handling the radioactive waste-related problems in Ukraine and the Chernobyl Exclusion Zone and, in particular, the pathways and strategies stipulated by the National Radioactive Waste Management Program.

  5. Management of radioactive waste in nuclear power: handling of irradiated graphite from water-cooled graphite reactors

    International Nuclear Information System (INIS)

    Anfimov, S.S.

    2001-01-01

    In this paper an radioactive waste processing of graphite from graphite moderated nuclear reactors at its decommissioning is discussed. Methods of processing of irradiated graphite are presented. It can be concluded that advanced methods for graphite radioactive waste handling are available nowadays. Implementation of these methods will allow to enhance environmental safety of nuclear power that will benefit its progress in the future

  6. Integrated data base report - 1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1997-12-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions

  7. Residual radioactivity in the soil of the Semipalatinsk Nuclear Test Site in the former USSR.

    Science.gov (United States)

    Yamamoto, M; Tsukatani, T; Katayama, Y

    1996-08-01

    This paper deals with our efforts to survey residual radioactivity in the soil sampled at the Semipalatinsk Nuclear Test Site and at off-site areas in Kazakhstan. The soil was sampled at the hypocenter where the first Soviet nuclear explosion was carried out on 29 August 1949, and at the bank of the crater called "Bolapan," which was formed by an underground nuclear detonation on 15 January 1965 along the Shagan River. As a comparison, other soil was also sampled in the cities of Kurchatov and Almaty. These data have allowed a preliminary evaluation of the contemporary radioactive contamination of the land in and around the test site. At the first nuclear explosion site and at Bolapan, higher than background levels of 239,240Pu with weapons-grade plutonium were detected together with fission and activation products such as 137Cs, 60Co, 152Eu, and 154Eu.

  8. An international education agenda in nuclear energy and radioactive waste management for the 21st century

    International Nuclear Information System (INIS)

    Powell, R.R.; Wohlpart, A.; James, E.

    1992-01-01

    As many countries have turned to scientific and technological advancements for human well being and national security, there has emerged a pressing need to promote scientific and technological literacy in national work forces. One benefit of this literacy is scientifically informed decision making on issues related to energy conservation in general and nuclear energy in particular. Realizing the need for increased literacy relative to nuclear energy, the Office of Civilian Radioactive Waste Management (OCRWM) of the Department of Energy, U.S.A., the Organization of Economic Co-Operation and Development (OECD) and the Nuclear Energy Agency (NEA) sponsored an international conference on education in the field of radioactive waste management. This paper discusses recommendations made at the conference for developing education materials. Also described is a three-phase international plan for developing school curriculum materials relative to nuclear waste management

  9. An investigation of awareness on the Fukushima nuclear accident and Radioactive contamination

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Jeong Chul; Song, Young Ju [Dept. of Consumer Safety, Korea Consumer Agency, Eumseong (Korea, Republic of)

    2016-05-15

    The objective of this study was to investigate Korean people's awareness about impact of the Fukushima nuclear power plant accident in Japan and radioactive contamination caused by it. The respondents of the survey were 600 adults who resided in the Seoul metropolitan area. The survey results show that the majority of respondents were concerned about impact of radiation leakage that might have an effect on our environment. They were worried about radioactive contamination of foodstuffs, particularly fishery products and preferred to acquire information through TV(49.8%) or the Internet(31.3%). Meanwhile, respondents mentioned that the information on the Fukushima nuclear accident and radioactive contamination had not been sufficient and they didn't know well about the follow-up measures of the government on the accident. Most respondents answered that information on radioactive contamination levels and safety of foods and environment was most needed. The results of this study could be useful to enhance awareness on radioactivity and improve risk communication on nuclear power plant accidents.

  10. Intermediate storage of radioactive waste and spent nuclear fuel at the Kola Peninsula

    International Nuclear Information System (INIS)

    Bohmer, N.

    1999-01-01

    The problem of nuclear waste and disused nuclear submarines are a product of the arms race and the Cold War. Russia still continues to build new nuclear submarines, but there are very few provisions being made to properly store old nuclear submarines, and develop sufficient storage facilities for spent nuclear fuel and other radioactive waste. A solution to this problem is proposed: to construct a new regional interim storage facilities at Kola for the spent nuclear fuel instead of transporting it to Mayak, the existing reprocessing plant. This storage should have the capacity to handle the fuel in the existing storage and the fuel still on board of retired nuclear submarines. Its lifetime should be 50 years. later it would be possible to make a decision on the future of this fuel

  11. International symposium on technologies for the management of radioactive waste from nuclear power plants and back end nuclear fuel cycle activities. Book of extended synopses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-09-01

    This document includes 79 extended synopses of presentations delivered at the symposium. The topics discussed include: radioactive waste management policies and technologies; geological disposal of radioactive wastes; spent nuclear fuel management; economic and social aspects of nuclear fuel cycle. Every paper has been indexed separately Refs, figs, tabs

  12. International symposium on technologies for the management of radioactive waste from nuclear power plants and back end nuclear fuel cycle activities. Book of extended synopses

    International Nuclear Information System (INIS)

    1999-09-01

    This document includes 79 extended synopses of presentations delivered at the symposium. The topics discussed include: radioactive waste management policies and technologies; geological disposal of radioactive wastes; spent nuclear fuel management; economic and social aspects of nuclear fuel cycle. Every paper has been indexed separately

  13. Characterization, treatment and conditioning of radioactive graphite from decommissioning of nuclear reactors

    International Nuclear Information System (INIS)

    2006-09-01

    Graphite has been used as a moderator and reflector of neutrons in more than 100 nuclear power plants and in many research and plutonium-production reactors. It is used primarily as a neutron reflector or neutron moderator, although graphite is also used for other features of reactor cores, such as fuel sleeves. Many of the graphite-moderated reactors are now quite old, with some already shutdown. Therefore radioactive graphite dismantling and the management of radioactive graphite waste are becoming an increasingly important issue for a number of IAEA Member States. Worldwide, there are more than 230 000 tonnes of radioactive graphite which will eventually need to be managed as radioactive waste. Proper management of radioactive graphite waste requires complex planning and the implementation of several interrelated operations. There are two basic options for graphite waste management: (1) packaging of non-conditioned graphite waste with subsequent direct disposal of the waste packages, and (2) conditioning of graphite waste (principally either by incineration or calcination) with separate disposal of any waste products produced, such as incinerator ash. In both cases, the specific properties of graphite - such as Wigner energy, graphite dust explosibility, and radioactive gases released from waste graphite - have a potential impact on the safety of radioactive graphite waste management and need to be carefully considered. Radioactive graphite waste management is not specifically addressed in IAEA publications. Only general and limited information is available in publications dealing with decommissioning of nuclear reactors. This report provides a comprehensive discussion of radioactive graphite waste characterization, handling, conditioning and disposal throughout the operating and decommissioning life cycle. The first draft report was prepared at a meeting on 23-27 February 1998. A technical meeting (TM) was held in October 1999 in coincidence with the Seminar on

  14. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    Energy Technology Data Exchange (ETDEWEB)

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq); Cochran, John R. [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)

    2013-07-01

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the

  15. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    International Nuclear Information System (INIS)

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi; Cochran, John R.

    2013-01-01

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning

  16. The regulation of radioactive effluent release in France (mainly from large nuclear installations)

    International Nuclear Information System (INIS)

    Hebert, Jean.

    1978-01-01

    In parallel with the licensing system for construction and operation of classified or so-called large nuclear installations (INB) there are in France regulations for the release of radioactive effuents from such installations. The regulations applicable to installations other than INBs are not specifically of a nuclear nature, while those covering INBs, which are analysed in this study, in particular, cover effluent release in liquid or gaseous form. The licensing and control procedures for such release are analysed in detail. (NEA) [fr

  17. Interpretation of the concepts of ALARA and bat for radioactive effluent releases from nuclear installation

    International Nuclear Information System (INIS)

    Chen Xiaoqiu

    2009-01-01

    Based on the understanding of the important concepts of both ALARA and BAT associated with the characteristics of effluent releases from the existing nuclear installations and the abatement techniques for effluents, this paper elaborates the principle of controlling radioactive effluent concentration from nuclear installation, that is based on the BAT focusing on the abatement techniques for effluents, introduces the good practice in the projects, and optimize the effluent releases with account taken of external factors such as the site condition. (authors)

  18. Illegal handling of radioactive and nuclear materials. Threats and suggestions for measures

    International Nuclear Information System (INIS)

    Oliver, Lena; Melin, Lena; Prawitz, Jan; Ringbom, Anders; Sandstroem, Bjoern; Wigg, Lars; Wirstam, Jens

    2004-01-01

    This project deals with threats from smuggling or other illegal transportation of radioactive or nuclear materials across the borders to Sweden, and with the security of handling such materials in Sweden. The project has included studies of relevant documentation; visits and interviews at industries, hospitals, research institutes and military institutions in Sweden that handle radioactive materials; a pilot study at the Stockholm freeport, where equipment for detection of radioactive materials has been tested for six months; an analysis of incidents reported to the IAEA database; and an analysis of Swedish incidents. The following conclusions are drawn: Stricter rules regarding the physical protection of radiation sources and radioactive materials should be implemented in Sweden. The recommendations recently issued by IAEA should serve as a point of departure for working out such rules

  19. Structure and dimensions of radioactive contamination caused by use of nuclear weapons

    International Nuclear Information System (INIS)

    Ilijas, B.

    1996-01-01

    Radioactive contamination is one of unavoidable consequences of nuclear burst. Its structure and dimensions are depended of many factors connected with type of weapon, with meteorological conditions and location of burst and characteristics of area involved. Contamination manifests in two ways - as induced radioactivity in the nearness of the center of explosion and as radioactive fallout. Induced radioactivity originates from interaction of neutrons from primary beam with elements naturally presents in environment, which results in creating radionuclides and area of radioactive contamination. Radioactive fallout consists of material formed or collected in the explosion that falls on earth in form of small particles. This contaminant contains α, β and γ sources with structure dependent of explosive energy and location of burst. Some radionuclides, often present in fallout, are very dangerous as internal sources ( 90 Sr, 131 I, 137 Cs, 239 Pu). Dimension of contaminated area varies widely, but if one has Knowledge of enough parameters, it is possible to predict its shape, as well as dose rate on some distance from zero point. Preciseness of this work is essentially affected by credibility of data involved and by kind of selected model. Using of well-chosen model enables on-time evaluation of risk from radioactive contamination and planning adequate protection. (author)

  20. State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants

    International Nuclear Information System (INIS)

    1980-04-01

    A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report