Air filters for use at nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Linder, P [Aktiebolaget Atomenergi, Studsvik, Nykoeping (Sweden)

1970-12-01

The ventilation system of a nuclear facility plays a vital role in ensuring that the air in working areas and the environment remains free from radioactive contamination. An earlier IAEA publication, Techniques for Controlling Air Pollution from the Operation of Nuclear Facilities, Safety Series No. 17, deals with the design and operation of ventilation systems at nuclear facilities. These systems are usually provided with air-cleaning devices which remove the contaminants from the air. This publication is intended as a guide to those who are concerned with the design of air-filtering systems and with the testing, operation and maintenance of air-filter installations at nuclear facilities. Emphasis is mainly placed on so-called high-efficiency particulate air filters (HEPA filters) and on providing general information on them. Besides describing the usual filter types, their dimensions and construction materials, the guidebook attempts to explain their properties and behaviour under different operating conditions. It also gives advice on testing and handling the filters so that effective and safe performance is ensured. The guidebook should serve as an introduction to the use of high efficiency particulate air filters in countries where work with radioactive materials has only recently commenced. The list of references at the end of the book indicates sources of more advanced information for those who already have comprehensive experience in this field. It is assumed here that the filters are obtained from a manufacturer, and the guidebook thus contains no information on the design and development of the filter itself, nor does it deal with the cleaning of the intake air to a plant, with gas sorption or protective respiratory equipment.

Air filters for use at nuclear facilities

International Nuclear Information System (INIS)

Linder, P.

1970-01-01

The ventilation system of a nuclear facility plays a vital role in ensuring that the air in working areas and the environment remains free from radioactive contamination. An earlier IAEA publication, Techniques for Controlling Air Pollution from the Operation of Nuclear Facilities, Safety Series No. 17, deals with the design and operation of ventilation systems at nuclear facilities. These systems are usually provided with air-cleaning devices which remove the contaminants from the air. This publication is intended as a guide to those who are concerned with the design of air-filtering systems and with the testing, operation and maintenance of air-filter installations at nuclear facilities. Emphasis is mainly placed on so-called high-efficiency particulate air filters (HEPA filters) and on providing general information on them. Besides describing the usual filter types, their dimensions and construction materials, the guidebook attempts to explain their properties and behaviour under different operating conditions. It also gives advice on testing and handling the filters so that effective and safe performance is ensured. The guidebook should serve as an introduction to the use of high efficiency particulate air filters in countries where work with radioactive materials has only recently commenced. The list of references at the end of the book indicates sources of more advanced information for those who already have comprehensive experience in this field. It is assumed here that the filters are obtained from a manufacturer, and the guidebook thus contains no information on the design and development of the filter itself, nor does it deal with the cleaning of the intake air to a plant, with gas sorption or protective respiratory equipment

Phase I aging assessment of nuclear air-treatment system high efficiency particulate air and adsorbers

International Nuclear Information System (INIS)

Winegardner, W.K.

1996-01-01

A phase I aging assessment of high efficiency particulate air filters and activated carbon gas adsorption units was performed by the Pacific Northwest Laboratory as part of the US Nuclear Regulatory Commission's Nuclear Plant Aging Research Program. Information was compiled concerning design features, failure experience, aging mechanisms, effects, and stressors, and monitoring methods. Over 1100 failures, or 12% of the filter installations, were reported as part of a US Department of energy survey. Investigators from other laboratories have suggested that aging could have contributed to over 80% of these failures. Several instances of impaired performance as the result of the premature aging of carbon were reported. Filter aging mechanisms range from those associated with particle loading to reactions that alter the properties of gaskets. Mechanisms that can lead to impaired adsorber performance include the loss of potentially available active sites as a result of the adsorption of moisture or pollutants. Stressors include heat, moisture, radiation, and airborne particles and contaminants. (orig.)

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

The ''Nuclear-Karlsruhe'' air-filter system

International Nuclear Information System (INIS)

Berliner, P.; Ohlmeyer, M.; Stotz, W.

1976-01-01

Increasing requirements for exhaust-air filter systems used in nuclear facilities induced the Gesellschaft fuer Kernforschung to develop the ''Nuclear-Karlsruhe'' HEPA filter system. This novel development has profited by experience gained in previous incidents as well as by maitenance and decontamination work performed with different HEPA filter systems. The proved ''Nuclear-Karlsruhe'' system takes equally into account the demands for optimum safety, maximum efficiency and economy, and is distinguished by the following features: (1) The air current is defected by 180 0 in the casing. Deflection causes quite a number of improvements, results in substantial reduction of space requirements, and avoids the dispersion of pollutants to the clean-air side. Besides, the HEPA filter is protected from damage by condensed particles or foreign materials entrained; (2) The ''Nuclear-Karlsruhe'' system allows gas-tight filter replacement. Special replacement collars have been provided at the casing, which allow the tight fastening of replacement bags which are self-locking. (3) In-place testing in the operating condition can be carried out very conveniently because the air is deflected. Minimum leaks in the filter medium or in the filter gasket can be detected by the high-sensitivity visual oil-thread test, which makes leaks distinctly visible as oil mist threads through a transparent front window provided on the clean-air side. The test takes only some minutes and its sensitivity is hardly matched by any other technique. (4) The clamping mechanism is installed outside the casing, i.e. outside the polluted or aggressive media. The contact force is spring-loaded absolutely uniformly to the circular filter gasket. (5) For practical and econmic reasons the filter casings can be locked individually so as to be gas-tight. (6) The entire system is made of stainless or coated steel and metal parts which are corrosion and fire-resistant. (author)

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

Experience of air transport of nuclear fuel material as type A package

International Nuclear Information System (INIS)

Kawasaki, Masashi; Kageyama, Tomio; Suzuki, Toru

2004-01-01

Special law on nuclear disaster countermeasures (hereafter called as to nuclear disaster countermeasures low) that is domestic law for dealing with measures for nuclear disaster, was enforced in June, 2000. Therefore, nuclear enterprise was obliged to report accidents as required by nuclear disaster countermeasures law, besides meeting the technical requirement of existent transport regulation. For overseas procurement of plutonium reference materials that are needed for material accountability, A Type package must be transported by air. Therefore, concept of air transport of nuclear fuel materials according to the nuclear disaster countermeasures law was discussed, and the manual including measures against accident in air transport was prepared for the oversea procurement. In this presentation, the concept of air transport of A Type package containing nuclear fuel materials according to the nuclear disaster countermeasures law, and the experience of a transportation of plutonium solution from France are shown. (author)

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

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

Radionuclide characterization of environmental air around nuclear facilities

International Nuclear Information System (INIS)

Gede Sutresna Wijaya; Anung Muharini

2015-01-01

Air is an important environmental component in human life. Presence of air pollutants or contaminants will have a negative impact on human health. According to the existence of a nuclear facility in Yogyakarta, the characterization of radionuclides in the air is absolutely necessary to ensure the safety of people and the environment and also to supervise the safe operation of the facility. In this research the characterization of radionuclides in the air was carried through the air sampling by using High Volume Air Sampler equipped with filter TFA 2133, followed by analysis using combination of a gamma and alpha spectrometers. The concentration of radioactivity in the air fluctuates depending on the time and duration of sampling. Characterization of gamma emitting radionuclides in the air is dominated by radon progeny radionuclides such as 214 Pb, 214 Bi with activity 20.09 ± 1.23 until 32.91 ± 4.87 Bq/m 3 and 31.22 ± 1.76 until 44.25 ± 4.91 Bq/m 3 . Alpha emitter radionuclide was dominated by 214 Po (7.69 MeV) which is also radon progeny and a primordial radionuclides. It can be concluded that the presence of radionuclides in the environmental air not as a product resulting from the operation of nuclear facilities in Yogyakarta. (author)

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

The Air Blast Wave from a Nuclear Explosion

Science.gov (United States)

Reines, Frederick

The sudden, large scale release of energy in the explosion of a nuclear bomb in air gives rise, in addition to nuclear emanations such as neutrons and gamma rays, to an extremely hot, rapidly expanding mass of air.** The rapidly expanding air mass has an initial temperature in the vicinity of a few hundred thousand degrees and for this reason it glows in its early stages with an intensity of many suns. It is important that the energy density in this initial "ball of fire" is of the order of 3 × 103 times that found in a detonating piece of TNT and hence that the initial stages of the large scale air motion produced by a nuclear explosion has no counterpart in an ordinary. H. E. explosion. Further, the relatively low temperatures ˜2,000°C associated with the initial stages of an H. E. detonation implies that the thermal radiation which it emits is a relatively insignificant fraction of the total energy involves. This point is made more striking when it is remembered that the thermal energy emitted by a hot object varies directly with the temperature in the Rayleigh Jeans region appropriate to the present discussion. The expansion of the air mass heated by the nuclear reaction produces, in qualitatively the same manner as in an H.E. explosion or the bursting of a high pressure balloon, an intense sharp pressure pulse, a shock wave, in the atmosphere. As the pressure pulse spreads outward it weakens due to the combined effects of divergence and the thermodynamically irreversible nature of the shock wave. The air comprising such a pressure pulse or blast wave moves first radially outward and then back towards the center as the blast wave passes. Since a permanent outward displacement of an infinite mass of air would require unlimited energy, the net outward displacement of the air distant from an explosion must approach zero with increasing distance. As the distance from the explosion is diminished the net outward displacement due to irreversible shock heating of

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)

Applied research on air pollution using nuclear-related analytical techniques

International Nuclear Information System (INIS)

1994-01-01

A co-ordinated research programme (CRP) on applied research on air pollution using nuclear-related techniques is a global CRP which will run from 1992-1996, and will build upon the experience gained by the Agency from the laboratory support that it has been providing for several years to BAPMoN - the Background Air Pollution Monitoring Network programme organized under the auspices of the World Meterological Organization. The purpose of this CRP is to promote the use of nuclear analytical techniques in air pollution studies, e.g. NAA, XFR, and PIXE for the analysis of toxic and other trace elements in suspended particulate matter (including air filter samples), rainwater and fog-water samples, and in biological indicators of air pollution (e.g. lichens and mosses). The main purposes of the core programme are i) to support the use of nuclear and nuclear-related analytical techniques for practically-oriented research and monitoring studies on air pollution ii) to identify major sources of air pollution affecting each of the participating countries with particular reference to toxic heavy metals, and iii) to obtain comparative data on pollution levels in areas of high pollution (e.g. a city centre or a populated area downwind of a large pollution source) and low pollution (e.g. rural areas). This document reports the discussions held during the first Research Co-ordination Meeting (RCM) for the CRP which took place at the IAEA Headquarters in Vienna. Refs, figs and tabs

Mapping air pollution. Application of nuclear techniques

International Nuclear Information System (INIS)

Parr, R.M.; Stone, S.F.; Zeisler, R.

1996-01-01

Nuclear techniques have important applications in the study of air pollution and many of its components. However, it is in the study of airborne particulate matter (APM) that nuclear analytical techniques find many of their most important applications. This article focuses on those applications, and on the work of the IAEA in this important field of study. 2 figs

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

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.

Subcritical wet air oxidation of organic solvents and chelating agents of the nuclear fuel

International Nuclear Information System (INIS)

Bachir, Souley

1999-01-01

This document deals with the environment control, more specially organic solvents and chelating agents destruction, employed in the nuclear industry. This work details the subcritical wet air oxidation process. Another part of the document deals with the possible coupling between this process and the biodegradation technic in the framework of the sewage sludges treatment. (A.L.B.)

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

The Evolution of Air and Nuclear Doctrine: The Theories that Shaped SIOP-62

Science.gov (United States)

2016-06-01

STUDIES AIR UNIVERSITY MAXWELL AIR FORCE BASE, ALABAMA JUNE 2016 DISTRIBUTION A. Approved for public release: distribution unlimited ii...recommendations including, in April 1956, advanced authorization to Air Defense Command to use nuclear-tipped Nike -Hercules surface-to-air missiles to...The Sources of Military Doctrine, 14-15. 58 nuclear strike.101 In response, the Secretary of Defense ordered deployment of Nike -Hercules

Ventilation and air conditioning system in waste treatment and storage facilities

International Nuclear Information System (INIS)

Kinoshita, Hirotsugu; Sugawara, Kazushige.

1987-01-01

So far, the measures concerning the facilities for treating and storing radioactive wastes in nuclear fuel cycle in Japan were in the state which cannot be said to be sufficient. In order to cope with this situation, electric power companies constructed and operated radioactive waste concentration and volume reduction facilities, solid waste storing facilities for drums, high level solid waste storing facilities, spent fuel cask preserving facilities and so on successively in the premises of nuclear power stations, and for the wastes expected in future, the research and the construction plan of the facilities for treating and storing low, medium and high level wastes have been advanced. The ventilation and air conditioning system for these facilities is the important auxiliary system which has the mission of maintaining safe and pleasant environment in the facilities and lowering as far as possible the release of radioactive substances to outside. The outline of waste treatment and storage facilities is explained. The design condition, ventilation and air conditioning method, the features of respective waste treatment and storage facilities, and the problems for the future are described. Hereafter, mechanical ventilation system continues to be the main system, and filters become waste, while the exchange of filters is accompanied by the radiation exposure of workers. (Kako, I.)

Air Shipment of Highly Enriched Uranium Spent Nuclear Fuel from Romania

Energy Technology Data Exchange (ETDEWEB)

K. J. Allen; I. Bolshinsky; L. L. Biro; M. E. Budu; N. V. Zamfir; M. Dragusin

2010-07-01

Romania safely air shipped 23.7 kilograms of Russian origin highly enriched uranium (HEU) spent nuclear fuel from the VVR S research reactor at Magurele, Romania, to the Russian Federation in June 2009. This was the world’s first air shipment of spent nuclear fuel transported in a Type B(U) cask under existing international laws without special exceptions for the air transport licenses. This shipment was coordinated by the Russian Research Reactor Fuel Return Program (RRRFR), part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), in cooperation with the Romania National Commission for Nuclear Activities Control (CNCAN), the Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH), and the Russian Federation State Corporation Rosatom. The shipment was transported by truck to and from the respective commercial airports in Romania and the Russian Federation and stored at a secure nuclear facility in Russia where it will be converted into low enriched uranium. With this shipment, Romania became the 3rd country under the RRRFR program and the 14th country under the GTRI program to remove all HEU. This paper describes the work, equipment, and approvals that were required to complete this spent fuel air shipment.

Air Shipment of Highly Enriched Uranium Spent Nuclear Fuel from Romania

International Nuclear Information System (INIS)

Allen, K.J.; Bolshinsky, I.; Biro, L.L.; Budu, M.E.; Zamfir, N.V.; Dragusin, M.

2010-01-01

Romania safely air shipped 23.7 kilograms of Russian-origin highly enriched uranium (HEU) spent nuclear fuel from the VVR-S research reactor at Magurele, Romania, to the Russian Federation in June 2009. This was the world's first air shipment of spent nuclear fuel transported in a Type B(U) cask under existing international laws without special exceptions for the air transport licenses. This shipment was coordinated by the Russian Research Reactor Fuel Return Program (RRRFR), part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), in cooperation with the Romania National Commission for Nuclear Activities Control (CNCAN), the Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH), and the Russian Federation State Corporation Rosatom. The shipment was transported by truck to and from the respective commercial airports in Romania and the Russian Federation and stored at a secure nuclear facility in Russia where it will be converted into low enriched uranium. With this shipment, Romania became the 3. country under the RRRFR program and the 14. country under the GTRI program to remove all HEU. This paper describes the work, equipment, and approvals that were required to complete this spent fuel air shipment. (authors)

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)

Ventilation and air-conditioning system for PWR nuclear power plant

International Nuclear Information System (INIS)

Ohmoto, Kenji

1987-01-01

This report outlines the ventilation and air conditioning facilities for PWR nuclear power plant as well as design re-evaluation and optimization of ventilation and air-conditioning. The primary PWR installations are generally housed in the nuclear reactor building, auxiliary buildings and control building, which are equipped with their own ventilation and air-conditioning systems to serve for their specific purposes. A ventilation/air-conditioning system should be able to work effectively not only for maintaining the ordinary reactor operation but also for controlling the environmental temperature in the event of an accident. Designing of a ventilation/air-conditioning system relied on empirical data in the past, but currently it is performed based on information obtained from various analyses to optimize the system configuration and ventilation capacity. Design re-evaluation of ventilation/air-conditioning systems are conducted widely in various areas, aiming at the integration of safety systems, optimum combination of air-cooling and water-cooling systems, and optimization of the ventilation rate for controlling the concentrations of radioactive substances in the atmosphere in the facilities. It is pointed out that performance evaluation of ventilation/air-conditioning systems, which has been conducted rather macroscopically, should be carried out more in detal in the future to determine optimum air streams and temperature distribution. (Nogami, K.)

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

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

Techniques for controlling air pollution from the operation of nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

1966-03-01

This manual is provided for the guidance of those persons or authorities who are responsible for the organization, control and operation of ventilation systems and air-cleaning installations in nuclear establishments. It is intended to generalize about existing experience in the operation of such systems at nuclear facilities including reactors and laboratories for production, use and handling of radionuclides and other toxic materials. This manual will provide designers and operators of nuclear facilities in which ventilation and air-cleaning systems are used with the factors which have to be considered to create safe working conditions inside facilities and without polluting the atmosphere or the environment to a hazardous level. Refs, 24 figs, 5 tabs.

Structural dynamic and resistance to nuclear air blast

International Nuclear Information System (INIS)

Qureshi, S.M.

2003-01-01

A need exists to design protective shelters attached to specialized facilities against nuclear airbursts, explosive shocks and impacting projectiles. Designing such structures against nuclear and missile impact is a challenging task that needs to be looked into for design methodology formulation and practicability. Structures can be designed for overpressure pulsed generated by a nuclear explosion as well as the scabbing and perforation/punching of an impacting projectile. This paper discuses and formulates the methods of dynamic analysis and design required to undertake such a task. Structural resistance to peak overpressure pulse for a 20 KT weapons and smaller tactical nuclear weapons of 1 KT (16 psi, overpressure) size as a direct air blast overpressure has been considered in design of walls, beams and slabs of a special structure under review. The design of shear reinforcement as lacing is also carried out. Adopting the philosophy of strengthening and hardening can minimize the effect of air blast overpressure and projectile impact. The objective is to avoid a major structural failure. The structure then needs to be checked against ballistic penetration by a range of weapons or be required to resist explosive penetration from the charge detonated in contact with the structure. There is also a dire need to formulate protective guidelines for all existing and future critical facilities. (author)

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

Experience of air transport of nuclear fuel material in Japan

International Nuclear Information System (INIS)

Yamashita, T.; Toguri, D.; Kawasaki, M.

2004-01-01

Certified Reference Materials (hereafter called as to CRMs), which are indispensable for Quality Assurance and Material Accountability in nuclear fuel plants, are being provided by overseas suppliers to Japanese nuclear entities as Type A package (non-fissile) through air transport. However, after the criticality accident at JCO in Japan, special law defining nuclear disaster countermeasures (hereafter called as to the LAW) has been newly enforced in June 2000. Thereafter, nuclear fuel materials must meet not only to the existing transport regulations but also to the LAW for its transport

Thermal oxidation of nuclear graphite: A large scale waste treatment option

Science.gov (United States)

Jones, Abbie N.; Marsden, Barry J.

2017-01-01

This study has investigated the laboratory scale thermal oxidation of nuclear graphite, as a proof-of-concept for the treatment and decommissioning of reactor cores on a larger industrial scale. If showed to be effective, this technology could have promising international significance with a considerable impact on the nuclear waste management problem currently facing many countries worldwide. The use of thermal treatment of such graphite waste is seen as advantageous since it will decouple the need for an operational Geological Disposal Facility (GDF). Particulate samples of Magnox Reactor Pile Grade-A (PGA) graphite, were oxidised in both air and 60% O2, over the temperature range 400–1200°C. Oxidation rates were found to increase with temperature, with a particular rise between 700–800°C, suggesting a change in oxidation mechanism. A second increase in oxidation rate was observed between 1000–1200°C and was found to correspond to a large increase in the CO/CO2 ratio, as confirmed through gas analysis. Increasing the oxidant flow rate gave a linear increase in oxidation rate, up to a certain point, and maximum rates of 23.3 and 69.6 mg / min for air and 60% O2 respectively were achieved at a flow of 250 ml / min and temperature of 1000°C. These promising results show that large-scale thermal treatment could be a potential option for the decommissioning of graphite cores, although the design of the plant would need careful consideration in order to achieve optimum efficiency and throughput. PMID:28793326

Thermal oxidation of nuclear graphite: A large scale waste treatment option.

Directory of Open Access Journals (Sweden)

Alex Theodosiou

Full Text Available This study has investigated the laboratory scale thermal oxidation of nuclear graphite, as a proof-of-concept for the treatment and decommissioning of reactor cores on a larger industrial scale. If showed to be effective, this technology could have promising international significance with a considerable impact on the nuclear waste management problem currently facing many countries worldwide. The use of thermal treatment of such graphite waste is seen as advantageous since it will decouple the need for an operational Geological Disposal Facility (GDF. Particulate samples of Magnox Reactor Pile Grade-A (PGA graphite, were oxidised in both air and 60% O2, over the temperature range 400-1200°C. Oxidation rates were found to increase with temperature, with a particular rise between 700-800°C, suggesting a change in oxidation mechanism. A second increase in oxidation rate was observed between 1000-1200°C and was found to correspond to a large increase in the CO/CO2 ratio, as confirmed through gas analysis. Increasing the oxidant flow rate gave a linear increase in oxidation rate, up to a certain point, and maximum rates of 23.3 and 69.6 mg / min for air and 60% O2 respectively were achieved at a flow of 250 ml / min and temperature of 1000°C. These promising results show that large-scale thermal treatment could be a potential option for the decommissioning of graphite cores, although the design of the plant would need careful consideration in order to achieve optimum efficiency and throughput.

Space Nuclear Thermal Propulsion (SNTP) Air Force facility

Science.gov (United States)

Beck, David F.

The Space Nuclear Thermal Propulsion (SNTP) Program is an initiative within the US Air Force to acquire and validate advanced technologies that could be used to sustain superior capabilities in the area or space nuclear propulsion. The SNTP Program has a specific objective of demonstrating the feasibility of the particle bed reactor (PBR) concept. The term PIPET refers to a project within the SNTP Program responsible for the design, development, construction, and operation of a test reactor facility, including all support systems, that is intended to resolve program technology issues and test goals. A nuclear test facility has been designed that meets SNTP Facility requirements. The design approach taken to meet SNTP requirements has resulted in a nuclear test facility that should encompass a wide range of nuclear thermal propulsion (NTP) test requirements that may be generated within other programs. The SNTP PIPET project is actively working with DOE and NASA to assess this possibility.

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.

A study of air-operated valves in U.S. nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Rothberg, O. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States); Khericha, S. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States); Watkins, J. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States); Holbrook, M. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States)

2000-02-01

A study of air-operated valves in nuclear power plant applications was conducted for the NRC Office of Research (the project was initiated by NRC/AEOD). The results of the study were based on visits to seven nuclear power plant sites, literature studies, and examinations of event records in databases available to the NRC. The purpose is to provide information to the NRC staff concerning capabilities and performance of air-operated valves (AOVs). Descriptions of air systems and AOVs were studied along with the support systems and equipment. Systems and equipment that contain AOVs and SOVs were studied to determine their dependencies. Applications of AOVs and SOVs were listed along with current NRC requirements.

A study of air-operated valves in U.S. nuclear power plants

International Nuclear Information System (INIS)

Rothberg, O.; Khericha, S.; Watkins, J.; Holbrook, M.

2000-01-01

A study of air-operated valves in nuclear power plant applications was conducted for the NRC Office of Research (the project was initiated by NRC/AEOD). The results of the study were based on visits to seven nuclear power plant sites, literature studies, and examinations of event records in databases available to the NRC. The purpose is to provide information to the NRC staff concerning capabilities and performance of air-operated valves (AOVs). Descriptions of air systems and AOVs were studied along with the support systems and equipment. Systems and equipment that contain AOVs and SOVs were studied to determine their dependencies. Applications of AOVs and SOVs were listed along with current NRC requirements.

Development of Air Dispersion Modeling for Future Nuclear Plant in Malaysia

International Nuclear Information System (INIS)

Mohd Nahar Othman

2011-01-01

The impact development of Nuclear power plant in Malaysia, can be very negative to the nearby population, causing public restlessness and consequently affecting the image of the authorities in the countries. The precise source of the pollution from the nuclear power plant must be determined, pollution emission level and the meteorological conditions are needed to predict and established the ambient air to the save level at the perimeter fence of the plant and address it with respect to the radiological ambient standards. Upon modeling using an established package as well as site measurements, the radiological level at the perimeter fence of the plant must deduced and lower than the normal ambient level. Based on this issue, a modeling study was made in vicinity of Malaysian Nuclear Agency TRIGA reactor in the area of Bangi, Selangor to evaluate the possibility of movement of air around the area and their impact. This paper will address and discuss the modeling base on the data getting from Meteorological Department such as measurement of wind speed, temperature, humidity, ambient air radiological concentration and ect. The purpose of Air Dispersion Modeling is to establish the critical ambient emission level, as well as radiological modeling. The focus will be made on exploring the use of Ausplume modeling to develop correlations between the radiological concentrations, chemical compositions and ambient model for emission controls. (author)

Air box shock absorber for a nuclear reactor

International Nuclear Information System (INIS)

Pradhan, A.V.; George, J.A.

1977-01-01

Disclosed is an air box type shock absorber primarily for use in an ice condenser compartment of a nuclear reactor. The shock absorber includes a back plate member and sheet metal top, bottom, and front members. The front member is prefolded, and controlled clearances are provided among the members for predetermined escape of air under impact and compression. Prefolded internal sheet metal stiffeners also absorb a portion of the kinetic energy imparted to the shock absorber, and limit rebound. An external restraining rod guided by restraining straps insures that the sheet metal front member compresses inward upon impact. 6 claims, 11 figures

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

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

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.)

Air pollution and international law: a subject important to nuclear power

International Nuclear Information System (INIS)

Rose, D.J.

1985-01-01

An increasingly important advantage of nuclear power is its minimal air pollution, in particular the absence of combustion products such as acid rain and carbon dioxide. Developing a consensus about acceptable limits of such pollutants is a slow process that culminates in domestic an international agreements. Therefore, the pace of adoption of new technologies, nuclear power included, is often controlled by the level and intensity of debate, rather than by the technology alone. The state of understanding and consensus about local and long-range transboundary air pollution is therefore germane to the nuclear sector. Progress over the past several decades, mainly between the United States and Canada and within Europe, in developing a more comprehensive and effective international consensus, both informal and formal, is reviewed. There appears to be a trend toward more effective international participation in seeking a less-polluting world, albeit it is punctuated at times by unconcern

Compressed-air and backup nitrogen systems in nuclear power plants

International Nuclear Information System (INIS)

Hagen, E.W.

1982-07-01

This report reviews and evaluates the performance of the compressed-air and pressurized-nitrogen gas systems in commercial nuclear power units. The information was collected from readily available operating experiences, licensee event reports, system designs in safety analysis reports, and regulatory documents. The results are collated and analyzed for significance and impact on power plant safety performance. Under certain circumstances, the fail-safe philosophy for a piece of equipment or subsystem of the compressed-air systems initiated a series of actions culminating in reactor transient or unit scram. However, based on this study of prevailing operating experiences, reclassifying the compressed-gas systems to a higher safety level will neither prevent (nor mitigate) the reoccurrences of such happenings nor alleviate nuclear power plant problems caused by inadequate maintenance, operating procedures, and/or practices. Conversely, because most of the problems were derived from the sources listed previously, upgrading of both maintenance and operating procedures will not only result in substantial improvement in the performance and availability of the compressed-air (and backup nitrogen) systems but in improved overall plant performance

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)

Tritium concentration in ambient air around Kaiga Nuclear Power Plant

Directory of Open Access Journals (Sweden)

Srinivas S Kamath

2018-01-01

Full Text Available Tritium (3H is one of the important long-lived radioisotopes in the gaseous effluent from nuclear power plants. In this article, we present the results of 3H monitoring in ambient air samples around the Kaiga Nuclear Power Plant, on the West Coast of India. Air samples were collected by moisture condensation method and the 3H concentration was determined by liquid scintillation spectrometry. The 3H concentration in the 2.3–15 km zone of the power plant varied in the range of <0.04–6.64 Bq m−3 with a median of 0.67 Bq m−3. The samples collected from the 2.3–5 km zone of the power plant exhibit marginally higher concentration when compared to the 5–10 km and 10–15 km zones, which is as expected. The values observed in the present study for Kaiga region are similar to those reported from other nuclear power plants, both within India and other parts of the world.

Air quality assessment in the vicinity of nuclear and thermal power stations

International Nuclear Information System (INIS)

Sivaramasundaram, K.; Vijay Bhaskar, B.; Muthusubramanian, P.; Rajan, M.P.; Hegde, A.G.

2007-01-01

The status and ranking of any country, in the context of globalisation, is decided by its economic progress, which is directly linked into power generation. The power is generated by many routes and the nuclear and thermal routes are noteworthy among them. As the power production and its associated activities may cause qualitative deterioration, it is essential to study the impact of power production on atmospheric environment. In this connection, a comparative study has been carried out to assess the air quality with special reference to criteria pollutants in the vicinity of nuclear and thermal power stations. In the present investigation, the air samples are collected on weekly basis and the pollutants such as sulphur dioxide (SO 2 ), nitrogen oxides (NOx), carbon monoxide (CO), suspended particulate matter (SPM) and respirable particulate matter (RPM) are estimated by adopting standard procedures set by United States-Environmental Protection Agency (US-EPA) and Central Pollution Control Board (CPCB). As the micro meteorological parameters influence on the status of air quality, simultaneous measurements of these parameters are also carried, out during sampling. It is studied that estimated concentrations of all criteria pollutants in the vicinity of these power stations are within the permissible limits set by CPCB. On the basis of the generated database pertaining to the concentrations of criteria air pollutants in the vicinity of nuclear and thermal power stations, it is concluded that nuclear power production may be considered as a viable option in terms of environmental protection in our country. (author)

Testing of adsorbents used in nuclear power plant air cleaning systems using the open-quotes Newclose quotes standards

International Nuclear Information System (INIS)

Freeman, W.P.

1993-01-01

Ever since the publication of the NRC Information Notice No. 87-32: Deficiencies in the Testing of Nuclear-Grade Activated Charcoal, nuclear power facilities in the US have struggled in their efforts to open-quotes...review the information for applicability to their facilities and consider action, if appropriate ...close quotes as stated in the notice. The encouragement of resident NRC inspectors at some nuclear power facilities has prompted a variety of responses ranging from no change at all in testing requirements to contemplated changes in plant technical specifications. This confusion is the result of a couple factors. The first factor is the lack of a current revision to NRC Regulatory Guide 1.52, the basic document used in nuclear power plant technical specifications for the testing of engineered-safety feature (ESF) post accident air cleaning systems. The second factor is the standards that have been written since the last revision of Reg. Guide 1.52 which include two revision of ANSI N509 and N510, two revisions of RDT M16-1T, two version of ASTM D3803, two versions of ASTM D4069, and three versions of an SME code AG-1. Few of the standards and codes listed above are commensurate with each other and, thus, present a nearly insolvable maze to the HVAC engineer asked to upgrade adsorbent testing requirements following the standards. This paper describes the authors experience with a number of nuclear power facilities in their efforts to meet the requirements of the new standards of testing adsorbents from nuclear power plant air cleaning systems. The existing standards are discussed in light of the current state of the art for adsorbent testing of adsorbent media from nuclear air treatment systems. Test results are presented showing the impact of new test requirements on acceptance criteria when compared to the old test requirements and recommendations are offered for solution of this testing problem in the future. 12 refs., 5 tabs

A simple method to determine Tr concentrations in the moisture of the exhaust air of nuclear facilities and in the ambient air

International Nuclear Information System (INIS)

Weber, H.W.; Schuettelkopf, H.

1983-04-01

In the course of nuclear power plant operation radioactive tritium is generated which is released to the environment as HTO via the exhaust air and the liquid effluents. Measurement and balancing of the tritium emissions are required in order to be able to evaluate the resulting radiation exposure of the population. For determination of the HTO emission the humidity of the measured air is absorbed at a rod shaped molecular sieve of 1/16'' mesh size. The desiccant is contacted with T-free water and the T activity concentration of the water is determined after 3 H/ 1 H isotope exchange. The rod shaped molecular sieves are suited for use under this method on account of their drying capacity largely independent of temperature and air humidity and the good handling capability. The detection limit is at 19 Bq HTO/m 3 air. The exhaust air from several 3 H-emitters of the Karlsruhe Nuclear Research Center was monitored by this method for its HTO content and the results were compared with the values measured at existing points of measurement. The good results have been the reason for the application of such collectors in the routine T-measurement performed within the framework of exhaust air monitoring on the site of the Karlsruhe Nuclear Research Center. (orig./HP) [de

Determination of the radioiodine species in the exhaust air of nuclear facilities

International Nuclear Information System (INIS)

Deuber, H.

1977-01-01

Using the selective I 2 sorption materials DSM 10 and DSM 11 measurements were performed with radioiodine species samplers in the exhaust air of a research reactor and of several nuclear power stations (BWR, PWR). The radioiodine species samplers were used upstream and downstream of iodine filters (containment exhaust air stand-by filter, shutoff room exhaust air filter) as well as in the exhaust air of the stack. The results obtained by use of DSM 10 and DSM 11 generally agreed. The percentage of aerosol iodine was low in all cases ( [de

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)

Review of nuclear air treatment system related License Event Reports for the period 1985 - 1987

International Nuclear Information System (INIS)

Jacox, J.W.

1989-01-01

This paper will continue the review of HVAC/NATS related LERS presented at past Air Cleaning Conferences by Dr. D. W. Moeller and his associates. The general approach and format are similar. LER abstracts from mid 1985 through 1987 were reviewed and those related to HVAC/NATS classified and analyzed. The categories were jointly developed by Dr. Moeller, Dr. Casper Sun and myself. In appropriate cases both primary and secondary categories fora problem are given. A basic listing by category and brief statistical review are presented. Additionally a number of categories are discussed in some detail. The categories chosen for specific review are intended to highlight particular problem areas. NUREG/CR-2000 License Event Report (LER) Compilation is the basis for the initial review and coding. In essentially all cases where an LER is classified as of interest the complete LER was obtained and reviewed in full. The intent of this paper is to provide a basis for the industry to document and analyze problem areas that require additional attention. It appears that about 15% of all LERS in the subject period are HVAC/NATS related. This figure is generally consistent with those reported at the 17th DOE Nuclear Air Cleaning Conference. It is hoped that such attention will allow additional resources to be allocated to upgrade systems, procedures and training as well as in some cases government regulation

Indoor Air Nuclear, Biological, and Chemical Health Modeling and Assessment System

Energy Technology Data Exchange (ETDEWEB)

Stenner, Robert D.; Hadley, Donald L.; Armstrong, Peter R.; Buck, John W.; Hoopes, Bonnie L.; Janus, Michael C.

2001-03-01

Indoor air quality effects on human health are of increasing concern to public health agencies and building owners. The prevention and treatment of 'sick building' syndrome and the spread of air-borne diseases in hospitals, for example, are well known priorities. However, increasing attention is being directed to the vulnerability of our public buildings/places, public security and national defense facilities to terrorist attack or the accidental release of air-borne biological pathogens, harmful chemicals, or radioactive contaminants. The Indoor Air Nuclear, Biological, and Chemical Health Modeling and Assessment System (IA-NBC-HMAS) was developed to serve as a health impact analysis tool for use in addressing these concerns. The overall goal was to develop a user-friendly fully functional prototype Health Modeling and Assessment system, which will operate under the PNNL FRAMES system for ease of use and to maximize its integration with other modeling and assessment capabilities accessible within the FRAMES system (e.g., ambient air fate and transport models, water borne fate and transport models, Physiologically Based Pharmacokinetic models, etc.). The prototype IA-NBC-HMAS is designed to serve as a functional Health Modeling and Assessment system that can be easily tailored to meet specific building analysis needs of a customer. The prototype system was developed and tested using an actual building (i.e., the Churchville Building located at the Aberdeen Proving Ground) and release scenario (i.e., the release and measurement of tracer materials within the building) to ensure realism and practicality in the design and development of the prototype system. A user-friendly "demo" accompanies this report to allow the reader the opportunity for a "hands on" review of the prototype system's capability.

Application of nuclear air cleaning and treatment codes

International Nuclear Information System (INIS)

Kriskovich, J.R.

1995-01-01

All modifications to existing ventilation systems, as well as any new ventilation systems used on the Hanford Site are required to meet both American Society of Mechanical Engineers (ASME) codes N509 and N510. Difficulties encountered when applying code N509 at the Hanford Site include the composition of the ventilation air stream and requirements related to ventilation equipment procurement. Also, the existing ventilation systems for the waste tanks at the Hanford Site cannot be tested in accordance with code N510 because of the current configuration of these systems

Application of nuclear air cleaning and treatment codes

Energy Technology Data Exchange (ETDEWEB)

Kriskovich, J.R. [Westinghouse Hanford Company, Richland, WA (United States)

1995-02-01

All modifications to existing ventilation systems, as well as any new ventilation systems used on the Hanford Site are required to meet both American Society of Mechanical Engineers (ASME) codes N509 and N510. Difficulties encountered when applying code N509 at the Hanford Site include the composition of the ventilation air stream and requirements related to ventilation equipment procurement. Also, the existing ventilation systems for the waste tanks at the Hanford Site cannot be tested in accordance with code N510 because of the current configuration of these systems.

The investigation on compressed air quality analysis results of nuclear power plants

International Nuclear Information System (INIS)

Sung, K. B.; Kim, H. K.; Kim, W. S.

2000-01-01

The compressed air system of nuclear power plants provides pneumatic power for both operation and control of various plant equipment, tools, and instrumentation. Included in the air supply systems are the compressors, coolers, moisture separators, dryers, filters and air receiver tanks that make up the major items of equipment. The service air system provides oil-free compressed air for general plant and maintenance use and the instrument air system provides dry, oil-free, compressed air for both nonessential and essential components and instruments. NRC recommended the periodic checks on GL88-14 'Instrument air supply system problems affecting safety-related equipment'. To ensure that the quality of the instrument air is equivalent to or exceeds the requirement s of ISA-S7.3(1975), air samples are taken at every refueling outage and analyzed for moisture, oil and particulate content. The over all results are satisfied the requirements of ISA-S7.3

Applied research on air pollution using nuclear-related analytical techniques. Report on the second research co-ordination meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

A co-ordinated research programme (CRP) on applied research on air pollution using nuclear-related techniques is a global CRP which started in 1992, and is scheduled to run until early 1997. The purpose of this CRP is to promote the use of nuclear analytical techniques in air pollution studies, e.g. NAA, XRF, and PIXE for the analysis of toxic and other trace elements in air particulate matter. The main purposes of the core programme are i) to support the use of nuclear and nuclear-related analytical techniques for research and monitoring studies on air pollution, ii) to identify major sources of air pollution affecting each of the participating countries with particular reference to toxic heavy metals, and iii) to obtain comparative data on pollution levels in areas of high pollution (e.g. a city centre or a populated area downwind of a large pollution source) and low pollution (e.g. rural area). This document reports the discussions held during the second Research Co-ordination Meeting (RCM) for the CRP which took place at ANSTO in Menai, Australia. (author)

Applied research on air pollution using nuclear-related analytical techniques. Report on the second research co-ordination meeting

International Nuclear Information System (INIS)

1995-01-01

A co-ordinated research programme (CRP) on applied research on air pollution using nuclear-related techniques is a global CRP which started in 1992, and is scheduled to run until early 1997. The purpose of this CRP is to promote the use of nuclear analytical techniques in air pollution studies, e.g. NAA, XRF, and PIXE for the analysis of toxic and other trace elements in air particulate matter. The main purposes of the core programme are i) to support the use of nuclear and nuclear-related analytical techniques for research and monitoring studies on air pollution, ii) to identify major sources of air pollution affecting each of the participating countries with particular reference to toxic heavy metals, and iii) to obtain comparative data on pollution levels in areas of high pollution (e.g. a city centre or a populated area downwind of a large pollution source) and low pollution (e.g. rural area). This document reports the discussions held during the second Research Co-ordination Meeting (RCM) for the CRP which took place at ANSTO in Menai, Australia. (author)

Damage Curves of a Nuclear Reactor Structure exposed to Air Blast Loading

International Nuclear Information System (INIS)

Brandys, I.; Ornai, D.; Ronen, Y.

2014-01-01

Nuclear Power Plant (NPP) radiological hazards due to accidental failure or deliberated attacks are of most concern due to their destructive and global consequences: large area contaminations, injuries, exposure to ionizing radiation (which can cause death or illness, depends on the levels of exposure), loss of lives of both humans and animals, and severe damage to the environment. Prevention of such consequences is of a global importance and it has led to the definition of safety & design guidelines, and regulations by various authorities such as IAEA, U.S. NRC, etc. The guidelines define general requirements for the integrity of a NPP’s physical barriers (such as protective walls) when challenged by external events, for example human induced explosion. A more specific relation to the design of a NPP is that its structures and equipment (reactor building, fuel building, safeguards building, diesel-generator building, pumping station, nuclear auxiliaries building, and effluent treatment building) must function properly: shutdown the reactor, removal of decayed heat, storage of spent fuel, and treatment and containment of radioactive effluents) under external explosion. It requires that the NPP’s structures and equipment resistance to external explosion should be analyzed and verified. The air blast loading created by external explosion, as well as its effects & consequences on different kinds of structures are described in the literature. Structural elements response to the air blast can be analyzed in general by a Single Degree of Freedom (SDOF) system that converts a distributed mass, loads, and resistance to concentrated mass, force, and stiffness located at a representative point of the structure's element where the displacements are the highest one. Proper shielding should be designed if the explosion blast effects are greater than the resistance capacity.External explosion effects should be considered within the Screening Distance Value (SDV) of the NPP

Techniques for controlling air pollution from the operation of nuclear facilities. Report of a panel

International Nuclear Information System (INIS)

1966-01-01

This manual is provided for the guidance of those persons or authorities who are responsible for the organization, control and operation of ventilation systems and air-cleaning installations in nuclear establishments. It is intended to generalize about existing experience in the operation of such systems at nuclear facilities including reactors and laboratories for production, use and handling of radionuclides and other toxic materials. This manual will provide designers and operators of nuclear facilities in which ventilation and air-cleaning systems are used with the factors which have to be considered to create safe working conditions inside facilities and without polluting the atmosphere or the environment to a hazardous level.

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

Air contamination analysis during emergency medical treatment

International Nuclear Information System (INIS)

Yamada, Y.; Fukutsu, K.; Yuuki, M.; Akashi, M.

2009-01-01

After radiological emergencies, patients contaminated with radioactivity are taken to radiation emergency hospitals for treatment. Numerical simulations using the computer software 'Flow Designer R were made in order to evaluate indoor air contamination caused by the breathing out of contaminated air. The National Inst. of Radiological Sciences facility was used for the numerical evaluation. Results indicate that the dispersion of contaminated air depends on the characteristics of the contaminants, and that the dispersion range was limited and localised. Only medical staff standing in a special position near the patient was exposed to almost un-diluted contaminated air. Highly contaminated air was evacuated with a local exhaust pump system. Room air quality was monitored using a continuous air sampling system, but it was found that the sampling point was not representative for the purpose of radiation protection. From the air-flow analysis, some problems that affect radiological safety were revealed and valuable information and measures for preventing secondary contamination were determined. (authors)

Air Force Nuclear Enterprise Organization: A Case Study

Science.gov (United States)

2016-09-15

changes. To address the objectives of this study, five investigative questions ( IQ ) are posed: IQ1. What constitutes the Air Force Nuclear Enterprise...are an effective tool being used to raise the level of training. But it is not only necessary to move away from training that merely checks a box...down to an authoritative brain trust of just a few pertinent players (e.g. AFGSC/CC, HAF/A10 Director, AFNWC/CC, etc). As this study has portrayed

Supply air filters after the nuclear reactor accident at Chernobyl

International Nuclear Information System (INIS)

Bonka, H.

1989-01-01

In the case of increased activity concentration in the air supply air filters are the facility compounds where enhanced activity is collected. Therefore, it was understandable that the people put questions about the doses caused by supply air filters after the nuclear reactor accident at Chernobyl. When comparing the local dose rate at a distance of 1 m in front of filters with the outdoor local dose rate due to dry deposited radionuclides, nearly the same local dose rate results assuming an air flow rate of approx. 60 m 3 /h. Supposing a 10 hours stay at a distance of 1 m in front of filters and an air flow rate of approx. 5000 m 3 /h the same dose is obtained after a 10 days delay as the dose due to outdoor inhalation. At Aachen, the local dose rate near to filters increased up to approx. 10 μSv/h. After a suitable time delay of one month filters could be rejected like normal waste. A review is given on individual measured values

Air contamination measurements for the evaluation of internal dose to workers in nuclear medicine departments

Science.gov (United States)

De Massimi, B.; Bianchini, D.; Sarnelli, A.; D'Errico, V.; Marcocci, F.; Mezzenga, E.; Mostacci, D.

2017-11-01

Radionuclides handled in nuclear medicine departments are often characterized by high volatility and short half-life. It is generally difficult to monitor directly the intake of these short-lived radionuclides in hospital staff: this makes measuring air contamination of utmost interest. The aim of the present work is to provide a method for the evaluation of internal doses to workers in nuclear medicine, by means of an air activity sampling detector, to ensure that the limits prescribed by the relevant legislation are respected. A continuous air sampling system measures isotope concentration with a Nal(TI) detector. Energy efficiency of the system was assessed with GEANT4 and with known activities of 18F. Air is sampled in a number of areas of the nuclear medicine department of the IRST-IRCCS hospital (Meldola- Italy). To evaluate committed doses to hospital staff involved (doctors, technicians, nurses) different exposure situations (rooms, times, radionuclides etc) were considered. After estimating the intake, the committed effective dose has been evaluated, for the different radionuclides, using the dose coefficients mandated by the Italian legislation. Error propagation for the estimated intake and personal dose has been evaluated, starting from measurement statistics.

Without the nuclear, would air be more breathable?

International Nuclear Information System (INIS)

Le Ngoc, Boris

2015-01-01

As pollution peaks are noticed in all big cities with dramatic consequences on health and on the economy, this article first outline these consequences of the use of fossil energies: 480.000 premature deaths in OECD countries due to the consequences of atmospheric pollution which results in heart and respiratory diseases, coronary diseases, cerebrovascular accidents or lung cancers, and nearly 120.000 deaths in dwellings, mainly in developing countries, due to the use of solid fuels for cooking and heating. Figures of the assessment of the economic cost and health impact of air pollution in 53 European countries are given. The author then outlines that the use of nuclear energy does not generate these pollutions: according to a study, nuclear energy avoided 1.8 million deaths between 1971 and 2009, and its replacement by coal would result in 4 to 7 million additional deaths

Nuclear fuel treatment facility for 'Mutsu'

International Nuclear Information System (INIS)

Kanazawa, Toshio; Fujimura, Kazuo; Horiguchi, Eiji; Kobayashi, Tetsuji; Tamekiyo, Yoshizou

1989-01-01

A new fixed mooring harbor in Sekinehama and surrounding land facilities to accommodate a test voyage for the nuclear-powered ship 'Mutsu' in 1990 were constructed by the Japan Atomic Energy Research Institute. Kobe Steel took part in the construction of the nuclear fuel treatment process in various facilities, beginning in October, 1988. This report describes the outline of the facility. (author)

Nuclear waste treatment program: Annual report for FY 1987

International Nuclear Information System (INIS)

Brouns, R.A.; Powell, J.A.

1988-09-01

Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs

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

Nuclear Waste Treatment Program: Annual report for FY 1986

International Nuclear Information System (INIS)

Burkholder, H.C.; Brouns, R.A.; Powell, J.A.

1987-09-01

To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs

Nuclear Waste Treatment Program: Annual report for FY 1986

Energy Technology Data Exchange (ETDEWEB)

Burkholder, H.C.; Brouns, R.A. (comps.); Powell, J.A. (ed.)

1987-09-01

To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs.

Chemical aspects of nuclear waste treatment

International Nuclear Information System (INIS)

Bond, W.D.

1980-01-01

The chemical aspects of the treatment of gaseous, liquid, and solid wastes are discussed in overview. The role of chemistry and the chemical reactions in waste treatment are emphasized. Waste treatment methods encompass the chemistry of radioactive elements from every group of the periodic table. In most streams, the radioactive elements are present in relatively low concentrations and are often associated with moderately large amounts of process reagents, or materials. In general, it is desirable that waste treatment methods are based on chemistry that is selective for the concentration of radionuclides and does not require the addition of reagents that contribute significantly to the volume of the treated waste. Solvent extraction, ion exchange, and sorbent chemistry play a major role in waste treatment because of the high selectivity provided for many radionuclides. This paper deals with the chemistry of the onsite treatment methods that is typically used at nuclear installations and is not concerned with the chemistry of the various alternative materials proposed for long-term storage of nuclear wastes. The chemical aspects are discussed from a generic point of view in which the chemistry of important radionuclides is emphasized

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

Treatment of air leak in polytrauma patients with blunt chest injury.

Science.gov (United States)

Halat, Gabriel; Negrin, Lukas L; Chrysou, Konstantina; Hoksch, Beatrix; Schmid, Ralph A; Kocher, Gregor J

2017-09-01

Precise diagnostics and an adequate therapeutic approach are mandatory in the treatment of air leak in polytrauma patients with blunt chest trauma. The aim of this study was to evaluate the incidence, characteristics, and management of air leak following this injury pattern. Data from 110 polytrauma patients was collected retrospectively. Fifty-four patients received initial treatment by chest tube placement for pneumothorax. These patients were classified into two groups, one with severe air leak and one with minor air leak. An evaluation of injury pattern, chest wall injuries in particular, duration of air leak, reason for drainage maintenance in place, hospital length of stay, ICU stay, ventilator duration, type of treatment, and the delay to surgical intervention was performed. Whereas 4 patients showed severe air leak and were subsequently scheduled for timely surgical intervention, the remaining 50 patients only showed minor air leak. Only 7 patients with minor air leak suffered from prolonged air leak (>5days), which spontaneously resolved in all of them after a mean duration of 7.7days (range 6-12days). Absence of a prolonged air leak resulted in a shorter length of stay and a shorter duration of mechanical ventilation, although no statistical significance was observed. Early spontaneous cessation of most minor air leaks as well as early surgical intervention for severe air leak lead to very satisfactory patient outcomes with a relatively short hospital stay in our patients. We therefore advocate early surgery for lacerations of the pulmonary parenchyma resulting in severe air leak, whereas minor air leaks can usually be treated conservatively. Copyright © 2017 Elsevier Ltd. All rights reserved.

Phenomenology of deflagration and detonation of hydrogen-air mixtures in water cooled nuclear power plants

International Nuclear Information System (INIS)

Lombardi, G.

1984-01-01

This paper summarizes fundamentals of the flammability of the hydrogen-air mixtures and hydrogen-air containing added steam or other inerting agent. The flammability behaviour of such gaseous mixtures is described with reference to physical and chemical conditions close enough to those expected in the containment of a nuclear reactor during a LOCA

New challenges to air/gas cleaning systems

Energy Technology Data Exchange (ETDEWEB)

Kovach, J.L. [NUCON International, Inc., Columbus, OH (United States)

1997-08-01

This paper discusses the need for changes in the design and manufacturing of air and gas cleaning systems to meet waste management and site remediation requirements. Current design and manufacturing practices are primarily directed toward evaluating operational problems with existing systems in nuclear reactor facilities. However, nuclear waste management needs have developed which are much broader in scope and have different processing conditions. Numerous examples of air cleaning needs for waste management activities are provided; the major differences from operating facility needs are the requirement for continuous effluent treatment under widely different processing conditions. Related regulatory issues are also discussed briefly. 1 ref.

Licensing Air and Transboundary Shipments of Spent Nuclear Fuel

International Nuclear Information System (INIS)

Komarov, S.V.; Budu, M.E.; Derganov, D.V.; Savina, O.A.; Bolshinsky, I.M.; Moses, S.D.; Biro, L.

2016-01-01

Since 1996 the IAEA TS-R-1 regulation included new requirements applicable to transport of fissile materials by air. The later 2005 and 2009 editions confirmed the validity of those provisions. Despite the fact that the IAEA TS-R-1 allows for air shipments of SNF in Type B and Type C packages, the examples of such shipments are not abundant. Nuclear regulatory bodies and transport safety experts are cautious about air shipments of SNF. Why so? What are the risks? What are the alternatives? In this new regulatory framework, in 2009, two air shipments in Type B packages of Research Reactor (RR) Spent Nuclear Fuel (SNF) from Romania and Libya were performed under the U.S. DOE/NNSA RRRFR Program. The first licensing process of such shipment brought up many questions about package and shipment safety from the licensing experts' side and so the scope of analyses exceeded the requirements of IAEA. Under the thorough supervision of Rosatom and witnessed by DOE and CNCAN, all questions were answered by various strength analyses and risk evaluations. But the progress achieved didn't stop here. In 2010-2011, an energy absorption container (EAC) with titanium spheres as absorbers based on the SKODA VPVR/M cask was designed as the first Type C package in the world destined for RR SNF, currently under approval process. At the same time, intense preparations for the safe removal of the Russian-origin damaged RR SNF from Serbia, Vinca were in progress. The big amount of SNF and its rapidly worsening condition imposed as requirements to organize only one shipment as fast as possible, i.e. using at the maximum extent the entire experience available from other SNF shipments. The long route, several transit countries and means of transport, two different casks, new European regulations and many other issues resulted for the Serbian shipment in one of the most complex SNF shipments’ licensing exercise. This paper shows how the international regulatory framework ensures the

Determination of air pollutants by nuclear chemical analysis

International Nuclear Information System (INIS)

Lesny, J.; Toelgyessy, J.

1975-01-01

Nuclear analytical methods are discussed with a view to their applicability in the determination of air pollutants. It is shown that some methods (use of radioactive kryptonates in automatic analyzers, application of activation analysis, X-ray fluorescence methods) are developed in theory and proven in practice in such an extent to be widely used in the near future in the control of the environment. Many other methods are becoming increasingly important for the solution of specific problems of environmental protection (such as the control of sudden environmental contamination in the proximity of chemical plants and industrial centers). (author)

Air Monitoring to Control the Intake of Airborne Radioiodine-131 Contaminants by Nuclear Medicine Workers

International Nuclear Information System (INIS)

Jiemwutthisak, P.; Sritongkul, N.; Chaudakshetrin, P.; Kanchanaphiboon, P.; Tuntawiroon, M.

2012-01-01

Inhalation of radioiodine-131 is the largest cause of internal dose to nuclear medicine workers. The concentration of radioiodine-131 in air is limited by the Derived Air Concentration (DAC) of 416.67 Bq/m3. In this study air monitoring shall be performed to measure the radioiodine-131 contaminant in air by sample collection and analysis. Air samples were drawn from areas where there is a potential for I-131 airborne radioactivity e.g. in the hot laboratory, radioiodine treatment rooms, radioactive waste collection areas and waste water treatment plant. A portable battery-operated air sampler, Gilian BDX II with carbon- impregnated cellulose filters was used for air sampling. The flow rate was adjusted to 3 liters per minute and the sampler run for 180 minutes. Iodine-131 radioactivity on filter was measured for 10 minutes by 2 NaI(Tl) gamma counters, Perkin Elmer Wallac Wizard 1480 (3''x3'') and Atomlab 950 PC (2''x2'') with and objective for inter comparison. Counting efficiency of the counters are 57 and 39 percent respectively. Agreeable results of I-131 radioactivity were obtained from both gamma counters. The mean I-131 concentrations measured by Wallac(Atomlab) were 31.59±16.31 (29.84±14.74) Bq/m 3 in radioiodine fume hood for treatment dose dispensing, 8.98±4.33 (7.58±5.10) Bq/m 3 in fume hood accommodated with a dose calibrator, 7.80±5.39 (7.54±5.04) Bq/m 3 in radioactive waste storage area, 0.03±0.54 (0.03±0.57) Bq/m 3 in patient waiting area, 2.94±3.60 (2.55±2.98) Bq/m 3 in hospital ward waste collection area and 0.03±0.01 (0.03±0.01) Bq/m 3 in the water treatment plant area. Radioiodine concentrations in patient's room increases linearly as the administered dose was increasing. Mean±SD of the measured concentrations were 11.63±9.30 (9.86±8.98) Bq/m 3 , 18.57±13.24 (17.35±12.33) Bq/m 3 and 31.90±22.32 (30.90±22.49) Bq/m 3 for the administered doses of 3.7, 5.55 and 7.4 Bq respectively. Radioiodine concentrations in all specified areas

In situ treatment of arsenic-contaminated groundwater by air sparging.

Science.gov (United States)

Brunsting, Joseph H; McBean, Edward A

2014-04-01

Arsenic contamination of groundwater is a major problem in some areas of the world, particularly in West Bengal (India) and Bangladesh where it is caused by reducing conditions in the aquifer. In situ treatment, if it can be proven as operationally feasible, has the potential to capture some advantages over other treatment methods by being fairly simple, not using chemicals, and not necessitating disposal of arsenic-rich wastes. In this study, the potential for in situ treatment by injection of compressed air directly into the aquifer (i.e. air sparging) is assessed. An experimental apparatus was constructed to simulate conditions of arsenic-rich groundwater under anaerobic conditions, and in situ treatment by air sparging was employed. Arsenic (up to 200 μg/L) was removed to a maximum of 79% (at a local point in the apparatus) using a solution with dissolved iron and arsenic only. A static "jar" test revealed arsenic removal by co-precipitation with iron at a molar ratio of approximately 2 (iron/arsenic). This is encouraging since groundwater with relatively high amounts of dissolved iron (as compared to arsenic) therefore has a large theoretical treatment capacity for arsenic. Iron oxidation was significantly retarded at pH values below neutral. In terms of operation, analysis of experimental results shows that periodic air sparging may be feasible. Copyright © 2014 Elsevier B.V. All rights reserved.

Use of nuclear and nuclear-related analytical techniques in studies of trace and minor elements in air pollution

International Nuclear Information System (INIS)

Smodis, Borut; Stropnik, Boris

1994-01-01

Among nuclear and nuclear-related analytical techniques, neutron activation and X-ray fluorescence analysis are particularly useful for environmental studies owing to their non-destructive character and multi-element capability. In this work, procedures for k o -standardized instrumental neutron activation analysis (INAA) and energy-dispersive X-ray fluorescence (EDXRF) spectrometry for trace and minor elements in air pollution studies were investigated. The methods applied were validated by the analysis of suitable reference materials. Using INAA, 20 experimentally obtained elemental values out of 21 certified and all 29 experimentally obtained values compared with 'consensus' values (for the elements where no certified numbers are available) in two SRMs were statistically indistinguishable. Also, the contents of 28 elements in candidate NIST SRM 1573a Tomato Leaves are reported. The EDXRF results were statistically indistinguishable from certified values for eight out of nine elements in NIST SRM 3087. The detection limit for this method is around at 0.1 μg cm -2 per element, so in BCR CRM No. 128, which is intended for ambient air pollution data, only Fe and Zn out of 14 elements reported in the certificate were detected with acceptable precision (i.e., 10%) owing to the very low air particulate matter loading, lying in the region of only 250 μg cm -2 . (Author)

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

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.

Reactive inspection response of NRC Region III to potential technical deficiencies identified in recent Nuclear Air Cleaning Conference papers

International Nuclear Information System (INIS)

Gill, C.F.

1987-01-01

In order to effectively meet its responsibility to protect the public health and safety, the Nuclear Regulatory Commission (NRC) nuclear power plant licensing and inspection programs respond to potential technical deficiencies identified by conference and professional society meeting papers when deemed appropriate. The NRC staff's response mechanisms for such technical deficiencies include: generic letters, Bulletins, Information Notices, Standard Review Plan (NUREG-0800) revisions, docketed Final Safety Analysis Report (FSAR) questions, special studies, special (reactive) inspection, and inspection program revisions. This paper describes reactive inspection efforts by Region III in response to potential technical deficiencies identified in recent air cleaning conference papers, including: post-accident effluent sample line deposition losses; failure to implement good engineering practices in the design, construction, and testing of Nuclear Air Treatment Systems (NATS); filter bypass via filter housing drain lines; spinster carbon degradation; use of silicone sealants and other temporary patching material in NATS; filter housing fire protection deluge system problems; lack of charcoal batch traceability; Quality Assurance records problems involving equipment, vendor, filter, and personnel qualifications; inadequate ANSI/ASME N510 acceptance criteria and tests; and failure to adequately demonstrate control room habitability per 10 CFR 50, Appendix A, General Design Criterion-19. Region III inspections indicate that many of these deficiencies appear to be prevalent. Inspection findings and utility responses to the findings are discussed. NRC Region III and Headquarters programmatic reactions to the identified generic problem areas are also discussed

Microbial contamination of the air at the wastewater treatment plant

Directory of Open Access Journals (Sweden)

Monika Vítězová

2012-01-01

Full Text Available Wastewater treatment plants (WWTPs primarily serve to protect the environment. Their task is to clean waste water from the agglomerations. On the other hand wastewater treatment plants can also negatively affect the environment in their neighbourhood. These include emissions of odour and microorganisms. This article discusses the microbial contamination of the air, called bioaerosols in selected wastewater treatment plant for 18 000 p.e. From results of the work is evident that the largest group of microorganisms in the monitored air were psychrophilic and mesophilic bacteria and microscopic fungi. The number of psychrophilic bacteria ranged from 14 to 12 000 CFU/m3 (colony forming units in 1 m3, the number of mesophilic bacteria varied in the range from 20 to 18 500 CFU/m3 and the fungi from 25 to 32 000 CFU/m3 in the air. The amount of actinomycetes ranged from 1 to 1 030 CFU/m3 and faecal coliform bacteria from 0 to 2 500 CFU/m3. Furthermore, it was confirmed that the highest air contamination was around the activation tank, area for dewatered sludge and around the building of mechanical cleaning, depending on the season. The density of studied microorganisms correlated with air temperature.

Planning of emergency medical treatment in nuclear power plant

International Nuclear Information System (INIS)

Kusama, Tomoko

1989-01-01

Medical staffs and health physicists have shown deep concerning at the emergency plans of nuclear power plants after the TMI nuclear accident. The most important and basic countermeasure for accidents was preparing appropriate and concrete organization and plans for treatment. We have planed emergency medical treatment for radiation workers in a nuclear power plant institute. The emergency medical treatment at institute consisted of two stages, that is on-site emergency treatment at facility medical service. In first step of planning in each stage, we selected and treatment at facility medical service. In first step of planning in each stage, we selected and analyzed all possible accidents in the institute and discussed on practical treatments for some possible accidents. The manuals of concrete procedure of emergency treatment for some accidents were prepared following discussion and facilities and equipment for medical treatment and decontamination were provided. All workers in the institute had periodical training and drilling of on-site emergency treatment and mastered technique of first aid. Decontamination and operation rooms were provided in the facillity medical service. The main functions at the facility medical service have been carried out by industrial nurses. Industrial nurses have been in close co-operation with radiation safety officers and medical doctors in regional hospital. (author)

Anti-seismic analysis for air storage tank used in the nuclear power plant

International Nuclear Information System (INIS)

Hua Jun; Ren Xin; Feng Ping

2011-01-01

This text calculates and analyses the structure of the air storage tank used for the SBO diesel generator set of Taishan nuclear power plant through finite element method, and simply introduces the mechanical modeling, loading condition and seismic response spectrum analyzing method for the structure, then get the natural frequency, vibration mode and response under seismic load of the structure through calculation. Evaluate the stress under the combined load such as gravity, internal stress, earthquake of the structure according to RCCM. The result shows that the structure intensity of the air storage tank meets the requirements of the specification. The calculating result gives the accordance for the seismic design of the air storage tank. (authors)

Silencing of dedicator of cytokinesis (DOCK180) obliterates pregnancy by interfering with decidualization due to blockage of nuclear entry of autoimmune regulator (AIRE).

Science.gov (United States)

Mohan, Jasna Jagan; Narayan, Prashanth; Padmanabhan, Renjini Ambika; Joseph, Selin; Kumar, Pradeep G; Laloraya, Malini

2018-03-08

Dedicator of cytokinesis (DOCK 180) involved in cytoskeletal reorganization is primarily a cytosolic molecule. It is recently shown to be nuclear in HeLa cells but its nuclear function is not known. The spatiotemporal distribution of DOCK180 in uterus was studied in uterine cytoplasmic and nuclear compartments during the "window of implantation." The functional significance of nuclear DOCK180 was explored by homology modeling, co-immunoprecipitation assays, and mass spectrometric analysis. Dock180's role in early pregnancy was ascertained by Dock 180 silencing and subsequent quantitative real-time PCR and Western blotting analysis. Our study shows a nuclear DOCK180 in the uterus during "window of implantation." Estrogen and progesterone mediate expression and nuclear translocation of DOCK180. The nuclear function of DOCK180 is attributed to its ability to import autoimmune regulator (AIRE) into the nucleus. Silencing of Dock180 inhibited AIRE nuclear shuttling which influenced its downstream targets, thereby affecting decidualization with AIRE and HOXA-10 as the major players as well as lack of implantation site formation due to impact on angiogenesis-associated genes. DOCK180 has an indispensable role in pregnancy establishment as knocking down Dock180 abrogates pregnancy by a consolidated impact on decidualization and angiogenesis by regulating AIRE nuclear entry. © 2018 John Wiley & Sons A/S. Published by John Wiley & Sons Ltd.

Annular air space effects on nuclear waste canister temperatures in a deep geologic waste repository

International Nuclear Information System (INIS)

Lowry, W.E.; Cheung, H.; Davis, B.W.

1980-01-01

Air spaces in a deep geologic repository for nuclear high level waste will have an important effect on the long-term performance of the waste package. The important temperature effects of an annular air gap surrounding a high level waste canister are determined through 3-D numerical modeling. Air gap properties and parameters specifically analyzed and presented are the air gap size, surfaces emissivity, presence of a sleeve, and initial thermal power generation rate; particular emphasis was placed on determining the effect of these variables have on the canister surface temperature. Finally a discussion based on modeling results is presented which specifically relates the results to NRC regulatory considerations

Dosimetric impact of gastrointestinal air column in radiation treatment of pancreatic cancer.

Science.gov (United States)

Estabrook, Neil C; Corn, Jonathan B; Ewing, Marvene M; Cardenes, Higinia R; Das, Indra J

2018-02-01

Dosimetric evaluation of air column in gastrointestinal (GI) structures in intensity modulated radiation therapy (IMRT) of pancreatic cancer. Nine sequential patients were retrospectively chosen for dosimetric analysis of air column in the GI apparatus in pancreatic cancer using cone beam CT (CBCT). The four-dimensional CT (4DCT) was used for target and organs at risk (OARs) and non-coplanar IMRT was used for treatment. Once a week, these patients underwent CBCT for air filling, isocentre verification and dose calculations retrospectively. Abdominal air column variation was as great as ±80% between weekly CBCT and 4DCT. Even with such a large air column in the treatment path for pancreatic cancer, changes in anteroposterior dimension were minimal (2.8%). Using IMRT, variations in air column did not correlate dosimetrically with large changes in target volume. An average dosimetric deviation of mere -3.3% and a maximum of -5.5% was observed. CBCT revealed large air column in GI structures; however, its impact is minimal for target coverage. Because of the inherent advantage of segmentation in IMRT, where only a small fraction of a given beam passes through the air column, this technique might have an advantage over 3DCRT in treating upper GI malignancies where the daily air column can have significant impact. Advances in knowledge: Radiation treatment of pancreatic cancer has significant challenges due to positioning, imaging of soft tissues and variability of air column in bowels. The dosimetric impact of variable air column is retrospectively studied using CBCT. Even though, the volume of air column changes by ± 80%, its dosimetric impact in IMRT is minimum.

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.

Air toxics evaluation for a nuclear power plant

International Nuclear Information System (INIS)

Lokey, D.; Orr, W.

1994-01-01

An emission inventory of nonradiological hazardous air pollutants (HAP) was prepared for TVA's Browns Ferry Nuclear Plant (BFN). The purpose of this effort was to determine whether BFN is a major HAP emission source. About 40 specific HAP were identified in products used at FBN. HAP emission totals from BFN were estimated at 6 T/Y, well below the major-source cutoff. Off-site waste disposal reduced gross emission estimates by about 8 percent. HAP emission evaluation by product categories showed the largest portion due to paints and coatings, followed by cleaning compounds. HAP emission breakdown by chemical species showed xylene to be the predominate HAP emitted, followed by methyl ethyl ketone

System approach for evaluation of air pollution toxic compounds in the 30-km area of nuclear power plants

International Nuclear Information System (INIS)

Shevtsova, O.V.; Zhigunova, L.N.; Makovskaya, N.A.; Pavlovich, E.L.

2012-01-01

The article shows the importance of a systematic approach to address environmental problems that arise during the construction of nuclear power plants, and identified the need to consider the transformation and biotransformation of primary pollutants and monitoring secondary pollutants. The basic pathways of pollutants in the air a 30-km zone of nuclear power plants established. The content of primary and secondary air pollutants identified. The evaluation of general toxic risk from primary pollutant and the calculation of the carcinogenic risk of secondary pollutants entering the body by inhalation are carried out. (authors)

Introduction to the study of the treatment of spent nuclear fuel

International Nuclear Information System (INIS)

Floh, B.; Araujo, J.A. de; Matsuda, H.T.

1975-01-01

An introduction is made to the study of the treatment of spent nuclear fuels. Main topics discussed are: basic information, volatilization processes, treatment of thorium based fuels (Thorex process), analytical chemistry of spent nuclear fuel and design of industrial facilities

Automatization of the radiotherapy treatment at Nuclear Medicine Center

International Nuclear Information System (INIS)

Anjak, O.; Al'Bahra, E.; Kharita, M.H.

2007-01-01

NMC Program for Automatization of the radiotherapy treatment at Nuclear Medicine Center. The program NMC written in Delphi 6. This program can be run under Windows XP as single and multi users. Program makes all necessary and required calculations for treatment time for patient who is under radiotherapy treatment in Nuclear Medicine Center by using Co-60 units. Also this program is perform statistical study for patients according to tumor type, Syrian City, sex, and age. Data is stored on disk files and then whenever should be displayed. Statistical data is displayed on the screen or printed in reports. (author)

A Survey on the effective role of nuclear power plants in decreasing air pollution and its relevant hazards

International Nuclear Information System (INIS)

Mohammadi, A.

2008-01-01

Nowadays air pollution, consequent reduction of Ozone layer's thickness and increase of UV radiations are included as the hazardous phenomenon, which confronts mankind with fundamental challenges. Increase of population, use of high living standards together with the consumption of fossil fuels for generations of electrical energy have increases air pollution at the global. scale. According to the carried out studies carried out in the three latest decades, alteration of atmospheric gases such as Ozone, dioxide azoth, dioxide sulphur, dioxide carbon, Methane, monoxide carbon and hydrocarbons have caused the appearance of water and air new forms of pollutions all over the world the harmful side effects resulted from air pollution on the respiratory systems and other cordial and blood vessels are well documented. Due to the air and water uncommon pollutions resulted from fossil fuels consumptions, use of nuclear power plants as a safe option can prevent several pollutants such as gases, poisoning metals and suspended elements or downpour of acidic rains in environment. In this article, it is tried difficulties and hazardous results of air pollution and resulted from consumption of fossil fuels, and discusses the effective role of nuclear energy studies in reduction of such pollutions

Super-compactor and grouting. Efficient and safe treatment of nuclear waste

International Nuclear Information System (INIS)

Li, Hongyou; Starke, Holger; Muetzel, Wolfgang; Winter, Marc

2014-01-01

The conditioning and volume reduction of nuclear waste are increasingly important factors throughout the world. Efficient and safe treatment of nuclear waste therefore plays a decisive role. Babcock Noell designed, manufactured and supplied a complete waste treatment facility for conditioning of the solid radioactive waste of a nuclear power plant to China. This facility consists of a Sorting Station, a Super-Compactor, a Grouting Unit with Capping Device and other auxiliary equipment which is described in more detail in the following article. This article gives an overview of the efficient and safe treatment of nuclear waste. Babcock Noell is a subsidiary of the Bilfinger Power Systems and has 40 years of experience in the field of design, engineering, construction, static and dynamic calculations, manufacturing, installation, commissioning, as well as in the service and operation of a wide variety of nuclear components and facilities worldwide.

Monitoring of the vegetable garden open air spinach and soil radioactivity in Beijing during the Japan Fukushima nuclear accident

International Nuclear Information System (INIS)

Zhou Qiang; Xu Cuihua; Tuo Fei; Zhang Jing; Li Wenhong; Zhang Qing; Zhang Weijun; Zhang Jianfeng; Su Xu

2012-01-01

Objective: To detect artificial radionuclide content in the spinach and soil in open air vegetable garden in Beijing during Fukushima nuclear accident and to study the radioactive contamination characteristics of the samples. Methods: 6 spinach samples and 3 soil samples in open air vegetable garden were obtained through continuously sampling. High-purity germanium (HPGe) γ spectrometry was used to analyze activity concentrations of artificial radionuclide 131 I etc in these samples. Results: Artificial radionuclide 131 I was detected in the 6 open air spinach samples. Artificial radionuclide 137 Cs was detected in 3 vegetable garden soil samples, trace amount of 131 I was detected in 1 open-air surface soil sample alone. Conclusions: Following the Fukushima nuclear accident, spinach in Beijing's open-air vegetable garden was slightly polluted by artificial radionuclide 131 I, with the highest values of pollution appeared around April 4, 2011, but it could not cause harm to human health. (authors)

Highly Polluted Wastewaters Treatment by Improved Dissolved Air Flotation Technology

Science.gov (United States)

Moga, I. C.; Covaliu, C. I.; Matache, M. G.; Doroftei, B. I.

2017-06-01

Numerous investigations are oriented towards the development of new wastewater treatment technologies, having high efficiencies for removing even low concentrations of pollutants found in water. These efforts were determined by the destroyer impact of the pollutants to the environment and human’s health. For this reason this paper presents our study concerning an improved dissolved air flotation technology for wastewater treatment. There is described a dissolved air flotation (DAF) installation composed by two equipments: pressurized capsule and lamellar settling. Also, there are presented some advantages of using nanoparticles as flotation collectors.

Deployment evaluation methodology for the electrometallurgical treatment of DOE-EM spent nuclear fuel

International Nuclear Information System (INIS)

Dahl, C.A.; Adams, J.P.; Ramer, R.J.

1998-07-01

Part of the Department of Energy (DOE) spent nuclear fuel (SNF) inventory may require some type of treatment to meet acceptance criteria at various disposition sites. The current focus for much of this spent nuclear fuel is the electrometallurgical treatment process under development at Argonne National Laboratory. Potential flowsheets for this treatment process are presented. Deployment of the process for the treatment of the spent nuclear fuel requires evaluation to determine the spent nuclear fuel program need for treatment and compatibility of the spent nuclear fuel with the process. The evaluation of need includes considerations of cost, technical feasibility, process material disposition, and schedule to treat a proposed fuel. A siting evaluation methodology has been developed to account for these variables. A work breakdown structure is proposed to gather life-cycle cost information to allow evaluation of alternative siting strategies on a similar basis. The evaluation methodology, while created specifically for the electrometallurgical evaluation, has been written such that it could be applied to any potential treatment process that is a disposition option for spent nuclear fuel. Future work to complete the evaluation of the process for electrometallurgical treatment is discussed

The results of air treatment process modeling at the location of the air curtain in the air suppliers and ventilation shafts

Directory of Open Access Journals (Sweden)

Nikolaev Aleksandr

2017-01-01

Full Text Available In the existing shaft air heater installations (AHI, that heat the air for air suppliers in cold seasons, a heater channel is used. Some parts of the air from the heater go to the channel, other parts are sucked through a pithead by the general shaft pressure drawdown formed by the main ventilation installation (MVI. When this happens, a mix of two air flows leads to a shaft heat regime violation that can break pressurization of intertubular sealers. The problem of energy saving while airing underground mining enterprises is also very important. The proposed solution of both tasks due to the application of an air curtain is described in the article. In cold seasons the air treatment process should be used and it is offered to place an air curtain in the air suppliers shaft above the place of interface of the calorifer channel to a trunk in order to avoid an infiltration (suction of air through the pithead. It’s recommended to use an air curtain in a ventilation shaft because it reduces external air leaks thereby improving energy efficiency of the MVI work. During the mathematical modeling of ventilation and air preparation process (in SolidWorks Flowsimulation software package it was found out that the use of the air curtain in the air supply shaft can increase the efficiency of the AHI, and reduce the electricity consumption for ventilation in the ventilation shaft.

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

Air Treatment Techniques for Abatement of Emissions from Intensive Livestock Production

OpenAIRE

Melse, R.W.; Ogink, N.W.M.; Rulkens, W.H.

2009-01-01

Intensive livestock production is connected with a number of environmental effects, including emissions of ammonia (NH3), greenhouse gases (CH4 and N2O), odour, and particulate matter (PM10 and PM2.5). Possible strategies for emission reduction include feed management, adaptation of housing design, and, in case of mechanically ventilated animal houses, the application of end-of-pipe air treatment, viz acid scrubbers and bioscrubbers. Air treatment techniques can achieve very high emission red...

Intensity of the absorbing dose of the gamma rays in the air of Krusevac during and after nuclear accident in Chernobil

International Nuclear Information System (INIS)

Fortuna, D.

1997-01-01

In this paper are compared overage daily values of the intensity of the absorbing doses of the gamma rays in the air of Krusevac, during and after nuclear accident in Cernobil. Average daily values of intensity of the absorbing doses of gamma rays in the air of Krusevac, immediately after nuclear accident in Cernobil were, three to seven time higher than of the average daily values of the natural rays. (author)

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

Recommended radiological air sampling and internal contamination control at nuclear power plants

International Nuclear Information System (INIS)

Rich, B.L.; Ritter, P.D.; Martz, D.E.

1984-01-01

It has long been recognized by the NRC Technical Staffs that estimating the quantity of radioactivity inhaled by an individual worker involved large uncertainties. General air samples usually produce concentrations lower than those in the workers Breathing Zone (BZ). NRC guides have recognized this problem by specifying air monitoring programs which sample the Breathing Zone or concentrations known to be higher than that actually inhaled. In addition the availability of suitable samplers to obtain BZ samples and the practicality of requiring their use was somewhat in question to the NRC technical staff. AN NRC development contract was issued to provide a detailed review of the technical aspects of the problems and recommendations for practical upgrade of federal guidance. This project accomplished a review of the nuclear industry experience and knowledge through a literature search, site visits to representative licensed facilities, telephone surveys of many others, laboratory testing of personal air samplers (lapel samplers) and aerosol diffusion experiments to verify key conclusions and assumptions

Utilization of analytical techniques in aid the implantation of nuclear installations

International Nuclear Information System (INIS)

Ferreira, M.P.; Sabino, C.V.S.; Avelar, M.M.

1984-01-01

Nuclear, physico-chemical and classic techniques developed and utilized by Centro de Desenvolvimento de Tecnicas Nucleares are presented, as back up to the implementation and operation of nuclear installations related with several parts of fuel cycle from uranium prospecting to waste treatment samples of soils, ores, alloys, plastics, paints, biological materials, air and water were analysed. (M.C.K) [pt

Development of a non-radiological air emissions inventory for a nuclear industrial facility

International Nuclear Information System (INIS)

Patnoe, C.A.; Porter, G.V.; Almquist, R.S.

1991-01-01

This paper describes the major issues that impacted the organization and structure of a project for developing a comprehensive non- radiological air emissions inventory for a nuclear weapons facility. The major issues addressed paralleled the development of the inventory project and fall into the following categories: (1) defining the scope of work, (2) developing and managing the air emission inventory project, and (3) field investigations and evaluating operations for air emissions. This paper also describes the lines of communication that were established with state regulators to resolve problems and develop a successful working relationship. This paper illustrates a means to complete a complex air emission inventory with proper organization and cooperation with regulatory agencies. Further, it indicates the need of critical evaluation of project tasks to evaluate their impact on project schedule; it provides a method for implementing a quality assurance program that audits all phases of the emission survey; and it demonstrates a way of effectively managing outside contractors to meet schedule requirements and assure a high quality product. This paper is of value to those undertaking a similar complex air emission survey. 2 refs

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

Nuclear power plant laundry drain treatment using membrane bio reactor

International Nuclear Information System (INIS)

Tsukamoto, Masaaki; Kohanawa, Osamu; Kinugasa, Atsushi; Ogawa, Naoki; Murogaki, Kenta

2012-01-01

In nuclear power plant, the radioactive effluent generated by washing the clothes worn in controlled area and the hand and shower water used at the controlled area are treated in laundry drain treatment system. Although various systems which treat such liquid waste preexist, the traditional treatment system has disadvantages such as high running cost and a large amount of secondary waste generation. To solve these matters, we have considered application of an activated sludge system, membrane bio reactor, which has been practically used in general industry. For nuclear power plant, the activated sludge system has been developed, tested in its adaptability and the adequacy has been proved. Some preexisting treatment systems have been replaced with this activated sludge system for the first time in a domestic nuclear power plant, and the renewal system is now in operation. The result is reported. (author)

Heterogeneous Photocatalysis: Fundamentals and Application for Treatment of Polluted Air

Directory of Open Access Journals (Sweden)

Tomašić, V.

2011-07-01

the photocatalytic degradation of organic compounds is generally more efficient in the gas phase than in the liquid phase, and the fact that the treatment cost may be significantly lower than that of the water phase photocatalytic treatment, the scientific interest has shifted towards the application of photocatalysis for air treatment. This paper describes the basics of heterogeneous photocatalysis, mainly on TiO2 and the application of photocatalytic processes for air treatment purposes. Review of more interesting practical application of heterogeneous photocatalysis for the treatment of polluted air is presented. Special efforts are made to describe the technical aspects of the photocatalytic processes and to characterize different photocatalytic reactors in use for air treatment.

Waster water treatment with Cavitation Air Flotation (CAF) system; Tratamiento de las aguas residuales utilizando el sistema de flotacion por aire inducido (CAF)

Energy Technology Data Exchange (ETDEWEB)

Escofet Lugstenmann, I.

1998-12-01

In wastewater treatment from industries, the flotation process as physical-chemical treatment or primary treatment, based on the difference of densities of the solid-liquid suspension, is an important step for the elimination of the contaminant material, both as suspended solids and oils and greases. The Cavitation Air Flotation (CAF) system is an unique, innovative and very easy method which introduces air into the flotation system. It was created to come over the problems and limitations of more conventional techniques of Dissolved Air Flotation (DAF). (Author) 9 refs.

Contamination mechanisms of air basin with tritium in venues of underground nuclear explosions at the former Semipalatinsk test site

International Nuclear Information System (INIS)

Lyakhova, O.N.; Lukashenko, S.N.; Larionova, N.V.; Tur, Y.S.

2012-01-01

During the period of testing from 1945 to 1962 at the territory of Semipalatinsk test site (STS) within the Degelen Mountains in tunnels, 209 underground nuclear explosions were produced. Many of the tunnels have seasonal water seepage in the form of streams, through which tritium migrates from the underground nuclear explosion (UNE) venues towards the surface. The issue of tritium contamination occupies a special place in the radioactive contamination of the environment. In this paper we assess the level and distribution of tritium in the atmospheric air of ecosystems with water seepage at tunnels № 176 and № 177, located on “Degelen” site. There has been presented general nature of tritium distribution in the atmosphere relative to surface of a watercourse which has been contaminated with tritium. The basic mechanisms were studied for tritium distribution in the air of studied ecosystems, namely, the distribution of tritium in the systems: water–atmosphere, tunnel air–atmosphere, soil water–atmosphere, vegetation–atmosphere. An analytical calculation of tritium concentration in the atmosphere by the concentration of tritium in water has been performed. There has experimentally obtained the dependence for predictive assessment of tritium concentrations in air as a function of tritium concentration in one of the inlet sources such as water, tunnel air, soil water, vegetation, etc.. The paper also describes the general nature of tritium distribution in the air in the area “Degelen”. - Highlights: ► The basic mechanisms for tritium distribution in the air of nuclear testing sites were examined. ► We researched the distribution of tritium in the systems such as water–atmosphere, tunnel air–atmosphere, soil water–atmosphere and vegetation–atmosphere. ► An analytical calculation of tritium concentration in the atmosphere was performed. ► We experimentally obtained the dependence for predictive assessment of tritium concentrations in

Treatment of refractory organic pollutants in industrial wastewater by wet air oxidation

Directory of Open Access Journals (Sweden)

Mingming Luan

2017-02-01

Full Text Available Wet air oxidation (WAO is one of the most economical and environmentally-friendly advanced oxidation processes. It makes a promising technology for the treatment of refractory organic pollutants in industrial wastewaters. In wet air oxidation aqueous waste is oxidized in the liquid phase at high temperatures (125–320 °C and pressures (0.5–20 MPa in the presence of an oxygen-containing gas (usually air. The advantages of the process include low operating costs and minimal air pollution discharges. The present review is concerned about the literature published in the treatment of refractory organic pollutants in industrial wastewaters, such as dyes. Phenolics were taken as model pollutants in most cases. Reports on effect of treatment for the WAO of refractory organic pollutants in industrial wastewaters are reviewed, such as emulsified wastewater, TNT red water, etc. Discussions are also made on the mechanism and kinetics of WAO and main technical parameters influencing WAO. Finally, development direction of WAO is summed up.

Use of nuclear and related analytical techniques in environmental research as exemplified by selected air pollution studies

International Nuclear Information System (INIS)

Smodis, B.; Jacimovic, R.; Jeran, Z.; Stropnik, B.; Svetina, M.

2000-01-01

Among nuclear and nuclear related analytical techniques, neutron activation analysis and X-ray fluorescence spectrometry proved to be particularly useful for environmental studies owing to their nondestructive character and multi element capability. This paper emphasizes their importance among other multielement analytical methods by discussing their specific role due to specific physics basis, quite different to other destructive non-nuclear methods, and by summarizing results obtained in several studies related to air pollution research, including analyses of airborne particulate matter, water samples, lichens and mosses. (author)

Spent fuel treatment to allow storage in air

International Nuclear Information System (INIS)

Williams, K.L.

1988-01-01

During Fiscal Year 1987 (FY-87), research began at the Idaho National Engineering Laboratory (INEL) to develop a treatment material and process to coat fuel rods in commercial spent fuel assemblies to allow the assemblies to be stored in hot (up to 380 0 C) air without oxidation of the fuel. This research was conducted under a research and development fund provided by the U.S. Department of Energy (DOE) and independently administered by EG and G Idaho, Inc., DOE's prime contractor at the INEL. The objectives of the research were to identify and evaluate possible treatment processes and materials, identify areas of uncertainty, and to recommend the most likely candidate to allow spent fuel dry storage in hot air. The results of the research are described: results were promising and several good candidates were identified, but further research is needed to examine the candidates to the point where comparison is possible

Dry air oxidation kinetics of K-Basin spent nuclear fuel

International Nuclear Information System (INIS)

Abrefah, J.; Buchanan, H.C.; Gerry, W.M.; Gray, W.J.; Marschman, S.C.

1998-06-01

The safety and process analyses of the proposed Integrated Process Strategy (IPS) to move the N-Reactor spent nuclear fuel (SNF) stored at K-Basin to an interim storage facility require information about the oxidation behavior of the metallic uranium. Limited experiments have been performed on the oxidation reaction of SNF samples taken from an N-Reactor outer fuel element in various atmospheres. This report discusses studies on the oxidation behavior of SNF using two independent experimental systems: (1) a tube furnace with a flowing gas mixture of 2% oxygen/98% argon; and (2) a thermogravimetric system for dry air oxidation

5 CFR 842.405 - Air traffic controllers, firefighters, law enforcement officers, and nuclear materials couriers.

Science.gov (United States)

2010-01-01

... 5 Administrative Personnel 2 2010-01-01 2010-01-01 false Air traffic controllers, firefighters, law enforcement officers, and nuclear materials couriers. 842.405 Section 842.405 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT (CONTINUED) CIVIL SERVICE REGULATIONS (CONTINUED) FEDERAL EMPLOYEES RETIREMENT SYSTEM-BASIC ANNUITY Computations ...

Frontier of Advanced Accelerator Applications and Medical Treatments Using Nuclear Techniques. Abstract

International Nuclear Information System (INIS)

2015-01-01

To address the challenges of research-based practice, developing advanced accelerator applications, and medical treatments using nuclear tecniqoes, researchers from Rajamakala University of Technology Lanna, Office of Atoms for Peace, and Chiang Mai University have joined in hosting this conference. Nuclear medicine, amedical specialty, diagnoses and treats diseases in a safe and painless way. Nuclear techniques can determine medical information that may otherwise be unavailable, require surgery, or necessitate more expensive and invasive diagnostic tests. Advance in nuclear techniques also offer the potential to detect abnormalities at earlier stages, leasding to earlier treatment and a more successful prognosis.

Features of adsorbed chemical elements and their isotopes distribution in iodine air filters AU-1500 of nuclear power plant

International Nuclear Information System (INIS)

Neklyudov, I.M.; Dovbnya, A.N.; Dikiy, N.P.; Ledenyov, O.P.; Lyashko, Yu.V.

2013-01-01

The main aim of research is to investigate the physical features of spatial distribution of the adsorbed chemical elements and their isotopes in the granular filtering medium in the iodine air filters of the type of AU-1500 in the forced-exhaust ventilation at the nuclear power plant. The ?-activation analysis method is applied to accurately characterize the distribution of the adsorbed radioactive chemical elements and their isotopes in the granular filtering medium in the AU-1500 iodine air filter after its long term operation at the nuclear power plant. The typical spectrum of the detected chemical elements and their isotopes in the AU-1500 iodine air filter, which was exposed by the irradiation of bremsstrahlung gamma-quantum producing by the accelerating electrons in the tantalum target, are obtained. The spatial distributions of the detected chemical element 127 I and some other chemical elements and their isotopes in the layer of absorber, which was made of the cylindrical coal granules of the type of SKT-3, in the AU-1500 iodine air filter are also researched. The possible influences by the standing wave of air pressure in the iodine air filter on the spatial distribution of the chemical elements and their isotopes in the iodine air filter are discussed. The comprehensive analysis of obtained research results on the distribution of the adsorbed chemical elements and their isotopes in the absorber of iodine air filter is performed.

Aging and service wear of air compressors and dryers in nuclear power plants

International Nuclear Information System (INIS)

Moyers, J.C.

1989-01-01

Compressed air systems and their associated compressors and dryers as incorporated in LWR power plants usually are not classified as safety related systems and components because their continued operation is not required to bring the plant to a safe shutdown condition. However, control air is a vital requirement for maintaining stable plant operation and its loss often results in a reactor trip and, on occasion, the actuation of engineered safety feature systems. Concerns caused by repeated instances of failures in air systems resulted in the high-priority ranking of Generic Issue No. 43, ''Reliability of Air Systems'' by the NRC. In support of the Nuclear Plant Aging Research (NPAR) Program, the Oak Ridge National Laboratory is carrying out a Phase I aging assessment of air compressors and dryers used in LWR power plants. The objectives of this study include: (1) determination of the types and ratings of equipment utilized in typical plants; (2) identification of aging and service wear stressors imposed on the machines; (3) evaluation of operating experience with the machines; (4) comparison of user and manufacturer-recommended inspection, surveillance, and monitoring (ISM) methods; and (5) the identification of any improved ISM methods that might lead to longer, more reliable, service. 2 refs

Safe-air view: a decision support system for nuclear emergencies

International Nuclear Information System (INIS)

Triacchini, G.; D'Alberti, F.; Canepa, E.

2004-01-01

It was therefore necessary to implement a PC based software for the prediction of the radiological impact on the environment and on the population around the JRC Ispra site caused by any accident occurring at any nuclear facilities within the site. For this reason the SSRP unit has developed with other partners a specific decision PC based support tool, whose characteristics are described in this paper. The developed SW is the first implementation of GIS technology applied to an existing MS-DOS trademark model validated model for wind field definition, calculation of atmospheric dispersion and concentration of pollutants at receptors. The software has been designed as to be able to superimpose, for each point in an area of 50 km radius from the JRC Ispra, layers of information coming from customisable databases. The result is a user-friendly Windows trademark based software, able to quickly calculate and display values of ground and air radioactive contamination around JRC Ispra, following an accidental release of radioactive substances from within a JRC Ispra nuclear installation. (orig.)

Accidental behaviour of nuclear fuel in a warehousing site under air: investigation of the nuclear ceramic oxidation and of fission gas release

International Nuclear Information System (INIS)

Desgranges, L.

2006-12-01

After a brief presentation of the context of his works, i.e. the nuclear fuel, its behaviour in a nuclear reactor, and studies performed in high activity laboratory, the author more precisely presents its research topic: the behaviour of defective nuclear fuel in air. Then, he describes the researches performed in three main directions: firstly, the characterization and understanding of fission gas localisation (experimental localisation, understanding of the bubble forming mechanisms), secondly, the determination of mechanisms related to oxidation (atomic mechanisms related to UO 2 oxidation, oxidation of fragments of irradiated fuel, the CROCODILE installation). He finally presents his scientific project which notably deals with fission gas release (from UO 2 to U 3 O 7 , and from U 3 O 7 to U 3 O 8 ), and with further high activity laboratory experiments

Study on treatment of dust by dismantling

International Nuclear Information System (INIS)

Torikai, K.; Suzuki, K.

1987-01-01

In dismantling of nuclear reactors, various kinds of treatment of dust generated by cutting or dismantling concrete structures of components of reactors are evaluated for safety, cost, and performance comparing the work in air with water. A method of dust treatment for work in air is discussed. The dry method has an easy operation in practice and a good performance in the equipment, but has problem on the prevention from radioactive contamination by diffusion of dust in air. For the purpose of advancing the strong points and eliminating the weak points in dry method, an improved venturi scrubber system is proposed for dismantling work as a dust collecting system. The system consists of dust absorbing pipe, dust collector, separator of dust and water and dust transfer equipment to a storage of waste. This system would be expected to have better performance and lower operating cost in decommissioning nuclear reactors, especially, the number of dust filters, for example, HEPA filters, will be considerably saved

SU-F-J-05: The Effect of Air Pockets in the Urinary Bladder During Bladder Hyperthermia Treatment

Energy Technology Data Exchange (ETDEWEB)

Schooneveldt, G.; Kok, H.P.; Bakker, A.; Geijsen, E.D.; Reijke, T.M. de; Crezee, J. [Academisch Medisch Centrum / Universiteit van Amsterdam, Amsterdam (Netherlands)

2016-06-15

Purpose: Hyperthermia combined with Mitomycin C is used for the treatment of non-muscle invasive bladder cancer (NMIBC), using a phased array system of microwave antennas for bladder heating. Often some air is present in the bladder, which effectively blocks the microwave radiation, potentially preventing proper treatment of that part of the bladder. Air can be a relevant fraction of the bladder content and large air pockets are expected to have a noticeable influence on achieved temperatures. Methods: We analysed 14 NMIBC patients treated at our institute with our AMC-4 hyperthermia device with four 70MHz antennas around the pelvis. A CT scan was made after treatment and a physician delineated the bladder on the CT scan. On the same scan, the amount of air present in the bladder was delineated. Using our in-house developed hyperthermia treatment planning system, we simulated the treatment using the clinically applied device settings. We did this once with the air pocket delineated on the CT scan, and once with the same volume filled with bladder tissue. Results: The patients had on average 4.2ml (range 0.8–10.1ml) air in the bladder. The bladder volume was delineated by the physician, that is including air pocket and bladder wall, was on average 253ml (range 93–452ml). The average volume in which changes exceeded 0.25°C was 22ml (range 0–108 ml), with the bladder being up to 2°C cooler when an air pocket was present. Except for extreme cases, there was no evident relation between the quantity of air and the difference in temperature. Conclusion: The effect of an air pocket in the bladder during bladder hyperthermia treatment varies strongly between patients. Generally, this leads to lower temperatures in the bladder, potentially affecting treatment quality, and suggesting that care need be taken to minimise the size of air pockets during hyperthermia treatments. The KWF Dutch Cancer Society financially supported this work, grant UVA 2012-5539.

The use of CFD code for numerical simulation study on the air/water countercurrent flow limitation in nuclear reactors

International Nuclear Information System (INIS)

Morghi, Youssef; Mesquita, Amir Zacarias; Santos, Andre Augusto Campagnole dos; Vasconcelos, Victor

2015-01-01

For the experimental study on the air/water countercurrent flow limitation in Nuclear Reactors, were built at CDTN an acrylic test sections with the same geometric shape of 'hot leg' of a Pressurized Water Reactor (PWR). The hydraulic circuit is designed to be used with air and water at pressures near to atmospheric and ambient temperature. Due to the complexity of the CCFL experimental, the numerical simulation has been used. The aim of the numerical simulations is the validation of experimental data. It is a global trend, the use of computational fluid dynamics (CFD) modeling and prediction of physical phenomena related to heat transfer in nuclear reactors. The most used CFD codes are: FLUENT®, STAR- CD®, Open Foam® and CFX®. In CFD, closure models are required that must be validated, especially if they are to be applied to nuclear reactor safety. The Thermal- Hydraulics Laboratory of CDTN offers computing infrastructure and license to use commercial code CFX®. This article describes a review about CCFL and the use of CFD for numerical simulation of this phenomenal for Nuclear Rector. (author)

The use of CFD code for numerical simulation study on the air/water countercurrent flow limitation in nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Morghi, Youssef; Mesquita, Amir Zacarias; Santos, Andre Augusto Campagnole dos; Vasconcelos, Victor, E-mail: ymo@cdtn.br, E-mail: amir@cdtn.br, E-mail: aacs@cdtn.br, E-mail: vitors@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2015-07-01

For the experimental study on the air/water countercurrent flow limitation in Nuclear Reactors, were built at CDTN an acrylic test sections with the same geometric shape of 'hot leg' of a Pressurized Water Reactor (PWR). The hydraulic circuit is designed to be used with air and water at pressures near to atmospheric and ambient temperature. Due to the complexity of the CCFL experimental, the numerical simulation has been used. The aim of the numerical simulations is the validation of experimental data. It is a global trend, the use of computational fluid dynamics (CFD) modeling and prediction of physical phenomena related to heat transfer in nuclear reactors. The most used CFD codes are: FLUENT®, STAR- CD®, Open Foam® and CFX®. In CFD, closure models are required that must be validated, especially if they are to be applied to nuclear reactor safety. The Thermal- Hydraulics Laboratory of CDTN offers computing infrastructure and license to use commercial code CFX®. This article describes a review about CCFL and the use of CFD for numerical simulation of this phenomenal for Nuclear Rector. (author)

Effects of atmospheric air plasma treatment on interfacial properties of PBO fiber reinforced composites

Energy Technology Data Exchange (ETDEWEB)

Zhang, Chengshuang, E-mail: cszhang83@163.com; Li, Cuiyun; Wang, Baiya; Wang, Bin; Cui, Hong

2013-07-01

Poly(p-phenylene benzobisoxazole) (PBO) fiber was modified by atmospheric air plasma treatment. The effects of plasma treatment power and speed on both surface properties of PBO fibers and interfacial properties of PBO/epoxy composites were investigated. Surface chemical composition of PBO fibers were analyzed by X-ray photoelectron spectroscopy (XPS). Surface morphologies of the fibers and interface structures of the composites were examined using scanning electron microscopy (SEM). Interfacial adhesion property of the composites was evaluated by interlaminar shear strength (ILSS). Mechanical properties of PBO multifilament were measured by universal testing machine. The results indicate that atmospheric air plasma treatment introduced some polar or oxygen-containing groups to PBO fiber surfaces, enhanced surface roughness and changed surface morphologies of PBO fibers by plasma etching and oxidative reactions. The plasma treatment also improved interfacial adhesion of PBO/epoxy composites but has little effect on tensile properties of PBO multifilament. The ILSS of PBO/epoxy composites increased to 40.0 MPa after atmospheric air plasma treatment with plasma treatment power of 300 W and treatment speed of 6 m/min.

Fiscal 2000 achievement report. Development of technologies for waste treatment and recycling (Development of technologies for appropriate treatment of air bags); 2000 nendo haikibutsu recycle kanren gijutsu kaihatsu seika hokokusho. Air bag tekisei shori gijutsu no kaihatsu nado

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-03-01

A centralized treatment process respecting environmental protection and safety for unused air bags aboard disused automobiles is developed. In concrete terms, a heating facility owned by Daicel Chemical Industries, Ltd., is used, which includes an apparatus for examining exhaust gas dioxins and an exhaust gas treatment apparatus and, with this facility, studies are made for appropriately treating waste gas and waste water to be generated when air bag modules undergo centralized heating. Endeavors in fiscal 2000 center about (1) the development of waste gas treatment technologies, (2) development of waste water treatment technologies, (3) chemical analysis of waste water sludge, dusts and air bag residues, and (4) the study of appropriate treatment of non-azide air bag modules. As to the development of exhaust gas treatment technology, it was proved that the exhaust gas treatment system consisting of secondary incineration furnace, exhaust gas cooling tower and bag filter worked effectively. (NEDO)

Method for treatment of wastewater of nuclear power plants

International Nuclear Information System (INIS)

Ito, Kazutoshi; Suzuki, Katsumi; Suzuki, Mamoru; Minato, Akira.

1984-01-01

A method for treatment of wastewater of nuclear power plants is characterized by the fact that concentration and volume reduction are performed after Ca and Mg as components for the formation of an adhering scale is converted to an 8-oxyquinoline complex, which is hardly soluble in water, and does not precipitate out as an adhering scale, by the addition of 8-oxyquinoline into nuclear power plant wastewater

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.

Pollution of atmospheric air with toxic and radioactive particulate matter investigated by means of nuclear techniques

International Nuclear Information System (INIS)

Jagielak, J.

1978-01-01

The application of spectrometric methods of nuclear techniques to the investigations of atmospheric air pollution by toxic and radioactive elements and results of these investigations conducted in the highly industrialized and urbanized regions of Poland have been presented. The method of precipitation of the samples, the measurements and analysis of radiation spectra of alpha and gamma radiation emitted by isotopes present in the samples have been described. The concentrations of toxic metal dust in the air have been evaluated by neutron activation and X-ray fluorescence analysis. Appropriate methods of measurement, calibration of instrument and the discussion of results have been presented. The work presents the results of investigations performed in Siersza within the years 1973-1974 and in Warsaw in the period of 1975-1977, which have permitted to estimate the mean monthly values of concentration in the atmospheric air of the following radioisotopes: 7 Be, 54 Mn, 95 Zr, 103 Ru, 106 Ru, 125 Sb, 131 I, 137 Cs, 140 Ba, 141 Ce, 144 Ce, 226 Ra, Th-nat, U-nat and the following stable elements: Sc, Cr, Fe, Co, Zn, As, Se, Sb, W, Pb. The analysis of changes in concentration of each particular artificial radioisotope in the air for the region of Poland in connection with Chinese nuclear explosions have been given. On the basis of the performed environmental investigations the method of analysis of relations between the concentrations of particular elements present in the dust has been discussed. The applications of this method have been presented. The hazard to the population and the environment caused by the radioactive and toxic dust present in the atmospheric air has been estimated. (author)

Effects of secondary containment air cleanup system leakage on the accident offsite dose as determined during preop tests of the Sequoyah Nuclear Plant

International Nuclear Information System (INIS)

Klaes, L.J.; Nass, S.A.; Proctor, L.D.

1981-01-01

The Sequoyah Nuclear Plant has two secondary containments. One is the annular region between the primary containment and the shield building surrounding the primary containment. The second is the auxiliary building secondary containment enclosure which is potentially subject to direct airborne radioactivity. Two air cleanup systems are provided to serve these areas. The emergency gas treatment system (EGTS) serves the annulus between the primary containment and the shield building, and the auxiliary building gas treatment system (ABGTS) serves the area inside of the auxiliary building secondary containment enclosure. The major function served by these air cleanup systems is that of controlling and processing airborne contamination released in these areas during any accident up to a design basis accident. This is accomplished by (1) creating a negative pressure in the areas served to ensure that no unprocessed air is released to the atmosphere, (2) providing filtration units to process all air exhausted from the secondary containment spaces, and (3) providing a low-leakage enclosure to limit exhaust flows. Offsite dose effects due to secondary containment release rates, bypass leakage, and duct and damper leakages are presented and parameter variations are considered. For the EGTS, a recirculation system, the most important parameter is the total inleakage of the system which causes an increase in both whole body (gamma) and thyroid (iodine) doses. For the ABGTS, a once-through system, the most important paramter is the inleakage which bypasses the filters resulting in an increase in the thyroid dose only. Actual preoperational test data are utilized. Problems encountered during the preop test are summarized. Solutions incorporated to bring the EGTS and ABGTS air cleanup systems within the test acceptance criteria required to meet offsite dose limitations are discussed and the resultant calculated offsite dose is presented

Contamination mechanisms of air basin with tritium in venues of underground nuclear explosions at the former Semipalatinsk test site.

Science.gov (United States)

Lyakhova, O N; Lukashenko, S N; Larionova, N V; Tur, Y S

2012-11-01

During the period of testing from 1945 to 1962 at the territory of Semipalatinsk test site (STS) within the Degelen Mountains in tunnels, 209 underground nuclear explosions were produced. Many of the tunnels have seasonal water seepage in the form of streams, through which tritium migrates from the underground nuclear explosion (UNE) venues towards the surface. The issue of tritium contamination occupies a special place in the radioactive contamination of the environment. In this paper we assess the level and distribution of tritium in the atmospheric air of ecosystems with water seepage at tunnels № 176 and № 177, located on "Degelen" site. There has been presented general nature of tritium distribution in the atmosphere relative to surface of a watercourse which has been contaminated with tritium. The basic mechanisms were studied for tritium distribution in the air of studied ecosystems, namely, the distribution of tritium in the systems: water-atmosphere, tunnel air-atmosphere, soil water-atmosphere, vegetation-atmosphere. An analytical calculation of tritium concentration in the atmosphere by the concentration of tritium in water has been performed. There has experimentally obtained the dependence for predictive assessment of tritium concentrations in air as a function of tritium concentration in one of the inlet sources such as water, tunnel air, soil water, vegetation, etc.. The paper also describes the general nature of tritium distribution in the air in the area "Degelen". Copyright © 2012 Elsevier Ltd. All rights reserved.

Review of biotechnology applications to nuclear waste treatment

International Nuclear Information System (INIS)

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

1990-01-01

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

Evaluation of the effect of media velocity on filter efficiency and most penetrating particle size of nuclear grade high-efficiency particulate air filters.

Science.gov (United States)

Alderman, Steven L; Parsons, Michael S; Hogancamp, Kristina U; Waggoner, Charles A

2008-11-01

High-efficiency particulate air (HEPA) filters are widely used to control particulate matter emissions from processes that involve management or treatment of radioactive materials. Section FC of the American Society of Mechanical Engineers AG-1 Code on Nuclear Air and Gas Treatment currently restricts media velocity to a maximum of 2.5 cm/sec in any application where this standard is invoked. There is some desire to eliminate or increase this media velocity limit. A concern is that increasing media velocity will result in higher emissions of ultrafine particles; thus, it is unlikely that higher media velocities will be allowed without data to demonstrate the effect of media velocity on removal of ultrafine particles. In this study, the performance of nuclear grade HEPA filters, with respect to filter efficiency and most penetrating particle size, was evaluated as a function of media velocity. Deep-pleat nuclear grade HEPA filters (31 cm x 31 cm x 29 cm) were evaluated at media velocities ranging from 2.0 to 4.5 cm/sec using a potassium chloride aerosol challenge having a particle size distribution centered near the HEPA filter most penetrating particle size. Filters were challenged under two distinct mass loading rate regimes through the use of or exclusion of a 3 microm aerodynamic diameter cut point cyclone. Filter efficiency and most penetrating particle size measurements were made throughout the duration of filter testing. Filter efficiency measured at the onset of aerosol challenge was noted to decrease with increasing media velocity, with values ranging from 99.999 to 99.977%. The filter most penetrating particle size recorded at the onset of testing was noted to decrease slightly as media velocity was increased and was typically in the range of 110-130 nm. Although additional testing is needed, these findings indicate that filters operating at media velocities up to 4.5 cm/sec will meet or exceed current filter efficiency requirements. Additionally

Air particulate pollution studies in Asian countries using nuclear analytical techniques

International Nuclear Information System (INIS)

Hien, P.D.

1998-01-01

Air particulate pollution is regarded as critical in Asian cities. The levels of suspended particulate matter in major Asian cities far exceed the WHO's guideline. Nuclear analytical techniques have been widely used in the studies of air particulate pollution to provide aerosol elemental compositions for the purpose of deriving the structure of emission sources. This paper presents some preliminary observations and findings based on publications in scientific literatures. Data on PM-10 levels and socio-economic indicators are used for searching a relationship between air quality and the level of development across Asia. An inverse linear relationship between PM-10 levels and logarithm of per capita GDP appears to exist, although there are large fluctuations of data caused by the very different climatic and geographical conditions of cities studied. Soil dust is generally a major, or even predominant aerosol source in Asian cities. Other common sources include vehicular emissions, coal and oil combustion, burning of refuse (in open) and biomass (including forest fires). The relevance and the trends of these sources in Asian context are discussed. Multivariate receptor modelling techniques applied in source characterization are illustrated through the cases of Lahore and Hochiminh City. Although having limitations in dealing with mixing and overlapping sources, receptor modelling based on principal component factor analysis has been proven to be uncomplicated and sufficiently reliable for characterising aerosol sources in urban areas. (author)

Gas processing at DOE nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Jacox, J.

1995-02-01

The term {open_quotes}Gas Processing{close_quotes} has many possible meanings and understandings. In this paper, and panel, we will be using it to generally mean the treatment of gas by methods other than those common to HVAC and Nuclear Air Treatment. This is only a working guideline not a rigorous definition. Whether a rigorous definition is desirable, or even possible is a question for some other forum. Here we will be discussing the practical aspects of what {open_quotes}Gas Processing{close_quotes} includes and how existing Codes, Standards and industry experience can, and should, apply to DOE and NRC Licensed facilities. A major impediment to use of the best engineering and technology in many nuclear facilities is the administrative mandate that only systems and equipment that meet specified {open_quotes}nuclear{close_quotes} documents are permissible. This paper will highlight some of the limitations created by this approach.

Steam generation: fossil-fired systems: utility boilers; industrial boilers; boiler auxillaries; nuclear systems: boiling water; pressurized water; in-core fuel management; steam-cycle systems: condensate/feedwater; circulating water; water treatment

International Nuclear Information System (INIS)

Anon.

1982-01-01

A survey of development in steam generation is presented. First, fossil-fired systems are described. Progress in the design of utility and industrial boilers as well as in boiler auxiliaries is traced. Improvements in coal pulverizers, burners that cut pollution and improve efficiency, fans, air heaters and economisers are noted. Nuclear systems are then described, including the BWR and PWR reactors, in-core fuel management techniques are described. Finally, steam-cycle systems for fossil-fired and nuclear power plants are reviewed. Condensate/feedwater systems, circulating water systems, cooling towers, and water treatment systems are discussed

Effects of porosity and temperature on oxidation behavior in air of selected nuclear graphites

International Nuclear Information System (INIS)

Chen Dongyue; Li Zhengcao; Miao Wei; Zhang Zhengjun

2012-01-01

Nuclear graphite endures gas oxidation in High Temperature Gas-cooled Reactor (HTGR), which may threaten the safety of reactor. To study the oxidation behavior of nuclear graphite, weight loss curve is usually measured through Thermo Gravimetric Analysis (TGA) method. In this work, three brands of nuclear graphite for HTGR (i.e., HSM-SC, IG-11, and NBG-18) are oxidized under 873 and 1073 K in open air, and their weight loss curves are obtained. The acceleration of oxidizing rate is observed for both HSM-SC and IG-11, and is attributed to the large porosity increase during oxidation process. For HSM-SC, the porosity increase comes from preferential binder oxidation, and thus its binder quality shall be improved to obtain better oxidation resistance. Temperature effects on oxidation for HSM-SC are also studied, which shows that oxidizing gas tends to be exhausted at graphite surface at high temperature instead of penetrate into the interior of bulk. (author)

Theme day: corrosion and surface treatments in nuclear facilities. Proceedings

International Nuclear Information System (INIS)

2012-02-01

This document brings together the available presentations given at the theme day organized by the Bourgogne Nuclear Pole on the topic of corrosion and surface treatments in nuclear facilities. Eleven presentations (slides) are compiled in this document: 1 - Introduction - PNB centre of competitiveness and R and D activities (A. Mantovan, PNB); 2 - Corrosion damage (M. Foucault, Areva NP - Centre Technique Le Creusot); 3 - Corrosion mechanisms (R. Oltra, UB-ICB); 4 - Examples of expertise management (C. Duret-Thual, Institut de la corrosion/Corrosion Institute); 5 - General framework of surface treatments (C. Nouveau, ENSAM Cluny Paris Tech); 6 - Surfaces et interfaces characterisation - Part A (C. Langlade, Y. Gachon, UTBM and HEF); 7 - Surfaces et interfaces characterisation - Part B (C. Langlade, Y. Gachon, UTBM and HEF); 8 - Ion beam surface treatment (Y. Le Guellec, Quertech Ingenierie); 9 - Impact surface treatment (G. Saout, Sonats); 10 - Metal oxides Characterisation by US laser (R. Oltra, UB-ICB); 11 - Detection and Characterisation of intergranular corrosion (Y. Kernin, Stephane Bourgois, Areva Intercontrole)

Determination of the radioiodine species in the exhaust air of nuclear facilities

International Nuclear Information System (INIS)

Birke, G.; Deuber, H.

1977-01-01

In the stack exhaust air of the nuclear power stations the portion of inorganic 131 I was, apart from 2 sampling periods, less than 50%. In the stack exhaust air of the research reactor the inorganic 131 I prevailed. The removal efficiency of the I 2 sorption materials DSM 11 and DSM 17 for 131 I in the form of CH 3 I and C 6 H 5 I was very low. 131 I in the form of C 6 H 5 I was removed by AC 6120 and LMS 13 X-Ag (Linde molecular sieve in the Ag form) to a very small extent too, by activated charcoal impregnated with KI or TEDA however to a very high extent. In the experiments concerning the preparation and removal of 131 I in the form of HIO an iodine species that was difficult to remove with AC 6120 was found which could be HIO. Its maximum portion in the carrier gas was 50%. (orig./RW) [de

Treatment of reverse osmosis (RO) concentrate by the combined Fe/Cu/air and Fenton process (1stFe/Cu/air-Fenton-2ndFe/Cu/air).

Science.gov (United States)

Ren, Yi; Yuan, Yue; Lai, Bo; Zhou, Yuexi; Wang, Juling

2016-01-25

To decompose or transform the toxic and refractory reverse osmosis (RO) concentrate and improve the biodegradability, 1stFe/Cu/air-Fenton-2ndFe/Cu/air were developed to treat RO concentrate obtained from an amino acid production plant in northern China. First, their operating conditions were optimized thoroughly. Furthermore, 5 control experiments were setup to confirm the superiority of 1stFe/Cu/air-Fenton-2ndFe/Cu/air and synergistic reaction between Fe/Cu/air and Fenton. The results suggest that the developed method could obtain high COD removal (65.1%) and BOD5/COD ratio (0.26) due to the synergistic reaction between Fe/Cu/air and Fenton. Under the optimal conditions, the influent and effluent of 1stFe/Cu/air-Fenton-2ndFe/Cu/air and 5 control experiments were analyzed by using UV, FTIR, EEM and LC, which confirm the superiority of 1stFe/Cu/air-Fenton-2ndFe/Cu/air. Therefore, the developed method in this study is a promising process for treatment of RO concentrate. Copyright © 2015 Elsevier B.V. All rights reserved.

Air Emission Reduction Benefits of Biogas Electricity Generation at Municipal Wastewater Treatment Plants.

Science.gov (United States)

Gingerich, Daniel B; Mauter, Meagan S

2018-02-06

Conventional processes for municipal wastewater treatment facilities are energy and materially intensive. This work quantifies the air emission implications of energy consumption, chemical use, and direct pollutant release at municipal wastewater treatment facilities across the U.S. and assesses the potential to avoid these damages by generating electricity and heat from the combustion of biogas produced during anaerobic sludge digestion. We find that embedded and on-site air emissions from municipal wastewater treatment imposed human health, environmental, and climate (HEC) damages on the order of $1.63 billion USD in 2012, with 85% of these damages attributed to the estimated consumption of 19 500 GWh of electricity by treatment processes annually, or 0.53% of the US electricity demand. An additional 11.8 million tons of biogenic CO 2 are directly emitted by wastewater treatment and sludge digestion processes currently installed at plants. Retrofitting existing wastewater treatment facilities with anaerobic sludge digestion for biogas production and biogas-fueled heat and electricity generation has the potential to reduce HEC damages by up to 24.9% relative to baseline emissions. Retrofitting only large plants (>5 MGD), where biogas generation is more likely to be economically viable, would generate HEC benefits of $254 annually. These findings reinforce the importance of accounting for use-phase embedded air emissions and spatially resolved marginal damage estimates when designing sustainable infrastructure systems.

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.

Comprehensive Technical Report, General Electric Direct-Air-Cycle Aircraft Nuclear Propulsion Program, Program Summary and References

Energy Technology Data Exchange (ETDEWEB)

Thornton, G.; Rothstein, A.J.

1962-06-28

This is one of twenty-one volumes sumarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This volume discusses the background to the General Electric program, and summarizes the various direct-air-cycle nuclear test assemblies and power plants that were developed. Because of the requirements of high performance, low weight, and small size, vast improvements in existing technology were required to meet the flight objectives. The technological progress achieved during the program is also summarized. The last appendix contains a compilation of the abstracts, tables of contents, and reference lists of the other twenty volumes.

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)

Compilation of data on the release of radioactive substances in the vent air of nuclear power plants in the Federal Republic of Germany in 1975

International Nuclear Information System (INIS)

Winkelmann, I.; Endrulat, H.J.; Haubelt, R.; Westpfahl, U.

1976-04-01

The present compilation of data on the release of radioactive substances in the vent air of nuclear power plants in the FRG is a continuation of a report series on aerosol filter and iodine filter samples from the exhaust air control systems of the nuclear power plants Gundremmingen, Obrigheim, Wuergassen, Stade, Lingen and Biblis A. The reports have been issued by the Federal public health office since 1972. This report is supplemented by annual release values on radioactive noble gases, on short- and long-lived aerosols, and on gaseous 131 I, supplied by the individual nuclear power plants as in previous years on uniform questionnaires. Data on the release of tritium are also available from some nuclear power plants. (orig.) [de

Erythritol-Enriched Air-Polishing Powder for the Surgical Treatment of Peri-Implantitis

Directory of Open Access Journals (Sweden)

Silvio Taschieri

2015-01-01

Full Text Available Peri-implantitis represents a major complication that can compromise the success and survival of implant-supported rehabilitations. Both surgical and nonsurgical treatment protocols were proposed to improve clinical parameters and to treat implants affected by peri-implantitis. A systematic review of the literature was performed on electronic databases. The use of air-polishing powder in surgical treatment of peri-implantitis was investigated. A total of five articles, of different study designs, were included in the review. A meta-analysis could not be performed. The data from included studies reported a substantial benefit of the use of air-polishing powders for the decontamination of implant surface in surgical protocols. A case report of guided bone regeneration in sites with implants affected by peri-implantitis was presented. Surgical treatment of peri-implantitis, though demanding and not supported by a wide scientific literature, could be considered a viable treatment option if an adequate decontamination of infected surfaces could be obtained.

Unit for air decontamination; Unidad para descontaminacion de aire

Energy Technology Data Exchange (ETDEWEB)

Mariano H, E

1991-02-15

To fulfill the applicable requirements of safety to the ventilation systems in nuclear facilities, it is necessary to make a cleaning of the air that hurtles to the atmosphere. For that which was designed and it manufactured an unit for decontamination of the air for the Pilot plant of production of Nuclear Fuel that this built one with national parts, uses Hepa national filters and the design can adapt for different dimensions of filters, also can be added a lodging for a prefilter or to adopt two Hepa filters. (Author)

Facilities for treatment of radioactive contaminated water in nuclear power plants

International Nuclear Information System (INIS)

1981-02-01

The standard applies to processes applied in facilities for treatment of radioactive contaminated water in nuclear power plants with LWR- and HTR-type reactors. It does not apply to the treatment of concentrates obtained in the decontamination of water. (orig.) [de

Effect of using dissolved air flotation system on industrial wastewater treatment in pilot scale

International Nuclear Information System (INIS)

Yahya, Habibzadeh

2010-01-01

In the present paper the application of Dissolved Air Flotation (DAF) system for wastewater treatment, especially for industrial wastewater on a designed pilot system has been investigated. It is for the first time in dissolved air flotation system that instead of air dissolving tube, hydro cyclone technology is used to dissolve air in water with ratio of 1:1 (almost 100 percent) in the form of small air bubbles and a circular flotation tank instead of rectangular tank. The advantage of usage of circular tank in DAF system is the capability of being treated in higher rate of mass, so less space is needed. Although application of hydro cyclone with different diameters of holes for producing mixing energy which also has the capability of direct injection of chemical coagulant and polymeric materials leads to the higher efficiency of treatment and so reduces the cost of pump and consumed air. Investigations on the efficiency of this system was done by providing and analyzing samples of wastewater with and without adding of PAC (Poly-Aluminium-Chloride). Sampling and analyzing was done according to standard methods. The results of the analyses show that pilot system has high efficiency, especially for oil removal

Inactivation of Salmonella on pecan nutmeats by hot air treatment and oil roasting.

Science.gov (United States)

Beuchat, Larry R; Mann, David A

2011-09-01

Studies were done to determine the effectiveness of hot air drying, dry roasting, and oil roasting in killing Salmonella on pecan nutmeats. Pecan halves and pieces were inoculated by immersion in a five-serotype suspension of Salmonella or by surface application of powdered chalk containing the pathogen. Hot air treatment of low-moisture (2.8 to 4.1%) and high-moisture (10.5 to 11.2%) immersion-inoculated nutmeats (initial population, 6.18 to 7.16 log CFU/g) at 120°C for 20 min reduced the number of Salmonella by 1.18 to 1.26 and 1.89 to 2.04 log CFU/g, respectively. However, regardless of the moisture content, hot air treatment of pecan halves containing 0.77 log CFU/g at 120°C for 20 min failed to eliminate Salmonella. Reductions were >7 log CFU/g when dry pieces were dry roasted at 160°C for 15 min. Treatment of halves at 140°C for 20 min, 150°C for 15 min, or 170°C for 10 min reduced Salmonella by 5 log CFU/g. The pathogen was slightly more heat resistant in immersion-inoculated nutmeats than on surface-inoculated nutmeats. Exposure of immersion-inoculated pieces to peanut oil at 127°C for 1.5 min or 132°C for 1.0 min reduced the number of Salmonella by 5 log CFU/g. Treatment of halves at 138°C for 2.0 min reduced Salmonella by 5 log CFU/g; treatment at 132°C for 2.5 to 4.0 min did not always achieve this reduction. Hot air treatment cannot be relied upon to reduce Salmonella by 5 log CFU/g of raw pecan nutmeats without changing sensory qualities. Treatment temperatures and times typically used to oil roast nutmeats appear to be sufficient to reduce Salmonella by 5 log CFU/g.

Development of Nuclear Control and Management Information Treatment System

Energy Technology Data Exchange (ETDEWEB)

Yoo, J. G.; Lee, B. D.; So, D. S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2007-07-01

To implement obligations under the Non-Proliferation Treaty (NPT) and the bilateral agreements more effectively, we proposed a computerized system named the Nuclear Control and Management Information Treatment System (NCAMITS) as a part of the Nuclear Transparency Enhancement Project at the Korea Atomic Energy Research Institute (KAERI). The database system is designed not only to undertake the facility-level accounting for and control of nuclear material at KAERI, but also to meet the requirements of the State (National) System of Accounting and Control (SSAC). Since the NCAMITS will provide services for the facility operators as well as the safeguard information managers at KAERI, the development of the system is supposed to accommodate the end-user's convenience and the manager's sophisticated specifications as well.

Air Emissions Damages from Municipal Drinking Water Treatment Under Current and Proposed Regulatory Standards.

Science.gov (United States)

Gingerich, Daniel B; Mauter, Meagan S

2017-09-19

Water treatment processes present intersectoral and cross-media risk trade-offs that are not presently considered in Safe Drinking Water Act regulatory analyses. This paper develops a method for assessing the air emission implications of common municipal water treatment processes used to comply with recently promulgated and proposed regulatory standards, including concentration limits for, lead and copper, disinfection byproducts, chromium(VI), strontium, and PFOA/PFOS. Life-cycle models of electricity and chemical consumption for individual drinking water unit processes are used to estimate embedded NO x , SO 2 , PM 2.5 , and CO 2 emissions on a cubic meter basis. We estimate air emission damages from currently installed treatment processes at U.S. drinking water facilities to be on the order of $500 million USD annually. Fully complying with six promulgated and proposed rules would increase baseline air emission damages by approximately 50%, with three-quarters of these damages originating from chemical manufacturing. Despite the magnitude of these air emission damages, the net benefit of currently implemented rules remains positive. For some proposed rules, however, the promise of net benefits remains contingent on technology choice.

Radioactive waste treatment at the Boris Kidric Institute of nuclear sciences

International Nuclear Information System (INIS)

Vukovic, Z.

1989-01-01

The results of many years work on the problems of treatment and interim storage of radioactive waste at the Boris Kidric Institute of nuclear sciences are presented. The main R/D work based on chemical treatment, solidification and pressing is described (author)

Radioactive waste treatment at the Boris Kidric Institute of nuclear sciences

Energy Technology Data Exchange (ETDEWEB)

Vukovic, Z [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1989-07-01

The results of many years work on the problems of treatment and interim storage of radioactive waste at the Boris Kidric Institute of nuclear sciences are presented. The main R/D work based on chemical treatment, solidification and pressing is described (author)

Safety Aspects of Nuclear Waste Treatment

International Nuclear Information System (INIS)

Glubrecht, H.

1986-01-01

In the nuclear fuel cycle - like in most other industrial processes - some waste is produced which can be harmful to the environment and has to be stored safely and isolated from the Biosphere. This radioactive waste can be compared with toxic chemical waste under many aspects, but it has some special features, some of which make its handling more difficult, others make it easier. The difficulties are that radioactive waste does not only affect living organisms after incorporation, but also from some distance through its radiation. Therefore this waste has not only to be encapsuled, but also shielded. At higher concentrations radioactive waste produces heat and this has to be continuously derived from the storage area. On the other hand the control of even extremely small amounts of radioactive waste is very much easier than that of toxic chemical waste due to the high sensitivity of radiation detection methods. Furthermore radioactive waste is not persistent like most of the chemical waste. Of course some components will decay only after millennia, but a high percentage of radioactive waste becomes inactive after days, weeks or years. An important feature of safety aspects related to nuclear waste is the fact that problems of its treatment and storage have been discussed from the very beginning of Nuclear Energy Technology - what has not been the case in relation to most other industrial wastes

Final Environmental Impact Statement for the Treatment and Management of Sodium-Bonded Spent Nuclear Fuel

International Nuclear Information System (INIS)

2000-01-01

DOE is responsible for the safe and efficient management of its sodium-bonded spent nuclear fuel. This fuel contains metallic sodium, a highly reactive material; metallic uranium, which is also reactive; and in some cases, highly enriched uranium. The presence of reactive materials could complicate the process of qualifying and licensing DOE's sodium-bonded spent nuclear fuel inventory for disposal in a geologic repository. Currently, more than 98 percent of this inventory is located at the Idaho National Engineering and Environmental Laboratory (INEEL), near Idaho Falls, Idaho. In addition, in a 1995 agreement with the State of Idaho, DOE committed to remove all spent nuclear fuel from Idaho by 2035. This EIS evaluates the potential environmental impacts associated with the treatment and management of sodium-bonded spent nuclear fuel in one or more facilities located at Argonne National Laboratory-West (ANL-W) at INEEL and either the F-Canyon or Building 105-L at the Savannah River Site (SRS) near Aiken, South Carolina. DOE has identified and assessed six proposed action alternatives in this EIS. These are: (1) electrometallurgical treatment of all fuel at ANL-W, (2) direct disposal of blanket fuel in high-integrity cans with the sodium removed at ANL-W, (3) plutonium-uranium extraction (PUREX) processing of blanket fuel at SRS, (4) melt and dilute processing of blanket fuel at ANL-W, (5) melt and dilute processing of blanket fuel at SRS, and (6) melt and dilute processing of all fuel at ANL-W. In addition, Alternatives 2 through 5 include the electrometallurgical treatment of driver fuel at ANL-W. Under the No Action Alternative, the EIS evaluates both the continued storage of sodium-bonded spent nuclear fuel until the development of a new treatment technology or direct disposal without treatment. Under all of the alternatives, the affected environment is primarily within 80 kilometers (50 miles) of spent nuclear fuel treatment facilities. Analyses indicate

Aging of control and service air compressors and dryers used in nuclear power plants

International Nuclear Information System (INIS)

Moyers, J.C.

1990-07-01

This report was produced under the Detection of Defects and Degradation Monitoring of Nuclear Plant Safety Equipment element of the Nuclear Plant Aging Research Program. This element includes the identification of practical and cost-effective methods for detecting, monitoring, and assessing the severity of time-dependent degradation (aging) of control and service air compressors and dryers in nuclear power plants. These methods are to provide capabilities for establishing degradation trends prior to failure and developing guidance for effective maintenance. The topics of this Phase 1 assessment report are failure modes and causes resulting from aging, manufacturer--recommended maintenance and surveillance practices, and measurable parameters (including functional indicators) for use in assessing operational readiness, establishing degradation trends, and detecting incipient failure. the results presented are based on information derived from operating experience records, manufacturer-supplied information, and input from plant operators. For each failure mode, failure causes are listed by subcomponent, and parameters potentially useful for detecting degradation that could lead to failure are identified. 13 refs., 9 figs., 16 tabs

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

Analysing the Air: Experiences and Results of Long Term Air Pollution Monitoring in the Asia-Pacific Region Using Nuclear Analysis Techniques

International Nuclear Information System (INIS)

Atanacio, Armand J.

2015-01-01

Particles present in the air we breathe are now recognized as a major cause of disease and premature death globally. In fact, a World Health Organization (WHO) report recently ranked ambient air pollution as one of the top 10 causes of death in the world, directly contributing annually to around 3.7 million premature deaths worldwide 65% of which occurred in the Asian region alone. Airborne particulate matter (PM) can be generated from natural sources such as windblown soil or coastal sea-spray; as well as anthropogenic sources such as power stations, industry, vehicles and domestic biomass burning. At low concentration these fine pollution particles are too small to be seen by eye, but penetrate deep into our lungs and even our blood stream as our nose and throat are inefficient at filtering them out. At large concentrations, they can also have wider regional effects including reduced visibility, acid rain and even climate variability. The International Atomic Energy Agency (IAEA) in 2000, recognizing air pollution as a significant local, national and global challenge, initiated a collaborative air pollution study involving 14 countries across the greater Asia-pacific region from 2000 to 2015. This has amassed a database containing more than 14,000 data lines of PM mass concentration and the concentration of up to 40 elements using nuclear analytical techniques. It represents the most comprehensive and long-term airborne PM data set compiled to date for the Asia-Pacific region and as will be discussed, can be used to statistically resolve individual source fingerprints and their contributions to total air pollution using Positive Matrix Factorization (PMF). This sort of data necessary for implementing or reviewing the effectiveness of policy level changes aimed at targeted air pollution reduction. (author)

Air treatment techniques for abatement of emissions from intensive livestock production

NARCIS (Netherlands)

Melse, R.W.

2009-01-01

Keywords: Air treatment; Scrubber; Bioscrubber; Biofilter; Biotrickling filter; Ammonia; NH3; Odour; Livestock production; Animal husbandry; Pig; Poultry.

Intensive livestock production is connected with a number of environmental effects, including emissions of ammonia (NH3), greenhouse

An assessment of air sampling location for stack monitoring in nuclear facility

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Bok [University of Science and Technology, Daejeon (Korea, Republic of); Kim, Tae Hyoung; Lee, Jong Il; Kim, Bong Hwan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2017-06-15

In this study, air sampling locations in the stack of the Advanced Fuel Science Building (AFSB) at the Korea Atomic Energy Research Institute (KAERI) were assessed according to the ANSI/HPS N13.1-1999 specification. The velocity profile, flow angle and 10 μm aerosol particle profile at the cross-section as functions of stack height L and stack diameter D (L/D) were assessed according to the sampling location criteria using COMSOL. The criteria for the velocity profile were found to be met at 5 L/D or more for the height, and the criteria for the average flow angle were met at all locations through this assessment. The criteria for the particle profile were met at 5 L/D and 9 L/D. However, the particle profile at the cross-section of each sampling location was found to be non-uniform. In order to establish uniformity of the particle profile, a static mixer and a perimeter ring were modeled, after which the degrees of effectiveness of these components were compared. Modeling using the static mixer indicated that the sampling locations that met the criteria for the particle profile were 5-10 L/D. When modeling using the perimeter ring, the sampling locations that met the criteria for particle profile were 5 L/D and 7-10 L/D. The criteria for the velocity profile and the average flow angle were also met at the sampling locations that met the criteria for the particle profile. The methodologies used in this study can also be applied during assessments of air sampling locations when monitoring stacks at new nuclear facilities as well as existing nuclear facilities.

Nuclear propulsion apparatus with alternate reactor segments

International Nuclear Information System (INIS)

Szekely, T.

1979-01-01

Nuclear propulsion apparatus comprising: (a) means for compressing incoming air; (b) nuclear fission reactor means for heating said air; (c) means for expanding a portion of the heated air to drive said compressing means; (d) said nuclear fission reactor means being divided into a plurality of radially extending segments; (e) means for directing a portion of the compressed air for heating through alternate segments of said reactor means and another portion of the compressed air for heating through the remaining segments of said reactor means; and (f) means for further expanding the heated air from said drive means and the remaining heated air from said reactor means through nozzle means to effect reactive thrust on said apparatus. 12 claims

Nuclear waste treatment using Iranian natural zeolites

International Nuclear Information System (INIS)

Kazemian, H.; Ghannadi Maraghe, M.

2001-01-01

Full text: The zeolite researches in Iran is a relatively new subject which has started about 10 years ago. The motivation for this scientific and interesting field was provided after discovery of significant deposits of natural zeolites in different regions of Iran as well as further developments of research institutions and the national concern to environmental protection especially the wastewater clean-up in point of view of recycling of such waste water to compensate some needs to water in other utilizations. This paper intends to review and describes scientific researches which have done on using zeolites in the field of nuclear waste treatment in Iran to introduce the potential resources to the world in more details. Zeolite tuffs are widely distributed in huge deposits in different regions of Iran. So far, the clinoptilolite tuffs are the most abundant natural zeolite which exist with zeolite content of 65%- 95%. Nowadays several different types of Iranian natural zeolites are characterized in point of view of chemical composition, type of structure, chemical, thermal, and radiation resistance using different instrumental and classical methods such as; X-ray diffraction (XRD), X-ray fluoresce (XRF), thermal methods of analysis (TA), scanning electron microscopy (SEM), analytical chemistry and radioanalytical methods as well as different ion-exchange techniques (e.g.3-7). The ability of Iranian natural clinoptilolite for removal of some fission products from nuclear wastewaters have been investigated. The selectivity of all investigated zeolites toward radiocesium and radiostrontium have been promising (e.g. 8-10). The successful synthesize of P zeolite from Iranian clinoptilolite-reach tuffs under different conditions were performed. The compatibility of zeolites with glass and cement matrices, for final disposal of radwaste, as well as their selectivity toward most dangerous heat generating radionuclides (e.g. 137 Cs and 90 Sr) is very important in using

Monitoring of air toxics through air pathways in support of a No-Migration permit at a refinery land treatment facility

International Nuclear Information System (INIS)

Wineberry, W.T. Jr.; McReynolds, J.

1991-01-01

As part of Exxon's petition of the EPA for No-Migration variances, ambient concentrations of toxicants and carcinogens are required to be verified through onsite monitoring for comparison to the appropriate health based limits as well as for calibration of previously used atmospheric dispersion models. Ambient air around land treatment facilities us a very complex, dynamic system of interacting chemicals. Pollutants can be found in the gas phase, in the particulate phase, or in the aerosol phase. The complex nature of the dynamic air system around these facilities contributes to the complexity of the sampling and analytical selection for the identification and quantification for these chemicals. The selection of the proper sampling and analysis methods for a pollutant depends on many important interrelated factors, including compounds of interest, the level of detection required, the degree of specificity needed, and the purpose of the data collected. Other factors which may be as important as the above are cost, the accuracy and precision required, need for real-time versus long-term data, and the need for on-site or off-site analysis. Sampling time, sampling rate, the volume of air to be sampled and the acceptable risk level are also factors which must be considered when choosing a sampling method. The purpose of the ambient air monitoring program is to obtain a comparison of predicted concentration to those measured. This paper will focus on the ambient air monitoring program at Exxon's land treatment facility as part of a No-Migration variance to EPA's Land Ban Regulations. Ambient Air Monitoring data involving volatile, semi-volatile and metals/particulate matter less than ten microns (PM-10) will be presented

Air lock

International Nuclear Information System (INIS)

Palkovich, P.; Gruber, J.; Madlener, W.

1974-01-01

The patent refers to an air lock system preferably for nuclear stations for the transport of heavy loads by means of a trolley on rails. For opening and closing of the air lock parts of the rails are removed, e.g. by a second rail system perpendicular to the main rails. (P.K.)

Hydrogen treatment system in the Genkai nuclear power plant No. 2

International Nuclear Information System (INIS)

Nakamura, Masayuki; Kodama, Hideo; Murashima, Masayasu

1977-01-01

The new hydrogen treatment system which injects hydrogen into the volume control tank for purging the mixed waste gas of Kr, Xe, etc. is adopted in the Genkai nuclear power plant No. 2. The system is composed of mainly the waste gas pretreatment equipment, a palladium alloy membrane type hydrogen separator, a hydrogen compressor, and a waste gas decay tank. The outline of the primary cooling system and the chemical volume control system of PWR, the hydrogen treatment system, and the gaseous waste disposal system of original and new types for the Genkai nuclear power plants No. 1 and 2 are explained in this paper. This newly added hydrogen treatment system will be able to reduce the rare gas concentration rate in the primary coolant to about 1/2 and 1/5 for Kr 85 and Xe 133 , respectively. (auth.)

Nuclear power station main control room habitability

International Nuclear Information System (INIS)

Paschal, W.B.; Knous, W.S.

1989-01-01

The main control room at a nuclear power station must remain habitable during a variety of plant conditions and postulated events. The control room habitability requirement and the function of the heating, ventilating, air-conditioning, and air treatment system are to control environmental factors, such as temperature, pressure, humidity, radiation, and toxic gas. Habitability requirements provide for the safety of personnel and enable operation of equipment required to function in the main control room. Habitability as an issue has been gaining prominence with the Advisor Committee of Reactor Safeguards and the Nuclear Regulatory Commission since the incident at Three Mile Island. Their concern is the ability of the presently installed habitability systems to control the main control room environment after an accident. This paper discusses main control room HVAC systems; the concern, requirements, and results of NRC surveys and notices; and an approach to control room habitability reviews

Effect of non-thermal air atmospheric pressure plasma jet treatment on gingival wound healing

International Nuclear Information System (INIS)

Lee, Jung-Hwan; Choi, Eun-Ha; Kim, Kwang-Mahn; Kim, Kyoung-Nam

2016-01-01

Non-thermal atmospheric pressure plasmas have been applied in the biomedical field for the improvement of various cellular activities. In dentistry, the healing of gingival soft tissue plays an important role in health and aesthetic outcomes. While the biomedical application of plasma has been thoroughly studied in dentistry, a detailed investigation of plasma-mediated human gingival fibroblast (HGF) migration for wound healing and its underlying biological mechanism is still pending. Therefore, the aim of this study is to apply a non-thermal air atmospheric pressure plasma jet (NTAAPPJ) to HGF to measure the migration and to reveal the underlying biological mechanisms involved in the migration. After the characterization of NTAAPPJ by optical emission spectroscopy, the adherent HGF was treated with NTAAPPJ or air with a different flow rate. Cell viability, lipid peroxidation, migration, intracellular reactive oxygen species (ROS), and the expression of migration-related genes (EGFR, PAK1, and MAPK3) were investigated. The level of statistical significance was set at 0.05. NTAAPPJ and air treatment with a flow rate of 250–1000 standard cubic centimetres per minute (sccm) for up to 30 s did not induce significant decreases in cell viability or membrane damage. A significant increase in the migration of mitomycin C-treated HGF was observed after 30 s of NTAAPPJ treatment compared to 30 s air-only treatment, which was induced by high levels of intracellular reactive oxygen species (ROS). An increase in migration-related gene expression and EGFR activation was observed following NTAAPPJ treatment in an air flow rate-dependent manner. This is the first report that NTAAPPJ treatment induces an increase in HGF migration without changing cell viability or causing membrane damage. HGF migration was related to an increase in intracellular ROS, changes in the expression of three of the migration-related genes (EGFR, PAK1, and MAPK1), and EGFR activation. Therefore

The contribution of waste water treatment plants to PBDEs in ambient air

International Nuclear Information System (INIS)

Martellini, Tania; Jones, Kevin C.; Sweetman, Andy; Giannoni, Martina; Pieri, Francesca; Cincinelli, Alessandra

2012-01-01

Air samples were collected at different sites in and around two wastewater treatment plants (WWTPs) located in central Italy to determine the concentrations, compositional profiles and contribution to ambient levels of eight polybrominated diphenyl ethers (PBDEs). The investigated WWTPs were selected as they treat industrial wastewater produced by local textile industries along with municipal wastewater. PBDE concentrations within the WWTPs were higher than those measured at reference sites located 4 and 5 km away with BDE-209 dominating the BDE congener composition in all air samples in 2008. Ambient PBDE concentrations measured in and around the WWTPs and estimates of emissions from aeration tanks suggest that WWTPs are sources of PBDEs to ambient air. Principal component analysis and Pearson correlations confirmed this result. The effect of distance from the plant and wind direction on atmospheric concentrations was also investigated. Although the primary fate of PBDEs in WWTPs will be partitioning to sewage sludge, this study suggests that plants can provide a measurable source of these compounds to local ambient air. - Highlights: ► Levels and distribution profiles of PBDEs in the atmosphere surrounding two WWTPs. ► Airborne polybrominated diphenyl ethers in the surrounding area of two WWTPs in Italy. ► To investigate WWTPs as sources of PBDEs to the atmosphere. ► Samples collected downwind respect to the plant showed BDE-209 as dominant congener. ► The effect of distance and wind direction on atmospheric concentrations was also investigated. - Waste water treatment plants as sources of PBDEs to the ambient air.

The broad view of nuclear technology for aerospace

International Nuclear Information System (INIS)

Buden, D.; Angelo, J.A. Jr.

1991-01-01

Nuclear technologies can directly support advanced space initiatives. For near-Earth missions, nuclear technology can be used to power air traffic control, communications and manufacturing platforms, provide emergency power for manned platforms, provide power for maneuvering units, move asteroids for mining, measure the natural radiation environment, provide radiation protection instruments, and design radiation hardened robotic systems. For the Lunar and Mars surfaces, nuclear technology can be used for base stationary, mobile, and emergency power, energy storage, process heat, nuclear thermal and electric rocket propulsion, excavation and underground engineering, water and sewage treatment and sterilization, food processing and preservation, mineral exploration, self-luminous systems, radiation protection instrumentation, radiation environmental warning systems, and habitat shielding design. Outer planet missions can make use of nuclear technology for power and propulsion. Programs need to be initiated to ensure the full beneficial use of nuclear technologies in advanced space missions

Current situation of the facilities, equipments and human resources in nuclear medicine in Argentina

International Nuclear Information System (INIS)

Chiliutti, Claudia A.

2008-01-01

The current situation of nuclear medicine in Argentina, taking into account the facilities, their equipment and human resources available is presented in this paper. A review and analysis of the equipment, including technical characteristics and a survey of the professionals and technicians of the area, was carried out. In Argentina, there are 266 centers of nuclear medicine distributed all over the country. The operating licenses are granted by the Nuclear Regulatory Authority (Autoridad Regulatoria Nuclear - ARN). Forty four percent of the installed equipment are SPECT of 1 or 2 heads and 39,4 % are gamma camera. Besides, there are eleven PET operating in Argentina. There are 416 nuclear medicine physicians with individual permit for diagnostic purposes and 50% of them has also individual permit for treatment purposes. With the purpose of analyzing the regional distribution of the available resources in nuclear medicine, the country was divided into 7 geographical regions: City of Buenos Aires, Province of Buenos Aires, Pampa, Cuyo, Northeast, Northwest and Patagonia. From the analysis of the gathered information it is possible to conclude that the nuclear medicine equipment as well as the personnel present an irregular distribution, with a major concentration in the City of Buenos Aires and Province of Buenos Aires. The Northeast region presents the lowest number of Nuclear Medicine centers and the Patagonia region has the lowest number of medicine nuclear physicians with individual permits. The number of SPECT and gamma cameras is 7,3 per million of inhabitants. The information about the available resources in nuclear medicine presented in this paper and its comparison with the international information available provide elements for a better planning of the future activities in the area not only for the operators but also from the regulatory point of view. (author)

The Effects of Nuclear Weapons. Third edition

Energy Technology Data Exchange (ETDEWEB)

Glasstone, S; Dolan, P J

1977-01-01

Since the last edition of ''The Effects of Nuclear Weapons'' in 1962 much new information has become available concerning nuclear weapon effects. This has come in part from the series of atmospheric tests, including several at very high altitudes, conducted in the Pacific Ocean area in 1962. In addition, laboratory studies, theoretical calculations, and computer simulations have provided a better understanding of the various effects. A new chapter has been added on the electromagnetic pulse. The chapter titles are as follows: general principles of nuclear explosions; descriptions of nuclear explosions; air blast phenomena in air and surface bursts; air blast loading; structural damage from air blast; shock effects of surface and subsurface bursts; thermal radiation and its effects; initial nuclear radiation; residual nuclear radiation and fallout; radio and radar effects; the electromagnetic pulse and its effects; and biological effects. (LTN)

Preliminary assessment of the thermal effects of an annular air space surrounding an emplaced nuclear waste canister

International Nuclear Information System (INIS)

Davis, B.W.

1979-01-01

Modeling results have previously shown that the presence of a large air space (e.g., a repository room) within a nuclear waste repository is expected to cause a waste canister's temperature to remain cooler than it would otherwise be. Results presented herein show that an annular air space surrounding the waste canisters can have similar cooling effects under certain prescribable conditions; for a 16 ft x 1 ft diameter canister containing 650 PWR rods which initially generate a total of 4.61 kw, analysis will show that annular air spaces greater than 11 in will permit the canister surface to attain peak temperatures lower than that which would result from a zero-gap/perfect thermal contact. It was determined that the peak radial temperature gradient in the salt varies in proportion to the inverse of the drill hole radius. Thermal radiation is shown to be the dominant mode of heat transfer across an annular air space during the first two years after emplacement. Finally, a methodology is presented which will allow investigators to easily model radiation and convection heat transfer through air spaces by treating the space as a conduction element that possesses non-linear temperature dependent conductivity

Optimization in the nuclear fuel cycle II: Concentration of alpha emitters in the air

International Nuclear Information System (INIS)

Pereira, W.S.; Silva, A.X.; Lopes, J.M.; Carmo, A.S.; Mello, C.R.; Fernandes, T.S.; Kelecom, A.

2017-01-01

Optimization is one of the bases of radioprotection and aims to move doses away from the dose limit that is the borderline of acceptable radiological risk. The work aims to use the monitoring of the concentration of alpha emitters in the air as a tool of the optimization process. We analyzed 27 sampling points of airborne alpha concentration in a nuclear fuel cycle facility. The monthly averages were considered statistically different, the highest in the month of February and the lowest in the month of August. All other months were found to have identical mean activity concentration values. Regarding the sampling points, the points with the highest averages were points 12, 15 and 9. These points were indicated for the beginning of the optimization process. Analysis of the production of the facility should be performed to verify possible correlations between production and concentration of alpha emitters in the air

Air radon equilibrium factor measurement in a Waste Water Pre-Treatment Plant

International Nuclear Information System (INIS)

Martinez, J.E.; Juste, B.; Ortiz, J.; Martorell, S.; Verdu, G.

2017-01-01

We analyze in this paper a Waste Water Pre-Treatment Plant (WWTP) located at the Mediterranean coast with air radon concentration above Spanish action level (600 Bq per cubic meter). This paper presents a method for radon equilibrium determination by gamma spectrometry measuring of the radon progeny concentrations in the air, in order to estimate WWTP workers effective dose more exactly. The method is based on simultaneous sampling of air through a filter paper and alpha spectrometry measurement of radon activity concentration in the air. According to the measured radon activity concentration in the air of 368±45 Bq/m 3 the equilibrium factor between radon and progenies is estimated to be F=0.27, which is in good agreement with expected values. - Highlights: • High levels of Radon in a workplace can increase health risks in the employees. • Using the typical equilibrium factor 0.4 could lead to an error in the estimation of radon doses. • We present a method for radon equilibrium determination. • Equilibrium factor is calculated by gamma spectrometry measuring of radon progeny concentrations in the air.

Water treatment process for nuclear reactors

International Nuclear Information System (INIS)

Marwan, M.A.; Khattab, M.S.; Hanna, A.N.

1993-01-01

Water treatment for purification is very important in reactor cooling systems as well as in many industrial applications. Since impurities in water are main source of problems, it is necessary to achieve and maintain high purity of water before utilization in reactor cooling systems. The present work investigates water treatment process for nuclear reactor utilization. Analysis of outwater chemistry proved that demineralizing process is an appropriate method. Extensive experiments were conducted to determine economical concentration of the regenerants to obtain the optimum quantity of pure water which reached to 15 cubic-meter instead of 10 cubic-meter per regeneration. Running cost is consequently decreased by about 30%. Output water chemistry agrees with the recommended specifications for reactor utilization. The radionuclides produced in the primary cooling water due to reactor operation are determined. It is found that 70% of radioactive contaminants are retained by purification through resin of reactor filter. Decontamination factor and filter efficiency are also determined

Water treatment process for nuclear reactors

International Nuclear Information System (INIS)

Marwan, M.A.; Khattab, M.S.; Hanna, A.N.

1992-01-01

Water treatment for purification is very important in reactor cooling systems as well as in many industrial applications. Since impurities in water are main source of problems, it is necessary to achieve and maintain high purity of water before utilization in reactor cooling systems. The present work investigate water treatment process for nuclear reactor utilization. Analysis of output water chemistry proved that demineralizing process is an appropriate method. Extensive experiments were conducted to determine economical concentration of the regenerates to obtain the optimum quantity of pure water which reached to 15 cubic meter instead of 10 cubic-meter per regeneration. Running cost is consequently decreased by about 30 %. output water chemistry agree with the recommended specifications for reactor utilization. The radionuclides produced in the primary cooling water due to reactor operation are determined. It is found that 70% of radioactive contaminants are retained by purification through resin of reactor filter. Decontamination factor and filter efficiency are also determined.5 fig., 3 tab

Diffuse plasma treatment of polyamide 66 fabric in atmospheric pressure air

International Nuclear Information System (INIS)

Li, Lee; Peng, Ming-yang; Teng, Yun; Gao, Guozhen

2016-01-01

Graphical abstract: - Highlights: • A cylindrical-electrode nanosecond-pulse diffuse-discharge reactor is presented. • Large-scale non-thermal plasmas were generated steadily in atmospheric air. • Treated PA66 fabric is etched with oxygen-containing group increases. • The hydrophily of treated PA66 fabric improves effectively. • Extending the treatment time is a method to reduce the treatment frequency. - Abstract: The polyamide 66 (PA66) fabrics are hard to be colored or glued in industrial production due to the poor hydrophily. Diffuse plasma is a kind of non-thermal plasma generated at atmospheric pressure in air. This paper proposes that large-scale diffuse plasma generated between wire electrodes can be employed for improving the hydrophily of PA66 fabrics. A repetitive nanosecond-pulse diffuse-discharge reactor using a cylindrical wire electrode configuration is presented, which can generate large-scale non-thermal plasmas steadily at atmospheric pressure without any barrier dielectric. Then the reactor is used to treat PA66 fabrics in different discharge conditions. The hydrophilicity property of modified PA66 is measured by wicking test method. The modified PA66 is also analyzed by atomic force microscopy (AFM) and X-ray photoelectron spectroscopy (XPS) to prove the surface changes in physical microstructure and chemical functional groups, respectively. What's more, the effects of treatment time and treatment frequency on surface modification are investigated and discussed.

Properties of aerosol floating in the air in a nuclear power plant workplace environment

International Nuclear Information System (INIS)

Karasawa, H.; Funabashi, M.; Ito, M.

1992-01-01

An investigation was carried out on properties of radioactive aerosol floating in the air at several workplaces in nuclear power plant. The principal results are as follows: the aerosol particle size distributions consisted of two particle groups, whose aerodynamic diameters ranged from 4 to 7 microns and from 0.4 to 0.6 microns; the radioactive aerosol particle size distribution were unimodal. The mean activity median aerodynamic diameter (AMAD) was 6 microns, with geometric standard deviation microns; and, the average density of the aerosol was about 2.2g/cm 3 . (author)

Air pollution, nuclear power and electricity demand: an economic perspective

International Nuclear Information System (INIS)

Chapman, D.; Mount, T.; Czerwinski, M.; Younger, M.

1983-09-01

We have studied the potential for physical or financial disruption of the electric utility system in New York as it may be affected by nuclear power availability, air pollution control policy, inflation, and economic growth. The method of analysis is the EPA-sponsored CCMU model which integrates utility economics, demand forecasting and customer charges, air pollution control, and power plant dispatching. The CCMU model is a partial version of the AUSM; the latter model is being developed to include coal supply and capacity planning. Of all the cases examined, only one type seems to create a severe crisis which leads to possible public reorganization of the industry. These are the cases in which the Shoreham and Nine Mile 2 plants are not operated, and 50% or more of the investment cost is not allowed in the rate base. In these circumstances, the state's utilities would apparently be unable to meet debt obligations and would also need to discontinue dividend payments. The extremity of this situation should be emphasized. These specific cases already assume that liability for debt and dividend payments has been shared equally over all of the state's utilities and customers. It assumes that the state's Power Pool has already implemented a plan by which the principal owners of the two plants are relieved of their principal financial and generating responsibilities. In all other cases studied, the statewide industry appears capable of managing the problems examined

Environmental planning and the siting of nuclear facilities: the integration of water, air, coastal, and comprehensive planning into the nuclear siting process. Improving regulatory effectiveness in federal/state siting actions

International Nuclear Information System (INIS)

Noble, J.B.; Epting, J.T.; Blumm, M.C.; Ackerman, S.; Laist, D.W.

1977-02-01

The National Environmental Policy Act, the Coastal Zone Management Act, the Federal Water Pollution Control Act, the Clean Air Act Amendments, and the Housing and Urban 701 Comprehensive Planning Assistance Program are discussed in relation to the planning and siting of nuclear facilities

Cascade air stripping: Techno-economic evaluation of a new ground water treatment process

International Nuclear Information System (INIS)

Nirmalakhandan, N.; Peace, G.L.; Shanbhag, A.R.; Speece, R.E.

1992-01-01

A simple modification of the conventional air-stripping process introduced as cascade air stripping is proposed for efficient and economical removal of semivolatile and low volatility contaminants from ground water. The technical feasibility and economic viability of this process are evaluated using field test results and cost model simulations. The field tests enabled the process model to be verified at various water flow rates ranging from 150 gpm to 400 gpm. The field study also demonstrated the feasibility of the proposed system at a near full-scale level. Cost models were used to compare the proposed process to conventional air stripping and granular-activated carbon adsorption in removing a range of contaminants. This analysis showed that the treatment cost (cents/1,000 gal) of cascade air stripping is about 15% lower than conventional air stripping and about 40% lower than granular-activated carbon adsorption

Nuclear energy worldwide

International Nuclear Information System (INIS)

Fertel, M.

2000-01-01

In this short paper the author provides a list of tables and charts concerning the nuclear energy worldwide, the clean air benefits of nuclear energy, the nuclear competitiveness and the public opinion. He shows that the nuclear energy has a vital role to play in satisfying global energy and environmental goals. (A.L.B)

Animal Effects from Soviet Atmospheric Nuclear Tests

Science.gov (United States)

2008-03-01

describes the effect on animal models of atmospheric nuclear weapons tests performed by the Soviet Union at the Semipalatinsk Test Site . Part I describes...understand the pathogenic mechanisms of injury and the likelihood of efficacy of proposed treatment measures. 15. SUBJECT TERMS Semipalatinsk Test Site ...the Semipalatinsk Test Site . Part 1 describes the air blast and thermal radiation effects. Part 2 covers the effects of primary (prompt) radiation and

Counting systems characterization for air activity measurements

International Nuclear Information System (INIS)

Vijayakumar, B.; Balamurugan, M.; Ravi, P.M.

2018-01-01

Air activity measurements are carried out continuously at all the nuclear power plant (NPP) sites both during pre-operational phase and also during operation of nuclear facility. These measurements provide a trend line for the background air activity in the surrounding environments of an operating NPP. Any increase in air activity over the benchmark level becomes very handy to investigate the releases from the station and to give feedback to the operators of NPP about the prevailing air activity levels and their correlation to the plant releases. This paper compiles the results obtained for air filter samples using different counters operating in GM region and also plastic scintillators

Treatment Wetland Aeration without Electricity? Lessons Learned from the First Experiment Using a Wind-Driven Air Pump

Directory of Open Access Journals (Sweden)

Johannes Boog

2016-11-01

Full Text Available Aerated treatment wetlands have become an increasingly recognized technology for treating wastewaters from domestic and various industrial origins. To date, treatment wetland aeration is provided by air pumps which require access to the energy grid. The requirement for electricity increases the ecological footprint of an aerated wetland and limits the application of this technology to areas with centralized electrical infrastructure. Wind power offers another possibility as a driver for wetland aeration, but its use for this purpose has not yet been investigated. This paper reports the first experimental trial using a simple wind-driven air pump to replace the conventional electric air blowers of an aerated horizontal subsurface flow wetland. The wind-driven air pump was connected to a two-year old horizontal flow aerated wetland which had been in continuous (24 h aeration since startup. The wind-driven aeration system functioned, however it was not specifically adapted to wetland aeration. As a result, treatment performance decreased compared to prior continuous aeration. Inconsistent wind speed at the site may have resulted in insufficient pressure within the aeration manifold, resulting in insufficient air supply to the wetland. This paper discusses the lessons learned during the experiment.

Measurement of 131I activity in air indoor Polish nuclear medical hospital as a tool for an internal dose assessment.

Science.gov (United States)

Brudecki, K; Szczodry, A; Mróz, T; Kowalska, A; Mietelski, J W

2018-03-01

This paper presents results of 131 I air activity measurements performed within nuclear medical hospitals as a tool for internal dose assessment. The study was conducted at a place of preparation and administration of 131 I ("hot room") and at a nurse station. 131 I activity measurements were performed for 5 and 4 consecutive working days, at the "hot room" and nurse station, respectively. Iodine from the air was collected by a mobile HVS-30 aerosol sampler combined with a gas sampler. Both the gaseous and aerosol fractions were measurement. The activities in the gaseous fraction ranged from (28 ± 1 Bq m -3 ) to (492 ± 4) Bq m -3 . At both sampling sites, the activity of the gaseous iodine fraction trapped on activated charcoal was significantly higher than that of the aerosol fraction captured on Petrianov filter cloth. Based on these results, an attempt has been made to estimate annual inhalation effective doses, which were found to range from 0.47 mSv (nurse female) to 1.3 mSv (technician male). The highest annual inhalation equivalent doses have been found for thyroid as 32, 27, 13, and 11 mSv, respectively, for technician male, technical female, nurse male, and nurse female. The method presented here allows to fill the gaps in internal doses measurements. Moreover, because method has been successful used for many years in radioactive contamination monitoring of air in cases of serious nuclear accidents, it should also be used in nuclear medicine.

Effect of polyphenol oxidase (PPO and air treatments on total phenol and tannin content of cocoa nibs

Directory of Open Access Journals (Sweden)

Brito Edy Sousa de

2002-01-01

Full Text Available Cocoa flavour is greatly influenced by polyphenols. These compounds undergo a series of transformations during cocoa processing leading to the characteristic cocoa flavour. The use of exogenous polyphenol oxidase (PPO proved to be useful to reduce polyphenol content in cocoa nibs. The effect of a PPO associated or not with air over total phenol and tannin content was evaluated. Cocoa nibs were autoclaved and treated with a PPO or water in the absence or presence of an air flow for 0.5, 1, 2 and 3 hours. Total phenol content was reduced in PPO or water treatments, but when associated with air there was an increase in phenol content. Tannin content was reduced only by the treatment with water and air.

Biomonitoring of air pollution in Jamaica through trace-element analysis of epiphytic plants using nuclear and related analytical techniques

International Nuclear Information System (INIS)

Vutchkov, Mitko

2001-01-01

The main goal of the Coordinated Research Project (No:9937/R0), entitled 'Biomonitoring of Air Pollution in Jamaica Through Trace-Element Analysis of Epiphytic Plants Using Nuclear and Related Analytical Techniques', is to identify and validate site specific epiphytic plants for biomonitoring the atmospheric pollution in Jamaica using nuclear analytical techniques at the International Centre for Environmental and Nuclear Sciences (ICENS). The specific objectives for the second year of the project were: Development of HOP for sampling epiphytic plants in Jamaica; Sampling design and sample collection; Sample preparation and analysis; Development of an in-house SRM and participation in the NAT-5 inter-laboratory study; Data analysis and interpretation of the results; Development of a work plan of the third year of the project

Spent nuclear fuel storage vessel

International Nuclear Information System (INIS)

Watanabe, Yoshio; Kashiwagi, Eisuke; Sekikawa, Tsutomu.

1997-01-01

Containing tubes for containing spent nuclear fuels are arranged vertically in a chamber. Heat releasing fins are disposed horizontal to the outer circumference of the containing tubes for rectifying cooling air and promoting cooling of the containing tubes. Louvers and evaporation sides of heat pipes are disposed at a predetermined distance in the chamber. Cooling air flows from an air introduction port to the inside of the chamber and takes heat from the containing tubes incorporated with heat generating spent nuclear fuels, rising its temperature and flows off to an air exhaustion exit. The direction for the rectification plate of the louver is downward from a horizontal position while facing to the air exhaustion port. Since the evaporation sides of the heat pipes are disposed in the inside of the chamber and the condensation side of the heat pipes is disposed to the outside of the chamber, the thermal energy can be recovered from the containing tubes incorporated with spent nuclear fuels and utilized. (I.N.)

Copper Doping of Zinc Oxide by Nuclear Transmutation

Science.gov (United States)

2014-03-27

Copper Doping of Zinc Oxide by Nuclear Transmutation THESIS Matthew C. Recker, Captain, USAF AFIT-ENP-14-M-30 DEPARTMENT OF THE AIR FORCE AIR...NUCLEAR TRANSMUTATION THESIS Presented to the Faculty Department of Engineering Physics Graduate School of Engineering and Management Air Force...COPPER DOPING OF ZINC OXIDE BY NUCLEAR TRANSMUTATION Matthew C. Recker, BS Captain, USAF Approved: //signed// 27 February 2014 John W. McClory, PhD

Treatment and recycling of spent nuclear fuel. Actinide partitioning - Application to waste management

International Nuclear Information System (INIS)

Abonneau, E.; Baron, P.; Berthon, C.; Berthon, L.; Beziat, A.; Bisel, I.; Bonin, L.; Bosse, E.; Boullis, B.; Broudic, J.C.; Charbonnel, M.C.; Chauvin, N.; Den Auwer, C.; Dinh, B.; Duhamet, J.; Escleine, J.M.; Grandjean, S.; Guilbaud, P.; Guillaneux, D.; Guillaumont, D.; Hill, C.; Lacquement, J.; Masson, M.; Miguirditchian, M.; Moisy, P.; Pelletier, M.; Ravenet, A.; Rostaing, C.; Royet, V.; Ruas, A.; Simoni, E.; Sorel, C.; Vaudano, A.; Venault, L.; Warin, D.; Zaetta, A.; Pradel, P.; Bonin, B.; Bouquin, B.; Dozol, M.; Lecomte, M.; Forestier, A.; Beauvy, M.; Berthoud, G.; Defranceschi, M.; Ducros, G.; Guerin, Y.; Latge, C.; Limoge, Y.; Madic, C.; Santarini, G.; Seiler, J.M.; Sollogoob, P.; Vernaz, E.; Bazile, F.; Parisot, J.P.; Finot, P.; Roberts, J.F.

2008-01-01

subsequent to its in-reactor dwell time, spent fuel still contains large amounts of materials that are recoverable, for value-added energy purposes (uranium, plutonium), together with fission products, and minor actinides, making up the residues from nuclear reactions. The treatment and recycling of spent nuclear fuel, as implemented in France, entail that such materials be chemically partitioned. The development of the process involved, and its deployment on an industrial scale stand as a high achievement of French science, and technology. Treatment and recycling allow both a satisfactory management of nuclear waste to be implemented, and substantial savings, in terms of fissile material. Bolstered of late as it has been, due to spectacularly skyrocketing uranium prices, this strategy is bound to become indispensable, with the advent of the next generation of fast reactors. This Monograph surveys the chemical process used for spent fuel treatment, and its variants, both current, and future. It outlines currently ongoing investigations, setting out the challenges involved, and recent results obtained by CEA. (authors)

Treatment and recycling of spent nuclear fuel. Actinide partitioning - Application to waste management

Energy Technology Data Exchange (ETDEWEB)

Abonneau, E.; Baron, P.; Berthon, C.; Berthon, L.; Beziat, A.; Bisel, I.; Bonin, L.; Bosse, E.; Boullis, B.; Broudic, J.C.; Charbonnel, M.C.; Chauvin, N.; Den Auwer, C.; Dinh, B.; Duhamet, J.; Escleine, J.M.; Grandjean, S.; Guilbaud, P.; Guillaneux, D.; Guillaumont, D.; Hill, C.; Lacquement, J.; Masson, M.; Miguirditchian, M.; Moisy, P.; Pelletier, M.; Ravenet, A.; Rostaing, C.; Royet, V.; Ruas, A.; Simoni, E.; Sorel, C.; Vaudano, A.; Venault, L.; Warin, D.; Zaetta, A.; Pradel, P.; Bonin, B.; Bouquin, B.; Dozol, M.; Lecomte, M.; Forestier, A.; Beauvy, M.; Berthoud, G.; Defranceschi, M.; Ducros, G.; Guerin, Y.; Latge, C.; Limoge, Y.; Madic, C.; Santarini, G.; Seiler, J.M.; Sollogoob, P.; Vernaz, E.; Bazile, F.; Parisot, J.P.; Finot, P.; Roberts, J.F

2008-07-01

subsequent to its in-reactor dwell time, spent fuel still contains large amounts of materials that are recoverable, for value-added energy purposes (uranium, plutonium), together with fission products, and minor actinides, making up the residues from nuclear reactions. The treatment and recycling of spent nuclear fuel, as implemented in France, entail that such materials be chemically partitioned. The development of the process involved, and its deployment on an industrial scale stand as a high achievement of French science, and technology. Treatment and recycling allow both a satisfactory management of nuclear waste to be implemented, and substantial savings, in terms of fissile material. Bolstered of late as it has been, due to spectacularly skyrocketing uranium prices, this strategy is bound to become indispensable, with the advent of the next generation of fast reactors. This Monograph surveys the chemical process used for spent fuel treatment, and its variants, both current, and future. It outlines currently ongoing investigations, setting out the challenges involved, and recent results obtained by CEA. (authors)

Adsorption onto activated carbons in environmental engineering: some trends in water and air treatment processes

Energy Technology Data Exchange (ETDEWEB)

Le Cloirec, P. [Ecole des Mines de Nantes, UMR CNRS 6144 GEPEA, 44 (France)

2005-07-01

Full text of publication follows: Adsorption is commonly used in environmental protection processes and particularly in water and air treatment systems. Organic pollutants in aqueous or gaseous phases are transferred and adsorbed onto porous materials. Activated carbon (powder, grains) treatment is usually carried out and filters are used to eliminate volatile organic compounds (VOC), odors or micropollutants. The main objectives of this paper are to present examples of classical or new activated carbon processes used in drinking water production, wastewater purification or in air treatment in terms of processes, performances and modeling. - Water treatment: Micropollutants such as pesticides, herbicides... are classically removed by activated carbon granular systems in drinking water treatment plants. In order to get a good water quality and to safe money, the breakthrough time has to be accurately determined. Models with mass balance and transfer equations are proposed. However, some difficulties are found especially for complex solutions to get good agreement between experimental data and calculated values. A statistical approach using neural networks is proposed to simulate breakthrough curves. Examples are presented and compared to deterministic models. In order to intensify processes, a combination of ultrafiltration and activated carbon fiber cloth (ACFC) is presented to remove the large spectra of particles and organic molecules present in water. Systems (UF/ACFC) for surface water and industrial colored wastewater are applied and performances are determined as a function of operating conditions. - Air treatment: Activated carbon grain filters are used to control VOC emissions. Due to an exothermic reaction, an increase of local temperature in the reactor is noted and some fire accidents have been reported. For safety technologies, this temperature has to be previously determined. A model is proposed to simulate the breakthrough curves and temperatures

Adsorption onto activated carbons in environmental engineering: some trends in water and air treatment processes

International Nuclear Information System (INIS)

Le Cloirec, P.

2005-01-01

Full text of publication follows: Adsorption is commonly used in environmental protection processes and particularly in water and air treatment systems. Organic pollutants in aqueous or gaseous phases are transferred and adsorbed onto porous materials. Activated carbon (powder, grains) treatment is usually carried out and filters are used to eliminate volatile organic compounds (VOC), odors or micropollutants. The main objectives of this paper are to present examples of classical or new activated carbon processes used in drinking water production, wastewater purification or in air treatment in terms of processes, performances and modeling. - Water treatment: Micropollutants such as pesticides, herbicides... are classically removed by activated carbon granular systems in drinking water treatment plants. In order to get a good water quality and to safe money, the breakthrough time has to be accurately determined. Models with mass balance and transfer equations are proposed. However, some difficulties are found especially for complex solutions to get good agreement between experimental data and calculated values. A statistical approach using neural networks is proposed to simulate breakthrough curves. Examples are presented and compared to deterministic models. In order to intensify processes, a combination of ultrafiltration and activated carbon fiber cloth (ACFC) is presented to remove the large spectra of particles and organic molecules present in water. Systems (UF/ACFC) for surface water and industrial colored wastewater are applied and performances are determined as a function of operating conditions. - Air treatment: Activated carbon grain filters are used to control VOC emissions. Due to an exothermic reaction, an increase of local temperature in the reactor is noted and some fire accidents have been reported. For safety technologies, this temperature has to be previously determined. A model is proposed to simulate the breakthrough curves and temperatures

Assessment of airborne bacteria and noroviruses in air emission from a new highly-advanced hospital wastewater treatment plant

DEFF Research Database (Denmark)

Uhrbrand, Katrine; Schultz, Anna Charlotte; Koivisto, A. J.

2017-01-01

Exposure to bioaerosols can pose a health risk to workers at wastewater treatment plants (WWTPs) and to habitants of their surroundings. The main objective of this study was to examine the presence of harmful microorganisms in the air emission from a new type of hospital WWTP employing advanced...... wastewater treatment technologies. Air particle measurements and sampling of inhalable bacteria, endotoxin and noroviruses (NoVs) were performed indoor at the WWTP and outside at the WWTP ventilation air exhaust, downwind of the air exhaust, and upwind of the WWTP. No significant differences were seen...... in particle and endotoxin concentrations between locations. Bacterial concentrations were comparable or significantly lower in the exhaust air than inside the WWTP and in the upwind reference. Bacterial isolates were identified using matrix-assisted laser desorption-ionization time-of-flight mass spectrometry...

Nuclear power

International Nuclear Information System (INIS)

Abd Khalik Wood

2005-01-01

This chapter discussed the following topics related to the nuclear power: nuclear reactions, nuclear reactors and its components - reactor fuel, fuel assembly, moderator, control system, coolants. The topics titled nuclear fuel cycle following subtopics are covered: , mining and milling, tailings, enrichment, fuel fabrication, reactor operations, radioactive waste and fuel reprocessing. Special topic on types of nuclear reactor highlighted the reactors for research, training, production, material testing and quite detail on reactors for electricity generation. Other related topics are also discussed: sustainability of nuclear power, renewable nuclear fuel, human capital, environmental friendly, emission free, impacts on global warming and air pollution, conservation and preservation, and future prospect of nuclear power

Unit for air decontamination

International Nuclear Information System (INIS)

Mariano H, E.

1991-02-01

To fulfill the applicable requirements of safety to the ventilation systems in nuclear facilities, it is necessary to make a cleaning of the air that hurtles to the atmosphere. For that which was designed and it manufactured an unit for decontamination of the air for the Pilot plant of production of Nuclear Fuel that this built one with national parts, uses Hepa national filters and the design can adapt for different dimensions of filters, also can be added a lodging for a prefilter or to adopt two Hepa filters. (Author)

Background air pollution studies in urban and rural areas of Bangladesh using nuclear-related analytical techniques

International Nuclear Information System (INIS)

Khan, A.H.; Khaliquzzaman, M.; Tarafdar, S.A.; Biswas, S.K.; Islam, A.

1994-01-01

The trace element constituents of aerosols such as Hg, Pb, Cd, Se, As, Cu, Zn, Cr, V, etc. are permanent pollutants affecting the biosphere and the general ecosystem. The measurements of these elements collected on air filters, in rainwater, and also in some bioindicators such as moss and lichen, can yield very significant information on the origin, transport, removal and deposition of these pollutants. A set of sensitive and precise nuclear-related and chemical methods such as PIXE, EDXRF, FAAS and DPASV have, therefore, been developed and applied to analyze a number of trace and minor elements in air particulates, coal fly ash, plant materials, moss and water. Further analytical developments would include INAA and TRXRF. Some of the results from air particulates (integral), coal fly ash and moss analyses are presented to illustrate the experience level of the Laboratory. A core programme of study on the trace element composition of aerosols from urban and rural atmosphere in Bangladesh has been planned for implementation within the framework of this CRP. 10 refs, 1 fig., 5 tabs

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.)

RadNet Radiological Air Monitoring Network

International Nuclear Information System (INIS)

Scott Telofski, J.; Askren, D.R.; Petko, Ch.M.; Fraass, R.G.

2010-01-01

The United States Environmental Protection Agency operates a national environmental radiation monitoring program called RadNet. RadNet monitors airborne particulates, precipitation, milk, and drinking water for radiation levels. The primary purpose of the original program in the 1950's and 1960's was to collect and analyze samples in various media to assess the effects of radioactive fallout from above-ground nuclear weapon testing. As above-ground testing diminished in the 1970's, the program, especially the air network, became critical in evaluating effects of other types of nuclear incidents, such as the nuclear reactor accident at Chernobyl, as well as monitoring trends in environmental radioactive contamination. The value of rapid data collection subsequent to such incidents led to the consideration of developing air monitors with radiation detectors and telecommunication equipment for real-time radiation measurement. The strengthened United States homeland security posture after 2001 led to production and installation of the current real-time RadNet air monitors. There are now 118 stationary, continuously operating air monitoring stations and 40 mobile air monitors for site specific monitoring. The stationary air monitors include radiation detectors, meteorological sensors, a high-volume air sampler, and communication devices for hourly data transfers. When unusual levels are detected, scientists download a full sodium iodide detector spectrum for analysis. The real-time data collected by RadNet stationary systems permit rapid identification and quantification of airborne nuclides with sufficient sensitivity to provide critical information to help determine protective actions. The data also may help to rapidly refine long-range radioactive plume models and estimate exposure to the population. This paper provides an overview of the airborne particulate monitoring conducted during above-ground nuclear weapon testing, summarizes the uses of data from the program

Nuclear law in progress; Derecho nuclear en evolución

Energy Technology Data Exchange (ETDEWEB)

Manóvil, Rafael Mariano [ed.

2014-07-01

The 21. AIDN / INLA Congress was organized by the International Nuclear Law Association, in Buenos Aires, between the October 20 and 23, 2014. In this event, were presented almost 50 papers about these subjects: radioactive sources, safety and licensing, radioactive waste management, radiation protection, nuclear transport, security and non-proliferation, nuclear liability and insurance, etc.

Dose factors to calculate the radiation exposure due to radioactive waste air from nuclear facilities

International Nuclear Information System (INIS)

Brenk, H.D.; Vogt, K.J.

1977-01-01

An evaluation of the environmental impact of nuclear plants according to paragraph 45 of the Radiation Protection Directive of the Federal Republic of Germany requires the calculation of dose conversion factors indicating the correlation between the contaminated medium and individual radiation exposure. The present study is to be conceived as a contribution to discussion on this subject. For the determination of radiation exposure caused by the waste air of nuclear plants, models are being specified for computing the dose conversion factors for the external exposure pathways of β-submersion, γ-submersion and γ-radiation from contaminated ground as well as the internal exposure pathways of inhalation and ingestion, which further elaborate and improve the models previously applied, especially as far as the ingestion pathway is concerned, which distinguishes between 6 major food categories. The computer models are applied to those radionuclides which are significan for nuclear emitters, in particular nuclear light-water power stations. The results obtained for the individual exposure pathways and affected organs are specified in the form of tables. For this purpose, calculations were first of all carried out for the so-called 'reference man'. The results can be transferred to population groups with different consumption habits (e.g. vegetarians) by the application of correction factors. The models are capable of being extended with a view to covering other age groups. (orig.) [de

The treatment of liquid effluents from the nuclear industry

International Nuclear Information System (INIS)

Carley-Macauly, K.W.

1983-01-01

This paper reviews the sources, and principles of management, of radioactive liquid wastes in the nuclear industry. The selection of processes for their treatment is based on consideration of the solution chemistry and of the total system for active waste disposal which must ensure that the activity or radiation dose arriving in the biosphere is kept within acceptable limits. Treatment processes aim primarily at concentration of the active species into a small volume, as by evaporation, selective ion exchange or precipitation. These well established methods have counterparts or developments among the more novel means of separation, such as membrane processes. (author)

Effects of atmospheric air plasma treatment of graphite and carbon felt electrodes on the anodic current from Shewanella attached cells.

Science.gov (United States)

Epifanio, Monica; Inguva, Saikumar; Kitching, Michael; Mosnier, Jean-Paul; Marsili, Enrico

2015-12-01

The attachment of electrochemically active microorganisms (EAM) on an electrode is determined by both the chemistry and topography of the electrode surface. Pre-treatment of the electrode surface by atmospheric air plasma introduces hydrophilic functional groups, thereby increasing cell attachment and electroactivity in short-term experiments. In this study, we use graphite and carbon felt electrodes to grow the model EAM Shewanella loihica PV-4 at oxidative potential (0.2 V vs. Ag/AgCl). Cell attachment and electroactivity are measured through electrodynamic methods. Atmospheric air plasma pre-treatment increases cell attachment and current output at graphite electrodes by 25%, while it improves the electroactivity of the carbon felt electrodes by 450%. Air plasma pre-treatment decreased the coulombic efficiency on both carbon felt and graphite electrodes by 60% and 80%, respectively. Microbially produced flavins adsorb preferentially at the graphite electrode, and air plasma pre-treatment results in lower flavin adsorption at both graphite and carbon felt electrodes. Results show that air plasma pre-treatment is a feasible option to increase current output in bioelectrochemical systems. Copyright © 2015 Elsevier B.V. All rights reserved.

Biomonitoring of air pollution in Jamaica through trace-element analysis of epiphytic plants using nuclear and related analytical techniques

International Nuclear Information System (INIS)

Vutchkov, M.; Lalor, G.C.; Preston, J.

1999-01-01

Air quality has been monitored at selected areas in Jamaica using high volume samplers. The results obtained, showed elevated levels of aluminium in bauxitic areas and very high lead concentrations in urban areas, from 5 to 35 times greater than in rural areas. The lower throughput of the conventional air particulate samplers however, restricts the air quality and health assessment on a nation-wide scale. Biomonitoring offers a cost-effective alternative to air-quality assessment if appropriate indicator species are chosen. The epiphytic lower plants such as lichens and mosses have been used as indicators of regional air quality in several European countries and USA. However, there is not enough studies on lichens and mosses in tropical countries, probably due to the lower occurrence of these species, which cover only 8% of the world's land surface. In Jamaica the epiphytic higher plants, represented by the genus Tillandsia are widely distributed, which make them along with the lichens and mosses potential site-specific bioindicators of air quality. The IAEA Co-ordinated Research Project entitled 'Biomonitoring of Air Pollution in Jamaica Through Trace-Element Analysis of Epiphytic Plants Using Nuclear And Related Analytical Techniques' will address these needs of the country. The primary purpose of the present study was to develop specific bioindicators of atmospheric air pollution in Jamaica, which will provide baseline information for health hazards assessment

Low-level radioactive wastes: Their treatment, handling, disposal

Energy Technology Data Exchange (ETDEWEB)

Straub, Conrad P [Robert A. Taft Sanitary Engineering Center, Radiological Health Research Activities, Cincinnati, OH(United States)

1964-07-01

The release of low level wastes may result in some radiation exposure to man and his surroundings. This book describes techniques of handling, treatment, and disposal of low-level wastes aimed at keeping radiation exposure to a practicable minimum. In this context, wastes are considered low level if they are released into the environment without subsequent control. This book is concerned with practices relating only to continuous operations and not to accidental releases of radioactive materials. It is written by use for those interested in low level waste disposal problems and particularly for the health physicist concerned with these problems in the field. It should be helpful also to water and sewage works personnel concerned with the efficiency of water and sewage treatment processes for the removal of radioactive materials; the personnel engaged in design, construction, licensing, and operation of treatment facilities; and to student of nuclear technology. After an introduction the following areas are discussed: sources, quantities and composition of radioactive wastes; collection, sampling and measurement; direct discharge to the water, soil and air environment; air cleaning; removal of radioactivity by water-treatment processes and biological processes; treatment on site by chemical precipitation , ion exchange and absorption, electrodialysis, solvent extraction and other methods; treatment on site including evaporation and storage; handling and treatment of solid wastes; public health implications. Appendices include a glossary; standards for protection against radiation; federal radiation council radiation protection guidance for federal agencies; site selection criteria for nuclear energy facilities.

Molecular-level removal of proteinaceous contamination from model surfaces and biomedical device materials by air plasma treatment.

Science.gov (United States)

Banerjee, K K; Kumar, S; Bremmell, K E; Griesser, H J

2010-11-01

Established methods for cleaning and sterilising biomedical devices may achieve removal of bioburden only at the macroscopic level while leaving behind molecular levels of contamination (mainly proteinaceous). This is of particular concern if the residue might contain prions. We investigated at the molecular level the removal of model and real-life proteinaceous contamination from model and practical surfaces by air plasma (ionised air) treatment. The surface-sensitive technique of X-ray photoelectron spectroscopy (XPS) was used to assess the removal of proteinaceous contamination, with the nitrogen (N1s) photoelectron signal as its marker. Model proteinaceous contamination (bovine serum albumin) adsorbed on to a model surface (silicon wafer) and the residual proteinaceous contamination resulting from incubating surgical stainless steel (a practical biomaterial) in whole human blood exhibited strong N1s signals [16.8 and 18.5 atomic percent (at.%), respectively] after thorough washing. After 5min air plasma treatment, XPS detected no nitrogen on the sample surfaces, indicating complete removal of proteinaceous contamination, down to the estimated XPS detection limit 10ng/cm(2). Applying the same plasma treatment, the 7.7at.% nitrogen observed on a clinically cleaned dental bur was reduced to a level reflective of new, as-received burs. Contact angle measurements and atomic force microscopy also indicated complete molecular-level removal of the proteinaceous contamination upon air plasma treatment. This study demonstrates the effectiveness of air plasma treatment for removing proteinaceous contamination from both model and practical surfaces and offers a method for ensuring that no molecular residual contamination such as prions is transferred upon re-use of surgical and dental instruments. Crown Copyright © 2010. Published by Elsevier Ltd. All rights reserved.

State-of-the-art of the installations, equipments and human resources of nuclear medicine in Argentina

International Nuclear Information System (INIS)

Chiliutti, Claudia A.

2004-01-01

The current situation of nuclear medicine in Argentina, taking into account the facilities, their equipment and human resources available is presented in this paper. A review and analysis of the equipment, including technical characteristics and a survey of the professionals and technicians of the area, was carried out . In Argentina, there are 292 centers of nuclear medicine distributed all over the country. The operating licenses are granted by the Nuclear Regulatory Authority. Forty percent of the installed equipment are SPECT of 1 or 2 heads and 40 % are gamma camera. Besides, there are two PET operating in Argentina. There are 402 nuclear medicine physicians with individual permit for diagnostic purposes and 50% of them has also individual permit for treatment purposes. With the purpose of analyzing the regional distribution of the available resources in nuclear medicine, the country was divided into 7 geographical regions: City of Buenos Aires, Province of Buenos Aires, Pampeana, Cuyo, Northeast, Northwest and Patagonia. From the analysis of the gathered information it is possible to conclude that the nuclear medicine equipment as well as the personnel presents an irregular distribution, with a major concentration in the City of Buenos Aires and Province of Buenos Aires. The Northeast region presents the lowest number of Nuclear Medicine centers and the Patagonia region has the lowest number of nuclear medicine physicians with individual permits. The number of SPECT and gamma cameras is 8,65 per million of inhabitants. The information about the available resources in nuclear medicine presented in this paper and its comparison with the international available information provide elements for a better planning of the future activities in the area not only for the operators but also from the regulatory point of view. (author)

Principles of radiologic physics, dosimetry, and treatment planning

International Nuclear Information System (INIS)

Purdy, J.A.; Lightfoot, D.A.; Glasgow, G.P.

1987-01-01

A solid foundation in the principles of radiologic physics, dosimetry, and treatment planning is essential for the practice of radiation oncology. In this chapter, the authors consider several topics that lay the foundation for the material covered other chapters. Among the topics discussed here are atomic and nuclear structure; the production of x-rays; radioactivity; the interaction of x-rays with matter; radiation therapy treatment machines; the measurement of radiation exposure; the determination of absorbed dose; and definitions of various dosimetry parameters, such as percentage depth dose and tissue-air ratio. This chapter also discusses basic concepts used in calculations of dose and the standard correction methods used to account for air gaps and tissue inhomogeneities

Measurement of {sup 131}I activity in air indoor Polish nuclear medical hospital as a tool for an internal dose assessment

Energy Technology Data Exchange (ETDEWEB)

Brudecki, K.; Mietelski, J.W. [Polish Academy of Sciences, Institute of Nuclear Physics, Krakow (Poland); Szczodry, A.; Kowalska, A. [Department of Endocrinology and Nuclear Medicine Holycross Cancer Center, Kielce (Poland); Mroz, T. [Pedagogical University in Cracow, Krakow (Poland)

2018-03-15

This paper presents results of {sup 131}I air activity measurements performed within nuclear medical hospitals as a tool for internal dose assessment. The study was conducted at a place of preparation and administration of {sup 131}I (''hot room'') and at a nurse station. {sup 131}I activity measurements were performed for 5 and 4 consecutive working days, at the ''hot room'' and nurse station, respectively. Iodine from the air was collected by a mobile HVS-30 aerosol sampler combined with a gas sampler. Both the gaseous and aerosol fractions were measurement. The activities in the gaseous fraction ranged from (28 ± 1 Bq m{sup -3}) to (492 ± 4) Bq m{sup -3}. At both sampling sites, the activity of the gaseous iodine fraction trapped on activated charcoal was significantly higher than that of the aerosol fraction captured on Petrianov filter cloth. Based on these results, an attempt has been made to estimate annual inhalation effective doses, which were found to range from 0.47 mSv (nurse female) to 1.3 mSv (technician male). The highest annual inhalation equivalent doses have been found for thyroid as 32, 27, 13, and 11 mSv, respectively, for technician male, technical female, nurse male, and nurse female. The method presented here allows to fill the gaps in internal doses measurements. Moreover, because method has been successful used for many years in radioactive contamination monitoring of air in cases of serious nuclear accidents, it should also be used in nuclear medicine. (orig.)

Effluent treatment options for nuclear thermal propulsion system ground tests

International Nuclear Information System (INIS)

Shipers, L.R.; Brockmann, J.E.

1992-01-01

A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the strengths and weaknesses of different methods to handle effluent from nuclear thermal propulsion system ground tests

Oxidation parameters of nuclear graphite for HTGR air-ingress

International Nuclear Information System (INIS)

Kim, E.S.; No, H.C.

2004-01-01

In order to investigate chemical behaviors of the graphite during an air-ingress accident in HTGR, the kinetic tests on nuclear graphite IG-110 were performed in chemical reaction dominant regime. In the present experiment, inlet gas flow rate ranged between 8 and 18 SLPM, graphite temperatures and oxygen mole fraction ranged from 540 to 630degC and from 3 to 30% respectively. The test section was made of a quartz tube having 75 mm diameter and 750 mm length and the test specimen machined to the size of 21 mm diameter and 30 mm length was supported at the center of it by the alumina rod. The 15 kW induction heater was installed around the outside of test section to heat the specimen and its temperature was measured by 2 infrared thermometers. The oxidation rate was calculated from the gas concentration analysis between inlet and outlet using NDIR (non-dispersive infrared) gas analyzer. As a result the activation energy (Ea) and the order of reaction (n) were determined within 95% confidence level and the qualitative characteristics of the two parameters were also widely investigated by experimental and analytical methods. (author)

The non-nuclear legislation and the communal property; La legislacion no nuclear y el bien comun

Energy Technology Data Exchange (ETDEWEB)

Ciallella R, Norberto; Grancelli Cha, Nestor

1996-07-01

Since 1984, year in which the Bolson Municipality, Rio Negro province, declared the town a 'Non Nuclear Area', began to appear an abundant legislation that generically, it is know as 'Non Nuclear'. The provinces of Buenos Aires, Chubut, Formosa, La Pampa, Santa Cruz and Tierra del Fuego, have in their respective Constitutions non nuclear articles, while the provinces of Catamarca, Cordoba, Corrientes, Chaco, Entre Rios, Formosa, Rio Negro, San Luis, Santa Cruz, Santa Fe, Tierra del Fuego and Tucuman have sanctioned in their respective jurisdictions non nuclear laws. New projects of these laws are in consideration and treatment in the provinces of Catamarca, La Pampa, Mendoza, Santiago del Estero and Rio Negro. The present work compiles and analyzes the available information on this subject. Although the topic is not regulatory, it could have involved in the regulatory area in an eventual situation that could be presented between regulatory laws of federal and provincials reaches. This work describes the current situation and the probabilities consequences of the mentioned legislation. (author)

Innovative waste treatment and conditioning technologies at nuclear power plants

International Nuclear Information System (INIS)

2006-05-01

The objective of this publication is to provide Member States with information on the most innovative technologies and strategies used in waste treatment and conditioning. At present, some of those technologies and strategies might not be widely implemented at nuclear power plants (NPP), but they have an important potential for their use as part of the long range NPP, utility, or national strategy. Thus, the target audience is those decision makers at the national and organizational level responsible for selecting waste processing technologies and strategies over a period of three to ten years. Countries and individual nuclear plants have limited financial resources which can be applied toward radioactive waste processing (treatment and conditioning). They are challenged to determine which of the many available technologies and strategies are best suited to meet national or local needs. This publication reduces the selection of processes for wastes generated by nuclear power plants to those technologies and strategies which are considered innovative. The report further identifies the key benefits which may derive from the adoption of those technologies, the different waste streams to which each technology is relevant, and the limitations of the technologies. The technologies and strategies identified have been evaluated to differentiate between (1) predominant technologies (those that are widely practiced in multiple countries or a large number of nuclear plants), and (2) innovative technologies (those which are not so widely used but are considered to offer benefits which make them suitable for broader application across the industry). Those which fall into the second category are the primary focus of this report. Many IAEA publications address the technical aspects of treatment and conditioning for radioactive wastes, covering research, technological advances, and safety issues. These studies and reports primarily target the research and technical staff of a

A brief history of the air cleaning conferences

International Nuclear Information System (INIS)

First, M.W.

1995-01-01

I have been asked to prepare a history of the air cleaning conferences. Undertaking such a task is, of course, a wonderful opportunity for reminiscences and a chance to retell old war stories. I must admit that it has taken much longer than I anticipated because I found myself so completely engrossed rereading the old records that time seemed to stop, although the hours passed. But a history of the nuclear air cleaning conferences means more than a stroll down memory lane. The 23 recorded air cleaning conference proceedings reflect an important aspect of the history of major nuclear developments, both military and civilian, because engineered safety features designed to prevent dispersion of radioactive products to the environment have always been a necessity for progress in this field. For this reason, I hope the history of the nuclear air cleaning conferences will not only be enjoyable, but also have meaning for young people entering this field. The air cleaning conferences were an outgrowth of the operations of the U.S. Atomic Energy Commission's (AEC) Stack Gas Working Group established in 1948 to review air cleaning operations at AEC installations. AEC's Division of Engineering sponsored and funded air cleaning research and development at Harvard University's School of Public Health, beginning about the same time. In addition to research and development, the Harvard contract called for consulting and educational services. The latter provided the opportunity for meetings devoted to information on air cleaning that could be applied to ongoing and anticipated nuclear operations

A brief history of the air cleaning conferences

Energy Technology Data Exchange (ETDEWEB)

First, M.W.

1995-02-01

I have been asked to prepare a history of the air cleaning conferences. Undertaking such a task is, of course, a wonderful opportunity for reminiscences and a chance to retell old war stories. I must admit that it has taken much longer than I anticipated because I found myself so completely engrossed rereading the old records that time seemed to stop, although the hours passed. But a history of the nuclear air cleaning conferences means more than a stroll down memory lane. The 23 recorded air cleaning conference proceedings reflect an important aspect of the history of major nuclear developments, both military and civilian, because engineered safety features designed to prevent dispersion of radioactive products to the environment have always been a necessity for progress in this field. For this reason, I hope the history of the nuclear air cleaning conferences will not only be enjoyable, but also have meaning for young people entering this field. The air cleaning conferences were an outgrowth of the operations of the U.S. Atomic Energy Commission`s (AEC) Stack Gas Working Group established in 1948 to review air cleaning operations at AEC installations. AEC`s Division of Engineering sponsored and funded air cleaning research and development at Harvard University`s School of Public Health, beginning about the same time. In addition to research and development, the Harvard contract called for consulting and educational services. The latter provided the opportunity for meetings devoted to information on air cleaning that could be applied to ongoing and anticipated nuclear operations.

Determination and behaviour of plutonium emitted with liquid effluents and exhaust air into the environment of the Nuclear Research Centre Karlsruhe

International Nuclear Information System (INIS)

Schuettelkopf, H.; Pimpl, M.

1986-01-01

The plutonium concentrations in the surroundings of the Karlsruhe Nuclear Research Centre (KfK) are in the range of variation of the global plutonium contamination caused by fallout of atmospheric nuclear tests. Exclusively in the sediments of the Old River Rhine, which serves as main canal for the liquid effluents, higher plutonium concentrations could be detected. The dose exposure of the population living in the environment of the KfK caused by the measured plutonium concentrations is negligible low. From the Karlsruhe Reprocessing Plant (WAK) and the facilities needed to decontaminate radioactive wastes 0.48 GBq (13 mCi) plutonium alpha activity has been emitted within 11 years of operation until 1982 - 1/3 with the liquid effluents and 2/3 with the exhaust air. Following the pathway with the exhaust air, plutonium concentrations in the environment of the Karlsruhe Reprocessing Plant were measured in groundlevel air, in soil, in plants, in food and in animal tissues. Radioecological parameters like dispersion factors, deposition velocities, migration velocities in soil and transfer soil-to-plant were investigated. Following the pathway with the liquid effluents, plutonium concentrations were measured in surface waters, sediments, water plants, plankton and animals. Dilution and sedimentation behaviour were studied as well as the transfer water-to-plant and water-to-animals. (orig.) [de

An overview of the RCA/IAEA activities in the Australasian region using nuclear analysis techniques for monitoring air pollution

International Nuclear Information System (INIS)

Markwitz, Andreas

2005-01-01

The International Atomic Energy Agency (IAEA) via the Regional Co-operative Agreement (RCA) has identified air particulate matter pollution as a major transboundary environmental issue in the Australasian region. Sixteen countries in the region spanning from Pakistan to the Philippines and from China to New Zealand are participating in the regional programme RAS/7/013-Improved information of urban air quality management in the RCA region' that started in 1997. New Zealand is the lead-country for this programme in which nuclear analytical techniques, such as particle induced X-ray emission (PIXE), neutron activation analysis (NAA) and X-ray fluorescence spectrometry (XRF) are used to measure key elements in PM 2.5-0 and PM 10-2.5 filters from GENT stacked samplers collected twice weekly. Major sources of air particulate matter pollution are identified using statistical source apportionment techniques. To identify transboundary air particulate matter pollution events, the data is collated in a large database. Additionally, the data is used by end-users of the participating countries in the programme. An overview is presented. (author)

Prospects of electron beam treatment of flue gases in the Philippines

International Nuclear Information System (INIS)

Cabalfin, Estelita G.

2005-01-01

Coal-fired and oil-based power plants operated in Philippines are totally 11 and 58 units respectively. The government recognizes the threat of air pollution, because more than one third of the electricity generation is fueled by coal. The Philippines Congress therefore enacted Republic Act 8749 (Clean Air Act of 1999) under which sulfur and nitrogen oxides concentration at the point of emission from stationary sources shall be strictly regulated. Under the UNDP/IAEA regional project on industrial application of radiation, the Philippine Nuclear Research Institute (PNRI) in cooperation with the National Power Corporation hosted two national executive management seminars on electron beam treatment of flue gases in 1990 and 1994. The Philippine Smelting and Refining Corporation (PASAR) has interest in this technology of reducing 90% SO 2 removal efficiency with EB power of 380 kW. PNRI promotes, through training courses and seminars, the applications of nuclear technology and radiation including EB treatment of flue gases. (S. Ohno)

The Structure Characteristics and Air Permeability of PA and PES Plain and Plated Knits Influenced of Antimicrobial Treatment Conditions

Directory of Open Access Journals (Sweden)

Agne MICKEVIČIENĖ

2014-09-01

Full Text Available Textile materials are usually exposed to thermal, physical and mechanical effects during treatment processes. These influence the changes of material dimensions. Designing knitted products it is important to predict direction and rate of dimensions change, because this can affect physical properties such as air permeability of knits. The objective of this research was to investigate the influence of antimicrobial treatment conditions on the structure characteristics, thickness and air permeability of plain and plaited knits. The investigations were carried out with two groups of plain and plated single jersey knits. The face yarns of these groups were cotton, bamboo viscose yarn and polyester (Dacron® thread. 10 tex × 2 textured polyamide (PA and 20 tex textured polyester (PES threads were used as the base threads in plated knits. Knitted samples were treated with antimicrobial material Isys AG and organic-inorganic binder Isys MTX (CHT, Germany. It was established that blank and antimicrobial treated knits changed structure parameters, thickness and air permeability. The changes of structure parameters, thickness and air permeability were more associated with conditions of treatment (temperature, treatment in solution, mechanical action rather than with antimicrobial and sol-gel substances used in treatment. DOI: http://dx.doi.org/10.5755/j01.ms.20.3.3196

Ultralow Level Mercury Treatment Using Chemical Reduction and Air Stripping: Scoping Report

International Nuclear Information System (INIS)

Looney, B.B.

2000-01-01

Data collected during the first stage of a Savannah River Technology Center (SRTC) Strategic Research and Development Project confirmed the efficacy of chemical reduction and air stripping/sparging as an ultralow level mercury treatment concept for waters containing Hg(II). The process consists of dosing the water with low levels of stannous chloride to convert the mercury to Hg. This form of mercury can easily be removed from the water by air stripping or sparging. Samples of Savannah River Site (SRS) groundwater containing approximately 130 ng/L of total mercury (as Hg(II)) were used for the study. In undosed samples, sparging removed 0 percent of the initial mercury. In the dosed samples, all of the removals were greater than 94 percent, except in one water type at one dose. This sample, which was saturated with dissolved oxygen, showed a 63 percent reduction in mercury following treatment at the lowest dose. Following dosing at minimally effective levels and sparging, treated water contained less than 10 ng/L total mercury. In general, the data indicate that the reduction of mercury is highly favored and that stannous chloride reagent efficiently targets the Hg(II) contaminant in the presence of competing reactions. Based on the results, the authors estimated that the costs of implementing and operating an ultralow level mercury treatment process based on chemical reduction and stripping/sparging are 10 percent to 20 percent of traditional treatment technologies

Application of CPML to two-dimension numerical simulation of nuclear electromagnetic pulse from air explosions

International Nuclear Information System (INIS)

Gao Chunxia; Wang Lianghou

2005-01-01

The characteristics of different types of PML were analyzed and the convolutional PML was chosen to truncate the open boundaries in numerical simulation of nuclear electromagnetic pulse from air explosions. On the basis of the split-field PML and the plane-wave solution of electromagnetic field in free space, the unsplit-field PML was constructed. By applying the convolutional theorem of Fourier transform, the discrete iterative equations of electromagnetic field components were presented in the CPML media under the two-dimension prolate-spheroidal coordinate system. The numerical results indicate that the method of CPML can largely decrease calculation errors of boundary fields. (authors)

Order of 31 July 1987 on protection and control of nuclear materials carried by air

International Nuclear Information System (INIS)

1987-01-01

This Order is part of a series of texts on protection and control of nuclear materials which include: the Act of 25 July 1980 and the Decree of 12 May 1981 made in its implementation and, as regards the specific aspect of protection and control of materials during transport, the Order of 26 March 1982 amended in 1986. The 1987 Order lays down the conditions which must be complied with by approved carriers (the French or the foreign holders of a licence under the above-mentioned Act of 1980) in case of transport of such materials by air [fr

Benzo[a]pyrene treatment leads to changes in nuclear protein expression and alternative splicing

Energy Technology Data Exchange (ETDEWEB)

Yan Chunlan; Wu Wei [Department of Toxicology, Zhejiang University School of Public Health, 388 Yu-Hang-Tang Road, Hangzhou, Zhejiang 310058 (China); Li Haiyan [Department of Toxicology, Zhejiang University School of Public Health, 388 Yu-Hang-Tang Road, Hangzhou, Zhejiang 310058 (China); Huzhou Maternity and Child Care Hospital, Huzhou, Zhejiang 313000 (China); Zhang Guanglin [Department of Toxicology, Zhejiang University School of Public Health, 388 Yu-Hang-Tang Road, Hangzhou, Zhejiang 310058 (China); Duerksen-Hughes, Penelope J. [Department of Basic Sciences, Loma Linda University School of Medicine, Loma Linda, CA 92354 (United States); Zhu Xinqiang, E-mail: zhuxq@zju.edu.cn [Department of Toxicology, Zhejiang University School of Public Health, 388 Yu-Hang-Tang Road, Hangzhou, Zhejiang 310058 (China); Yang Jun, E-mail: gastate@zju.edu.cn [Department of Toxicology, Zhejiang University School of Public Health, 388 Yu-Hang-Tang Road, Hangzhou, Zhejiang 310058 (China); Zhejiang-California International Nanosystems Institute, Hangzhou, Zhejiang 310029 (China)

2010-04-01

Benzo[a]pyrene (BaP) is a potent pro-carcinogen generated from the combustion of fossil fuel and cigarette smoke. Previously, using a proteomic approach, we have shown that BaP can induce changes in the expression of many cellular proteins, including transcription regulators. In the present study, using a similar approach, we examined the nuclear protein response to BaP in HeLa cells and found that BaP treatment caused expression changes in many nuclear proteins. Twenty-four of these proteins were successfully identified, several of which are involved in the alternative splicing of mRNA, DNA replication, recombination, and repair. The changed expression levels were further confirmed by immunoblot analysis using specific antibodies for two proteins, Lamin A and mitotic checkpoint protein Bub3. The nuclear localization of these two proteins was also confirmed by confocal microscopy. To determine whether alternative splicing was activated following BaP treatment, we examined Fas and CD44, two genes previously shown to be targets of alternative splicing in respond to DNA damage. While no significant activation of alternative splicing was observed for Fas, CD44 splicing variants were found after BaP treatment. Together, these data show that DNA damage induces dramatic changes in nuclear protein expression, and that alternative splicing might be involved in the cellular response to DNA damage.

Spent nuclear fuel storage device and spent nuclear fuel storage method using the device

International Nuclear Information System (INIS)

Tani, Yutaro

1998-01-01

Storage cells attachably/detachably support nuclear fuel containing vessels while keeping the vertical posture of them. A ventilation pipe which forms air channels for ventilating air to the outer circumference of the nuclear fuel containing vessel is disposed at the outer circumference of the nuclear fuel containing vessel contained in the storage cell. A shielding port for keeping the support openings gas tightly is moved, and a communication port thereof can be aligned with the upper portion of the support opening. The lower end of the transporting and containing vessel is placed on the shielding port, and an opening/closing shutter is opened. The gas tightness is kept by the shielding port, the nuclear fuel containing vessel filled with spent nuclear fuels is inserted to the support opening and supported. Then, the support opening is closed by a sealing lid. (I.N.)

Seismic evaluation of nuclear installations; Avaliacao sismica de instalacoes nucleares

Energy Technology Data Exchange (ETDEWEB)

Mattar Neto, Miguel [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

1997-10-01

Some considerations regarding extreme external events, natural or man-induce, such as earthquakes, floods, air crashes, etc, shall be done for nuclear facilities to minimizing the potential impact of the installation on the public and the environment. In this paper the main aspects of the seismic evaluation of nuclear facilities (except the nuclear power reactors) will be presented based on different codes and standards. (author). 7 refs., 2 tabs.

Future-proof radioactive waste treatment technologies for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Buettner, Klaus; Braehler, Georg [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany)

2014-08-15

In order to select the optimal treatment method for radioactive waste three options can be considered. First, to treat the radioactive waste only to allow long term interim storage until the waste acceptance criteria are defined and the disposal sites are operable. Second, to select treatment methods just in compliance with the current state of discussion with the regard to the above. Third, taking also the future development in the field of waste acceptance criteria and disposal into account. When developing waste treatment systems for Nuclear Power Plants NUKEM Technologies follows the following targets, minimisation of the amount of radioactive waste, maximisation of free release material, volume reduction, avoidance of unwanted materials in the waste package, as well as efficient waste treatment solutions (low investment, high volume reduction). With its technologies produced waste packages fulfil the most stringent waste acceptance criteria.

POTENTIAL FOR HYDROGEN BUILDUP IN HANFORD SEALED AIR FILLED NUCLEAR STORAGE VESSELS

International Nuclear Information System (INIS)

HEY BE

2008-01-01

This calculation is performed in accordance with HNF-PRO-8259, PHMC Calculation Preparation and Issue and addresses the question as to whether a flammable mixture of hydrogen gas can accumulate in a Hanford sealed nuclear storage vessel where the only source of hydrogen is the moisture in the air that initially filled the vessel Of specific concern is nuclear fuel inside IDENT 69-Gs, placed in Core Component Containers (CCCs) located inside Interim Storage Vaults (ISVs) at the Plutonium Finishing Plant (PFP) The CCCs are to be removed from the ISVs and placed inside a Hanford Unirradiated Fuel Package (HUFP) for transport and interim storage. The repackaging procedures mandated that no plastics were permitted, all labels and tape were to be removed and the pins to be clean and inspected Loading of the fuel into the CCC/ISV package was permitted only if it was not raining or snowing. This was to preclude the introduction of any water The purpose was to minimize the presence of any hydrogenous material inside the storage vessels. The scope of NFPA 69, 'Standard on Explosion Prevention Systems', precludes its applicability for this case. The reactor fuel pins are helium bonded. The non-fuel pins, such as the pellet stacks, are also helium bonded. The fuel pellets were sintered at temperatures that preclude any residual hydrogenous material. Hydrogen gas can be formed from neutron and gamma radiolysis of water vapor. The radiolysis reaction is quite complex involving several intermediate radicals, and competing recombination reactions. Hydrogen gas can also be formed through corrosion. This analysis takes a simplistic approach and assumes that all water vapor present in the storage vessel is decomposed into hydrogen gas. Although the analysis is needed to specifically address HUFP storage of nuclear fuel, it is equally applicable to any sealed fuel storage vessel under the assumptions listed

Safety-related control air systems

International Nuclear Information System (INIS)

Anon.

1977-01-01

This Standard applies to those portions of the control air system that furnish air required to support, control, or operate systems or portions of systems that are safety related in nuclear power plants. This Standard relates only to the air supply system(s) for safety-related air operated devices and does not apply to the safety-related air operated device or to air operated actuators for such devices. The objectives of this Standard are to provide (1) minimum system design requirements for equipment, piping, instruments, controls, and wiring that constitute the air supply system; and (2) the system and component testing and maintenance requirements

National emergency medical assistance program for commercial nuclear power plants

International Nuclear Information System (INIS)

Linnemann, R.E.; Berger, M.E.

1987-01-01

Radiation Management Consultant's Emergency Medical Assistance Program (EMAP) for nuclear facilities provides a twenty-four hour emergency medical and health physics response capability, training of site and off-site personnel, and three levels of care for radiation accident victims: first air and rescue at an accident site, hospital emergency assessment and treatment, and definitive evaluation and treatment at a specialized medical center. These aspects of emergency preparedness and fifteen years of experience in dealing with medical personnel and patients with real or suspected radiation injury will be reviewed

Effects of air dielectric barrier discharge plasma treatment time on surface properties of PBO fiber

International Nuclear Information System (INIS)

Wang Qian; Chen Ping; Jia Caixia; Chen, Mingxin; Li Bin

2011-01-01

In this paper, the effects of air dielectric barrier discharge (DBD) plasma treatment time on surface properties of poly(p-phenylene benzobisoxazole) (PBO) fiber were investigated. The surface characteristics of PBO fiber before and after the plasma treatments were analyzed by dynamic contact angle (DCA) analysis, scanning electron microscopy (SEM), atomic force microscopy (AFM) and X-ray photoelectron spectroscopy (XPS). DCA measurements indicated that the surface wettability of PBO fiber was improved significantly by increasing the fiber surface free energy via air DBD plasma treatments. The results were confirmed by the improvement of adhesion of a kind of thermoplastic resin to PBO fiber which was observed by SEM, showing that more resin was adhering evenly to the fiber surface. AFM measurement revealed that the surface topography of PBO fiber became more complicated and the surface roughness was greatly enhanced after the plasma treatments, and XPS analysis showed that some new polar groups (e.g. -O-C=O) were introduced on plasma treated PBO fiber surface. The results of this study also showed that the surface properties of PBO fiber changed with the elongation of plasma treatment time.

Nuclear law in progress

International Nuclear Information System (INIS)

Manóvil, Rafael Mariano

2014-01-01

The 21. AIDN / INLA Congress was organized by the International Nuclear Law Association, in Buenos Aires, between the October 20 and 23, 2014. In this event, were presented almost 50 papers about these subjects: radioactive sources, safety and licensing, radioactive waste management, radiation protection, nuclear transport, security and non-proliferation, nuclear liability and insurance, etc.

Retention of fission products in air filters

International Nuclear Information System (INIS)

Sobnack, R.

1986-01-01

The plume from the Chernobyl nuclear reactor reached London in the morning of 1st May. Less than two weeks later, the Physics Department, University of Surrey, reported a measurable level of radioactivity in air filters. On 15th May air filters from within the air conditioning plant of the Radioisotope Department at the London Hospital were removed for radiation checks. Crude tests with a geiger counter gave readings of 5-10 times higher than background levels. Gamma-ray spectroscopy of the departmental air filters (AF1) using a 127 mm NaI detector revealed a pattern characteristic of emissions of fission products from a nuclear reactor. Another air filter (AF2), from the home of a member of staff, was much less active. Because of the complexity of the gamma-ray spectrum and the relatively high level of emission from the departmental air filter, a thorough investigation was carried out using a high purity germanium detector. (author)

Relation between 222Rn concentration in outdoor air and lower atmosphere

International Nuclear Information System (INIS)

Kataoka, Toshio; Mori, Tadashige; Yunoki, Eiji; Michihiro, Kenshuh; Sugiyama, Hirokazu; Shimizu, Mitsuo; Tsukamoto, Osamu; Sahashi, Ken.

1991-01-01

Using the height of the surface-based inversion layer obtained by the acoustic sounder returns and the variation of the 222 Rn concentration in the outdoor air during the presence of the surface-based inversion layer, the exhalation rate of 222 Rn is estimated to be 0.020 Bq·m -2 ·s -1 , which is observed elsewhere on land. Furthermore, the exposure rate at 1 m above the air-ground interface due to the short-lived 222 Rn daughters in the outdoor air during the presence of the surface-based inversion layer can be estimated using the height of the surface-based inversion layer and the 222 Rn concentrations in the outdoor air at the ground level before and after the onset of the surface-based inversion layer. From these treatment, it is clearly demonstrated that the monostatic acoustic sounder is useful as a supplementary method for a weather survey which forms a part of monitoring around the nuclear facilities. (author)

Ignition properties of nuclear grade activated carbons

International Nuclear Information System (INIS)

Freeman, W.P.; Hunt, J.R.; Kovach, J.L.

1983-01-01

The ignition property of new activated carbons used in air cleaning systems of nuclear facilities has been evaluated in the past, however very little information has been generated on the behavior of aged, weathered carbons which have been exposed to normal nuclear facility environment. Additionally the standard procedure for evaluation of ignition temperature of carbon is performed under very different conditions than those used in the design of nuclear air cleaning systems. Data were generated evaluating the ageing of activated carbons and comparing their CH 3 131 I removal histories to their ignition temperatures. A series of tests were performed on samples from one nuclear power reactor versus use time, a second series evaluated samples from several plants showing the variability of atmospheric effects. The ignition temperatures were evaluated simulating the conditions existing in nuclear air cleaning systems, such as velocity, bed depth, etc., to eliminate potential confusion resulting from artifically set current standard conditions

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)

Respirator studies for the Nuclear Regulatory Commission. Protection factors for supplied-air respirators. Progress report, October 1, 1976--September 30, 1977

International Nuclear Information System (INIS)

Hack, A.; Bradley, O.D.; Trujillo, A.

1977-12-01

This report describes the work performed during FY 1977 for the Nuclear Regulatory Commission. The Protection Factors (efficiency) provided by 25 NIOSH approved supplied-air respirators were determined while the devices were worn by a panel of anthropometrically selected test subjects. The major recommendation was that demand-type respirators should neither be used nor approved

Air treatment techniques for abatement of emissions from intensive livestock production

OpenAIRE

Melse, R.W.

2009-01-01

Keywords: Air treatment; Scrubber; Bioscrubber; Biofilter; Biotrickling filter; Ammonia; NH3; Odour; Livestock production; Animal husbandry; Pig; Poultry. Intensive livestock production is connected with a number of environmental effects, including emissions of ammonia (NH3), greenhouse gases (CH4 and N2O), odour, and particulate matter (PM10 and PM2.5). Possible strategies for emission reduction from animal houses include feed management, adaptation of housing design, and the application o...

Ninth Argentine congress on biology and nuclear medicine; fourth Southernmost sessions of ALASBIMN (Latin-American Association of Biology and Nuclear Medicine); first Spanish-Argentine congress on nuclear medicine; first Argentine sessions on nuclear cardiology

International Nuclear Information System (INIS)

1991-01-01

This work deals with all the papers presented at the 9. Argentine congress on biology and nuclear medicine; IV Southernmost sessions of ALASBIMN; I Spanish-Argentine congress on nuclear medicine and I Sessions Argentine sessions on nuclear cardiology held in Buenos Aires, Argentina, from October 14 - 18, 1991

Nuclear winter or nuclear fall?

Science.gov (United States)

Berger, André

Climate is universal. If a major modern nuclear war (i.e., with a large number of small-yield weapons) were to happen, it is not even necessary to have a specific part of the world directly involved for there to be cause to worry about the consequences for its inhabitants and their future. Indeed, smoke from fires ignited by the nuclear explosions would be transported by winds all over the world, causing dark and cold. According to the first study, by Turco et al. [1983], air surface temperature over continental areas of the northern mid-latitudes (assumed to be the nuclear war theatre) would fall to winter levels even in summer (hence the term “nuclear winter”) and induce drastic climatic conditions for several months at least. The devastating effects of a nuclear war would thus last much longer than was assumed initially. Discussing to what extent these estimations of long-term impacts on climate are reliable is the purpose of this article.

Application of fire-retardant treatment to the wood in Type A unirradiated nuclear fuel outer containers

International Nuclear Information System (INIS)

Whitlow, J.D.; Luna, R.E.

1992-01-01

Packagings for transporting unirradiated nuclear fuel assemblies in the United States are commonly constructed as rectangular boxes consisting of a metal inner container, a wooden outer container, and cushioning material separating the two. The wood in the outer container is a potential source of fuel for fire. Use of a fire-retardant treatment on the wood may reduce or eliminate the damage to nuclear fuel assemblies in some types of accidents involving fire. The applicability of using fire-retardant treatments on the wood of outer containers is addressed. An approximate cost-benefit analysis to determine if fire-retardant treatments are economically justified is presented. (Author)

The media treatment of nuclear risks

International Nuclear Information System (INIS)

Wilkinson, J.

1987-01-01

The way that newspapers, radio and television news work, is explained so that reporting of nuclear stories can be better understood. The media's attitude to what makes a story newsworthy is explained. This, coupled with a chronology of the rise of the anti-nuclear lobby, is used to explain why some stories have been given prominence. The secretive and evasive attitude of the nuclear industry coupled with poorly communicated information about leaks etc have contributed to a lack of trust and made the public more aware and concerned with nuclear matters. This has sometimes led to unbalanced reporting by the media. The coverage of the Chernobyl reactor accident is examined. Some general points about the openness of BNFL and the government's reporting of nuclear incidents are made. (UK)

Surface treatment of aramid fiber by air dielectric barrier discharge plasma at atmospheric pressure

International Nuclear Information System (INIS)

Jia Caixia; Chen Ping; Liu Wei; Li Bin; Wang Qian

2011-01-01

Aramid fiber samples are treated by air dielectric barrier discharge (DBD) plasma at atmospheric pressure; the plasma treatment time is investigated as the major parameter. The effects of this treatment on the fiber surface physical and chemical properties are studied by using surface characterization techniques. Scanning electron microscopy (SEM) is performed to determine the surface morphology changes, X-ray photoelectron spectroscopy (XPS) is analyzed to reveal the surface chemical composition variations and dynamic contact angle analysis (DCAA) is used to examine the changes of the fiber surface wettability. In addition, the wetting behavior of a kind of thermoplastic resin, poly(phthalazinone ether sulfone ketone) (PPESK), on aramid fiber surface is also observed by SEM photos. The study shows that there seems to be an optimum treatment condition for surface modification of aramid fiber by the air DBD plasma. In this paper, after the 12 s, 27.6 W/cm 3 plasma treatment the aramid fiber surface roughness is significantly improved, some new oxygen-containing groups such as C-O, C=O and O=C-O are generated on the fiber surface and the fiber surface wettability is greatly enhanced, which results in the better wetting behavior of PPESK resin on the plasma-treated aramid fiber.

Hydrogen production coupled to nuclear waste treatment: the safe treatment of alkali metals through a well-demonstrated process

International Nuclear Information System (INIS)

Rahier, A.; Mesrobian, G.

2006-01-01

In 1992, the United Nations emphasised the urgent need to act against the perpetuation of disparities between and within nations, the worsening of poverty, hunger, ill health and illiteracy and the continuing deterioration of ecosystems on which we depend for our well-being. In this framework, taking into account the preservation of both worldwide energy resources and ecosystems, the use of nuclear energy to produce clean energy carriers, such as hydrogen, is undoubtedly advisable. However, coping fully with the Agenda 21 statements requires defining adequate treatment processes for nuclear wastes. This paper discusses the possible use of a well-demonstrated process to convert radioactively contaminated alkali metals into sodium hydroxide while producing hydrogen. We conclude that a synergy between Chlor-Alkali specialists and nuclear specialists may help find an acceptable solution for radioactively contaminated sodium waste. (author)

Advanced biological treatment of aqueous effluent from the nuclear fuel cycle

International Nuclear Information System (INIS)

Pitt, W.W. Jr.; Hancher, C.W.; Patton, B.D.; Shumate, S.E. II.

1979-01-01

Many of the processing steps in the nuclear fuel cycle generate aqueous effluent streams bearing contaminants that can, because of their chemical or radiological properties, pose an environmental hazard. Concentration of such contaminants must be reduced to acceptable levels before the streams can be discharged to the environment. Two classes of contaminants, nitrates and heavy metals, are addressed in this study. Specific techniques aimed at the removal of nitrates and radioactive heavy metals by biological processes are being developed, tested, and demonstrated. Although cost comparisons between biological processes and current treatment methods are presented, these comparisons may be misleading because biological processes yield environmentally better end results which are difficult to price. However, a strong case is made for the use of biological processes for removing nitrates and heavy metals fron nuclear fuel cycle effluents. The estimated costs for these methods are as low as, or lower than, those for alternate processes. In addition, the resulting disposal products - nitrogen gas, CO 2 , and heavy metals incorporated into microorganisms - are much more ecologically desirable than the end products of other waste treatment methods

E-beam treatment of trichloroethylene-air mixtures: products and rates

International Nuclear Information System (INIS)

Mill, Theodore; Minggong Su; Yao, C.C.D.; Matthews, S.M.; Wang, F.T.S.

1997-01-01

Electron beam (E-beam) treatment of 3000 ppmv trichloroethylene (TCE) vapor in dry and wet air led to rapid, nearly quantitative, conversion of TCE to dichloroacetyl chloride, plus small amounts of phosgene. Higher E-beam dose, up to 110 kGy, led to oxidation of the initial products to CO, CO 2 , HCl and Cl 2 . The results parallel results found for photo- and Cl-atom initiated oxidation of TCE vapor, and are accounted for by an efficient Cl-atom chain oxidation. Lack of effect of 28,000 ppmv water vapor (90% RH) on rates or products reflects a very high efficiency for the Cl-atom chain oxidation and the very slow reaction of vapor phase water with acyl halides. Irradiation experiments conducted with TCE dissolved in aerated and deaerated water at 10 and 300 ppm showed marked differences in radiolytic products from those found in the vapor phase. A preliminary cost estimate indicates that E-beam treatment of TCE vapor is very competitive with conventional activated carbon treatment and catalytic oxidation. (author)

Air temperature determination inside residual heat removal pump room of Angra-1 nuclear power plant after a design basic accident

International Nuclear Information System (INIS)

Siniscalchi, Marcio Rezende

2005-01-01

This work develops heat transfer theoretical models for determination of air temperature inside the Residual Heat Removal Pump Room of Angra 1 Nuclear Power Plant after a Design Basis Accident without forced ventilation. Two models had been developed. The differential equations are solved by analytical methods. A software in FORTRAN language are developed for simulations of temperature inside rooms for different geometries and materials. (author)

REACTOR: an expert system for diagnosis and treatment of nuclear reactor accidents

International Nuclear Information System (INIS)

Nelson, W.R.

1982-01-01

REACTOR is an expert system under development at EG and G Idaho, Inc., that will assist operators in the diagnosis and treatment of nuclear reactor accidents. This paper covers the background of the nuclear industry and why expert system technology may prove valuable in the reactor control room. Some of the basic features of the REACTOR system are discussed, and future plans for validation and evaluation of REACTOR are presented. The concept of using both event-oriented and function-oriented strategies for accident diagnosis is discussed. The response tree concept for representing expert knowledge is also introduced

Deployment Evaluation Methodology for the Electrometallurgical Treatment of DOE-EM Spent Nuclear Fuel

International Nuclear Information System (INIS)

Dahl, C.A.; Adams, J.P.; Rynearson, M.A.; Ramer, R.J.

1999-01-01

The Department of Energy - Environmental Management (DOE-EM) National Spent Nuclear Fuel Program (NSNFP) is charged with the disposition of legacy spent nuclear fuel (SNF). While direct repository disposal of the SNF is the preferred disposition option, some DOE SNF may need treatment to meet acceptance criteria at various disposition sites. The treatments may range from electrometallurgical treatment (EMT) and chemical dissolution to engineering controls. As a planning basis, a need is assumed for a treatment process, either as a primary or backup technology, that is compatible with, and cost-effective for, this portion of the DOE-EM inventory. The current planning option for treating this SNF, pending completion of development work and National Environmental Policy Act (NEPA) analysis, is the EMT process under development by Argonne National Laboratory - West (ANL-W). A decision on the deployment of the EMT is pending completion of an engineering scale demonstration currently in progress at ANL-W. For this study, a set of questions was developed for the EMT process for fuels at several locations. The set of questions addresses all issues associated with design, construction, and operation of a production facility. A matrix table was developed to determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to identify a treatment process and costs from initial design to shipment of treatment products to final disposition. Costs were applied to determine the life-cycle cost of each option. This technique can also be applied to other treatment techniques for treating SNF

Pyrochemical head-end treatment for spent nuclear fuels

International Nuclear Information System (INIS)

Bowersox, D.F.

1977-01-01

A program based upon thermodynamic values and scouting experiments at Argonne National Laboratory is proposed for development of a pyrochemical head-end treatment of spent nuclear fuels to replace the proposed chopping and leaching operation in the Purex process. The treatment consists of separation of the cladding from the oxide fuel by dissolution into liquid zinc; oxide reduction of uranium and plutonium and dissolution into a zinc--magnesium alloy; separation of alkali, alkaline earth, and rare earth fission products into a molten salt; and, finally, separation and recovery of the plutonium and uranium in the alloy. Uranium and plutonium would be separated from the fuel cladding and selected fission products in a form readily dissolvable in nitric acid. The head-end process could be developed eventually into an optimum method for recovering uranium, plutonium, and selected fission products and for minimizing wastes as compact, stable solids. Developmental expenses are not known clearly, but the potential advantages of the process are impressive

Waste form development and characterization in pyrometallurgical treatment of spent nuclear fuel

International Nuclear Information System (INIS)

Ackerman, J.

1998-01-01

Electrometallurgical treatment is a compact, inexpensive method that is being developed at Argonne National Laboratory to deal with spent nuclear fuel, primarily metallic and oxide fuels. In this method, metallic nuclear fuel constituents are electrorefined in a molten salt to separate uranium from the rest of the spent fuel. Oxide and other fuels are subjected to appropriate head end steps to convert them to metallic form prior to electrorefining. The treatment process generates two kinds of high-level waste--a metallic and a ceramic waste. Isolation of these wastes has been developed as an integral part of the process. The wastes arise directly from the electrorefiner, and waste streams do not contain large quantities of solvent or other process fluids. Consequently, waste volumes are small and waste isolation processes can be compact and rapid. This paper briefly summarizes waste isolation processes then describes development and characterization of the two waste forms in more detail

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)

A risk-based review of Instrument Air systems at nuclear power plants

International Nuclear Information System (INIS)

DeMoss, G.; Lofgren, E.; Rothleder, B.; Villeran, M.; Ruger, C.

1990-01-01

The broad objective of this analysis was to provide risk-based information to help focus regulatory actions related to Instrument Air (IA) systems at operating nuclear power plants. We first created an extensive data base of summarized and characterized IA-related events that gave a qualitative indication of the nature and severity of these events. Additionally, this data base was used to calculate the frequencies of certain events, which were used in the risk analysis. The risk analysis consisted of reviewing published PRAs and NRC Accident Sequence Precursor reports for IA-initiated accident sequences, IA interactions with frontline systems, and IA-related risk significant events. Sensitivity calculations were performed when possible. Generically, IA was found to contribute less to total risk than many safety systems; however, specific design weaknesses in safety systems, non-safety systems, and the IA system were found to be significant in risk. 22 refs., 13 figs., 24 tabs

Evaluation of dissolved air flotation and membrane filtration for drinking water treatment

International Nuclear Information System (INIS)

Van Benschoten, J.; Martin, C.; Schaefer, J.; Xu, L.; Franceschini, S.

2002-01-01

Laboratory and pilot-scale testing was conducted to evaluate the use of dissolved air flotation (DAF) followed by membrane filtration (MF) for drinking water treatment. At the laboratory scale, four water samples of varying water quality were tested. Pilot- scale DAF and MF plants located at the City of Buffalo Water Treatment facility utilized Lake Erie as a raw water source to evaluate this combination of treatment processes. A polyaluminum coagulant was used throughout the study. Study results demonstrated beneficial effects of coagulant addition in extending MF run time. Pilot testing showed additional benefits to using DAF as a pretreatment step to MF. In all testing, MF produced excellent water quality. Particulate matter appeared more important than concentration or type of dissolved organic matter in membrane fouling. (author)

Heating, ventilating, and air-conditioning applications

International Nuclear Information System (INIS)

Anon.

1991-01-01

This book covers: Comfort air conditioning and heating of residences: Space HVAC systems; Industrial and special air conditioning and ventilation for nuclear facilities, and for mines; Energy sources, such as Geothermal energy, solar utilization, and energy resources; Building operation and maintenance; energy management, and Thermal storage

Nuclear safety inspection in treatment process for SG heat exchange tubes deficiency of unit 1, TNPS

International Nuclear Information System (INIS)

Zhang Chunming; Song Chenxiu; Zhao Pengyu; Hou Wei

2006-01-01

This paper describes treatment process for SG heat exchange tubes deficiency of Unit 1, TNPS, nuclear safety inspection of Northern Regional Office during treatment process for deficiency and further inspection after deficiency had been treated. (authors)

Simple approach to carboxyl-rich materials through low-temperature heat treatment of hydrothermal carbon in air

Energy Technology Data Exchange (ETDEWEB)

Chen Zhen; Ma Lijian; Li Shuqiong; Geng Junxia; Song Qiang; Liu Jun; Wang Chunli; Wang Hang; Li Juan [College of Chemistry, Sichuan University, Key Laboratory of Radiation Physics and Technology (Sichuan University), Ministry of Education, Chengdu 610064 (China); Qin Zhi [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Li Shoujian, E-mail: sjli000616@scu.edu.cn [College of Chemistry, Sichuan University, Key Laboratory of Radiation Physics and Technology (Sichuan University), Ministry of Education, Chengdu 610064 (China)

2011-08-01

It was found that a large number of oxygen-containing functional groups (OFGs) could be created on the surface of hydrothermal carbon (HTC) by simply heating at lower temperature in air during the course of our preliminary experiments which focused on oxidation pre-treatment of pristine HTC for the purpose of grafting functionalization. Especially carboxyl groups on HTC would increase significantly, from 0.53 to 3.70 mmol/g after heat treatment at 300 deg. C. So, effects of heat-treatment on the OFGs on the carbon microsphere were deeply studied to confirm and explain the findings. Experiments involving different materials (HTC, activated carbon and glucose) were performed under varying conditions (heating temperature and time, in air or in Ar atmosphere). A reaction mechanism for newly generating carboxyl groups on HTC surface during heat-treatment process was supposed based on the results from the sample characterization using Boehm titrations, infrared spectra, X-ray photoelectron spectroscopy, energy dispersive spectrometry and elemental analysis. In addition, the as heat-treated product has excellent sorption capability for Pb{sup 2+} and Cd{sup 2+} ions.

Air leakage control in chief tunnel of uranium mines using air screen

International Nuclear Information System (INIS)

Xiao Gengsheng

1987-01-01

In this paper the results of air leakage control are described using air screen in the chief tunnels of some uranium mines. The air leakage decreases by 79-91% after using air screen. On the basis of mathematical treatment, the formulas for calculating the air resistance efficiency of air screen are presented

Cooperative activation of transcription by autoimmune regulator AIRE and CBP

International Nuclear Information System (INIS)

Pitkaenen, J.; Rebane, A.; Rowell, J.; Murumaegi, A.; Stroebel, P.; Moell, K.; Saare, M.; Heikkilae, J.; Doucas, V.; Marx, A.; Peterson, P.

2005-01-01

Autoimmune regulator (AIRE) is a transcriptional regulator that is believed to control the expression of tissue-specific genes in the thymus. Mutated AIRE is responsible for onset of the hereditary autoimmune disease APECED. AIRE is able to form nuclear bodies (NBs) and interacts with the ubiquitous transcriptional coactivator CBP. In this paper, we show that CBP and AIRE synergistically activate transcription on different promoter reporters whereas AIRE gene mutation R257X, found in APECED patients, interferes with this coactivation effect. Furthermore, the overexpression of AIRE and CBP collaboratively enhance endogenous IFNβ mRNA expression. The immunohistochemical studies suggest that CBP, depending on the balance of nuclear proteins, is a component of AIRE NBs. We also show that AIRE NBs are devoid of active chromatin and, therefore, not sites of transcription. In addition, we demonstrate by 3D analyses that AIRE and CBP, when colocalizing, are located spatially differently within AIRE NBs. In conclusion, our data suggest that AIRE activates transcription of the target genes, i.e., autoantigens in collaboration with CBP and that this activation occurs outside of AIRE NBs

Project Increase of infrastructure: 'Establishment of a laboratory for studies of pollutants in air, water and soil through atomic and nuclear techniques; Proyecto Incremento de infraestructura: 'Establecimiento de un laboratorio para estudios de contaminantes en aire, agua y suelo mediante tecnicas atomicas y nucleares'

Energy Technology Data Exchange (ETDEWEB)

Aldape U, F [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1993-10-15

In this report there are the guidelines of this project as well as the goals, activities and costs. The general objectives were: 1. A laboratory that allows to analyze with efficiency samples of air, water and soil pollutants using atomic and nuclear origin techniques as PIXE (Proton Induced X-ray Emission, NRA (Nuclear Reaction Analysis) and RBS (Rutherford Backscattering) as well as auxiliary and/or complementary techniques. 2. To obtain indicators of the influence of the pollution of the Valley of Mexico about the ecology and the health of the inhabitants of Mexico City with perspectives of carrying out studies in other cities. 3. To develop an appropriate technology for the realization of those studies and to generate human resources in this area. (Author)

The non-nuclear legislation and the communal property

International Nuclear Information System (INIS)

Ciallella R, Norberto; Grancelli Cha, Nestor

1996-01-01

Since 1984, year in which the Bolson Municipality, Rio Negro province, declared the town a 'Non Nuclear Area', began to appear an abundant legislation that generically, it is know as 'Non Nuclear'. The provinces of Buenos Aires, Chubut, Formosa, La Pampa, Santa Cruz and Tierra del Fuego, have in their respective Constitutions non nuclear articles, while the provinces of Catamarca, Cordoba, Corrientes, Chaco, Entre Rios, Formosa, Rio Negro, San Luis, Santa Cruz, Santa Fe, Tierra del Fuego and Tucuman have sanctioned in their respective jurisdictions non nuclear laws. New projects of these laws are in consideration and treatment in the provinces of Catamarca, La Pampa, Mendoza, Santiago del Estero and Rio Negro. The present work compiles and analyzes the available information on this subject. Although the topic is not regulatory, it could have involved in the regulatory area in an eventual situation that could be presented between regulatory laws of federal and provincials reaches. This work describes the current situation and the probabilities consequences of the mentioned legislation. (author)

Initial substantial reduction in air dose rates of Cs origin and personal doses for residents owing to the Fukushima nuclear accident

International Nuclear Information System (INIS)

Yoshida, Hiroko; Saito, Junko; Hirasawa, Noriyasu; Kobayashi, Ikuo

2013-01-01

The initial substantial reduction in the air dose rate and personal dose equivalent [Hp(10)] for residents were compared between the Marumori and Kosugo regions for the period from September 2011 to September 2012 after the occurrence of the Fukushima nuclear accident. Marumori is a rural settlement, and Kosugo is a suburban city along a freeway. A similar tendency was observed in the Hp(10) results for Marumori residents and in the air dose rates for both regions: values dropped during the heavy snow season and a faster reduction in the air dose rate than the radioactive decay of 134 Cs and 137 Cs was observed after the snow had thawed. These reductions are considered to be caused by the weathering and/or migration of radionuclides down the soil column. However, neither a drop due to an accumulation of snow nor faster reduction was observed in Hp(10) for Kosugo residents. This discrepancy between the air dose rate and Hp(10) for Marumori and Kosugo residents might be caused by differences in their living environment. (author)

Air leakage analysis of research reactor HANARO building in typhoon condition for the nuclear emergency preparedness

Energy Technology Data Exchange (ETDEWEB)

Lee, Goany Up; Lee, Hae Cho; Kim, Bong Seok; Kim, Jong Soo; Choi, Pyung Kyu [Dept. of Emergency Preparedness, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-12-15

To find out the leak characteristic of research reactor 'HANARO' building in a typhoon condition MELCOR code which normally is used to simulate severe accident behavior in a nuclear power plant was used to simulate the leak rate of air and fission products from reactor hall after the shutdown of the ventilation system of HANARO reactor building. For the simulation, HANARO building was designed by MELCOR code and typhoon condition passed through Daejeon in 2012 was applied. It was found that the leak rate is 0.1%·day{sup -1} of air, 0.004%·day{sup -1} of noble gas and 3.7×10{sup -5}%·day{sup -1} of aerosol during typhoon passing. The air leak rate of 0.1%·day can be converted into 1.36 m{sup 3}·hr{sup -1} , but the design leak rate in HANARO safety analysis report was considered as 600 m3·hr{sup -1} under the condition of 20 m·sec{sup -1} wind speed outside of the building by typhoon. Most of fission products during the maximum hypothesis accident at HANARO reactor will be contained in the reactor hall, so the direct radiation by remained fission products in the reactor hall will be the most important factor in designing emergency preparedness for HANARO reactor.

Air leakage analysis of research reactor HANARO building in typhoon condition for the nuclear emergency preparedness

International Nuclear Information System (INIS)

Lee, Goany Up; Lee, Hae Cho; Kim, Bong Seok; Kim, Jong Soo; Choi, Pyung Kyu

2016-01-01

To find out the leak characteristic of research reactor 'HANARO' building in a typhoon condition MELCOR code which normally is used to simulate severe accident behavior in a nuclear power plant was used to simulate the leak rate of air and fission products from reactor hall after the shutdown of the ventilation system of HANARO reactor building. For the simulation, HANARO building was designed by MELCOR code and typhoon condition passed through Daejeon in 2012 was applied. It was found that the leak rate is 0.1%·day -1 of air, 0.004%·day -1 of noble gas and 3.7×10 -5 %·day -1 of aerosol during typhoon passing. The air leak rate of 0.1%·day can be converted into 1.36 m 3 ·hr -1 , but the design leak rate in HANARO safety analysis report was considered as 600 m3·hr -1 under the condition of 20 m·sec -1 wind speed outside of the building by typhoon. Most of fission products during the maximum hypothesis accident at HANARO reactor will be contained in the reactor hall, so the direct radiation by remained fission products in the reactor hall will be the most important factor in designing emergency preparedness for HANARO reactor

Instrument air system - Aging impact on system availability

International Nuclear Information System (INIS)

Villaran, M.; Subudhi, M.

1989-01-01

As part of ongoing efforts to understand and manage the effects of aging in nuclear power plants, an aging assessment was performed for the Instrument Air (IA) system, a system that has been the subject of much scrutiny in recent years. Despite its non-safety classification, instrument air has been a factor in a number of potentially serious events. This report presents the results of the assessment and discusses the impact of instrument air system aging on system availability and plant safety. This work was performed for the US Nuclear Regulatory Commission (NRC) as part of the Nuclear Plant Aging Research (NPAR) program. To perform the complex task of analyzing an entire system, the Aging and Life Extension Assessment Program (ALEAP) System Level Plan was developed by Brookhaven National Laboratory and applied successfully in previous system aging studies. The work presented herein was performed using two parallel work paths, as described in the ALEAP plant. One path used deterministic techniques to assess the impact of aging on compressed air system performance, while the second path used probabilistic methods. Results from both paths then were used to characterize aging in the instrument air system. Some conclusions from this work are: compressors, air system valves, and air dryers were found to make up the majority of failures; the effectiveness and quantity of preventive maintenance devoted to a component significantly affected the amount of failures experienced; review of compressed air system designs and studies using a PRA-based system model revealed that the redundancy of key components (compressors, dryers, IA/SA crossconnect valve) was an important factor in system availability; total loss of air events are uncommon

An example of a complete treatment cycle for low- and medium-level waste at the nuclear research centre at Pupspitek-Serpong (Indonesia)

International Nuclear Information System (INIS)

Eymeri, M.J.; Gauthey, J.C.

1993-01-01

Nuclear power installations and nuclear research laboratories produce large quantities of liquid and solid waste in Indonesia. By controlling the entire waste treatment process from production to storage, TECHNICATOME has been able to set up for BATAN (BADAN TENEGA ATOM NASIONAL) the Indonesian nuclear research centre, a radioactive waste treatment plant on the PUPSPITEK site

Discussion about the application of treatment process for dehydrated wet waste at nuclear power station

International Nuclear Information System (INIS)

Li Guanghua; Wu Qiang

2009-01-01

In nuclear power station, the most popular treatment about low level radioactive wet waste generated during the unit operating and maintenance is embedded by cement. For radioactive waste minimization, this article introduces a new treatment process to dehydrate and compress wet waste. According to the development and application of the treatment process for the wet waste, and comparing with the formerly treatment-the cement embedding, prove that the new treatment can meet the purpose for volume reduction of wet waste. (authors)

Surface treatments for material protection in nuclear power plants

International Nuclear Information System (INIS)

De, P.K.; Gadiyar, H.S.

1987-01-01

The paper highlights some of the surface treatment methods used in nuclear power plants to improve their performance. The corrosion resistance of zirconium alloys results from the formation of an adherent and protective film of ZrO 2 . Graphite coating of zircaloy-2 cladding minimizes the susceptibility to environmental induced cracking. Magnetite formation during the hot conditioning operation improves the corrosion resistance of carbon steel as well as controls the spread of radioactivity. It has been illustrated how the surface treatment is helpful for redistributing residual stress to facilitate conversion of tensile stress to compressive stress to mitigate failures due to stress corrosion and fatigue corrosion. Inhibitors and passivators can modify the surface conditions (in situ) of condenser tubes and cooling water systems. These aspects have been dealt in the text of the paper. (author). 8 refs., 3 figures

Air-water ‘tornado’-type microwave plasmas applied for sugarcane biomass treatment

Science.gov (United States)

Bundaleska, N.; Tatarova, E.; Dias, F. M.; Lino da Silva, M.; Ferreira, C. M.; Amorim, J.

2014-02-01

The production of cellulosic ethanol from sugarcane biomass is an attractive alternative to the use of fossil fuels. Pretreatment is needed to separate the cellulosic material, which is packed with hemicellulose and lignin in cell wall of sugarcane biomass. A microwave ‘tornado’-type air-water plasma source operating at 2.45 GHz and atmospheric pressure has been applied for this purpose. Samples of dry and wet biomass (˜2 g) have been exposed to the late afterglow plasma stream. The experiments demonstrate that the air-water highly reactive plasma environment provides a number of long-lived active species able to destroy the cellulosic wrapping. Scanning electron microscopy has been applied to analyse the morphological changes occurring due to plasma treatment. The effluent gas streams have been analysed by Fourier-transform infrared spectroscopy (FT-IR). Optical emission spectroscopy and FT-IR have been applied to determine the gas temperature in the discharge and late afterglow plasma zones, respectively. The optimal range of the operational parameters is discussed along with the main active species involved in the treatment process. Synergistic effects can result from the action of singlet O2(a 1Δg) oxygen, NO2, nitrous acid HNO2 and OH hydroxyl radical.

Status, direction, and critical issues of waste treatment technology

International Nuclear Information System (INIS)

Knowles, D.E.; Bonner, W.F.

1983-01-01

Nuclear power production and related activities generate radioactive wastes that must be safely managed to protect workers and the general public. The liquid-fed ceramic melting (LFCM) vitrification process is the reference process for vitrifying high-level nuclear waste in the U.S. as well as in Japan and India. The French are currently using a rotary kiln calciner/metallic melter system at their reprocessing facility. Compaction or controlled-air incineration are the currently preferred options for low-level waste solids, followed by immobilization in an appropriate matrix. The Nuclear Waste Policy Act of 1982 is a significant step in proceeding with waste treatment and disposal. Programs can now build on past work to assure that public safety and regulations are met in a cost-effective manner

Breathing easier: Indonesia works towards cleaner air

International Nuclear Information System (INIS)

Madsen, Michael Amdi

2015-01-01

Indonesians can look forward to breathing cleaner air following upcoming changes in regulations introduced as a result of a study conducted using nuclear analytical techniques. Lead pollution and other fine particulate matter in the air is now, for the first time, being accurately monitored and is giving Indonesian officials a good understanding of their air pollution problem and how to manage it.

Act no 388 to amend Section 15 of the Nuclear Liability Act

International Nuclear Information System (INIS)

1986-01-01

Finland is ratifying the Montreal Protocols Nos 3 and 4 to the Warsaw Convention concerning carriage by air; protocol No 4 contains no exclusion clause for nuclear damage. This Act amends the 1972 Nuclear Liability Act to the effect that air carriers of nuclear substances have a right of recourse against the operator liable under nuclear legislation. In this way the principle of channelling liability onto the nuclear operator is maintained. (NEA) [fr

Simulation of the air flows in many industrial pleated filters

International Nuclear Information System (INIS)

Del Fabbro, L.; Brun, P.; Laborde, J.C.; Lacan, J.; Ricciardi, L.; Renoux, A.

2000-01-01

The study presents results concerning the characterization of the charge loss and the air flow in nuclear and automobile type pleated filters. The experimental studies in correlation with the numerical models showed an homogenous distribution of the air flows in a THE nuclear type filter, whereas the distribution is heterogenous in the case of an automobile filter. (A.L.B.)

Nuclear physics workshop

International Nuclear Information System (INIS)

1988-01-01

This Workshop in Nuclear Physics related to the TANDAR, took place in Buenos Aires in April from 23 to 26, 1987, with attendance of foreign scientists. There were presented four seminars and a lot of studies which deal with the following fields: Nuclear Physics at medium energies, Nuclear Structure, Nuclear Reactions, Nuclear Matter, Instrumentation and Methodology for Nuclear Spectroscopy, Classical Physics, Quantum Mechanics and Field Theory. It must be emphasized that the Electrostatic Accelerator TANDAR allows to work with heavy ions of high energy, that opens a new field of work in PIXE (particle induced X-ray emission). This powerful analytic technique makes it possiblethe analysis of nearly all the elements of the periodic table with the same accuracy. (M.E.L.) [es

Improvement of Polytetrafluoroethylene Surface Energy by Repetitive Pulse Non-Thermal Plasma Treatment in Atmospheric Air

International Nuclear Information System (INIS)

Yang Guoqing; Zhang Guanjun; Zhang Wenyuan

2011-01-01

Improvement of polytetrafluoroethylene surface energy by non-thermal plasma treatment is presented, using a nanosecond-positive-edge repetitive pulsed dielectric barrier discharge generator in atmospheric air. The electrical parameters including discharging power, peak and density of micro-discharge current were calculated, and the electron energy was estimated. Surface treatment experiments of polytetrafluoroethylene films were conducted for both different applied voltages and different treating durations. Results show that the surface energy of polytetrafluoroethylene film could be improved to 40 mJ/m 2 or more by plasma treatment. Surface roughness measurement and surface X-ray photoelectron spectroscopy analysis indicate that there are chemical etching and implantation of polar oxygen groups in the sample surface treating process, resulting in the improvement of the sample surface energy. Compared with an AC source of 50 Hz, the dielectric barrier discharges generated by a repetitive pulsed source could provide higher peak power, lower mean power, larger micro-discharge current density and higher electron energy. Therefore, with the same applied peak voltage and treating duration, the improvement of polytetrafluoroethylene surface energy using repetitive pulsed plasma is more effective, and the plasma treatment process based on repetitive pulsed dielectric barrier discharges in air is thus feasible and applicable.

A nuclear field treatment of the 3-particle system outside closed-shell nuclei

International Nuclear Information System (INIS)

Liotta, R.J.; Silvestre-Brac, B.

1978-01-01

The nuclear field treatment of the 3-particle system is carried out to all orders of perturbation theory but without including hole-excitations. It is shown that the theory properly corrects both the Pauli principle violations and the overcompleteness of the basis

QGSJET-II: physics, recent improvements, and results for air showers

Directory of Open Access Journals (Sweden)

Ostapchenko S.

2013-06-01

Full Text Available Modeling of high energy hadronic and nuclear interactions by the QGSJET-II generator is discussed. Recent updates related to the treatment of nonlinear effects inthe interaction dynamics and to the model calibration with new LHC data are described. A special attention is devoted to the predictions of the new model version forcharacteristics of extensive air showers initiated by high energy cosmic rays. In particular, an improved description of charge exchange processes in pion collisionsis discussed and the respective enhancement of the shower muon content is analyzed.

Atmospheric Tracer Depletion Testing for Unfiltered Air In-Leakage Determination at the Wolf Creek Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Sullivan, T. M. [Brookhaven National Lab. (BNL), Upton, NY (United States); Wilke, R. J. [Brookhaven National Lab. (BNL), Upton, NY (United States); Roberts, T. [Brookhaven National Lab. (BNL), Upton, NY (United States); Vignato, G. J. [Brookhaven National Lab. (BNL), Upton, NY (United States)

2017-03-01

Atmospheric Tracer Depletion tests were conducted at the Wolf Creek Nuclear Power Plant to quantify the unfiltered in-leakage (UI) into the Control Room (CR), Control Building (CB), and Equipment Rooms (ER) at the Wolf Creek Nuclear Power Plant. Wolf Creek has two independent charcoal filter Emergency Ventilation Systems (EVS) that can be used to purify air entering the control building and control room. The Bravo System contains a filtration system in Room 1501 in the Auxiliary Building for the Control Room and another filtration system (FGK02B) on Elevation 2016 for the Control Building. The Alpha system contains a filtration system in Room 1512 in the Auxiliary Building for the Control Room and another filtration system (FGK02A) on Elevation 2016 for the Control Building. The Atmospheric Tracer Depletion (ATD) test is a technique to measure in-leakage using the concentration of perfluorocarbon compounds that have a constant atmospheric background. These levels are present in the Control Room and Control Building under normal operating conditions. When air is supplied by either of the EVS, most of the PFTS are removed by the charcoal filters. If the concentrations of the PFTs measured in protected areas are the same as the levels at the output of the EVS, the in-leakage of outside air into the protected area would be zero. If the concentration is higher in the protected area than at the output of the filter system, there is in-leakage and the in-leakage can be quantified by the difference. Sampling was performed using state-of-the-art Brookhaven Atmospheric Tracer Samplers (BATS) air sampling equipment and analysis performed on Brookhaven National Laboratory (BNL) dedicated PFT analytical systems. In the Alpha test two tracers PMCH and mcPDCH were used to determine in-leakage into the control building. The analytical system was tuned to maximize sensitivity after initial analysis of the Alpha test. The increased sensitivity permitted accurate quantification of

Atmospheric Tracer Depletion Testing for Unfiltered Air In-Leakage Determination at the Wolf Creek Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Sullivan, T. M. [Brookhaven National Lab. (BNL), Upton, NY (United States); Wilke, R. J. [Brookhaven National Lab. (BNL), Upton, NY (United States); Roberts, T. [Brookhaven National Lab. (BNL), Upton, NY (United States); Vignato, G. J. [Brookhaven National Lab. (BNL), Upton, NY (United States)

2017-04-01

Atmospheric Tracer Depletion tests were conducted at the Wolf Creek Nuclear Power Plant to quantify the unfiltered in-leakage (UI) into the Control Room (CR), Control Building (CB), and Equipment Rooms (ER) at the Wolf Creek Nuclear Power Plant. Wolf Creek has two independent charcoal filter Emergency Ventilation Systems (EVS) that can be used to purify air entering the control building and control room. The Bravo System contains a filtration system in Room 1501 in the Auxiliary Building for the Control Room and another filtration system (FGK02B) on Elevation 2016 for the Control Building. The Alpha system contains a filtration system in Room 1512 in the Auxiliary Building for the Control Room and another filtration system (FGK02A) on Elevation 2016 for the Control Building.The Atmospheric Tracer Depletion (ATD) test is a technique to measure in-leakage using the concentration of perfluorocarbon compounds that have a constant atmospheric background. These levels are present in the Control Room and Control Building under normal operating conditions. When air is supplied by either of the EVS, most of the PFTS are removed by the charcoal filters. If the concentrations of the PFTs measured in protected areas are the same as the levels at the output of the EVS, the in-leakage of outside air into the protected area would be zero. If the concentration is higher in the protected area than at the output of the filter system, there is in-leakage and the in-leakage can be quantified by the difference.Sampling was performed using state-of-the-art Brookhaven Atmospheric Tracer Samplers (BATS) air sampling equipment and analysis performed on Brookhaven National Laboratory (BNL) dedicated PFT analytical systems. In the Alpha test two tracers PMCH and mcPDCH were used to determine in-leakage into the control building. The analytical system was tuned to maximize sensitivity after initial analysis of the Alpha test. The increased sensitivity permitted accurate quantification of five

Probabilistic reconstruction of internal exposure for nuclear power plant workers using air concentration measurements

International Nuclear Information System (INIS)

Linkov, I.; Burmistrov, D.

2000-01-01

Air surveys, whole-body counting, bioassays or combination of these measurements can be utilized for purposes or assessing internal doses to determine compliance with occupational dose equivalent limits. Air sampling with a little support provided by whole body counting and/or bioassays was often relied on in dose calculations. The utility of air sampling for internal dose reconstruction is addressed in this paper through the probabilistic analysis of environmental factors and their impact on dose estimates. In this paper we attempt to reconstruct an internal dose due to inhalation of beta + gamma emitting radionuclides for a contractual electrician, Mr. X. The data available for reconstruction of internal dose for Mr. X was found to be highly variable and uncertain. Uncertainty describes a lack of knowledge about a parameter, this lack of knowledge theoretically can be reduced, e.g., if more measurements were to be taken (for example, estimated activities for alpha-emitting radionuclides are uncertain due to the influence of naturally-occurring alpha-emitters). Variability describes the existence of different values that represent different environmental conditions (for example, the air concentrations of radionuclides may vary over time because of the different tasks performed by workers in the area). Variability can not be reduced by additional data collection because the varying values reflect the variable nature of the environment, not a lack of data. The high variability in measured air concentrations in the restricted areas of a LWR nuclear power plant where he worked do not allow adequate reconstruction of his individual internal dose using deterministic methods and therefore probabilistic methods are desirable. The guidance for probabilistic assessment developed by the United States Environmental Protection Agency as well as recommendations of the National Council of Radiation Protection provide an adequate framework for probabilistic reconstruction of

Ultrasound enhanced plasma treatment of glass-fibre-reinforced polyester in atmospheric pressure air for adhesion improvement

DEFF Research Database (Denmark)

Kusano, Yukihiro; Singh, Shailendra Vikram; Norrman, Kion

2011-01-01

A glass-fibre-reinforced polyester (GFRP) plate was treated with dielectric barrier discharge (DBD) at atmospheric pressure in air for adhesion improvement. The effects of ultrasonic irradiation using a high-power gas-jet generator during the treatment were investigated. The optical emission...... damage of the GFRP plates. The polar component of the surface energy of the polyester plate was 21 mJ/m2 before the treatment, increased markedly to 52 mJ/m2 after 2-s plasma treatment without ultrasonic irradiation, and further increased slightly after longer treatments. In addition, the polar component...

Analytical-numerical method for treatment of turbulent diffusion of particles in the air

International Nuclear Information System (INIS)

Arsov, L.J.

1976-01-01

This work deals with the problem of air pollution around a stationary punctual source. For description of air pollution from a punctual source a mathematical model is suggested, and for calculation of effluents concentration an analytical-numerical algorithm is given. In addition to the analitical treatment the mathematical model is far more flexible and complete. Eddy diffusivity is represented by an arbitrary function, and an arbitrary wind velocity profile ahs been proposed. The apsorption of the ground is introduced through a variable apsorption coefficient, and the sedimentation through the mean velocity of deposition. To determine the movement of particles a parabolic equation of diffusion is used. The method has been tested through calculation of effluents concentration for different values of physical parameters

Air pollution in Thailand using nuclear-related analytical techniques

International Nuclear Information System (INIS)

Leelhaphunt, N.; Chueinta, W.

1994-01-01

The methods of neutron activation, both instrumental and radiochemical, and atomic absorption spectrophotometry are used in a study of the concentrations of Al, As, Br, Cd, Cl, Co, Cr, Cu, Fe, Hg, Mn, Sb, Sc, Se, Si, V, Zn and Pb in airborne particulate matter collected from 7 permanent and 9 temporary air quality monitoring stations. The location of the stations are urban residential, suburban residential, mixed (commercial and residential), commercial and industrial areas and near major roads in Bangkok Metropolitan areas. Air sampling is performed once a month for 24 hours continuously using the high volume air sampler (GMW 2000 H) and for 5, 10, and 15 days continuously using an Anderson Air Sampler (SIBATA AN-200). The elements As, Cd and Cu are determined destructively using ion exchange chromatography while Hg and Se are determined by the dry combustion technique. The determination of Pb was done by atomic absorption spectrophotometry. The results of Pb concentrations in airborne particulate matters, collected during 1987 to 1991, were reported by the Office of the National Environment Board. Levels of Pb content were found to be lower than the National Ambient Air Quality Standards. (author). 3 refs, 4 tabs

Measurements of Chlorine by XPS and SIMS in Nuclear-Grade Graphite. Effect of Treatment by UV, Heat and Moisture

International Nuclear Information System (INIS)

Grossiord, C.; Amalric, J.; Rahmani, L.

2016-01-01

Pieces of historical nuclear-grade graphite from the same block were submitted to a treatment involving soft or hard UV and heating in moist air. XPS investigations before treatment have shown that – at the geometric surface at least – chlorine binds more commonly by covalent (30 to 100% depending on spots) than ionic bonds. After treatment, bond types are more balanced, though hardly more uniform. Shifts of the ionic peak indicating an oxidised bond were not found. Surface chlorine was measured up to 0.04% atomic. Treatment by hard UV and heating in moist air for 1 ½ hours up to 122°C led to a decrease of surface chlorine by a factor of 2 as measured by ToF and XPS, helped by an etching technique that ensured the accurate positioning of the spots under analysis. Treatment for 8 hours up to 151°C resulted in a decrease of the ToF Cl/ 13 C signal for surface chlorine from 0.73 to 0.20 and of the atomic fraction from 0.02% to 0% as measured by XPS. SIMS investigations reveal that in the first 6 μm from the geometric surface, chlorine, hydrogen and oxygen have a decreasing profile suggestive of diffusion from the surface. In the vicinity to the surface the amounts of all three elements are much greater than in the bulk, possibly due to the availability of dangling bonds. It is speculated that when these are not saturated, back diffusion from the bulk under treatment may increase the quantity of surface chlorine. Treatment in moist air by hard UV for to 1 ½ hours has no marked effect on chlorine in the bulk, although it alters the quantities of hydrogen and oxygen. Treatment for 8 hours decreases chlorine by a factor of about 5 throughout the analysed depth of 6 μm and possibly farther to 15 μm, suggesting its diffusivity to be at least an order greater than 3.10 -16m 2 /s and possibly than 2.10 -15 m²/s, although a range of values is expected owing to the diverse tortuosity and constrictivity of pores. Ratios of hydrogen to oxygen and of chlorine to

Effect of two activation treatments and age of blastomere karyoplasts on in vitro development of bovine nuclear transfer embryos

DEFF Research Database (Denmark)

Booth, Paul J; Holm, Peter; Vajta, Gabor

2001-01-01

The yield and quality of (a) parthenogenetic blastocysts produced by two activation treatments (cycloheximide [CHX] or 6-dimethylaminopurine [DMAP]) and (b) nuclear transfer blastocysts generated using these two activation treatments and three different ages of karyoplast derived from day 3, 4......, or 5 in vitro produced donor embryos, were examined in order to define an optimal nuclear transfer protocol. The two activation protocols comprised calcium ionophore followed by either CHX or DMAP. Parthenogenetic blastocyst yields were greater (P ....7 +/- 5.1 vs. 31.4 +/- 4.5 [mean +/- SEM]). In contrast, nuclear transfer blastocyst rates per fused embryo were lower (P

Significant improvement of mouse cloning technique by treatment with trichostatin A after somatic nuclear transfer

International Nuclear Information System (INIS)

Kishigami, Satoshi; Mizutani, Eiji; Ohta, Hiroshi; Hikichi, Takafusa; Thuan, Nguyen Van; Wakayama, Sayaka; Bui, Hong-Thuy; Wakayama, Teruhiko

2006-01-01

The low success rate of animal cloning by somatic cell nuclear transfer (SCNT) is believed to be associated with epigenetic errors including abnormal DNA hypermethylation. Recently, we elucidated by using round spermatids that, after nuclear transfer, treatment of zygotes with trichostatin A (TSA), an inhibitor of histone deacetylase, can remarkably reduce abnormal DNA hypermethylation depending on the origins of transferred nuclei and their genomic regions [S. Kishigami, N. Van Thuan, T. Hikichi, H. Ohta, S. Wakayama. E. Mizutani, T. Wakayama, Epigenetic abnormalities of the mouse paternal zygotic genome associated with microinsemination of round spermatids, Dev. Biol. (2005) in press]. Here, we found that 5-50 nM TSA-treatment for 10 h following oocyte activation resulted in more efficient in vitro development of somatic cloned embryos to the blastocyst stage from 2- to 5-fold depending on the donor cells including tail tip cells, spleen cells, neural stem cells, and cumulus cells. This TSA-treatment also led to more than 5-fold increase in success rate of mouse cloning from cumulus cells without obvious abnormality but failed to improve ES cloning success. Further, we succeeded in establishment of nuclear transfer-embryonic stem (NT-ES) cells from TSA-treated cloned blastocyst at a rate three times higher than those from untreated cloned blastocysts. Thus, our data indicate that TSA-treatment after SCNT in mice can dramatically improve the practical application of current cloning techniques

Air pollution meteorology

Energy Technology Data Exchange (ETDEWEB)

Shirvaikar, V V; Daoo, V J [Environmental Assessment Div., Bhabha Atomic Research Centre, Mumbai (India)

2002-06-01

This report is intended as a training cum reference document for scientists posted at the Environmental Laboratories at the Nuclear Power Station Sites and other sites of the Department of Atomic Energy with installations emitting air pollutants, radioactive or otherwise. Since a manual already exists for the computation of doses from radioactive air pollutants, a general approach is take here i.e. air pollutants in general are considered. The first chapter presents a brief introduction to the need and scope of air pollution dispersion modelling. The second chapter is a very important chapter discussing the aspects of meteorology relevant to air pollution and dispersion modelling. This chapter is important because without this information one really does not understand the phenomena affecting dispersion, the scope and applicability of various models or their limitations under various weather and site conditions. The third chapter discusses the air pollution models in detail. These models are applicable to distances of a few tens of kilometres. The fourth chapter discusses the various aspects of meteorological measurements relevant to air pollution. The chapters are followed by two appendices. Apendix A discusses the reliability of air pollution estimates. Apendix B gives some practical examples relevant to general air pollution. It is hoped that the document will prove very useful to the users. (author)

Climate risks by radioactive krypton-85 from nuclear fission. Atmospheric-electrical and air-chemical effects of ionizing radiation in the atmosphere

International Nuclear Information System (INIS)

Kollert, R.

1994-01-01

The study shows that krypton-85 from nuclear fission enhances air ionization and, thus, interferes with the atmospheric-electrical system and the water balance of the earth atmosphere. This is reason for concern: There are unforeseeable effects for weather and climate if the krypton-85 content of the earth atmosphere continues to rise. There may be a krypton-specific greenhouse effect and a collapse of the natural atmospheric-electrical field. In addition, human well-being may be expected to be impaired as a result of the diminished atmospheric-electrical field. There is also the risk of radiochemical actions and effects caused-by krypton-85-containing plumes in other air-borne pollutants like the latters' transformation to aggressive oxidants. This implies radiation smog and more acid rain in the countries exposed. This study summarizes findings gained in these issues by various sciences, analyses them and elaborates hypotheses on the actions and effects of krypton-85 on the air, the atmosphere and the climate. (orig./HP) [de

Safety-related control air systems - approved 1977

International Nuclear Information System (INIS)

Anon.

1978-01-01

This standard applies to those portions of the control air system that furnish air required to support, control, or operate systems or portions of systems that are safety related in nuclear power plants. This standard relates only to the air supply system(s) for safety-related air operated devices and does not apply to the safety-related air operated device or to air operated actuators for such devices. The objectives of this standard are to provide (1) minimum system design requirements for equipment, piping, instruments, controls, and wiring that constitute the air supply system; and (2) the system and component testing and maintenance requirements

Testing for Nuclear Thermal Propulsion Systems: Identification of Technologies for Effluent Treatment in Test Facilities

Data.gov (United States)

National Aeronautics and Space Administration — Key steps to ensure identification of relevant effluent treatment technologies for Nuclear Thermal Propulsion (NTP) testing include the following. 1. Review of...

Operational analysis and improvement of a spent nuclear fuel handling and treatment facility using discrete event simulation

International Nuclear Information System (INIS)

Garcia, H.E.

2000-01-01

Spent nuclear fuel handling and treatment often require facilities with a high level of operational complexity. Simulation models can reveal undesirable characteristics and production problems before they become readily apparent during system operations. The value of this approach is illustrated here through an operational study, using discrete event modeling techniques, to analyze the Fuel Conditioning Facility at Argonne National Laboratory and to identify enhanced nuclear waste treatment configurations. The modeling approach and results of what-if studies are discussed. An example on how to improve productivity is presented.

Air concentration of radiocaesium in Tsukuba, Japan following the release from the Tokai waste treatment plant: comparisons of observations with predictions

International Nuclear Information System (INIS)

Igarashi, Yasuhito; Aoyama, Michio; Miyao, Takashi; Hirose, Katsumi; Komura, Kazuhisa; Yamamoto, Masayoshi

1999-01-01

On March 11, 1997 a fire and explosion accident occurred at the bituminization facility of the Power Reactor and Nuclear Fuel Development, Tokai, Japan. As a result of this accident, 134,137 Cs was detected in an air filter sample collected at the Meteorological Research Institute, Tsukuba during March 10 to 12. The 134,137 Cs air concentration was about 100 and 10 μBq m -3 , respectively. This result suggests that there was little radiation exposure of the residents in the area. The average 137 Cs air concentration during this period was about two orders of magnitude higher than 'baseline' air (sub-μBq m -3 ) during February to April, 1997, measured by ultra-low background γ-spectrometry. By a simple calculation using a Gaussian plume model with the measured data, we estimated the minimum emission of the radioactivity by the PNC accident to be in the range 60 MBq to around 600 MBq. The meteorological condition during the week of the accident are also described

Institute for Nuclear Research and Nuclear Energy and Nuclear Science

International Nuclear Information System (INIS)

Stamenov, J.

2004-01-01

The Institute for Nuclear Research and Nuclear Energy (INRNE) of the Bulgarian Academy of Sciences is the leading Bulgarian Institute for scientific investigations and applications of nuclear science. The main Institute's activities in the field of elementary particles and nuclear physics, high energy physics and nuclear energy, radiochemistry, radioecology, radioactive wastes treatment, monitoring of the environment, nuclear instruments development ect. are briefly described. Several examples for: environmental radiation monitoring; monitoring of the radioactivity and heavy metals in aerosols, 99m Tc clinical use, Boron Neutron Capture Therapy application of IRT-2000 Research Reactor, neutron fluence for reactor vessel embrittlement, NPP safety analysis, nuclear fuel modelling are also presented

Modular head assembly and method of retrofitting existing nuclear reactor facilities

International Nuclear Information System (INIS)

Malandra, L.J.; Ledue, R.J.; Hankinson, M.F.; Kowalski, E.F.

1987-01-01

A method is described of retrofitting existing nuclear reactor facilities so as to form a modular closure head assembly for a nuclear reactor pressure vessel, where the existing nuclear reactor facilities comprise control rod drive mechanism cooling systems which include vertically extending elbow air ducts inter-connecting vertically spaced upper and lower air manifolds. The elbow air ducts extend radially beyond the peripheral envelope of the closure head, comprising the steps of: removing the upper air manifold; removing the vertically extending elbow air ducts; capping the air ports of the lower air manifold which ports were previously fluidically connecting the lower air manifold to the vertically extending elbow air ducts; disposing vertically upwardly extending air exhaust ducts above the lower air manifold in such an manner that the air exhaust ducts are disposed within the peripheral envelope of the closure head; fluidically connecting exhaust fans to the upper regions of the air exhaust ducts; fluidically connecting the lower regions of the air exhaust ducts the lower air manifold; permanently securing lift rods to the closure head at positions disposed radially outwardly of the lower air manifold; attaching a seismic support platform to the lift rods; proving fluidic passage of the vertically extending air exhaust ducts through the seismic support platform; attaching a missile shield plate to the lift rods; and proving fluidic passage of the vertically extending air exhaust ducts through the missile shield plate

131I concentrations in air, milk and antelope thyroids in southeastern Idaho

International Nuclear Information System (INIS)

Markham, O.D.; Halford, D.K.; Bihl, D.E.

1980-01-01

Iodine-131 concentrations were determined in air, milk, and antelope (Antilocapra americana) thyroids from southeastern Idaho during 1972-77. Samples were collected in the vicinity of the Idaho National Engineering Laboratory Site which has 17 operating nuclear reactors, a fuel reprocessing plant, and a nuclear waste management facility. Samples were also collected from control areas. During the study, fallout occurred from five People's Republic of China above-ground nuclear weapon detonations. All 131 I detected in air and milk samples was attributed to fallout from the Chinese nuclear tests. 131 I was detected in low-volume air samples following only one of the five detonations while 131 I was detected in milk following four of the detonations. 131 I occurred in antelope thyroids during all five of the fallout periods and following at least one atmospheric release from facilities at the Idaho National Engineering Laboratory Site. Thyroids were the most sensitive indicators of 131 I in the environment followed by milk and then air. Maximum concentrations in thyroids, milk, and air were 400, 20 and 4 times higher respectively than their respective detection limits. (author)

Project Increase of infrastructure: 'Establishment of a laboratory for studies of pollutants in air, water and soil through atomic and nuclear techniques; Proyecto Incremento de infraestructura: 'Establecimiento de un laboratorio para estudios de contaminantes en aire, agua y suelo mediante tecnicas atomicas y nucleares'

Energy Technology Data Exchange (ETDEWEB)

Aldape U, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1993-10-15

In this report there are the guidelines of this project as well as the goals, activities and costs. The general objectives were: 1. A laboratory that allows to analyze with efficiency samples of air, water and soil pollutants using atomic and nuclear origin techniques as PIXE (Proton Induced X-ray Emission, NRA (Nuclear Reaction Analysis) and RBS (Rutherford Backscattering) as well as auxiliary and/or complementary techniques. 2. To obtain indicators of the influence of the pollution of the Valley of Mexico about the ecology and the health of the inhabitants of Mexico City with perspectives of carrying out studies in other cities. 3. To develop an appropriate technology for the realization of those studies and to generate human resources in this area. (Author)

Factor analysis for the adoption of nuclear technology in diagnosis and treatment of chronic diseases

International Nuclear Information System (INIS)

Sato, Renato Cesar; Zouain, Desiree Moraes

2012-01-01

To identify and evaluate latent variables (variables that are not directly observed) for adopting and using nuclear technologies in diagnosis and treatment of chronic diseases. The measurement and management of these latent factors are important for health care due to complexities of the sector. Methods: An exploratory factor analysis study was conducted among 52 physicians practicing in the areas of Cardiology, Neurology and Oncology in the State of Sao Paulo who agreed to participate in the study between 2009 and 2010. Data were collected using an attitude measurement questionnaire, and analyzed according to the principal component method with Varimax rotation. Results: The component matrix after factor rotation showed three elucidative groups arranged according to demand for nuclear technology: clinical factors, structural factors, and technological factors. Clinical factors included questionnaire answers referring to medical history, previous interventions, complexity and chronicity of the disease. Structural factors included patient age, physician's practice area, and payment ability. Technological factors included prospective growth in the use of nuclear technology and availability of services. Conclusions: The clinical factors group dimension identified in the study included patient history, prior interventions, and complexity and chronicity of the disease. This dimension is the main motivating for adopting nuclear technology in diagnosis and treatment of chronic diseases. (author)

Size-dependent mechanical properties of PVA nanofibers reduced via air plasma treatment

International Nuclear Information System (INIS)

Fu Qiang; Song Xuefeng; Gao Jingyun; Han Xiaobing; Zhao Qing; Yu Dapeng; Jin Yu; Jiang Xingyu

2010-01-01

Organic nanowires/fibers have great potential in applications such as organic electronics and soft electronic techniques. Therefore investigation of their mechanical performance is of importance. The Young's modulus of poly(vinyl alcohol) (PVA) nanofibers was analyzed by scanning probe microscopy (SPM) methods. Air plasma treatment was used to reduce the nanofibers to different sizes. Size-dependent mechanical properties of PVA nanofibers were studied and revealed that the Young's modulus increased dramatically when the scales became very small (<80 nm).

Size-dependent mechanical properties of PVA nanofibers reduced via air plasma treatment.

Science.gov (United States)

Fu, Qiang; Jin, Yu; Song, Xuefeng; Gao, Jingyun; Han, Xiaobing; Jiang, Xingyu; Zhao, Qing; Yu, Dapeng

2010-03-05

Organic nanowires/fibers have great potential in applications such as organic electronics and soft electronic techniques. Therefore investigation of their mechanical performance is of importance. The Young's modulus of poly(vinyl alcohol) (PVA) nanofibers was analyzed by scanning probe microscopy (SPM) methods. Air plasma treatment was used to reduce the nanofibers to different sizes. Size-dependent mechanical properties of PVA nanofibers were studied and revealed that the Young's modulus increased dramatically when the scales became very small (<80 nm).

Migration of polycyclic aromatic hydrocarbons (PAHs) in urban treatment sludge to the air during PAH removal applications.

Science.gov (United States)

Karaca, Gizem; Cindoruk, S Siddik; Tasdemir, Yücel

2014-05-01

In the present study, the amounts of polycylic aromatic hydrocarbons (PAHs) penetrating into air during PAH removal applications from the urban treatment sludge were investigated. The effects of the temperature, photocatalyst type, and dose on the PAH removal efficiencies and PAH evaporation were explained. The sludge samples were taken from an urban wastewater treatment plant located in the city of Bursa, with 585,000 equivalent population. The ultraviolet C (UV-C) light of 254 nm wavelength was used within the UV applications performed on a specially designed setup. Internal air of the setup was vacuumed through polyurethane foam (PUF) columns in order to collect the evaporated PAHs from the sludge during the PAH removal applications. All experiments were performed with three repetitions. The PAH concentrations were measured by gas chromatography-mass spectrometry (GC-MS). It was observed that the amounts of PAHs penetrating into the air were increased with increase of temperature, and more than 80% of PAHs migrated to the air consisted of 3-ring compounds during the UV and UV-diethylamine (DEA) experiments at 38 and 53 degrees C. It was determined that 40% decrease was ensured in sigma12 (total of 12) PAH amounts with UV application and 13% of PAHs in sludge penetrated into the air. In the UV-TiO2 applications, a maximum 80% of sigma12 PAH removal was obtained by adding 0.5% TiO2 of dry weight of sludge. The quantity of PAH penetrating into air did not exceed 15%. UV-TiO2 applications ensured high levels of PAH removal in the sludge and also reduced the quantity of PAH penetrating into the air. Within the scope of the samples added with DEA, there was no increase in PAH removal efficiencies and the penetration of PAHs into air was not decreased. In light of these data, it was concluded that UV-TiO2 application is the most suitable PAH removal alternative that restricts the convection of PAH pollution.

Study on HVAC system in nuclear facility

International Nuclear Information System (INIS)

Baeg, S. Y.; Song, W. S.; Oh, Y. O.; Ju, Y. S.; Hong, K. P.

2003-01-01

Heating, Ventilation and Air Conditioning (HVAC) system in nuclear facility should be equipped and constructed more stable and allowable than that in common facility. The purpose of HVAC system is the maintenance of optimum working environment, the protection of worker against a contaminated air and the prevention of atmospheric contamination due to an outward ventilation, etc.. The basic scheme of a safety operation of nuclear facility is to prevent the atmospheric contamination even in low level. The adaptability of HVAC system which is in operation. In this study, the design requirements of HVAC system in nuclear facility and the HVAC systems in foreign countries are reviewed, and the results can be utilized in the design of HVAC system in nuclear facility

Elevated nuclear sphingoid base-1-phosphates and decreased histone deacetylase activity after fumonisin B1 treatment in mouse embryonic fibroblasts

Energy Technology Data Exchange (ETDEWEB)

Gardner, Nicole M., E-mail: nicolegardner@creighton.edu [Department of Pharmacology, Creighton University School of Medicine, Omaha, NE 68178 (United States); Riley, Ronald T.; Showker, Jency L.; Voss, Kenneth A. [USDA-ARS, Toxicology and Mycotoxin Research Unit, Athens, GA 30605 (United States); Sachs, Andrew J.; Maddox, Joyce R.; Gelineau-van Waes, Janee B. [Department of Pharmacology, Creighton University School of Medicine, Omaha, NE 68178 (United States)

2016-05-01

Fumonisin B1 (FB1) is a mycotoxin produced by a common fungal contaminant of corn. Administration of FB1 to pregnant LM/Bc mice induces exencephaly in embryos, and ingestion of FB1-contaminated food during early pregnancy is associated with increased risk for neural tube defects (NTDs) in humans. FB1 inhibits ceramide synthase enzymes in sphingolipid biosynthesis, causing sphinganine (Sa) and bioactive sphinganine-1-phosphate (Sa1P) accumulation in blood, cells, and tissues. Sphingosine kinases (Sphk) phosphorylate Sa to form Sa1P. Upon activation, Sphk1 associates primarily with the plasma membrane, while Sphk2 is found predominantly in the nucleus. In cells over-expressing Sphk2, accumulation of Sa1P in the nuclear compartment inhibits histone deacetylase (HDAC) activity, causing increased acetylation of histone lysine residues. In this study, FB1 treatment in LM/Bc mouse embryonic fibroblasts (MEFs) resulted in significant accumulation of Sa1P in nuclear extracts relative to cytoplasmic extracts. Elevated nuclear Sa1P corresponded to decreased histone deacetylase (HDAC) activity and increased histone acetylation at H2BK12, H3K9, H3K18, and H3K23. Treatment of LM/Bc MEFs with a selective Sphk1 inhibitor, PF-543, or with ABC294640, a selective Sphk2 inhibitor, significantly reduced nuclear Sa1P accumulation after FB1, although Sa1P levels remained significantly increased relative to basal levels. Concurrent treatment with both PF-543 and ABC294640 prevented nuclear accumulation of Sa1P in response to FB1. Other HDAC inhibitors are known to cause NTDs, so these results suggest that FB1-induced disruption of sphingolipid metabolism leading to nuclear Sa1P accumulation, HDAC inhibition, and histone hyperacetylation is a potential mechanism for FB1-induced NTDs. - Highlights: • FB1 treatment results in accumulation of Sa1P primarily in the nucleus of MEFs. • FB1 treatment and elevated nuclear Sa1P are associated with HDAC inhibition. • Sphk2 inhibition alone

Elevated nuclear sphingoid base-1-phosphates and decreased histone deacetylase activity after fumonisin B1 treatment in mouse embryonic fibroblasts

International Nuclear Information System (INIS)

Gardner, Nicole M.; Riley, Ronald T.; Showker, Jency L.; Voss, Kenneth A.; Sachs, Andrew J.; Maddox, Joyce R.; Gelineau-van Waes, Janee B.

2016-01-01

Fumonisin B1 (FB1) is a mycotoxin produced by a common fungal contaminant of corn. Administration of FB1 to pregnant LM/Bc mice induces exencephaly in embryos, and ingestion of FB1-contaminated food during early pregnancy is associated with increased risk for neural tube defects (NTDs) in humans. FB1 inhibits ceramide synthase enzymes in sphingolipid biosynthesis, causing sphinganine (Sa) and bioactive sphinganine-1-phosphate (Sa1P) accumulation in blood, cells, and tissues. Sphingosine kinases (Sphk) phosphorylate Sa to form Sa1P. Upon activation, Sphk1 associates primarily with the plasma membrane, while Sphk2 is found predominantly in the nucleus. In cells over-expressing Sphk2, accumulation of Sa1P in the nuclear compartment inhibits histone deacetylase (HDAC) activity, causing increased acetylation of histone lysine residues. In this study, FB1 treatment in LM/Bc mouse embryonic fibroblasts (MEFs) resulted in significant accumulation of Sa1P in nuclear extracts relative to cytoplasmic extracts. Elevated nuclear Sa1P corresponded to decreased histone deacetylase (HDAC) activity and increased histone acetylation at H2BK12, H3K9, H3K18, and H3K23. Treatment of LM/Bc MEFs with a selective Sphk1 inhibitor, PF-543, or with ABC294640, a selective Sphk2 inhibitor, significantly reduced nuclear Sa1P accumulation after FB1, although Sa1P levels remained significantly increased relative to basal levels. Concurrent treatment with both PF-543 and ABC294640 prevented nuclear accumulation of Sa1P in response to FB1. Other HDAC inhibitors are known to cause NTDs, so these results suggest that FB1-induced disruption of sphingolipid metabolism leading to nuclear Sa1P accumulation, HDAC inhibition, and histone hyperacetylation is a potential mechanism for FB1-induced NTDs. - Highlights: • FB1 treatment results in accumulation of Sa1P primarily in the nucleus of MEFs. • FB1 treatment and elevated nuclear Sa1P are associated with HDAC inhibition. • Sphk2 inhibition alone

Emission of bacteria and fungi in the air from wastewater treatment plants - a review.

Science.gov (United States)

Korzeniewska, Ewa

2011-01-01

An increase in global population, coupled with intensive development of industry and agriculture, has resulted in the generation and accumulation of large amounts of waste around the world. The spread of pathogenic microorganisms, endotoxins, odours and dust particles in the air is an inevitable consequence of waste production and waste management. Thus, the risk of infections associated with wastewater treatment plants (WWTPs) has become of a particular importance in recent decades. Sewage and unstable sludge contain various pathogens such as viruses, bacteria, and human and animal parasites. These microorganisms can be transmitted to the ambient air in wastewater droplets, which are generated during aeration or mechanical moving of the sewage. Bioaerosols generated during wastewater treatment may therefore pose a potential health hazard to workers of these plants or to habitants of their surroundings. The degree of human exposure to airborne bacteria, fungi, endotoxin and other allergens may vary significantly depending upon the type and the capacity of a plant, kind of the facilities, performed activities and meteorological conditions.

Wear Behavior of Selected Nuclear Grade Graphites at Room Temperature in Ambient Air Environment

International Nuclear Information System (INIS)

Kim, Eung-Seon; Park, Kwang-Seok; Kim, Yong-Wan

2008-01-01

In a very high temperature reactor (VHTR), graphite will be used not only for as a moderator and reflector but also as a major structural component due to its excellent neutronic, thermal and mechanical properties. In the VHTR, wear of graphite components is inevitable due to a neutron irradiation-induced dimensional change, thermal gradient, relative motions of graphite components and a shock load such as an earthquake. Large wear particles accumulated at the bottom of a reactor can influence the cooling of the lower part and small wear particles accumulated on the primary circuit and heat exchanger tube can make it difficult to inspect the equipment, and also decrease the heat exchange rate. In the present work, preliminary wear tests were performed at room temperature in ambient air environment to understand the basic wear characteristics of selected nuclear grade graphites for the VHTR

Accidental behaviour of nuclear fuel in a warehousing site under air: investigation of the nuclear ceramic oxidation and of fission gas release; Comportement accidentel du combustible nucleaire dans un site d'entreposage sous air: Etude de l'oxydation de la ceramique nucleaire et du relachement des gaz de fission

Energy Technology Data Exchange (ETDEWEB)

Desgranges, L.

2006-12-15

After a brief presentation of the context of his works, i.e. the nuclear fuel, its behaviour in a nuclear reactor, and studies performed in high activity laboratory, the author more precisely presents its research topic: the behaviour of defective nuclear fuel in air. Then, he describes the researches performed in three main directions: firstly, the characterization and understanding of fission gas localisation (experimental localisation, understanding of the bubble forming mechanisms), secondly, the determination of mechanisms related to oxidation (atomic mechanisms related to UO{sub 2} oxidation, oxidation of fragments of irradiated fuel, the CROCODILE installation). He finally presents his scientific project which notably deals with fission gas release (from UO{sub 2} to U{sub 3}O{sub 7}, and from U{sub 3}O{sub 7} to U{sub 3}O{sub 8}), and with further high activity laboratory experiments

Effects of the Air Flow Rate on The Oxidation of NBG-18 and 25 Nuclear Graphite Grades

International Nuclear Information System (INIS)

Chi, Se-Hwan; Kim, Gen-Chan; Jang, Joon-Hee

2007-01-01

For a VHTR, graphite oxidation is regarded as a critical phenomenon for degrading the integrity of graphite components under normal or abnormal conditions. The oxidation of a graphite core component can occur by air which may permeate into the primary coolant operation and/or by impurities contained in the He coolant, or by air ingress during a severe accident. It is well known that the oxidation properties of a graphite are highly dependent on the source of raw materials, impurities, microstructures (crystallites, pore structure), and on the processing and environmental parameters, such as the forming methods, the coolant type, moisture and impurity content, temperature, flow rate and the oxygen potential of the coolants. A lot of work has been performed on the oxidation of graphite since the 1960s, and, for example, in the case of the temperature, a widely accepted oxidation model on the effects of a temperature has already been developed. However, in the case of the flow rate, even for its expected effects in a VHTR, for example, as to the expected changes in the bypass flow (10-20 %) during an operation, no systematic works have been performed. In this respect, as a preliminary study, the effects of an air flow rate on the oxidation of NBG-18 and 25 nuclear graphite were investigated

8. Peaceful uses of nuclear explosions

International Nuclear Information System (INIS)

Musilek, L.

1992-01-01

The chapter deals with peaceful uses of nuclear explosions. Described are the development of the underground nuclear explosion, properties of radionuclides formed during the explosion, their distribution, the release of radioactive products of underground nuclear explosions into the air, their propagation in the atmosphere, and fallout in the landscape. (Z.S.). 1 tab., 8 figs., 19 refs

Treatment of ammonia in waste air using packed column coupling with chemical reaction

Directory of Open Access Journals (Sweden)

Thepchai, R.

2007-05-01

Full Text Available Ammonia is a common chemical used in various industries. Emission of air contaminated with ammonia to the atmosphere without any treatment causes several effects on human health and environment.A high efficiency method for ammonia removal from waste air is then necessary. In this research, an absorption coupling with chemical reaction was investigated for ammonia removal from waste air using a packedcolumn. The packed column of 10 cm diameter and 200 cm height was packed with 1.4x1.4 cm Raschig rings. Three liquids including water, NaOCl and H2SO4 solution were used as an absorbent for the investigation.The objectives of this research were to determine a suitable absorbent and the optimum condition for ammonia removal from waste air. The packed column was operated at room temperature and atmosphericpressure. The tested conditions were as follows: the gas to liquid ratio (G:L ratio was 35-90 m3 gas/m3 liquid, the inlet concentration of ammonia was 150-500 ppm and the air flow rate was 18 m3/h. The results showedthat the ammonia removal efficiency depends on type of the absorbent and the operating condition. The efficiencies increased with decreasing of G:L ratio and with increasing absorbent concentration. They were70%, 80-92%, and 95-100% for pure water, sodium hypochlorite solution and sulphuric acid solution, respectively. The efficiency decreased with time when water was used as an absorbent while it was almostconstant when NaOCl and H2SO4 solution were applied. The ammonia removal efficiency when using H2SO4 as the absorbent was not dependent on G:L ratio and inlet ammonia concentration, in the range used in thisinvestigation. Since H2SO4 solution gave the highest removal efficiency and can reduce ammonia concentration in waste air to levels which meet the TLV-TWA standard, it is recommended as an absorbent solution forammonia removal from waste air.

Air conditioning device for pool facilities in nuclear power plant buildings

International Nuclear Information System (INIS)

Taruishi, Yoshiaki; Ishida, Seiji.

1981-01-01

Purpose: To improve the temperature and humidity conditions for the working circumstance, prevent condensations on the wall surface and enable the reduction in the irradiation exposure to workers. Constitution: Air intake ports are provided on the side wall of a fuel storage pool or an equipment installation pool above the water level and connected by way of their exhaust ducts to the exhaust ducts of an air ventilation system. While on the other hand, air feed ducts having horizontally opened blowing ports and air exhaust ducts having horizontally opened exhaust ports above and in adjacent to the air feed ducts are provided on the side walls of the pool buildings at the height near the floor level. With this structure, fresh outdoor airs blown out horizontally from the blowing ports provided near the floor level can improve the temperature and humidity conditions of the working circumstance for the workers working on the floor. Further, an air clean up device is provided to the feed and exhaust systems for clean up the feed and exhaust airs. (Furukawa, Y.)

Application of reverse osmosis to the treatment of liquid effluents produced by nuclear power plants

International Nuclear Information System (INIS)

Huet, Y.; Poulat, B.; Menjeaud, C.

1989-01-01

Radioactive liquid effluents generated during the operation of PWR nuclear power units are currently treated by two independent systems. The effluents from the reactor coolant system are recycled, unlike the others, which, after treatment, are released into the river or ocean that provides cooling water for the unit. The objective of the treatment of nonrecycled effluents is to separate from them as much of the radioactive particles that they contain as possible, so as to release into the environment a maximum volume of nonradioactive waste, and to be left with only a minimum volume of concentrated waste, containing most of the initial radioactivity, which must be loaded into casks for storage. Membrane-based filtration techniques, because they have excellent separation performances, can logically be used for this decontamination of the liquid effluents. Having developed its own reverse osmosis membrane, a possible application in a nuclear power plant, i.e., integration of a reverse osmosis unit into a radioactive liquid effluent treatment system is presented. (author)

Status, direction, and critical issues of waste treatment technology

International Nuclear Information System (INIS)

Knowlton, D.E.; Bonner, W.F.

1983-06-01

Nuclear power production and related activities generate radioactive wastes that must be safely managed to protect workers and the general public. The liquid-fed ceramic melting (LFCM) vitrification process is the reference process for vitrifying high-level nuclear waste in the US as well as in Japan and India. The French are currently using a rotary kiln calciner/metallic melter system at their reprocessing facility. Compaction or controlled-air incineration are the currently preferred options for low-level waste solids, followed by immobilization in an appropriate matrix. The Nuclear Waste Policy Act of 1982 is a significant step in proceeding with waste treatment and disposal. Programs can now build on past work to assure that public safety and regulations atre met in a cost-effective manner. 7 references, 2 figures, 3 tables

Storage and treatment of SNF of Alfa class nuclear submarines: current status and problems

International Nuclear Information System (INIS)

Ignatiev, Sviatoslav; Zabudko, Alexey; Pankratov, Dmitry; Somov, Ivan; Suvorov, Gennady

2007-01-01

Available in abstract form only. Full text of publication follows: The current status and main problems associated with storage, defueling and following treatment of spent nuclear fuel (SNF) of Nuclear Submarines (NS) with heavy liquid metal cooled reactors are considered. In the final analysis these solutions could be realized in the form of separate projects to be funded through national and bi- and multilateral funding in the framework of the international collaboration of the Russian Federation on complex utilization of NS and rehabilitation of contaminated objects allocated in the North-West region of Russia. (authors)

Seismic evaluation of nuclear installations

International Nuclear Information System (INIS)

Mattar Neto, Miguel

1997-01-01

Some considerations regarding extreme external events, natural or man-induce, such as earthquakes, floods, air crashes, etc, shall be done for nuclear facilities to minimizing the potential impact of the installation on the public and the environment. In this paper the main aspects of the seismic evaluation of nuclear facilities (except the nuclear power reactors) will be presented based on different codes and standards. (author). 7 refs., 2 tabs

Controlled air pyrolysis incinerator

International Nuclear Information System (INIS)

Dufrane, K.H.; Wilke, M.

1982-01-01

An advanced controlled air pyrolysis incinerator has been researched, developed and placed into commercial operation for both radioactive and other combustible wastes. Engineering efforts cocentrated on providing an incinerator which emitted a clean, easily treatable off-gas and which produced a minimum amount of secondary waste. Feed material is continuously fed by gravity into the system's pyrolysis chamber without sorting, shredding, or other such pretreatment. Metal objects, liquids such as oil and gasoline, or solid products such as resins, blocks of plastic, tire, animal carcasses, or compacted trash may be included along with normal processed waste. The temperature of the waste is very gradually increased in a reduced oxygen atmosphere. Volatile pyrolysis gases are produced, tar-like substances are cracked and the resulting product, a relatively uniform, easily burnable material, is introduced into the combustion chamber. Steady burning is thus accomplished under easily controlled excess air conditions with the off-gasthen passing through a simple dry clean-up system. Gas temperatures are then reduced by air dilution before passing through final HEPA filters. Both commercial and nuclear installations have been operated with the most recent application being the central incinerator to service West Germany's nuclear reactors

Nuclear power and the nuclear fuel cycle

International Nuclear Information System (INIS)

Hardy, C.J.; Silver, J.M.

1985-09-01

The report provides data and assessments of the status and prospects of nuclear power and the nuclear fuel cycle. The report discusses the economic competitiveness of nuclear electricity generation, the extent of world uranium resources, production and requirements, uranium conversion and enrichment, fuel fabrication, spent fuel treatment and radioactive waste management. A review is given of the status of nuclear fusion research

Development of a method to measure the concentration of 14C in the stack air of nuclear power plants by accelerator mass spectrometry (AMS)

International Nuclear Information System (INIS)

Stenstroem, K.; Erlandsson, B.; Hellborg, R.; Haakansson, K.; Wiebert, A.; Skog, G.

1993-04-01

C-14, a pure low-energetic beta-emitter, is produced through various nuclear reactions in nuclear power plants. Some of this C-14 is air-borne and is transported via the ventilation system through the stack of the power station and is integrated in living matter in the surroundings of the plant. The long half-life of the isotope (T1/2=5730 years) and the biological importance of carbon may lead to a not negligible contribution of the radiation dose for those living in the neighbourhood of nuclear power plants. C-14 has earlier been measured radiometrically with mainly two different methods, using proportional counters or liquid scintillators. In this report a new method is described, using an accelerator based technique. accelerator mass spectrometry (AMS). This technique has at least three advantages over the radiometrical methods. It requires only a few litres of gas per sample, which is 100-1000 times less compared to the radiometrical methods. It is insensitive to the beta and gamma rays from other radioactive isotopes in the stack air. The measuring time with AMS, about 20 minutes per sample, is considerably shorter compared to the radiometrical methods, which demand several hours per sample. The integrity of the AMS method is high and it might be convenient for regulatory supervision. (22 refs.)

Radionuclides in ground-level air

International Nuclear Information System (INIS)

Sinkko, K.

1987-01-01

In the air surveillance programme the concentrations of artificial radionuclides are monitored in the air close to the ground to obtain the necessary basic data for estimating the exposure of the Finnish population to fall-out radionuclides and also to detect atmospheric traces of radioactive materials caused by their use or production. Airborne dust is collected on filters with high-volume air samplers and the concentrations of gamma-emitting radionuclides in the air are evaluated. In the first quarter of 1986 only long-lived cesium, caused by earlier atmospheric nuclear explosions was detected. The concentrations of cesium were very low. In January and March a small amount of short-lived, fresh fission and activation products were also observed

Data acquisition and treatment unit for use in nuclear medicine

Energy Technology Data Exchange (ETDEWEB)

Annaix, C; Prieur, G; Vilayleck, S; Jallet, P [C.H.R., Angers (France)

1981-01-01

Here is below a one-channel data acquisition unit piloted through a minicomputer programmed by means of an advanced language of the Basic type. This unit allows, especially in nuclear medicine, pulse counts from a spectrometer according to a programmed sequence. Moreover, it provides treatment of measures as well as printing and filing of interpreted results. The acquisition unit is linked to the minicomputer through a RS 232 C serial mode, which ensures both easy operation and universal use of the system here described. Accuracy of measurement is also examined.

The effect of mercuric chloride treatment as biocide for herbaria on the indoor air quality

NARCIS (Netherlands)

Havermans, J.B.G.A.; Dekker, R.; Sportel, R.

2015-01-01

One of the most previous conservation treatments for plant specimen in herbarium collections was mercuric chloride (HgCl2). However, due time HgCl2 may decompose and it may cause (metallic) mercury (Hg) emission. Hg vapour in indoor air should be avoided as mercury poisoning can already occur at

Nuclear industry technology boomerang

International Nuclear Information System (INIS)

Scholler, R.W.

1987-01-01

The benefits to the medical, pharmaceutical, semiconductor, computer, video, bioscience, laser, defense, and numerous high-tech industries from nuclear technology development fallout are indeed numerous and increase every day. Now those industries have made further progress and improvements that, in return, benefit the nuclear industry. The clean-air and particle-free devices and enclosures needed for protection and decontamination are excellent examples

Occupational and public radiation protection in the treatment with iodine 131

International Nuclear Information System (INIS)

Di Trano, Jose L.; Rojo, Ana M.; Kunst, Juan J.

2004-01-01

A common radionuclide therapy carried out by nuclear medicine departments is the administration of 131 I for thyroid ablation and for hyperthyroid treatment. The administration of 140 a 600 MBq for hyperthyroid treatment and 3700 a 7400 MBq for carcinoma diseases is made after surgery to ablate thyroid tissues and metastasis. The revision of radiological protection was done on the occupational exposure of workers, members of the public and relatives of patients treated with 131 I. This paper presents the results of area and individual dosimetry to external exposure, surface activity and air concentration of 131 I carried out during the practice in the nuclear medicine department. An area survey in the isolation room allowed to determine exposure rate from surface activity and air concentration of 131 I. The patient clothes activity was determined as well as the activity excreted in urine and sweat. On the basis of this analysis, can be concluded that the annual effective dose for workers due to external and internal exposure, considering 40 iodine practice per year, reach values from 4 up to 30 mSv per year. The patients with cancer therapy treatment must be hospitalized during the first 48 hrs after iodine administration, in an isolated room taking into account the radioprotection of the staff, others patients and public during the isolation. The patients with hyperthyroid treatment do not need hospitalization but they must to follow the instructions given by the physician, which will take into account socioeconomic conditions. (author)

Nuclear war hazards

International Nuclear Information System (INIS)

Chazov, E.I.; Il'in, L.A.; Gus'kova, A.K.

1982-01-01

An attempt is made to forecast medical and bilogical and aftereffects of nuclear weapons application in a number of situations. In particular, the effects of a single high-yield air or surface nuclear explosion on a city with 1 mln population are considered as well as the aftereffects of the exposure of human beings to local radioactive fallouts outside the ground zero of a surface nuclear explosion. The aftereffects for the population of local and global radioactive fallouts caused by the realization of one of the adopted in the West variants of mass nuclear strives exchange between the hostile sides are estimated. Certain aspects of medical and biological aftereffects of neutron weapons application are discussed

Treatment of waste incinerator air-pollution-control residues with FeSO4: Concept and product characterization

DEFF Research Database (Denmark)

Lundtorp, Kasper; Jensen, Dorthe Lærke; Sørensen, Mette Abildgaard

2002-01-01

This paper describes a new concept for treatment of air- pollution-control (APC) residues from waste incineration and characterises the wastewater and stabilised residues generated by the process. The process involves mixing of APC-residues with a ferrous sulphate solution and subsequent oxidation...

Dry-air drying at room temperature - a practical pre-treatment method of tree leaves for quantitative analyses of phenolics?

Science.gov (United States)

Tegelberg, Riitta; Virjamo, Virpi; Julkunen-Tiitto, Riitta

2018-03-09

In ecological experiments, storage of plant material is often needed between harvesting and laboratory analyses when the number of samples is too large for immediate, fresh analyses. Thus, accuracy and comparability of the results call for pre-treatment methods where the chemical composition remains unaltered and large number of samples can be treated efficiently. To study if a fast dry-air drying provides an efficient pre-treatment method for quantitative analyses of phenolics. Dry-air drying of mature leaves was done in a drying room equipped with dehumifier (10% relative humidity, room temperature) and results were compared to freeze-drying or freeze-drying after pre-freezing in liquid nitrogen. The quantities of methanol-soluble phenolics of Betula pendula Roth, Betula pubescens Ehrh., Salix myrsinifolia Salisb., Picea abies L. Karsten and Pinus sylvestris L. were analysed with HPLC and condensed tannins were analysed using the acid-butanol test. In deciduous tree leaves (Betula, Salix), the yield of most of the phenolic compounds was equal or higher in samples dried in dry-air room than the yield from freeze-dried samples. In Picea abies needles, however, dry-air drying caused severe reductions in picein, stilbenes, condensed tannin and (+)-catechin concentrations compared to freeze-drying. In Pinus sylvestris highest yields of neolignans but lowest yields of acetylated flavonoids were obtained from samples freeze-dried after pre-freezing. Results show that dry-air drying provides effective pre-treatment method for quantifying the soluble phenolics for deciduous tree leaves, but when analysing coniferous species, the different responses between structural classes of phenolics should be taken into account. Copyright © 2018 John Wiley & Sons, Ltd.

Control in indoor radon decay products by air treatment devices

International Nuclear Information System (INIS)

Hinds, W.C.; Rudnick, S.N.; Maher, E.F.; First, M.W.

1983-01-01

An evaluation of the efficacy of household air cleaning devices as a means to control radon decay products in existing buildings is presented. Previous research on air cleaning methods for airborne radon decay products has been directed primarily to the control of radon decay products in mines and has only limited application to control in residences where dust concentration, air change rate, and humidity are lower than in mines. Results show that room size air cleaners can achieve substantial reductions in working levels in residences. Reductions observed at air infiltration rates of 0.52 air changes per hour ranged from 58 to 89%. Although the two air cleaners tested produced the greatest reductions, the low cost, simplicity, and other benefits of air circulating fans, particularly the ceiling fan, appear to make them most suitable for residences

The Defense Science Board Permanent Task Force on Nuclear Weapons Surety. Report on the Unauthorized Movement of Nuclear Weapons

National Research Council Canada - National Science Library

Welch, Larry D; Agnew, Harold M; Bien, Lyle G; Crawford, John C; Foster, Jr., John S; Gold, Sydell P; McCarthy, James P; Mies, Richard W; Neary, Thomas H; Selden, Robert L

2008-01-01

...]) and the Commander, U.S. Strategic Command to conduct an independent investigation of the unauthorized transfer of nuclear warheads between Minot Air Force Base, North Dakota, and Barksdale Air Force Base, Louisiana on 30 August 2007...

Qualification of box HEPA filters for nuclear applications

International Nuclear Information System (INIS)

Bergman, W.; Larsen, G.; Wilson, K.; Rainer, F.

1995-03-01

We have successfully completed qualification tests on high efficiency particulate air (HEPA) filters that are encapsulated within a box and manufactured by American Air Filters. The qualification tests are required by the American Society of Mechanical Engineers Standard ASME N509 and the U.S. Military Standard MIL-F-51068 for HEPA filters to be used in nuclear applications. The qualification tests specify minimum filter efficiencies following exposure to heated air, overpressure, and rough handling. Prior to this study, no box HEPA filters from any manufacturer had been qualified despite their wide-spread use in Department of Energy (DOE) facilities. Box HEPA filters are not addressed in any of the existing HEPA standards and only briefly discussed in the Nuclear Air Cleaning Handbook

Nuclear-specific AR-V7 Protein Localization is Necessary to Guide Treatment Selection in Metastatic Castration-resistant Prostate Cancer.

Science.gov (United States)

Scher, Howard I; Graf, Ryon P; Schreiber, Nicole A; McLaughlin, Brigit; Lu, David; Louw, Jessica; Danila, Daniel C; Dugan, Lyndsey; Johnson, Ann; Heller, Glenn; Fleisher, Martin; Dittamore, Ryan

2017-06-01

Circulating tumor cells (CTCs) expressing AR-V7 protein localized to the nucleus (nuclear-specific) identify metastatic castration-resistant prostate cancer (mCRPC) patients with improved overall survival (OS) on taxane therapy relative to the androgen receptor signaling inhibitors (ARSi) abiraterone acetate, enzalutamide, and apalutamide. To evaluate if expanding the positivity criteria to include both nuclear and cytoplasmic AR-V7 localization ("nuclear-agnostic") identifies more patients who would benefit from a taxane over an ARSi. The study used a cross-sectional cohort. Between December 2012 and March 2015, 193 pretherapy blood samples, 191 of which were evaluable, were collected and processed from 161 unique mCRPC patients before starting a new line of systemic therapy for disease progression at the Memorial Sloan Kettering Cancer Center. The association between two AR-V7 scoring criteria, post-therapy prostate-specific antigen (PSA) change (PTPC) and OS following ARSi or taxane treatment, was explored. One criterion required nuclear-specific AR-V7 localization, and the other required an AR-V7 signal but was agnostic to protein localization in CTCs. Correlation of AR-V7 status to PTPC and OS was investigated. Relationships with survival were analyzed using multivariable Cox regression and log-rank analyses. A total of 34 (18%) samples were AR-V7-positive using nuclear-specific criteria, and 56 (29%) were AR-V7-positive using nuclear-agnostic criteria. Following ARSi treatment, none of the 16 nuclear-specific AR-V7-positive samples and six of the 32 (19%) nuclear-agnostic AR-V7-positive samples had ≥50% PTPC at 12 weeks. The strongest baseline factor influencing OS was the interaction between the presence of nuclear-specific AR-V7-positive CTCs and treatment with a taxane (hazard ratio 0.24, 95% confidence interval 0.078-0.79; p=0.019). This interaction was not significant when nuclear-agnostic criteria were used. To reliably inform treatment selection

New developments in the air transport of plutonium

International Nuclear Information System (INIS)

Andersen, J.A.

1978-01-01

A new package for the air transport of plutonium has been developed in response to a United States Public Law which restricts the U.S. air transport of plutonium except for small medical devices. This new package, called PAT-1 for plutonium air transportable package model 1, is the result of the NRC-sponsored (NRC=U.S. Nuclear Regulatory Commission.) PARC (plutonium accident resistant container) project at Sandia Laboratories, Albuquerque. The PAT-1 package is designed to meet or exceed new criteria specified in NUREG-0360. These inclued a severe test sequence of impact (>250 knots) on an unyielding target, crush, puncture, slash, a large JP-4 fire for 1 hour, followed by water immersion, with stringent acceptance standards on plutonium release, nuclear shielding, and nuclear criticality. The PAT-1 package design features a high energy absorption capability with high-level fire protection. It weighs approximately 227 kg (500 lb) when loaded with 2 kg PuO 2 , and can accommodate up to 25 watts thermal energy from the plutonium load

Review of the environmental impact of nuclear energy

Energy Technology Data Exchange (ETDEWEB)

El-Hinnawi, E E

1978-04-01

The radioactivity released from the products of nuclear fission is the main focus of public concern about the expansion in the use of nuclear power despite stringent control measures and precautions taken. Environmental impacts associated with all the steps in the nuclear fuel cycle are examined. Discussed are: uranium mining and milling, manufacture of fuel elements for the reactor, transport and reprocessing of irradiated fuel, reactor operation, and management of wastes produced in the cycle. Environmental impacts of a coal-fired power plant are compared with impacts of three nuclear plants with the same generating capacities. Impacts compared are thermal heat waste, effluent radioactivity, air pollution, radioactive and ash waste products, and land used for the plant. The environmental advantages of the nuclear reactors occur in the categories of air pollutant effluents and land used for plants. (45 references, 3 tables)

Specialized medical sections for the treatment of radiation injuries from accidents in nuclear power plants

International Nuclear Information System (INIS)

Deanovic, Z.; Boranic, M.; Vitale, B.

1980-01-01

Presented is the organization of the final, highly specialized treatment (diagnostic and therapeutic) of persons that have been severely injured in a radiation or nuclear accident. In this organizational scheme, the leading idea was to group and establish suitable medical sections for the acceptance, diagnosic work-up, and treatment of radiation casualties, around a strong medical center in which the different specialists would be available

Effects of welding fumes on nuclear air cleaning system carbon adsorber banks

Energy Technology Data Exchange (ETDEWEB)

Roberson, P.W. [Duke Power Company, Huntersville, NC (United States)

1997-08-01

Standard Technical Specifications for nuclear air cleaning systems include requirements for surveillance tests following fire, painting, or chemical release in areas communicating with the affected system. To conservatively implement this requirement, many plants categorize welding as a chemical release process, and institute controls to ensure that welding fumes do not interact with carbon adsorbers in a filter system. After reviewing research data that indicated welding had a minimal impact on adsorber iodine removal efficiency, further testing was performed with the goal of establishing a welding threshold. It was anticipated that some quantity of weld electrodes could be determined that had a corresponding detrimental impact on iodine removal efficiency for the exposed adsorber. This value could be used to determine a conservative sampling schedule that would allow the station to perform laboratory testing to ensure system degradation did not occur without a full battery of surveillance tests. A series of tests was designed to demonstrate carbon efficiency versus cumulative welding fume exposure. Three series of tests were performed, one for each of three different types of commonly used weld electrodes. Carbon sampling was performed at baseline conditions, and every five pounds of electrode thereafter. Two different laboratory tests were performed for each sample; one in accordance with ASTM 3803/1989 at 95% relative humidity and 30 degrees C, and another using the less rigorous conditions of 70% relative humidity and 80 degrees C. Review of the test data for all three types of electrodes failed to show a significant correlation between carbon efficiency degradation and welding fume exposure. Accordingly, welding is no longer categorized as a `chemical release process` at McGuire Nuclear Station, and limits on welding fume interaction with ventilation systems have been eliminated. 4 refs., 3 figs., 1 tab.

Isopleths of surface air concentration and surface air kerma rate due to a radioactive cloud released from a stack (3)

International Nuclear Information System (INIS)

Tachibana, Haruo; Kikuchi, Masamitsu; Sekita, Tsutomu; Yamaguchi, Takenori

2004-06-01

This report is a revised edition of 'Isopleths of Surface Air Concentration and Surface Air Absorbed Dose Rate due to a Radioactive Cloud Released from a Stack(II) '(JAERI-M 90-206) and based on the revised Nuclear Safety Guidelines reflected the ICRP1990 Recommendation. Characteristics of this report are the use of Air Karma Rate (Gy/h) instead of Air Absorbed Dose Rate (Gy/h), and the record of isopleths of surface air concentration and surface air karma rate on CD-ROM. These recorded data on CD-ROM can be printed out on paper and/or pasted on digital map by personal computer. (author)

Project Increase of infrastructure: 'Establishment of a laboratory for studies of pollutants in air, water and soil through atomic and nuclear techniques

International Nuclear Information System (INIS)

Aldape U, F.

1993-10-01

In this report there are the guidelines of this project as well as the goals, activities and costs. The general objectives were: 1. A laboratory that allows to analyze with efficiency samples of air, water and soil pollutants using atomic and nuclear origin techniques as PIXE (Proton Induced X-ray Emission, NRA (Nuclear Reaction Analysis) and RBS (Rutherford Backscattering) as well as auxiliary and/or complementary techniques. 2. To obtain indicators of the influence of the pollution of the Valley of Mexico about the ecology and the health of the inhabitants of Mexico City with perspectives of carrying out studies in other cities. 3. To develop an appropriate technology for the realization of those studies and to generate human resources in this area. (Author)

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.)

Managing medical treatment waste and effluent: the point of view of a nuclear medicine practitioner

International Nuclear Information System (INIS)

Karcher, G.

2011-01-01

The nuclear medicine department of the Nancy CHU hospital is one of the largest in France: 16.000 patients are welcomed each year and 4.000 persons undergo a tomography there. 5 shielded and isolated rooms, dedicated to Iodine 131 treatment, allow the care of 150 to 200 patients each year. The head of the nuclear medicine department gives his meaning about the new regulation on the management of radioactive effluents. According to him, regulations are necessary but the values of the imposed thresholds have to be scientifically justified. Another point is that a lot of money is spent on radiation protection issues while the radioactive risks are almost null, which leads to wasting money. The elaboration of the radioprotection regulations must be made not as a whole but on a specific basis according to the domain: nuclear power plants, research reactors or nuclear medicine, it applies. (A.C.)

Tritium as an indicator of venues for nuclear tests.

Science.gov (United States)

Lyakhova, O N; Lukashenko, S N; Mulgin, S I; Zhdanov, S V

2013-10-01

Currently, due to the Treaty on the Non-proliferation of Nuclear Weapons there is a highly topical issue of an accurate verification of nuclear explosion venues. This paper proposes to consider new method for verification by using tritium as an indicator. Detailed studies of the tritium content in the air were carried in the locations of underground nuclear tests - "Balapan" and "Degelen" testing sites located in Semipalatinsk Test Site. The paper presents data on the levels and distribution of tritium in the air where tunnels and boreholes are located - explosion epicentres, wellheads and tunnel portals, as well as in estuarine areas of the venues for the underground nuclear explosions (UNE). Copyright © 2013 Elsevier Ltd. All rights reserved.

Radioactive air sampling methods

CERN Document Server

Maiello, Mark L

2010-01-01

Although the field of radioactive air sampling has matured and evolved over decades, it has lacked a single resource that assimilates technical and background information on its many facets. Edited by experts and with contributions from top practitioners and researchers, Radioactive Air Sampling Methods provides authoritative guidance on measuring airborne radioactivity from industrial, research, and nuclear power operations, as well as naturally occuring radioactivity in the environment. Designed for industrial hygienists, air quality experts, and heath physicists, the book delves into the applied research advancing and transforming practice with improvements to measurement equipment, human dose modeling of inhaled radioactivity, and radiation safety regulations. To present a wide picture of the field, it covers the international and national standards that guide the quality of air sampling measurements and equipment. It discusses emergency response issues, including radioactive fallout and the assets used ...

Lin's theory of flux and nuclear reactions

International Nuclear Information System (INIS)

Ping-Wha Lin

2002-01-01

Mathematical development of Lin's theory of flux is presented. Based on the Theory, when a chemical reaction system is subjected to a high time rate of temperature change, it changes from equilibrium to non-equilibrium conditions. It is proved mathematically that, when a gas system is subjected to a high time rate of temperature increase, the activities of particles (molecules, atoms or nuclei, and electrons) are increased: the particles are accelerated; frequencies and amplitudes of electron and atomic vibrations in a molecule increased; average kinetic energy of the particles increased; atomic bonds are ruptured; electrons are caused to leave their orbits. If most or all of the electrons leave their orbits, the gas fluid becomes plasma, which is very active chemically. The acceleration of nuclei in the dynamic condition can lead to nuclear reactions. In the pilot plant studies conducted at Research Triangle, NC, USA, for SO 2 conversion to SO 3 by rapid heating, a 10-ft high vertically fired combustor (VFC) was used. Air containing 0.5% SO 2 is forced continuously through the VFC, where it is heated by burners for conversion of SO 2 to SO 3 . During the idle period of operation, no external heat is added to the system by turning off the burners. It is observed that, as the air passing through the VFC during the idle period of sixteen hours, the temperature of the flowing air consistently rises up rapidly from ambient temperature (90 deg F) at inlet of the VFC to an average temperature as high as 582 deg F (in the range of 840 deg F to 455 deg F) at one section of the VFC, an increase of about 500 deg F. The air flow temperature increase of such large magnitude and long duration clearly indicates that nuclear reactions are present in VFC. It is also found that the water vapour in the air stream has completely disappeared in the VFC, for no sulphuric acid formation resulting from the reaction of water and SO 3 is detected there. Presumably, the water vapour in the

Metal waste forms from the electrometallurgical treatment of spent nuclear fuel

International Nuclear Information System (INIS)

Abraham, D.P.; McDeavitt, S.M.; Park, J.

1996-01-01

Stainless steel-zirconium alloys are being developed for the disposal of radioactive metal isotopes isolated using an electrometallurgical treatment technique to treat spent nuclear fuel. The nominal waste forms are stainless steel-15 wt% zirconium alloy and zirconium-8 wt% stainless steel alloy. These alloys are generated in yttria crucibles by melting the starting materials at 1,600 C under an argon atmosphere. This paper discusses the microstructures, corrosion and mechanical test results, and thermophysical properties of the metal waste form alloys

Risk assessment of intake of foods and soil, and air radiation dose after Fukushima Daiichi nuclear disaster

International Nuclear Information System (INIS)

Fujinaga, Aiichiro; Yoneda, Minoru; Ikegami, Maiko

2012-01-01

Risk assessment of soil contaminated with radionuclides, due to the accident of Fukushima nuclear power plant after the earthquake on March 11, 2011, was carried out by considering consumption of the contaminated food. The exposure routes were set as food intake, ingestion and inhalation of soil particles, and external radiation from the ground. As a result, exposures by ingestion, and inhalation of soil particles were negligible, and exposure by food intake and external exposure from the ground were comparatively large. This study shows air dose by the accident should be under 0.2 μSv/hour in order to control the radiation dose with consumption of food under 1 μSv/year. (author)

Development of the detection technology of the source area derived from nuclear activities

International Nuclear Information System (INIS)

Suh, Kyungsuk; Kim, Ingyu; Keum, Dongkwon; Lim, Kwangmuk; Lee, Jinyong

2012-07-01

- It is necessary to establish of the overall preparedness for analysis of the nuclear activities near the neighboring countries by increasing of the construction of the nuclear power plants and reprocessing facilities in China, North Korean Japan and Russia. - In Korea, the analysis and measurements for nuclear activities have been conducted, however the detection technology to find out the source area has not been developed. It is important to estimate the source origin of the radioisotope from the neighboring countries including Korea in the aspects of the surveillance and safety for the covert nuclear activities in Northeast Asia region - In this study, the data DB, treatment of the weather data and the development of connection module were conducted to track the origin of the radioisotope in the first year of the research. It had constructed the DB like the reactor types, places in China, Taiwan, Japan and Korea and the release amounts of the noble gas released into the air

Development of the detection technology of the source area derived from nuclear activities

Energy Technology Data Exchange (ETDEWEB)

Suh, Kyungsuk; Kim, Ingyu; Keum, Dongkwon; Lim, Kwangmuk; Lee, Jinyong

2012-07-15

- It is necessary to establish of the overall preparedness for analysis of the nuclear activities near the neighboring countries by increasing of the construction of the nuclear power plants and reprocessing facilities in China, North Korean Japan and Russia. - In Korea, the analysis and measurements for nuclear activities have been conducted, however the detection technology to find out the source area has not been developed. It is important to estimate the source origin of the radioisotope from the neighboring countries including Korea in the aspects of the surveillance and safety for the covert nuclear activities in Northeast Asia region - In this study, the data DB, treatment of the weather data and the development of connection module were conducted to track the origin of the radioisotope in the first year of the research. It had constructed the DB like the reactor types, places in China, Taiwan, Japan and Korea and the release amounts of the noble gas released into the air.

[Hygienic relevance of devices for indoor air treatment].

Science.gov (United States)

Wegner, J

1982-01-01

Shortcomings regarding design, construction, operation (including emissions), maintenance/repair and control of buildings with rooms for the accommodation of persons may be the reason to install air conditioning devices. According to manufacturers' data, such devices may be applied for various purposes, e.g. the creation of a defined air temperature or humidity, an increase of the supply of outdoor air, the cleaning and deodorization of indoor air or the alteration of the so-called electric climate of a room. The hygienic health evaluation of the different types of air conditioning devices should establish whether --there are aspects of health necessitating alterations of the microclimate of a room; --such alterations could be brought about in a more economic way by purely constructional or individual measures; --the function of individual apparatuses could be accomplished in a better way by replacing them by a larger device serving several rooms; --the operation of such devices may produce adverse health effects such as nuisance by noise, formation of undesirable gases (ozone), danger owing to non-adherence to electric safety rules; --there will be no damage to rooms and furniture, e.g. by water droplets. A look at a number of commercially available devices shows that they are generally dispensable. There are, however, special rare cases where the use of such devices may result in an improvement of the quality of indoor environments.

Sewage sludge as a sensitive indicator for airborne radionuclides from nuclear power plants

International Nuclear Information System (INIS)

Ingemansson, T.

1982-01-01

Sewage sludge collected at waste water treatment plants located in the vicinity of nuclear power stations, has been shown to be a sensitive and convenient indicator for airborne locally released activation products, 60 Co, 65 Zn, 58 Co and 54 Mn. We have therefore been able to study the distribution and behaviour of these radionuclides in the terrestrial environment of three Swedish nuclear power stations. Comparative measurements on ground level air and on samples of lichen (Cladonia alpestris) and soil have also been performed. The variation by distance from the power station of 60 Co measured in sludge as well as on air-filters could be described by the same power function. The temporal variation of the activity concentration in sludge samples well reflects the variation of the reported release rate of airborne radionuclides from the power stations if the prevalent wind direction is taken into consideration. The relation between the activity ratio 60 Co/ 7 Be in air and in sludge was investigated and indicated that most of the detected 60 Co and part of 58 Co and 54 Mn activity is released from a local source and is dry deposited on the ground before it is washed off by rain. (Author)

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

Surface treatment of polyethylene terephthalate film using atmospheric pressure glow discharge in air

International Nuclear Information System (INIS)

Fang Zhi; Qiu Yuchang; Wang Hui

2004-01-01

Non-thermal plasmas under atmospheric pressure are of great interest in polymer surface processing because of their convenience, effectiveness and low cost. In this paper, the treatment of Polyethylene terephthalate (PET) film surface for improving hydrophilicity using the non-thermal plasma generated by atmospheric pressure glow discharge (APGD) in air is conducted. The discharge characteristics of APGD are shown by measurement of their electrical discharge parameters and observation of light-emission phenomena, and the surface properties of PET before and after the APGD treatment are studied using contact angle measurement, x-ray photoelectron spectroscopy (XPS) and scanning electron microscopy (SEM). It is found that the APGD is homogeneous and stable in the whole gas gap, which differs from the commonly filamentary dielectric barrier discharge (DBD). A short time (several seconds) APGD treatment can modify the surface characteristics of PET film markedly and uniformly. After 10 s APGD treatment, the surface oxygen content of PET surface increases to 39%, and the water contact angle decreases to 19 degree, respectively. (authors)

[Measures against Radiation Exposure Due to Large-Scale Nuclear Accident in Distant Place--Radioactive Materials in Nagasaki from Fukushima Daiichi Nuclear Power Plant].

Science.gov (United States)

Yuan, Jun; Sera, Koichiro; Takatsuji, Toshihiro

2015-01-01

To investigate human health effects of radiation exposure due to possible future nuclear accidents in distant places and other various findings of analysis of the radioactive materials contaminating the atmosphere of Nagasaki due to the Fukushima Daiichi Nuclear Power Plant accident. The concentrations of radioactive materials in aerosols in the atmosphere of Nagasaki were measured using a germanium semiconductor detector from March 2011 to March 2013. Internal exposure dose was calculated in accordance with ICRP Publ. 72. Air trajectories were analyzed using NOAA and METEX web-based systems. (134)Cs and (137)Cs were repeatedly detected. The air trajectory analysis showed that (134)Cs and (137)Cs flew directly from the Fukushima Daiichi Nuclear Power Plant from March to April 2011. However, the direct air trajectories were rarely detected after this period even when (134)Cs and (137)Cs were detected after this period. The activity ratios ((134)Cs/(137)Cs) of almost all the samples converted to those in March 2011 were about unity. This strongly suggests that the (134)Cs and (137)Cs detected mainly originated from the Fukushima Daiichi Nuclear Power Plant accident in March 2011. Although the (134)Cs and (137)Cs concentrations per air volume were very low and the human health effects of internal exposure via inhalation is expected to be negligible, the specific activities (concentrations per aerosol mass) were relatively high. It was found that possible future nuclear accidents may cause severe radioactive contaminations, which may require radiation exposure control of farm goods to more than 1000 km from places of nuclear accidents.

Nuclear reaction data and nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Paver, N [University of Trieste (Italy); Herman, M [International Atomic Energy Agency, Vienna (Austria); Gandini, A [ENEA, Rome (Italy)

2001-12-15

These two volumes contain the lecture notes of the workshop 'Nuclear Reaction Data and Nuclear Reactors: Physics, Design and Safety', which was held at the Abdus Salam ICTP in the Spring of 2000. The workshop consisted of five weeks of lecture courses followed by practical computer exercises on nuclear data treatment and design of nuclear power systems. The spectrum of topics is wide enough to timely cover the state-of-the-art and the perspectives of this broad field. The first two weeks were devoted to nuclear reaction models and nuclear data evaluation. Nuclear data processing for applications to reactor calculations was the subject of the third week. On the last two weeks reactor physics and on-going projects in nuclear power generation, waste disposal and safety were presented.

Ex-vacuo nuclear reaction analysis of deuterium

International Nuclear Information System (INIS)

Lee, S.R.; Doyle, B.L.

1989-01-01

A novel technique for performing in-air d( 3 He, p) nuclear reaction analysis of deuterium using external 3 He ion beams ranging in energy from 0.3-2.0 MeV is presented. Variable on-target beam energies for the depth profiling of deuterium are obtained by varying the transmission distance of the external 3 He beam in air. The ex-vacuo nuclear reaction analysis (XNRA) apparatus is described, and unique aspects and limitations of in-air depth profiling of deuterium using the d( 3 He, p) reaction are discussed. Example analyses where XNRA has been used for the multidimensional measurement of deuterium in fusion reactor components are presented in order to illustrate the advantages of XNRA for deuterium. These advantages include nondestructive analysis of large targets, efficient depth profiling via variable air gap energy tuning, and rapid analysis of numerous samples in the absence of vacuum cycling. (orig.)

Measurement of volumic activities of radon in air in houses and in working rooms with solid state nuclear track detectors

International Nuclear Information System (INIS)

Hakam, O.K.

1993-01-01

In this work, a new method of measuring volumic activity of radon has been developed. This method is based on using solid state nuclear track detectors LR-115 type II. It has been applied to measurement of volumic activities of radon in air in houses and in working rooms in different regions of Morocco. These measurements, carried out for the first time in the country, allowed to estimate the dose equivalents of radon received by the population of the studied regions. 59 refs., 38 figs., 38 tabs. (F.M.)

Radiological assessment of water treatment processes in a water treatment plant in Saudi Arabia: Water and sludge radium content, radon air concentrations and dose rates

Energy Technology Data Exchange (ETDEWEB)

Al-Jaseem, Q.Kh., E-mail: qjassem@kacst.edu.sa [Nuclear Science Research Institute (NSRI), King Abdulaziz City for Science and Technology (KACST), P.O. Box 6086, Riyadh 11442 (Saudi Arabia); Almasoud, Fahad I. [Nuclear Science Research Institute (NSRI), King Abdulaziz City for Science and Technology (KACST), P.O. Box 6086, Riyadh 11442 (Saudi Arabia); Ababneh, Anas M. [Physics Dept., Faculty of Science, Islamic University in Madinah, Al-Madinah, P.O. Box 170 (Saudi Arabia); Al-Hobaib, A.S. [Nuclear Science Research Institute (NSRI), King Abdulaziz City for Science and Technology (KACST), P.O. Box 6086, Riyadh 11442 (Saudi Arabia)

2016-09-01

There is an increase demand for clean water sources in Saudi Arabia and, yet, renewable water resources are very limited. This has forced the authorities to explore deep groundwater which is known to contain large concentrations of radionuclides, mainly radium isotopes. Lately, there has been an increase in the number of water treatment plants (WTPs) around the country. In this study, a radiological assessment of a WTP in Saudi Arabia was performed. Raw water was found to have total radium activity of 0.23 Bq/L, which exceeds the international limit of 0.185 Bq/L (5 pCi/L). The WTP investigated uses three stages of treatment: flocculation/sedimentation, sand filtration and reverse osmosis. The radium removal efficiency was evaluated for each stage and the respective values were 33%, 22% and 98%. Moreover, the activity of radium in the solid waste generated from the WTP in the sedimentation and sand filtrations stages were measured and found to be 4490 and 6750 Bq/kg, respectively, which exceed the national limit of 1000 Bq/kg for radioactive waste. A radiological assessment of the air inside the WTP was also performed by measuring the radon concentrations and dose rates and were found in the ranges of 2–18 Bq/m{sup 3} and 70–1000 nSv/h, respectively. The annual effective dose was calculated and the average values was found to be 0.3 mSv which is below the 1 mSv limit. - Highlights: • Radiological assessment of groundwater treatment plant was performed. • Radium Removal efficiency was calculated for different stages during water treatment. • Radium concentrations in sludge were measured and found to exceed the national limit for radioactive waste. • Air radon concentrations and dose rates were monitored in the water treatment plant. • The Reverse Osmosis (RO) unit was found to record the highest air radon concentrations and dose rates.

Diaphragms in air-operated valves

Energy Technology Data Exchange (ETDEWEB)

Groeger, J.E.

1996-12-01

The author will present current issues related to diaphgrams in air-operated valves. Altran Materials Engineering, Inc., often performs root-cause analyses for nuclear power plant owners. The author will discuss various analyses that have been performed or are currently underway.

Ventilating system for reprocessing of nuclear fuel rods

International Nuclear Information System (INIS)

Szulinski, M.J.

1981-01-01

In a nuclear facility such as a reprocessing plant for nuclear fuel rods, the central air cleaner discharging ventilating gas to the atmosphere must meet preselected standards not only as to the momentary concentration of radioactive components, but also as to total quantity per year. In order to comply more satisfactorily with such standards, reprocessing steps are conducted by remote control in a plurality of separate compartments. The air flow for each compartment is regulated so that the air inventory for each compartment has a slow turnover rate of more than a day but less than a year, which slow rate is conveniently designated as quasihermetic sealing. The air inventory in each such compartment is recirculated through a specialized processing unit adapted to cool and/or filter and/or otherwise process the gas. Stale air is withdrawn from such recirculating inventory and fresh air is injected (eg., By the less than perfect sealing of a compartment) into such recirculating inventory so that the air turnover rate is more than a day but less than a year. The amount of air directed through the manifold and duct system from the reprocessing units to the central air cleaner is less than in reprocessing plants of conventional design

Air ventilation/controlling facility

Energy Technology Data Exchange (ETDEWEB)

Yoshikawa, Kazuhiro; Kinoshita, Shoichiro

1997-12-12

When all electricity supply from the outside of a power plant are lost, a power generator directly connected to an emergency steam turbine which is driven by steams introduced from a nuclear reactor is driven to supply electricity required in the power plant. Cool water prepared by a refrigerator is used as cooling water in an air ventilation/controlling facility of a room equipped with the power generating facility. As the refrigerator, a refrigerator of an existent emergency air cooling water system for an auxiliary air ventilation/controlling equipment is used. This can extend the period of time till the temperature of the room where the power generator is disposed exceeds the temperature range capable of keeping the integrity of the power generator even when all the AC power supply are lost to inactivate the function of the air ventilation/controlling system. (I.S.)

Particulate filtration in nuclear facilities

International Nuclear Information System (INIS)

1991-01-01

The removal of particulate radioactive material from exhaust air or gases is an essential feature of virtually all nuclear facilities. Recent IAEA publications have covered the broad designs of off-gas and air cleaning systems for the range of nuclear power plants and other facilities. This report is a complementary guidebook that examines in detail the latest developments in the design, operation, maintenance and testing of fibrous air filters. The original draft of the report was prepared by three consultants, M.W. First, of the School of Public Health, Harvard University, United States of America, K.S. Robinson, from the UKAEA Harwell Laboratory, United Kingdom, and H.G. Dillmann, of the Kernforschungzentrum, Karlsruhe, Germany. The Technical Committee Meeting (TCM), at which the report was reviewed and much additional information contributed, was attended by 11 experts and was held in Vienna, from 30 May to 3 June 1988. 64 refs, 41 figs, 10 tabs

Nuclear energy in the space: panorama 1985

International Nuclear Information System (INIS)

Corcuera, R.P.

1985-01-01

A panoramic view of different areas where nuclear energy can be applied in space is given. These are: radioisotope thermoelectric generators, nuclear reactors for space stations, space crafts and air crafts. The principal difficulties are pointed out and the safety aspect is emphasized. (author)

Measurement of air dose rates over a wide area around the Fukushima Dai-ichi Nuclear Power Plant through a series of car-borne surveys.

Science.gov (United States)

Andoh, Masaki; Nakahara, Yukio; Tsuda, Shuichi; Yoshida, Tadayoshi; Matsuda, Norihiro; Takahashi, Fumiaki; Mikami, Satoshi; Kinouchi, Nobuyuki; Sato, Tetsuro; Tanigaki, Minoru; Takamiya, Koichi; Sato, Nobuhiro; Okumura, Ryo; Uchihori, Yukio; Saito, Kimiaki

2015-01-01

A series of car-borne surveys using the Kyoto University RAdiation MApping (KURAMA) and KURAMA-II survey systems has been conducted over a wide area in eastern Japan since June 2011 to evaluate the distribution of air dose rates around the Fukushima Dai-ichi Nuclear Power Plant and to evaluate the time-dependent trend of decrease in air dose rates. An automated data processing system for the KURAMA-II system was established, which enabled rapid analysis of large amounts of data obtained using about 100 KURAMA-II units. The initial data used for evaluating the migration status of radioactive cesium were obtained in the first survey, followed by other car-borne surveys conducted over more extensive and wider measurement ranges. By comparing the measured air dose rates obtained in each survey (until December 2012), the decreasing trend of air dose rates measured through car-borne surveys was found to be more pronounced than those expected on the basis of the physical decay of radioactive cesium and of the air dose rates measured using NaI (Tl) survey meters in the areas surrounding the roadways. In addition, it was found that the extent of decrease in air dose rates depended on land use, wherein it decreased faster for land used as building sites than for forested areas. Copyright © 2014 Elsevier Ltd. All rights reserved.

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

Treatment of airborne asbestos and asbestos-like microfiber particles using atmospheric microwave air plasma

Energy Technology Data Exchange (ETDEWEB)

Averroes, A., E-mail: aulia.a.aa@m.titech.ac.jp [Department of Chemical Engineering, Tokyo Institute of Technology, 2-12-1 O-okayama, Meguro-ku, Tokyo 152-8552 (Japan); Sekiguchi, H. [Department of Chemical Engineering, Tokyo Institute of Technology, 2-12-1 O-okayama, Meguro-ku, Tokyo 152-8552 (Japan); Sakamoto, K. [Street Design Corporation, 6-9-30 Shimo odanaka, Kawasaki-shi, Kanagawa 211-0041 (Japan)

2011-11-15

Highlights: {yields} We use atmospheric microwave air plasma to treat ceramic fiber and stainless fiber as asbestos alike micro fiber particle. {yields} Spheroidization of certain type of ceramic fiber and stainless fiber particle. {yields} The evaluation of the treated particles by the fiber vanishing rate. {yields} Good fiber vanishing rate is observed for fiber particle with diameter below 10 {mu}m. {yields} The treatment of pure asbestos and a suggestion of the use of this method for the treatment airborne asbestos. - Abstract: Atmospheric microwave air plasma was used to treat asbestos-like microfiber particles that had two types of ceramic fiber and one type of stainless fiber. The treated particles were characterized via scanning electron microscopy (SEM) and X-ray diffraction (XRD). The experiment results showed that one type of ceramic fiber (Alumina:Silica = 1:1) and the stainless fiber were spheroidized, but the other type of ceramic fiber (Alumina:Silica = 7:3) was not. The conversion of the fibers was investigated by calculating the equivalent diameter, the aspect ratio, and the fiber content ratio. The fiber content ratio in various conditions showed values near zero. The relationship between the normalized fiber vanishing rate and the energy needed to melt the particles completely per unit surface area of projected particles, which is defined as {eta}, was examined and seen to indicate that the normalized fiber vanishing rate decreased rapidly with the increase in {eta}. Finally, some preliminary experiments for pure asbestos were conducted, and the analysis via XRD and phase-contrast microscopy (PCM) showed the availability of the plasma treatment.

Treatment of airborne asbestos and asbestos-like microfiber particles using atmospheric microwave air plasma

International Nuclear Information System (INIS)

Averroes, A.; Sekiguchi, H.; Sakamoto, K.

2011-01-01

Highlights: → We use atmospheric microwave air plasma to treat ceramic fiber and stainless fiber as asbestos alike micro fiber particle. → Spheroidization of certain type of ceramic fiber and stainless fiber particle. → The evaluation of the treated particles by the fiber vanishing rate. → Good fiber vanishing rate is observed for fiber particle with diameter below 10 μm. → The treatment of pure asbestos and a suggestion of the use of this method for the treatment airborne asbestos. - Abstract: Atmospheric microwave air plasma was used to treat asbestos-like microfiber particles that had two types of ceramic fiber and one type of stainless fiber. The treated particles were characterized via scanning electron microscopy (SEM) and X-ray diffraction (XRD). The experiment results showed that one type of ceramic fiber (Alumina:Silica = 1:1) and the stainless fiber were spheroidized, but the other type of ceramic fiber (Alumina:Silica = 7:3) was not. The conversion of the fibers was investigated by calculating the equivalent diameter, the aspect ratio, and the fiber content ratio. The fiber content ratio in various conditions showed values near zero. The relationship between the normalized fiber vanishing rate and the energy needed to melt the particles completely per unit surface area of projected particles, which is defined as η, was examined and seen to indicate that the normalized fiber vanishing rate decreased rapidly with the increase in η. Finally, some preliminary experiments for pure asbestos were conducted, and the analysis via XRD and phase-contrast microscopy (PCM) showed the availability of the plasma treatment.

The nuclear power generation

International Nuclear Information System (INIS)

Serres, R.

1999-01-01

The French nuclear generating industry is highly competitive. The installations have an average age of fifteen years and are half way through their expected life. Nuclear power accounts for 70% of the profits of the French generating company, EDF. Nuclear generation has a minimal effect on the atmosphere and France has a level of CO 2 emissions, thought to be the main cause of the greenhouse effect, half that of Europe as a whole. The air in France is purer than in neighbouring countries, mainly because 75% of all electrical power is generated in nuclear plants and 15% in hydroelectric stations. The operations and maintenance of French nuclear power plants in the service and distribution companies out of a total of 100 000 employees in all, 90 % of whom are based in mainland France. (authors)

Aging and service wear of air-operated valves used in safety-related systems at nuclear power plants

International Nuclear Information System (INIS)

Cox, D.F.; McElhaney, K.L.; Staunton, R.H.

1995-05-01

Air-operated valves (AOVs) are used in a variety of safety-related applications at nuclear power plants. They are often used where rapid stroke times are required or precise control of the valve obturator is required. They can be designed to operate automatically upon loss of power, which is often desirable when selecting components for response to design basis conditions. The purpose of this report is to examine the reported failures of AOVs and determine whether there are identifiable trends in the failures related to predictable causes. This report examines the specific components that comprise a typical AOV, how those components fail, when they fail, and how such failures are discovered. It also examines whether current testing frequencies and methods are effective in predicting such failures

Oxygen enriched air using membrane for palm oil wastewater treatment

Directory of Open Access Journals (Sweden)

Ramlah Mohd Tajuddin

2002-11-01

Full Text Available A research aimed to explore new method of aeration using oxygen enriched air performance on BOD reduction of palm oil wastewater was conducted. The oxygen enriched air was obtained from an Oxygen Enriched System (OES developed using asymmetric polysulfone hollow fiber membrane with composition consisting of PSF: 22%, DMAc: 31.8%, THF: 31.8%, EtOH: 14.4%. Palm oil wastewater samples were taken from facultative pond effluent. These samples were tested for its initial biochemical oxygen demand (BOD, total suspended solids (TSS, pH, conductivity, turbidity, dissolved oxygen (DO, suspended solids (SS, and total dissolved solids (TDS before being subjected to two modes of aeration system, that is diffused air and oxygen enriched air. These water quality concentrations were tested for every 20 minutes for two-hour period during the aeration process. Results of BOD, TSS, pH, conductivity, DO, SS and TDS concentrations against time of samples from the two modes of aeration were then compared. It was found that DO concentration achieved in oxygen enriched air aeration was better than aeration using diffused air system. Aeration using OES improve the DO concentration in the wastewater and thus improve the BOD reduction and also influence other physical characteristics of wastewater. This phenomenon indicates the advantage of using air with higher oxygen concentration for wastewater aeration instead of diffused air system.

Treatment, processing, and disposal of radioactive materials and wastes emanating from nuclear accidents

International Nuclear Information System (INIS)

Hemke, J.

1999-01-01

The objectives of the research project are: Elaboration of concepts for the disposal or treatment of radioactive agricultural produce and wastes resulting from a nuclear emergency. The major goal is minimization of the radiation dose to the population, using available technology, equipment and infrastructure. The waste management concepts will be tested for suitability and effectiveness within the framework of planning games. (orig./CB) [de

Peculiarities of radionuclide contamination of different Semipalatinsk nuclear test site (SNTS) zones

International Nuclear Information System (INIS)

Kadyrzhanov, K.K.; Khazhekber, S.; Lukashenko, S.N.; Solodukhin, V.P.; Kazachevskij, I.V.; Poznyak, V.L.; Knyazev, B.B.; Rofer, Ch.

2002-01-01

The Semipalatinsk Nuclear Test Site occupies about 18500 km 2 . There are 3 basic test zones in this territory including various test platforms where different character nuclear explosions were carried out. On the test platforms of the 'Opytnoe Pole' zone air and ground tests were performed, including nuclear and hydronuclear (without nuclear reaction) explosions. On the other zones (the Degelen mountains and Balapan valley) the underground tests including camouflaged and excavation nuclear explosions were carried out. Each kind of these tests can be characterised by the quantity and composition of radionuclides which were formed during the nuclear explosion, by the area of their distribution, localisation of the radionuclides at various sites, radionuclide species in soil. Transfer of the products of the air and the ground nuclear explosions by air flows and their sedimentation on the ground surfaces have caused broadband radioactive plumes extending over hundreds of kilometres. As a result of hydronuclear experiments, plenty of alpha-active radionuclides, consisting of a nuclear device is thrown locally out. Besides the ground and the air explosions, radiation conditions of the territory of the SNTS were influenced by excavation explosions with ground throwing out. Such tests resulted in an intensive local pollution. Other zone of an original pollution is the Degelen mountains. Although an basic mass of the nuclear explosion products is obviously concentrated in basin cavities of the tunnels, the radionuclides are taken out on a day time surface together with waters acting in the basin cavity of the tunnels. The results of investigation of radionuclide pollution on the various platforms of the SNTS territory are presented. The results characterise the radionuclide pollution by specificity of spent tests

Respiratory and protective equipment at a large nuclear facility

International Nuclear Information System (INIS)

Zippler, D.B.

1975-12-01

A variety of personal protective equipment is used in a large nuclear facility to protect employees against both nuclear and ordinary industrial materials. Equipment requirements are based on risk evaluation and may range from a minimum of shoe covers to whole body protection by air-supplied plastic suits. Types of equipment are listed and one-year costs are given. Criteria for evaluating and compartmentalizing risks are discussed. Air-supplied suits and hoods are discussed in detail

Model of tritium transfer into environment by the personnel of nuclear enterprises

International Nuclear Information System (INIS)

Batalin, J.; Krechetova, A.

2004-01-01

One of the ways of radionuclide transfer from a nuclear enterprise into an environment is analysed. This way of transfer is the transport of radionuclides by the personnel of a nuclear enterprise. During an active work in a nuclear enterprise the personnel accumulate radionuclides from the air of industrial premises. Accumulated radionuclides are released from the organism into an environment according to the effective period of half-draw. The main part of radionuclides is transferred from the organism of professional workers into an environment: first of all into the air and on furniture of their dwellings and later - into the organisms of their family members. In this way contamination of workers' dwellings and irradiation of their family members exceed the contamination through air and water. The model is confirmed as an example of tritium transfer from nuclear enterprises. (author)

Treatment of oily water by flotation

International Nuclear Information System (INIS)

Ortiz O, H.B.

2002-01-01

The operation of the nuclear power plants such as Laguna Verde (CLV) with nuclear reactors of the boiling water type (BWR) produce radioactive waste solids, liquids and gaseous which require of a special treatment in their operation and arrangement. Such is the case of the liquid wastes from CLV which are a mixture of water and synthetic oils coming from leaks and spilling by pressure of maintenance of electro-mechanical equipment associated to the performance of the nuclear power plant. This mixture of water and spent oils is pretreated by means of sedimentation, centrifugation and evaporation. However the realized efforts by the CLV, the spent oil obtained from the pretreatment contains concentrations of radioactive material higher than the tolerance limits established in the normative in force in radiological safety (0.37 Bq m L -1 for 60 Co and 54 Mn). In this context it was necessary to design an efficient treatment system and economically profitable which separates the oil, the heavy metals and the leftovers of radioactive material that could be present in water, with the purpose of fulfil with the Mexican Official Standards corresponding for its unload or even it can reuse it in the wash process of treated oil. The treatment system of oily water waste consists of: a) Coagulation-flocculation, b) Flotation system with modified air dissolved (DAFm). The proposed flotation process allows to reach a higher separation efficiencies of: Concentration of greases and oils: 94.11 %; Turbidity: 98.6 %; 60 Co: 82.3 % ; Co: 94.8 % and Cr: 99.9 % (Author)

Plasma surface treatment of Cu by nanosecond-pulse diffuse discharges in atmospheric air

Science.gov (United States)

Cheng, ZHANG; Jintao, QIU; Fei, KONG; Xingmin, HOU; Zhi, FANG; Yu, YIN; Tao, SHAO

2018-01-01

Nanosecond-pulse diffuse discharges could provide high-density plasma and high-energy electrons at atmospheric pressure. In this paper, the surface treatment of Cu by nanosecond-pulse diffuse discharges is conducted in atmospheric air. Factors influencing the water contact angle (WCA), chemical composition and microhardness, such as the gap spacing and treatment time, are investigated. The results show that after the plasma surface treatment, the WCA considerably decreases from 87° to 42.3°, and the surface energy increases from 20.46 mJ m-2 to 66.28 mJ m-2. Results of energy dispersive x-ray analysis show that the concentration of carbon decreases, but the concentrations of oxygen and nitrogen increase significantly. Moreover, the microhardness increases by approximately 30% after the plasma treatment. The aforementioned changes on the Cu surface indicate the plasma surface treatment enhances the hydrophilicity and microhardness, and it cleans the carbon and achieves oxidization on the Cu surface. Furthermore, by increasing the gap spacing and treatment time, better treatment effects can be obtained. The microhardness in the case of a 2.5 cm gap is higher than that in the case of a 3 cm gap. More oxygen and nitrogen species appear on the Cu surface for the 2.5 cm gap treatment than for the 3 cm gap treatment. The WCA significantly decreases with the treatment time when it is no longer than 90 s, and then it reaches saturation. In addition, more oxygen-containing and nitrogen-containing groups appear after extended plasma treatment time. They contribute to the improvement of the hydrophilicity and oxidation on the Cu surface.

Deployment Evaluation Methodology for the Electrometallurgical Treatment of DOE-EM Spent Nuclear Fuel

International Nuclear Information System (INIS)

Ramer, Ronald James; Adams, James Paul; Rynearson, Michael Ardel; Dahl, Christian Adam

1999-01-01

The Department of Energy - Environmental Management (DOE-EM) National Spent Nuclear Fuel Program (NSNFP) is charged with the disposition of legacy Spent Nuclear Fuel (SNF). The NSNFP, conducted by Lockheed Martin Idaho Technology Co. (LMITCO) at the Idaho National Engineering and Environmental Laboratory (INEEL), is evaluating final disposition of SNF in the DOE complex. While direct repository disposal of the SNF is the preferred disposition option, some DOE SNF may need treatment to meet acceptance criteria at various disposition sites. Evaluations of treatment needs and options have been previously prepared, and further evaluations are ongoing activities in the DOE-EM NSNFP. The treatments may range from electrometallurgical treatment (EMT) and chemical dissolution to engineering controls. As a planning basis, a need is assumed for a treatment process, either as a primary or backup technology, that is compatible with, and cost-effective for, this portion of the DOE-EM inventory. The current planning option for treating this SNF, pending completion of development work and National Environmental Policy Act (NEPA) analysis, is the EMT process under development by Argonne National Laboratory - West (ANL-W). A decision on the deployment of the EMT is pending completion of an engineering scale demonstration currently in progress at ANL-W. Treatment options and treatment locations will depend on fuel type and location of the fuel. One of the first steps associated with selecting one or more sites for treating SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. One of the major issues associated with SNF treatment is final disposition of treatment products and associated waste streams. During conventional SNF treatment, various chemicals are added that may increase the product

Children's (Pediatric) Nuclear Medicine

Medline Plus

Full Text Available ... bones. liver and gallbladder. gastrointestinal tract. heart. lungs. brain. thyroid. Nuclear medicine scans are typically used to ... differently than when breathing room air or holding his or her breath. With some exams, a catheter ...

Improving Hydrophobicity of Glass Surface Using Dielectric Barrier Discharge Treatment in Atmospheric Air

International Nuclear Information System (INIS)

Fang Zhi; Qiu Yuchang; Wang Hui; Kuffel, E

2007-01-01

Non-thermal plasmas under atmospheric pressure are of great interest in industrial applications, especially in material surface treatment. In this paper, the treatment of a glass surface for improving hydrophobicity using the non-thermal plasma generated by dielectric barrier discharge (DBD) at atmospheric pressure in ambient air is conducted, and the surface properties of the glass before and after the DBD treatment are studied by using contact angle measurement, surface resistance measurement and wet flashover voltage tests. The effects of the applied voltage and time duration of DBD on the surface modification are studied, and the optimal conditions for the treatment are obtained. It is found that a layer of hydrophobic coating is formed on the glass surface after spraying a thin layer of silicone oil and undergoing the DBD treatment, and the improvement of hydrophobicity depends on DBD voltage and treating time. It seems that there exists an optimum treating time for a certain applied voltage of DBD during the surface treatment. The test results of thermal aging and chemical aging show that the hydrophobic layer has quite stable characteristics. The interaction mechanism between the DBD plasma and the glass surface is discussed. It is concluded that CH 3 and large molecule radicals can react with the radicals in the glass surface to replace OH, and the hydrophobicity of the glass surface is improved accordingly

Radioactive Air Emissions Notice of Construction for the 105-KW Basin integrated water treatment system filter vessel sparging vent

Energy Technology Data Exchange (ETDEWEB)

Kamberg, L.D.

1998-02-23

This document serves as a notice of construction (NOC), pursuant to the requirements of Washington Administrative Code (WAC) 246-247-060, and as a request for approval to construct, pursuant to 40 Code of Federal Regulations (CFR) 61.07, for the Integrated Water Treatment System (IWTS) Filter Vessel Sparging Vent at 105-KW Basin. Additionally, the following description, and references are provided as the notices of startup, pursuant to 40 CFR 61.09(a)(1) and (2) in accordance with Title 40 Code of Federal Regulations, Part 61, National Emission Standards for Hazardous Air Pollutants. The 105-K West Reactor and its associated spent nuclear fuel (SNF) storage basin were constructed in the early 1950s and are located on the Hanford Site in the 100-K Area about 1,400 feet from the Columbia River. The 105-KW Basin contains 964 Metric Tons of SNF stored under water in approximately 3,800 closed canisters. This SNF has been stored for varying periods of time ranging from 8 to 17 years. The 105-KW Basin is constructed of concrete with an epoxy coating and contains approximately 1.3 million gallons of water with an asphaltic membrane beneath the pool. The IWTS, which has been described in the Radioactive Air Emissions NOC for Fuel Removal for 105-KW Basin (DOE/RL-97-28 and page changes per US Department of Energy, Richland Operations Office letter 97-EAP-814) will be used to remove radionuclides from the basin water during fuel removal operations. The purpose of the modification described herein is to provide operational flexibility for the IWTS at the 105-KW basin. The proposed modification is scheduled to begin in calendar year 1998.

Canyon air flow measurement utilizing ASME standard pitot tube arrays

International Nuclear Information System (INIS)

Moncrief, B.R.

1990-01-01

The Savannah River Site produces nuclear materials for national defense. In addition to nuclear reactors, the site has separation facilities for reprocessing irradiated nuclear fuel. The chemical separation of highly radioactive materials takes place by remote control in large buildings called canyons. Personnel in these buildings are shielded from radiation by thick concrete walls. Contaminated air is exhausted from the canyons and contaminants are removed by sand filters prior to release to the atmosphere through a stack. When these facilities were built on a crash basis in the early 1950's, inadequate means were provided for pressure and air flow measurement. This presentation describes the challenge we faced in retrofitting a highly radioactive, heavily shielded facility with instrumentation to provide this capability

Report of the Secretary of Defense Task Force on DoD Nuclear Weapons Management. Phase II: Review of the DoD Nuclear Mission

National Research Council Canada - National Science Library

Schlesinger, James R; Carns, Michael P; Crouch, II, J. D; Gansler, Jacques S; Giambastiani, Jr., Edmund P; Hamre, John J; Miller, Franklin C; Williams, Christopher A; Blackwell, Jr, James A

2008-01-01

Incidents related to the Air Force's mishandling of nuclear weapons and components led to the creation of the Task Force in June 2008 to provide advice on nuclear matters for the Secretary of Defense...

Nuclear Emergency and the Atmospheric Dispersion of Nuclear Aerosols: Discussion of the Shared Nuclear Future - 13163

International Nuclear Information System (INIS)

Rana, Mukhtar A.; Ali, Nawab; Akhter, Parveen; Khan, E.U.

2013-01-01

This paper has a twofold objective. One is to analyze the current status of high-level nuclear waste disposal along with presentation of practical perspectives about the environmental issues involved. Present disposal designs and concepts are analyzed on a scientific basis and modifications to existing designs are proposed from the perspective of environmental safety. Other is to understand the aerosol formation in the atmosphere for the case of the leakage from the nuclear waste containers or a nuclear accident. Radio-nuclides released from the waste will attach themselves to the existing aerosols in the atmosphere along with formation of new aerosols. Anticipating the nuclear accident when a variety of radioactive aerosols will form and exist in the atmosphere, as a simple example, measurement of naturally existing radioactive aerosols are made in the atmosphere of Islamabad and Murree. A comparison with similar measurements in 3 cities of France is provided. Measurement of radionuclides in the atmosphere, their attachment to aerosols and follow up transport mechanisms are key issues in the nuclear safety. It is studied here how "7Be concentration in the atmospheric air varies in the capital city of Islamabad and a Himalaya foothill city of Murree (Pakistan). Present results are compared with recent related published results to produce a "7Be concentration versus altitude plot up to an altitude of 4000 m (a.s.l.). Origin and variance of "7Be concentration at different altitudes is discussed in detail. The relevance of results presented here with the evaluation of implications of Chernobyl and Fukushima nuclear disasters has been discussed in a conclusive manner. It is the first international report of a joint collaboration/project. The project is being generalized to investigate and formulate a smooth waste storage and disposal policy. The project will address the fission and fusion waste reduction, its storage, its recycling, air, water and soil quality

Nuclear Emergency and the Atmospheric Dispersion of Nuclear Aerosols: Discussion of the Shared Nuclear Future - 13163

Energy Technology Data Exchange (ETDEWEB)

Rana, Mukhtar A. [Science-Admin Coherence Cell (SACC), PINSTECH Admin Blk, PAEC, Islamabad (Pakistan); Ali, Nawab [Physics Division, Directorate of Science, Pakistan Institute of Nuclear Science and Technology (PINSTECH), P.O. Nilore, Islamabad (Pakistan); Akhter, Parveen [Pakistan Institute of Engineering and Applied Sciences (PIEAS), Islamabad (Pakistan); Khan, E.U. [Department of Physics, International Islamic University (IIU), Kettle Fields, Kashmir Highways, Islamabad (Pakistan)

2013-07-01

This paper has a twofold objective. One is to analyze the current status of high-level nuclear waste disposal along with presentation of practical perspectives about the environmental issues involved. Present disposal designs and concepts are analyzed on a scientific basis and modifications to existing designs are proposed from the perspective of environmental safety. Other is to understand the aerosol formation in the atmosphere for the case of the leakage from the nuclear waste containers or a nuclear accident. Radio-nuclides released from the waste will attach themselves to the existing aerosols in the atmosphere along with formation of new aerosols. Anticipating the nuclear accident when a variety of radioactive aerosols will form and exist in the atmosphere, as a simple example, measurement of naturally existing radioactive aerosols are made in the atmosphere of Islamabad and Murree. A comparison with similar measurements in 3 cities of France is provided. Measurement of radionuclides in the atmosphere, their attachment to aerosols and follow up transport mechanisms are key issues in the nuclear safety. It is studied here how {sup 7}Be concentration in the atmospheric air varies in the capital city of Islamabad and a Himalaya foothill city of Murree (Pakistan). Present results are compared with recent related published results to produce a {sup 7}Be concentration versus altitude plot up to an altitude of 4000 m (a.s.l.). Origin and variance of {sup 7}Be concentration at different altitudes is discussed in detail. The relevance of results presented here with the evaluation of implications of Chernobyl and Fukushima nuclear disasters has been discussed in a conclusive manner. It is the first international report of a joint collaboration/project. The project is being generalized to investigate and formulate a smooth waste storage and disposal policy. The project will address the fission and fusion waste reduction, its storage, its recycling, air, water and soil

Hazardous air pollutant (HAP) emission characterization of sewage treatment facilities in Korea.

Science.gov (United States)

Kang, Kyoung-Hee; Dong, Jong-In

2010-04-01

Until recently, nearly all sewage treatment-related regulations and researches have focused on the removal of the conventional and toxic pollutants from liquid effluents. The discharge of toxic compounds to the atmosphere has been implicitly regarded as a way of removal or destruction. During sewage treatment, the fate mechanism of volatilization/stripping, sorption and biotransformation primarily determines the fate of volatile HAPs. The objectives of this study are to investigate the emission characteristics of HAPs, which are generated from the liquid surface of sewage treatment facilities, by using an emission isolation flux chamber. HAP emissions increased at the inlet of the aerobic chamber during summer due to the relatively high atmospheric temperature. The percent ratio of flux for toluene reached its peak in winter, accounting for 33.6-34.2% of the total, but decreased to 25.1-28.6% in summer. In autumn, trichloroethene (TCE) was the highest, recording 17.6-18.1%, with chloroform and toluene showing similar levels. It seems that the ratio of chlorinated hydrocarbons increases in both summer and autumn because the chamber temperature during that time is higher than winter. This study is the initial study to investigate the emission characteristics of volatile HAPs emitted from domestic sewage treatment facilities to the air in Korea. Therefore, the isolation flux chamber will be used as an emission estimations tool to measure HAPs from sewage treatment facilities and may be applied to develop the emission factor and national source inventory of HAPs.

Device for separating, purifying and recovering nuclear fuel material, impurities and materials from impurity-containing nuclear fuel materials or nuclear fuel containing material

International Nuclear Information System (INIS)

Sato, Ryuichi; Kamei, Yoshinobu; Watanabe, Tsuneo; Tanaka, Shigeru.

1988-01-01

Purpose: To separate, purify and recover nuclear fuel materials, impurities and materials with no formation of liquid wastes. Constitution: Oxidizing atmosphere gases are introduced from both ends of a heating furnace. Vessels containing impurity-containing nuclear fuel substances or nuclear fuel substance-containing material are continuously disposed movably from one end to the other of the heating furnace. Then, impurity oxides or material oxides selectively evaporated from the impurity-containing nuclear fuel substances or nuclear fuel substance-containing materials are entrained in the oxidizing atmosphere gas and the gases are led out externally from a discharge port opened at the intermediate portion of the heating furnace, filters are disposed to the exit to solidify and capture the nuclear fuel substances and traps are disposed behind the filters to solidify and capture the oxides by spontaneous air cooling or water cooling. (Sekiya, K.)

Nuclear materials transportation

International Nuclear Information System (INIS)

Ushakov, B.A.

1986-01-01

Various methods of nuclear materials transportation at different stages of the fuel cycle (U 3 O 8 , UF 6 production enrichment, fuel element manufacturing, storage) are considered. The advantages and drawbacks of railway, automobile, maritime and air transport are analyzed. Some types of containers are characterized

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

Nuclear power and public health in Michigan, July 1974-June 1976

International Nuclear Information System (INIS)

Anon.

1978-01-01

Environmental samples in the form of air particulates, air vapors, precipitation, external radiation, milk, drinking water, surface water, and aquatic biota were taken from various sites in Michigan and analyzed to determine if any effects due to nuclear power reactors could be detected. Seasonal and geographical variations in the air particulate gross beta data are evident and are attributable to corresponding variations in fallout from nuclear tests. No gross beta, gross alpha, or gross gamma results of air particulate and air vapor samples were found to be indicative of reaction operations. Precipitation data displayed similar trends, following the fallout cycle, while specific elevated results are attributable to sample size and not reactor operations. All milk results have been found to be well within the appropriate maximum permissible concentrations for the general population. In no cases did the data indicate either specific atmospheric nuclear tests or reactor operations. All drinking water results were so close to their respective minimum sensitivities that no specific or general trends due to nuclear power plant operations were indicated. No results exceeded either existing Public Health Service limits or the new EPA drinking water standards. While no general trends attributable to reactor operations were found in surface water results, specific plant liquid releases were revealed by the network. All detected radioactivity was below appropriate limits. Although barely detectable amounts of radioactivity were found in aquatic biota samples, no results were determined to be indicative of specific nuclear plant discharges. The cumulative results indicate that no public health problem exists

Comparative hygienic assessment of active ingredients content in the air environment after treatment of cereal spiked crops by combined fungicides.

Science.gov (United States)

Kondratiuk, Mykola; Blagaia, Anna; Pelo, Ihor

2018-01-01

Introduction: The quality of the air environment significantly affects the health of the population. Chemical plant protection products in the spring and summer time may be the main pollutants of the air environment in rural areas. Chemical plant protection products are dangerous substances of anthropogenic origin. If applying pesticides in high concentrations, the risk of poisoning by active ingredients of pesticide preparations in workers directly contacting with it increases. The aim: Comparative hygienic assessment of active ingredients content in the air environment after treatment of cereal spiked crops by combined fungicides was the aim of the work. Materials and methods: Active ingredients of the studied combined fungicides, samples of air, and swabs from workers' skin and stripes from overalls were materials of the research. Methods of full-scale in-field hygienic experiment, gas-liquid chromatography, high-performance liquid chromatography, as well as statistical and bibliographic methods were used in the research. Results and conclusions: Active ingredients of the studied combined fungicides were not detected in the working zone air and atmospheric air at the levels exceeding the limits of its detection by appropriate chromatography methods. Findings confirmed the air environment safety for agricultural workers and rural population if studied combined fungicides are applied following the hygienically approved suggested application rates and in accordance of good agricultural practice rules. However the possible complex risk for workers after certain studied fungicides application may be higher than acceptable due to the elevated values for dermal effects. The complex risk was higher than acceptable in еру case of aerial spraying of both studied fungicides, meanwhile only one combination of active ingredients revealed possible risk for workers applying fungicides by rod method of cereal spiked crops treatment.

Radiation protection review in nuclear medicine and analysis of new medical techniques. ACDOS-5-P-3 project. Final report, part 1

International Nuclear Information System (INIS)

Di Trano, Jose L.; Rojo, Ana M.; Kunst, Juan J.; Saule, Fabian A.; Ponce, Lujan E.; Fruttero, Nestor H.

2002-01-01

One of the more common radionuclide therapies performs by nuclear medicine departments is the administration of iodine 131 for thyroid ablation and for hyperthyroidism treatment. The revision of radiological protection was done on the occupational exposure of workers, member of the public and relatives of patients treated with iodine 131. This paper present the results from area and individual dosimetry to external exposure, surface activity and air concentration of iodine 131 carried out during the practice in the nuclear medicine department. An area survey in the isolation room allowed determined exposure rate surface activity and air concentration of iodine 131. The patients clothes was measured besides the activity excreted in urine and sweat. An instructive form for patients and relatives after iodine 131 treatment was proposed and the physicians with a clear explanation should give it. The international regulation aspect (USA, European Union, and some countries from South America) were reviewed and the wide range of criteria were analyzed mainly about the discharched of patients. An actual trend of taking into account the individual metabolic parameters and economic situation was discussed in the paper included: 'Patient specific dosimetry for radioprotection purpose in the thyroid cancer treatment with iodine 131'. (author)

Gas treatment processes for keeping the environment of nuclear plants free from gas-borne activity

International Nuclear Information System (INIS)

Schiller, H.

1977-01-01

The separation processes in gas treatment steps for the decontamination of circuit or offgas streams are described and their practicability is evaluated. Examples of the effectiveness of gas separation plants for keeping the environment within and without nuclear plants free from harmful gas-borne activity are presented. (orig.) [de

History of the Iraqi Nuclear Center of Tuwaitha

International Nuclear Information System (INIS)

Fabbri, Silvio

2009-01-01

The Tuwaitha site, 20 km south of Baghdad, was chosen at the beginning of the sixties to be the Center for Research and Development of the Iraqi Nuclear Program. The israeli air attack to the Osirak reactor in 1981, the clandestine activities for nuclear weapons production and the inspections carried out by the International Atomic Energy Agency (IAEA) to verify such activities are parts of the history of that nuclear complex. Its installations were extensively damaged in 1991 during the so called Golf War and finally destroyed by air bombardment during the invasion by the Coalition Forces in 2003. The IAEA and other several countries have elaborated an international assistance program for the future activities of installations dismantling and site remediation. (author) [es

Proceedings of NUCLEAR 2008 annual international conference on sustainable development through nuclear research and education

International Nuclear Information System (INIS)

Constantin, Marin; Turcu, Ilie

2008-01-01

The proceedings of the NUCLEAR 2008 annual international conference on sustainable development through nuclear research and education held at INR-Pitesti on May, 28 - 30 2008 contain 88 communications presented in 3 sections addressing the themes of Nuclear energy, Environmental protection, and Sustainable development. In turn these sections are addressing the following items: Section 1.1 - Nuclear safety and severe accidents (12 papers); Section 1.2 - Nuclear reactors (11 papers); Section 1.3 - Nuclear technologies and materials (20 papers); Section 2.1 - Radioprotection (5 papers); Section 2.2 - Radioactive waste management (20 papers); Section 2.3 - air, water and soil protection (5 papers); Section 3.1 - Strategies in energy (3 papers); Section 3.2 - Education, continuous formation and knowledge transfer (8 papers); Section 3.3 - International partnership for a sustainable development (4 papers)

Thermal treatment of historical radioactive solid and liquid waste into the CILVA incinerator

International Nuclear Information System (INIS)

Deckers, Jan; Mols, Ludo

2007-01-01

Since the very beginning of the nuclear activities in Belgium, the incineration of radioactive waste was chosen as a suitable technique for achieving an optimal volume reduction of the produced waste quantities. Based on the 35 years experience gained by the operation of the old incinerator, a new industrial incineration plant started nuclear operation in May 1995, as a part of the Belgian Centralized Treatment/Conditioning Facility named CILVA. Up to the end of 2006, the CILVA incinerator has burnt 1660 tonne of solid waste and 419 tonne of liquid waste. This paper describes the type and allowable radioactivity of the waste, the incineration process, heat recovery and the air pollution control devices. Special attention is given to the treatment of several hundreds of tonne historical waste from former reprocessing activities such as alpha suspected solid waste, aqueous and organic liquid waste and spent ion exchange resins. The capacity, volume reduction, chemical and radiological emissions are also evaluated. BELGOPROCESS, a company set up in 1984 at Dessel (Belgium) where a number of nuclear facilities were already installed is specialized in the processing of radioactive waste. It is a subsidiary of ONDRAF/NIRAS, the Belgian Nuclear Waste Management Agency. According to its mission statement, the activities of BELGOPROCESS focus on three areas: treatment, conditioning and interim storage of radioactive waste; decommissioning of shut-down nuclear facilities and cleaning of contaminated buildings and land; operating of storage sites for conditioned radioactive waste. (authors)

Experimental verification of air flow rate measurement for representative isokinetic air sampling in ventilation stacks

International Nuclear Information System (INIS)

Okruhlica, P.; Mrtvy, M.; Kopecky, Z.

2009-01-01

Nuclear facilities are obliged to monitor their discharge's influence on environment. Main monitored factions in NPP's ventilation stacks are usually noble gasses, particulates and iodine. These factions are monitored in air sampled from ventilation stack by means of sampling rosette and bypass followed with on-line measuring monitors and balance sampling devices with laboratory evaluations. Correct air flow rate measurement and representative iso-kinetic air sampling system is essential for physical correct and metrological accurate evaluation of discharge influence on environment. Pairs of measuring sensors (Anemometer, pressure gauge, thermometer and humidity meter) are symmetrically placed in horizontal projection of stack on positions based on measured air flow velocity distribution characteristic, Analogically diameter of sampling rosette nozzles and their placement in the middle of 6 - 7 annuluses are calculated for assurance of representative iso-kinetic sampling. (authors)

Experimental verification of air flow rate measurement for representative isokinetic air sampling in ventilation stacks

International Nuclear Information System (INIS)

Okruhlica, P.; Mrtvy, M.; Kopecky, Z.

2008-01-01

Nuclear facilities are obliged to monitor their discharge's influence on environment. Main monitored factions in NPP's ventilation stacks are usually noble gasses, particulates and iodine. These factions are monitored in air sampled from ventilation stack by means of sampling rosette and bypass followed with on-line measuring monitors and balance sampling devices with laboratory evaluations. Correct air flow rate measurement and representative iso-kinetic air sampling system is essential for physical correct and metrological accurate evaluation of discharge influence on environment. Pairs of measuring sensors (Anemometer, pressure gauge, thermometer and humidity meter) are symmetrically placed in horizontal projection of stack on positions based on measured air flow velocity distribution characteristic, Analogically diameter of sampling rosette nozzles and their placement in the middle of 6- 7 annuluses are calculated for assurance of representative iso-kinetic sampling. (authors)

The public scandal about the nuclear waste treatment industry

International Nuclear Information System (INIS)

1988-01-01

The events leading to the public scandal are summarized into three main items: (1) Accusation for taking bribe in the form of money and in kind. (2) Suspicion of false labelling of radioactive waste. (3) Suspicion of offense against the Non-Proliferation Treaty. The survey in hand is intended to prepare a sober judgement of the situation by: stating the facts and their significance in terms of safety; explaining the various types of radioactive wastes, their treatment and the quantities involved; explaining the legal provisions for transport of radioactive materials; discussing the problem of nuclear waste management in terms of quantity. The lesson to be drawn is that controls and further means of quality assurance are required to make the pathways of radioactive wastes pellucid and verifiable. (orig./HSCH) [de

Process for contamination containment of a workplace by means of an air jet

International Nuclear Information System (INIS)

Meline, F.

1984-01-01

Containment of pollution in an area, for example the room where nuclear fuel elements are cut, is obtained by an air curtain directed by a second air jet to improve the containment of pollutants. Contamined air is extracted by a cyclone and filtered [fr

Siloxane removal and sludge disintegration using thermo-alkaline treatments with air stripping prior to anaerobic sludge digestion

International Nuclear Information System (INIS)

Oshita, Kazuyuki; Fujime, Motochika; Takaoka, Masaki; Fujimori, Takashi; Appels, Lise; Dewil, Raf

2015-01-01

Highlights: • Siloxanes hamper the energy-use of anaerobic digestion biogas. • D5 siloxane was considered as target compound in this study. • The treatment removed 80% of D5 in sewage sludge at 55 °C and 135 g-NaOH kg −1 -VTS. • D5 removal and the disintegration of VSS in the sludge were correlated. • At the optimal conditions, the costs of anaerobic digestion were notably diminished. - Abstract: A thermo-alkaline treatment with air stripping was applied before anaerobic sludge digestion for both siloxane removal and sludge disintegration. The treatment was expected to increase the amount of biogas produced and to reduce the amount of siloxane in the gas. Adding sodium hydroxide (NaOH) to the sludge improved the removal of siloxane from the sludge, with approximately 90% of the siloxane removed to the gas phase using a thermo-alkaline treatment. Over 80% of decamethylcyclopentasiloxane (D5) could be removed under the following conditions: 55 °C treatment temperature, 135 g-NaOH kg −1 volatile total solids (VTS), and 0.5 L min −1 air-stripping rate. The disintegration ratio of volatile suspended solids (VSS) in the sludge was correlated with the D5 removal ratio. Because most of the siloxane was adsorbed to, or was contained in the VSS, the siloxane removal ratio increased with VSS disintegration. Finally, the energy consumption and operational costs of this system were evaluated for several scenarios. Thermo-alkaline treatment at the indicated operational conditions had the lowest operating costs for a 400 m 3 day −1 anaerobic sludge digestion system

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

[Effectiveness of conventional diagnostic radiology and nuclear medicine in the treatment of pain from bone metastases].

Science.gov (United States)

Genovese, Eugenio Annibale; Mallardo, Vania; Vaccaro, Andrea; Santagata, Mario; Raucci, Antonio; D'Agosto, Gianfranco; Fontanarosa, Antonio; Schillirò, Francesco