Radioactivity measurement of radioactive contaminated soil by using a fiber-optic radiation sensor

Science.gov (United States)

Joo, Hanyoung; Kim, Rinah; Moon, Joo Hyun

2016-06-01

A fiber-optic radiation sensor (FORS) was developed to measure the gamma radiation from radioactive contaminated soil. The FORS was fabricated using an inorganic scintillator (Lu,Y)2SiO5:Ce (LYSO:Ce), a mixture of epoxy resin and hardener, aluminum foil, and a plastic optical fiber. Before its real application, the FORS was tested to determine if it performed adequately. The test result showed that the measurements by the FORS adequately followed the theoretically estimated values. Then, the FORS was applied to measure the gamma radiation from radioactive contaminated soil. For comparison, a commercial radiation detector was also applied to measure the same soil samples. The measurement data were analyzed by using a statistical parameter, the critical level to determine if net radioactivity statistically different from background was present in the soil sample. The analysis showed that the soil sample had radioactivity distinguishable from background.

A guide to radiation and radioactivity levels near high energy particle accelerators

International Nuclear Information System (INIS)

Sullivan, A.H.

1992-01-01

An estimate of likely radiation and radioactivity levels is needed at the design stage of an accelerator for deciding the radiation safety features to be incorporated in the infrastructure of the machine and for predicting where radiation damage possibilities will have to be taken into account. Both these aspects can have a significant influence on the machine layout and cost. Failure to make a reasonable assessment at the right time may have far reaching consequences for future costs. The purpose of this guide is to bring together basic data and methods that have been found useful in assessing radiation situations around accelerators and to provide a practical means of arriving at the radiation and induced radioactivity levels that could occur under a wide variety of circumstances. An attempt is made to present the information in a direct and unambiguous way with sufficient confidence that the necessity for large safety factors is avoided. In many cases assumptions and simplifications have been made and reliance placed on extrapolating from experimental data into regions where the basic physics is too complicated to make meaningful absolute calculations. Wherever possible such extrapolations have been tied to real or otherwise acceptable data originating from independent sources. (Author)

Radiation protection. Radioactivity and health. 3. ed.

International Nuclear Information System (INIS)

Feinendegen, L.E.; Feldmann, A.; Muench, E.; Paschke, M.

1986-09-01

This booklet makes an attempt at elucidating the mutual influence of radioactivity and health in a way which is understandable to the non-expert. The basics of radioactivity are briefly explained by way of introduction, the next item to be described is exposure of man to natural and artificial radiation. Somatic and genetic effects of radiation on man are subsequently discussed. The whole area of radioecology - starting with radioactive discharge from nuclear plants and going on to the determination of man's exposure to radiation - is covered and supplemented by a description of the risks of radiation therapy. All this serves to describe the results of long-term research on questions of the radiobiological risks in an understandable way and provide useful information about this eminently important area. (orig.) [de

Provenance of nuclear radioactivity radiation and hazardous health risks

International Nuclear Information System (INIS)

Sakhuja, Geeta

2016-01-01

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

Radioactivity, radionuclides, radiation

CERN Document Server

Magill, Joseph

2005-01-01

RADIOACTIVITY – RADIONUCLIDES – RADIATION is suitable for a general audience interested in topical environmental and human health radiological issues such as radiation exposure in aircraft, food sterilisation, nuclear medicine, radon gas, radiation dispersion devices ("dirty bombs")… It leads the interested reader through the three Rs of nuclear science, to the forefront of research and developments in the field. The book is also suitable for students and professionals in the related disciplines of nuclear and radiochemistry, health physics, environmental sciences, nuclear and astrophysics. Recent developments in the areas of exotic decay modes (bound beta decay of ‘bare’ or fully ionized nuclei), laser transmutation, nuclear forensics, radiation hormesis and the LNT hypothesis are covered. Atomic mass data for over 3000 nuclides from the most recent (2003) evaluation are included.

Laypeople's understanding of radioactivity and radiation

International Nuclear Information System (INIS)

Henriksen, E.K.

1996-01-01

It may be argued that the population should have sufficient understanding of radiation phenomena to secure individual safety as well as democratic decisions. To attain this, it is necessary for the communicators of radiation information to be familiar with the lay person's perceptions of these phenomena. A questionnaire survey was conducted to examine non-experts' conceptions of radiation phenomena. The survey revealed incomplete understanding of concepts such as radioactive decay, half-life and absorption of radiation and a lack of differentiation between radiation and radioactive material. Many respondents did not distinguish between sources of ionising radiation and other environmental hazards. Nuclear power plants and submarines were the most feared sources of radiation. There are indications that the lay understanding of radiation phenomena and risk is to a large extent formed by mass media and that 'school knowledge' of these phenomena is not applied in situations belonging to the 'real world'. To resolve this problem, new teaching and information procedures are needed. These should take into account the learners' preconceptions and should integrate 'school knowledge' with considerations belonging to the 'real world'. (author)

Radioactivity handbook. Volume 2: radioactive disintegrations, radiations-matter interactions, applications of radioactivity

International Nuclear Information System (INIS)

Foos, J.; Bonfand, E.; Rimbert, J.N.

1994-01-01

This volume is the second one of a group of three. The first one exposed nuclides, with neutrons and protons in a stable building: atomic nucleus. Here is the second one with unstable, radioactive nucleus. After the description of different kinds of disintegrations, it is justified to follow radiations in matter and modifications attached to them; different uses of radioactivity are developed in medicine, age determination, industrial utilization and biology

Cellular retention of radioactivity and increased radiation dose. Model experiments with EGF-dextran

International Nuclear Information System (INIS)

Sundberg, Aasa Liljegren; Blomquist, Erik; Carlsson, Joergen; Steffen, Ann-Charlott; Gedda, Lars

2003-01-01

Targeting of tumor cells with radiolabeled biomolecules is a possible approach to inactivate disseminated tumor cells. However, rapid degradation of the biomolecules after cellular internalization and subsequent excretion of the radioactivity is a problem. We studied the possibility of using dextran as a carrier of radionuclides to improve the intracellular retention. An EGF-dextran conjugate, aimed for targeting of tumor cells overexpressing the EGF-receptor, was used as model. Retention tests were performed with 125 I on different parts: [ 125 I]-EGF-dextran-[ 125 I], [ 125 I]-EGF-dextran and EGF-dextran-[ 125 I]. Comparisons were made with [ 125 I]-EGF. The radiolabeled compounds were incubated with cultured glioma cells for different times. The cellular retention of radioactivity was then measured for up to 24 h. Expected radiation doses at the cellular level were calculated assuming that 131 I, instead of 125 I, was coupled to EGF and EGF-dextran. The results indicated that the EGF-part of the conjugate was degraded and the EGF-attached radioactivity was rapidly excreted, whereas radioactivity on dextran was retained intracellularly to a high degree, i.e. 70-80% of the radioactivity bound to dextran was still cell-associated after 24 h. The retention after 24 h was significantly higher (p < 0.001) when the radioactivity was on the dextran instead of the EGF-part. The radiolabeled EGF-dextran had a notably high specific radioactivity; up to 11 MBq/μg. There was potential for at least hundred times increased radiation dose per receptor interaction when the radioactivity was on the dextran part. The advantage with radioactivity on the dextran part was the high cellular retention and the high specific radioactivity (higher than previously reported for other residualizing labels) without severe loss of receptor specific binding. Thus, dextran seems suitable as a carrier of radionuclides aimed for therapy and gives potential for a highly increased radiation dose

Feasibility study on utilization of vitrified radioactive waste as radiation sources

International Nuclear Information System (INIS)

Makuuchi, Keizo; Yoshii, Fumio; Hyakutake, Kenichiro

1995-01-01

A feasibility study on utilization of vitrified high level radioactive waste (VW) as radiation source has been carried out. Natural rubber latex was radiation vulcanized with VW to demonstrate the feasibility. The dose rate was 0.1 kGy/hr. As a sensitizer, n-butyl acrylate was added. Negligible small activation of natural rubber (NR) latex by neutron from the VW was observed. The residual sensitizer in the irradiated latex and physical properties of film molded from the irradiated latex were the same level with the conventional radiation vulcanization of NR latex with γ-rays from Co-60. Surgical gloves and protective rubber gloves for radioactive contamination were produced from 20 litters of NR latex vulcanized with 2 VWs. The physical properties of both gloves were acceptable. These results suggested that vitrified high level waste can be used as an industrial radiation source. (author)

Actions of radiation protection in the collection of discarded radioactive material

International Nuclear Information System (INIS)

Neri, E.P.M.; Silva, F.C.A. da

2017-01-01

Brazil has approximately 2000 radiative facilities that use radiation sources in their processes and are controlled by The Brazilian Nuclear Energy Commission - CNEN through standards, authorizations and inspections. These radioactive materials, whether in the form of waste or radioactive source, used in medical, industrial, research, etc. are sometimes discarded and found in inappropriate places, such as garbage dumps, industrial waste, streets, squares, etc. found by urban cleaning professionals without the proper knowledge of them. The work presents the radiation protection actions required for the safe collection of radioactive material to be performed by these professionals. According to the type of radioactive material the main actions of radiation protection are, among others: recognition of a radioactive material; correct use of personal protective equipment to contain possible radiation contamination; implementation of an area control etc. In order for the actions of recognition and collection of discarded radioactive material to be effective, there is a need to implement a training program in radiation protection for urban cleaning professionals

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-08-15

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

Properties of Natural Radiation and Radioactivity

International Nuclear Information System (INIS)

Strom, Daniel J.

2009-01-01

Ubiquitous natural sources of radiation and radioactive material (naturally occurring radioactive material, NORM) have exposed humans throughout history. To these natural sources have been added technologically-enhanced naturally occurring radioactive material (TENORM) sources and human-made (anthropogenic) sources. This chapter describes the ubiquitous radiation sources that we call background, including primordial radionuclides such as 40K, 87Rb, the 232Th series, the 238U series, and the 235U series; cosmogenic radionuclides such as 3H and 14C; anthropogenic radionuclides such as 3H, 14C, 137Cs, 90Sr, and 129I; radiation from space; and radiation from technologically-enhanced concentrations of natural radionuclides, particularly the short-lived decay products of 222Rn ('radon') and 220Rn ('thoron') in indoor air. These sources produce radiation doses to people principally via external irradiation or internal irradiation following intakes by inhalation or ingestion. The effective doses from each are given, with a total of 3.11 mSv y-1 (311 mrem y-1) to the average US resident. Over 2.5 million US residents receive over 20 mSv y-1 (2 rem y-1), primarily due to indoor radon. Exposure to radiation from NORM and TENORM produces the largest fraction of ubiquitous background exposure to US residents, on the order of 2.78 mSv (278 mrem) or about 89%. This is roughly 45% of the average annual effective dose to a US resident of 6.2 mSv y-1 (620 mrem y-1) that includes medical (48%), consumer products and air travel (2%), and occupational and industrial (0.1%). Much of this chapter is based on National Council on Radiation Protection and Measurements (NCRP) Report No. 160, 'Ionizing Radiation Exposure of the Population of the United States,' for which the author chaired the subcommittee that wrote Chapter 3 on 'Ubiquitous Background Radiation.'

Natural radiation and radioactivity in education

International Nuclear Information System (INIS)

Sakanoue, Masanobu

1999-01-01

To understand radiation and radioactivity, it is important to recall the history of their investigation. At first, the works made by Elster and Geitel with a leaf electroscope about 100 years age are introduced. Then the variations of environmental radiation level are shown by the results obtained with a large volume NaI(Tl) detector on my car travelling all over Japan and the data with a pocket dosimeter during my tours in Europe. Among environmental radioactivity, radon and tritium are specially remarked from the historical and educational points of view, with various methods for their measurements. (author)

Natural radiation and radioactivity in education

Energy Technology Data Exchange (ETDEWEB)

Sakanoue, Masanobu [Kanazawa Univ., Takarazuka, Hyogo (Japan)

1999-09-01

To understand radiation and radioactivity, it is important to recall the history of their investigation. At first, the works made by Elster and Geitel with a leaf electroscope about 100 years age are introduced. Then the variations of environmental radiation level are shown by the results obtained with a large volume NaI(Tl) detector on my car travelling all over Japan and the data with a pocket dosimeter during my tours in Europe. Among environmental radioactivity, radon and tritium are specially remarked from the historical and educational points of view, with various methods for their measurements. (author)

Chapter 8. Ionisation radiation and human organism. Radioactivity of human tissues

International Nuclear Information System (INIS)

Toelgyessy, J.; Harangozo, M.

2000-01-01

This is a chapter of textbook of radioecology for university students. In this chapter authors deal with ionisation radiation and human organism as well as with radioactivity of human tissues. Chapter consists of next parts: (1) Radiation stress of human organism; (2) Radioactivity of human tissues and the factors influencing radioactive contamination; (3) Possibilities of decreasing of radiation stress

Disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Glasby, G.P.

1977-01-01

Although controversy surrounding the possible introduction of nuclear power into New Zealand has raised many points including radiation hazards, reactor safety, capital costs, sources of uranium and earthquake risks on the one hand versus energy conservation and alternative sources of energy on the other, one problem remains paramount and is of global significance - the storage and dumping of the high-level radioactive wastes of the reactor core. The generation of abundant supplies of energy now in return for the storage of these long-lived highly radioactive wastes has been dubbed the so-called Faustian bargain. This article discusses the growth of the nuclear industry and its implications to high-level waste disposal particularly in the deep-sea bed. (auth.)

Radiation surveys of radioactive material shipments

International Nuclear Information System (INIS)

Howell, W.P.

1986-07-01

Although contractors function under the guidance of the Department of Energy, there is often substantial variation in the methods and techniques utilized in making radiation measurements. When radioactive materials are shipped from one contractor to another, the measurements recorded on the shipping papers may vary significantly from those measured by the receiver and has been a frequent cause of controversy between contractors. Although significant variances occur in both measurements of radiation fields emanating from shipment containers and measurements of residual radioactivity on the surfaces of the containers, the latter have been the most troublesome. This report describes the measurement of contamination on the exterior surfaces of shipment containers

The induced radioactivity danger parameter for gamma radiation

International Nuclear Information System (INIS)

Perry, D.R.

1985-07-01

Dosimetric and practical aspects of the induced radioactivity danger parameter, as used for calculating the gamma radiation dose rate near to objects that have been exposed to high energy radiation, are examined. A simplified and more generally applicable method of calculation is proposed, based on energy balance in homogeneous media. The problems of applying this in practice are discussed, and it is shown that corrections are generally small enough to be neglected in many practical applications. Examples of calculations by previous and proposed methods are given. (author)

Remote detection of radioactive material using high-power pulsed electromagnetic radiation.

Science.gov (United States)

Kim, Dongsung; Yu, Dongho; Sawant, Ashwini; Choe, Mun Seok; Lee, Ingeun; Kim, Sung Gug; Choi, EunMi

2017-05-09

Remote detection of radioactive materials is impossible when the measurement location is far from the radioactive source such that the leakage of high-energy photons or electrons from the source cannot be measured. Current technologies are less effective in this respect because they only allow the detection at distances to which the high-energy photons or electrons can reach the detector. Here we demonstrate an experimental method for remote detection of radioactive materials by inducing plasma breakdown with the high-power pulsed electromagnetic waves. Measurements of the plasma formation time and its dispersion lead to enhanced detection sensitivity compared to the theoretically predicted one based only on the plasma on and off phenomena. We show that lower power of the incident electromagnetic wave is sufficient for plasma breakdown in atmospheric-pressure air and the elimination of the statistical distribution is possible in the presence of radioactive material.

Evaluating natural radiation level by existing airborne radioactive data

International Nuclear Information System (INIS)

Mingkao, Hu; Changqing, Han; Jiangqi, Fang; Zhengxin, Shen

2002-01-01

Airborne Survey and Remote Sensing Center of Nuclear Industry, founded in the middle of 1950s, is a unique unit specialized in uranium exploration by airborne radioactive survey in China. Large numbers of airborne data of radioactivity and abundant experience have been accumulated for more than 40 years. All-round detailed investigation of environmental radiation levels in our country will not be completed in the near future. Thus, at present it is considered to evaluate natural radiation levels using the existing radioactive data. This paper introduces the results of analysis and study comparing airborne radioactive data for radiation environmental evaluation obtained from survey area in Gansu, China, in the 2001 with the measurement results by ground gamma ray radiation dose-rate instrument for environment. The air-earth inter-comparison error does not exceed 30% at radiation fields with a definite area, and the air-earth inter-comparison error does not exceed 60% at outcrop of granite. In 6km long profile that has various circumstances, such as desert, Gobi, farmland and residential area, minimum of air absorbed dose rate is 47nGy/h at an altitude of 1 meter above the soil plane, maximum is 68nGy/h. The inter-comparison errors are usually less than 20%, and maximum is 25.38%. This shows that it is feasible to obtain natural radiation levels rapidly if we could use the existing radioactive data adequately and make some correction, such as geology factor

Ionising radiations, radioactive materials and the fire services

International Nuclear Information System (INIS)

Button, J.C.E.

1981-05-01

Extensive experience has shown that ionizing radiations and radioactive materials can be used safely in a wide variety of applications, provided a number of precautions are implemented. Transport of radioactive materials is common and regulations designed to ensure safety in such transport have resulted in an excellent safety record. Pre-planning for fire situations in buildings where radioactive materials are known to be present is very desirable. An Australian Standard, AS2243, recommends that Station Officers of the local fire brigade be appraised of the hazards and the need to take particular care in areas marked with ionizing radiation warning signs

Low-level radioactive waste disposal: radiation protection laws

International Nuclear Information System (INIS)

Chapuis, A.M.; Guetat, P.; Garbay, H.

1991-01-01

The politics of radioactive waste management is a part of waste management and activity levels are one of the components of potential waste pollutions in order to assume man and environment safety. French regulations about personnel and public' radiation protection defines clearly the conditions of radioactive waste processing, storage, transport and disposal. But below some activity levels definite by radiation protection laws, any administrative procedures or processes can be applied for lack of legal regulations. So regulations context is not actually ready to allow a rational low-level radioactive waste management. 15 refs.; 4 tabs.; 3 figs

Radiation Sialadenitis Induced by High-dose Radioactive Iodine Therapy

International Nuclear Information System (INIS)

Jeong, Shin Young; Lee, Jaetae

2010-01-01

Radioactive iodine ( 131 I) is accumulated in the thyroid tissue and plays an important role in the treatment of differentiated papillary and follicular cancers after thyroidectomy. Simultaneously, 131 I is concentrated in the salivary glands and secreted into the saliva. Dose-related damage to the salivary parenchyma results from the 131 I irradiation. Salivary gland swelling and pain, usually involving the parotid, can be seen. The symptoms may develop immediately after a therapeutic dose of 131 I and/or months later and progress in intensity with time. In conjunction with the radiation sialadenitis, secondary complications reported include xerostomia, taste alterations, infection, increases in caries, facial nerve involvement, candidiasis, and neoplasia. Prevention of 131 I sialadenitis may involve the use of sialogogic agents to hasten the transit time of the radioactive iodine through the salivary glands. However, studies are not available to delineate the efficacy of this approach. Treatment of the varied complications that may develop encompass numerous approaches and include gland massage, sialogogic agents, duct probing, antibiotics, mouthwashes, good oral hygiene, and adequate hydration. Recently interventional sialoendoscopy has been introduced an effective tool for the management of patients with 131 I-induced sialadenitis that is unresponsive to medical treatment.

Size measurement of radioactive aerosol particles in intense radiation fields using wire screens and imaging plates

Energy Technology Data Exchange (ETDEWEB)

Oki, Yuichi; Tanaka, Toru; Takamiya, Koichi; Ishi, Yoshihiro; UesugI, Tomonori; Kuriyama, Yasutoshi; Sakamoto, Masaaki; Ohtsuki, Tsutomu [Kyoto University Research Reactor Institute, Osaka (Japan); Nitta, Shinnosuke [Graduate School of Engineering, Kyoto University, Kyoto (Japan); Osada, Naoyuki [Advanced Science Research Center, Okayama University, Okayama (Japan)

2016-09-15

Very fine radiation-induced aerosol particles are produced in intense radiation fields, such as high-intensity accelerator rooms and containment vessels such as those in the Fukushima Daiichi nuclear power plant (FDNPP). Size measurement of the aerosol particles is very important for understanding the behavior of radioactive aerosols released in the FDNPP accident and radiation safety in high-energy accelerators. A combined technique using wire screens and imaging plates was developed for size measurement of fine radioactive aerosol particles smaller than 100 nm in diameter. This technique was applied to the radiation field of a proton accelerator room, in which radioactive atoms produced in air during machine operation are incorporated into radiation-induced aerosol particles. The size of 11C-bearing aerosol particles was analyzed using the wire screen technique in distinction from other positron emitters in combination with a radioactive decay analysis. The size distribution for 11C-bearing aerosol particles was found to be ca. 70 μm in geometric mean diameter. The size was similar to that for 7Be-bearing particles obtained by a Ge detector measurement, and was slightly larger than the number-based size distribution measured with a scanning mobility particle sizer. The particle size measuring method using wire screens and imaging plates was successfully applied to the fine aerosol particles produced in an intense radiation field of a proton accelerator. This technique is applicable to size measurement of radioactive aerosol particles produced in the intense radiation fields of radiation facilities.

Transport of radioactivity and radiation

International Nuclear Information System (INIS)

De Beer, G.P.

1988-01-01

The movement of radioactivity and radiation is of prime importance in a wide variety of fields and the present advanced degree of knowledge of transport mechanisms is due largely to the application of sophisticated computer techniques

Security of radioactive sources in radiation facilities

International Nuclear Information System (INIS)

2011-03-01

Safety codes and safety standards are formulated on the basis of internationally accepted safety criteria for design, construction and operation of specific equipment, systems, structures and components of nuclear and radiation facilities. Safety codes establish the objectives and set requirements that shall be fulfilled to provide adequate assurance for safety. Safety guides and guidelines elaborate various requirements and furnish approaches for their implementation. Safety manuals deal with specific topics and contain detailed scientific and technical information on the subject. These documents are prepared by experts in the relevant fields and are extensively reviewed by advisory committees of the Board before they are published. The documents are revised when necessary, in the light of experience and feedback from users as well as new developments in the field. In India, radiation sources are being widely used for societal benefits in industry, medical practices, research, training and agriculture. It has been reported from all over the world that unsecured radioactive sources caused serious radiological accidents involving radiation injuries and fatalities. Particular concern was expressed regarding radioactive sources that have become orphaned (not under regulatory control) or vulnerable (under weak regulatory control and about to be orphaned). There is a concern about safety and security of radioactive sources and hence the need of stringent regulatory control over the handling of the sources and their security. In view of this, this guide is prepared which gives provisions necessary to safeguard radiation installations against theft of radioactive sources and other malevolent acts that may result in radiological consequences. It is, therefore, required that the radiation sources are used safely and managed securely by only authorised personnel. This guide is intended to be used by users of radiation sources in developing the necessary security plan for

Ionization profile of beta radiation from radioactive cloud

International Nuclear Information System (INIS)

Vujovic, M.; Vojvodic, V.

1978-01-01

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

Effect of background radiation shielding on natural radioactivity distribution measurement with imaging plate

International Nuclear Information System (INIS)

Mori, C.; Suzuki, T.; Koido, S.; Uritani, A.; Miyahara, H.; Yanagida, K.; Miyahara, J.; Takahashi, K.

1996-01-01

Distribution images of natural radioactivity contained in various natural materials such as vegetable, animal meat and pottery work can be obtained with an imaging plate which has high sensitivity for nuclear radiations. For such very low levels of radioactivity, natural background radiations must be reduced using a shielding box. The lining, on the inside of the box, with low atomic number material such as acrylic resin is very effective in reducing electrons, β-rays and low energy X- and γ-rays emitted from the inner surface of the shielding material. Some images of natural radioactivity distribution were obtained and the radioactivity, mainly 40 K, contained in natural materials was measured by using an HPGe detector and also the imaging plate itself. (orig.)

Radioactivity in the groundwater of a high background radiation area.

Science.gov (United States)

Shabana, E I; Kinsara, A A

2014-11-01

Natural radioactivity was measured in groundwater samples collected from 37 wells scattered in an inhabited area of high natural background radiation, in a purpose of radiation protection. The study area is adjacent to Aja heights of granitic composition in Hail province, Saudi Arabia. Initial screening for gross α and gross β activities showed levels exceeded the national regulation limits set out for gross α and gross β activities in drinking water. The gross α activity ranged from 0.17 to 5.41 Bq L(-)(1) with an average value of 2.15 Bq L(-)(1), whereas gross β activity ranged from 0.48 to 5.16 Bq L(-)(1), with an average value of 2.60 Bq L(-)(1). The detail analyses indicated that the groundwater of this province is contaminated with uranium and radium ((226)Ra and (228)Ra). The average activity concentrations of (238)U, (234)U, (226)Ra and (228)Ra were 0.40, 0.77, 0.29 and 0.46 Bq L(-)(1), respectively. The higher uranium content was found in the samples of granitic aquifers, whereas the higher radium content was found in the samples of sandstone aquifers. Based on the obtained results, mechanism of leaching of the predominant radionuclides has been discussed in detail. Copyright © 2014 Elsevier Ltd. All rights reserved.

The physical protection of radiation sources and radioactive materials in Tanzania

International Nuclear Information System (INIS)

Sungita, Y.Y.; Massalu, I.

2002-01-01

Full text: In recognition of the legal deficiency and the awareness of radiation safety, the parliament of the United Republic of Tanzania enacted the protection from radiation act no. 5 of 1983, which established the national radiation commission (NRC) as a regulatory authority. The main objective of the act was to provide for a legal framework and guidance of the control of the use of radiation sources and radioactive materials with the view to achieve an assurance for acceptance level of radiation protection and safety standard. Due to trade liberalization that is currently experienced in the country, the increase in the number of radiation practices is observed yearly. medical diagnostic x-ray facilities constitute 72 % of all radiation installations in the country. Radioactive materials used in research, teaching and industrial application constitute 24 % and those used in therapy and nuclear medicine is 4 %. About seven radioactive materials incidents occurred in Tanzania during 1996-2000. Among these cases, some were illegal possession and across-boarder trafficking of radioactive materials. Theft and losses radioactive equipments or sources were also experienced. This presentation discusses the experienced incidents of illegal possession, theft and loss of radioactive materials and the lesson learnt from those events in connection with our operational laws. The needs for improvement of the whole system of notification, authorization, registration and licensing to cope up with increase in radiation practices and cross-border illegal trafficking of radioactive materials. The importance of involving immigration officers, police and custom officer with proper training in radiation safety aspect is emphasized. The recommendation are given in an attempt to rescue the situation. (author)

Radioactivity in consumer products : radiation safety and regulatory appraisal

International Nuclear Information System (INIS)

Murthy, B.K.S.; Venkataraman, G.; Subrahmanym, P.

1993-01-01

Use of radioactive materials in consumer products is in vogue almost since the discovery of radioactivity. There has been a rapid growth in the use of radioactive material in various consumer products such as Ionization Chamber Smoke Detectors (ICSD), Static eliminators, etc. In addition, there are certain manufacturing processes wherein the Naturally Occurring Radioactive Material (NORM) get incorporated in the consumer products. Certain phosphatic fertilizers, titanium dioxide pigments, phospho gypsum plaster boards are some examples in this category. The manufacture and use of these products result in radiation dose to the public apart from radiation exposure to the personnel involved in the manufacturing process. Appropriate radiation control measures have to be taken in the design, manufacture and use of consumer products to ensure that the radiation doses to the public and the population at large do not exceed the relevant limits. While appropriate regulatory controls and surveillance are established for manufacture and use of certain products, these are still to be recognised and established in respect of certain other processes and products. The current status of radiation safety and regulatory control and the lack of these in respect of some products are discussed in this paper. (author). 5 refs

The radiation protection and the radioactive wastes management

International Nuclear Information System (INIS)

Servais, F.; Woiche, Ch.; Hunin, Ch.

2003-01-01

This chapter concerns the radiation protection in relation with the radioactive waste management. Three articles make the matter of this file, the management of radioactive medical waste into hospitals, a new concept of waste storage on site, the protection devices on the long term with some lessons for the radioactive waste management. (N.C.)

Managing radioactive waste issues and misunderstandings (radiation realities, energy comparison, waste strategies)

International Nuclear Information System (INIS)

Rosen, M.

2001-01-01

The technical specialist is confident that radioactive waste can be safely managed, but many in the public remain totally unconvinced. There are issues and deep-seated misunderstandings that drive public doubts. Currently, a growing concern with pollution from other industrial waste is enabling radioactive waste issues to be debated in a wider context that allows comparisons with other potentially hazardous waste, particularly from energy generation sources. Health effects and time period issues are not unique to radioactive waste. This paper concentrates on 3 topics. The first concerns radiation health effects where the real realities of radiation are covered. The large misunderstandings that exist about radiation and its health effects have led to an almost zero health impact regulatory policy. A policy which must be more fully understood and dealt with. The second topic deals with a few revealing comparisons about the various energy generation systems. Nuclear power's 10 thousand fold lower fuel requirements, compared with a comparable fossil fuelled plant, is a dominating factor decisively minimising environmental impacts. The third topic examines waste disposal strategies. Extraordinarily small radioactive waste quantities permit a confinement strategy for disposal as opposed to the more common dispersion strategy for most toxic waste. The small quantities coupled with radioactive decay, contrary to the public perception, make any potential hazard from both low and high level radioactive waste exceedingly small. (author)

Environments with elevated radiation levels from natural radioactive substances

International Nuclear Information System (INIS)

Sohrabi, M.

2000-01-01

Some areas in the world have elevated levels of radioactive substances in the environment forming elevated radiation areas (ERAs) where public potential annual effective doses can exceed even the dose limit of radiation workers. Such radioactive substances are either terrestrial natural radioactivity added naturally in the soil or natural and/or man-made radioactivity from human activities added into the environment. If radioactivity is added naturally, elevated natural radiation areas (ENRAs) are formed. Based on the classification criteria introduced by the author, such regions are divided into static and dynamic areas. They are also classified in accordance with their level of potential effective dose to the public. Some main ENRAs are classified. Highlights are presented of the results of activity studies carried out in selected areas. The concepts discussed can also be applied to areas formed by human activities. The author suggests some guidelines for future studies, regulatory control and decision making, bearing in mind the need for harmonization of policies for regulatory control and remedial actions at sites to protect the public from environmental chronic exposures. (author)

Challenges in Regulating Radiation Sources and Radioactive Waste in Nigeria

International Nuclear Information System (INIS)

Ngwakwe, C.

2016-01-01

Identifying challenges that hamper the efficiency and efficacy of Regulatory Infrastructure (People and Processes) as regards ensuring safety & security of radiation sources and radioactive waste is a major step towards planning for improvement. In a world constantly motivated by technological advancements, there has been considerable increase in the use of new technologies incorporating radioactive sources in both medical and industrial applications due to its perceived benefits, hence changing the dynamics of regulation. This paper brings to the fore, contemporary challenges experienced by regulators in the course of regulating radiation sources and radioactive waste in Nigeria. These challenges encountered in the business of regulating radiation sources and radioactive waste in Nigeria amongst others include; knowledge gap in the use of novel technologies for industrial applications (e.g. radiotracers in oil & gas and wastewater management), inadequate collaboration with operators to ensure transparency in their operations, inadequate cooperation from other government agencies using ionizing radiation sources, lack of synergy between relevant government agencies, difficulty in establishing standard radioactive waste management facility for orphan & disused sources, and inadequate control of NORMS encountered in industrial activities (e.g. well logging, mining). Nigerian Nuclear Regulatory Authority (NNRA), the body saddled with the responsibility of regulating the use of ionizing radiation sources in Nigeria is empowered by the Nuclear Safety and Radiation Protection Act to ensure the protection of life, property, and the environment from the harmful effects of ionizing radiation, hence are not immune to the aforementioned challenges. (author)

National environmental radiation monitoring program: towards formulating policy on radioactive waste management

International Nuclear Information System (INIS)

Sukiman Sarmani

2002-01-01

Though Malaysia has no nuclear power station, but the management of its low level radioactive waste generated from industrial activities involves most of the same issues that must be considered in countries with nuclear power. These include public consultation at all stages, an open approach, high level scientific and engineering input and political decision by the Government. A carefully planned approach, which involves the public and gives time to build trust and confidence, is necessary for success. It is also pertinent to establish accurate and reliable data on environmental radiation to accurately assess possible risk. This is where a national monitoring program on environmental radiation is very important. While accurate data will help formulate sound policy on radioactive waste management, it should also be readily available to the public to gain support and acceptance. This paper presents arguments on the importance of a national monitoring program for environmental radiation as an input for formulating a policy on radioactive waste management in Malaysia. (Author)

Radiation Sialadenitis Induced by High-dose Radioactive Iodine Therapy

Energy Technology Data Exchange (ETDEWEB)

Jeong, Shin Young; Lee, Jaetae [Kyungpook National University Hospital, Daegu (Korea, Republic of)

2010-06-15

Radioactive iodine ({sup 131}I) is accumulated in the thyroid tissue and plays an important role in the treatment of differentiated papillary and follicular cancers after thyroidectomy. Simultaneously, {sup 131}I is concentrated in the salivary glands and secreted into the saliva. Dose-related damage to the salivary parenchyma results from the {sup 131}I irradiation. Salivary gland swelling and pain, usually involving the parotid, can be seen. The symptoms may develop immediately after a therapeutic dose of {sup 131}I and/or months later and progress in intensity with time. In conjunction with the radiation sialadenitis, secondary complications reported include xerostomia, taste alterations, infection, increases in caries, facial nerve involvement, candidiasis, and neoplasia. Prevention of {sup 131}I sialadenitis may involve the use of sialogogic agents to hasten the transit time of the radioactive iodine through the salivary glands. However, studies are not available to delineate the efficacy of this approach. Treatment of the varied complications that may develop encompass numerous approaches and include gland massage, sialogogic agents, duct probing, antibiotics, mouthwashes, good oral hygiene, and adequate hydration. Recently interventional sialoendoscopy has been introduced an effective tool for the management of patients with {sup 131}I-induced sialadenitis that is unresponsive to medical treatment.

Information by the German Federal Government. Environmental radioactivity and radiation exposure in 2010

International Nuclear Information System (INIS)

2010-01-01

The information by the German Federal Government on the environmental radioactivity and radiation exposure in 2010 includes five chapters. (I) Natural radiation exposure: radiation sources, contributions from cosmic radiation, contaminated construction materials, food and drinking water, and radon, evaluation of the different components of natural radiation exposure. (II) Civilization caused radiation exposure: nuclear power plants, research centers, nuclear fuel processing plants, other nuclear facilities (interim storage facilities, repositories); summarizing evaluation for nuclear facilities; environmental radioactivity due to mining; radioactive materials in research, technology and households; industrial and mining residues; fall-out as a consequence of the Chernobyl reactor accident and nuclear weapon testing. (III) Occupational radiation exposure: civil radiation sources, natural radiation sources, special events. (IV) Medical radiation exposure; X-ray diagnostics; nuclear medicine; radiotherapy using ionizing radiation; radiotherapy using open radioactive materials; evaluation of radiotherapy. (V) Non-ionizing radiation: electromagnetic fields; optical radiation; certification of solaria.

Vessel used in radiation counting to determine radioactivity levels

International Nuclear Information System (INIS)

Charlton, J.C.; Glover, J.S.; Shephard, B.P.

1977-01-01

This invention concerns the vessels used in radiation counting to determine radioactivity levels. These vessels prove to be particularly useful in analyses of the kind where a radioactive element or compound is separated into two phases and the radioactivity of one phase is determined. Such a vessel used in the counting of radiation includes an organic plastic substance tube appreciably cylindrical in shape whose upper end is open whilst the lower end is closed and integral with it, and an anti-radiation shield in metal or in metal reinforced plastic located at the lower end of the tube and extending along the wall of the tube up to a given height. The vessel contains a reaction area of 1 to 10 ml for holding fluid reagents [fr

Radioactive airborne species formed in the air in high energy accelerator tunnels

International Nuclear Information System (INIS)

Kondo, K.

2005-01-01

Many radioactive airborne species have been observed in the air of high energy accelerator tunnels during machine operation. Radiation protection against these induced airborne radioactivities is one of the key issues for radiation safety, especially at high-energy and high-intense proton accelerators such as the J-PARC (Japan Proton Accelerator Research Complex, Joint project of KEK and JAERI), which is now under construction at the TOKAI site of JAERI. Information on the chemical forms and particle sizes of airborne radioactivities is essential for the estimation of internal doses. For that purpose, the study on radioactive airborne species formed in the air of beam-line tunnels at high-energy accelerators have been extensively conducted by our group. For Be-7, Na-24, S-38, Cl-38,-39, C-11, and N-13, formed by various types of nuclear reactions including nuclear spallation reactions, their aerosol and gaseous fractions are determined by a filter technique. A parallel plate diffusion battery is used for the measurement of aerosol size distributions, and the formation of radioactive aerosols is explained by the attachment of radionuclides to ambient non-radioactive aerosols which are formed through radiation induced reactions. The chemical forms of gaseous species are also determined by using a selective collection method based on a filter technique. A review is given of the physico-chemical properties of these airborne radionuclides produced in the air of accelerator beam-line tunnels.

Occupational radiation exposure in work with radioactive materials

International Nuclear Information System (INIS)

Georgiev, G.V.

1975-01-01

Radiation exposure to personnel dealing with radioactive materials is studied on a national scale. The survey covers any type of radiation work except for mining and milling of radioactive ore, fuel production, and nuclear reactor operation. Assessments are based on a decade's collection of personnel monitoring data obtained by film dosimetry techniques, as well as on data from systematic operational site monitoring. Statistical analysis indicated exposures based on personal records to follow a normal distribution pattern and, hence, arithmetic averages to be representative. Airborne concontrations of radioactive materials and aerosols in working areas are shown to follow a logarithmic normal distribution pattern, so that geometric means are representative. Radiation exposures are generally found to be well below annual maximum permissible doses for radiation workers. However, their distribution among employee groups is nonuniform. Group A, comprising about 700 subjects, received mean annual gonad doses of more than 1000 mrem; group B, about 670 subjects, had doses ranging from 100 to 500 mrem per year; and group C, 1610 subjects, received less than 100 mrem per year. Most of the radiation dose is accounted for by external radiation, which contributed 0.327 mrem to the genetically significant population dose (0.227 from exposure to males, and 0.025 mrem from exposure to females). Analysis of accidental exposures occurring over the period 1963-1973 indicated that the contribution of this source is substantial as compared to routine work (1.0:0.3). Based on the results obtained, a number of preventive measures are developed and introduced into practice to improve radiological safety in work with radioactive materials. (A.B.)

NCRP Program Area Committee 5: Environmental Radiation and Radioactive Waste Issues.

Science.gov (United States)

Chen, S Y; Napier, Bruce

2016-02-01

Program Area Committee 5 of the National Council on Radiation Protection and Measurements (NCRP) focuses its activities on environmental radiation and radioactive waste issues. The Committee completed a number of reports in these subject areas, most recently NCRP Report No. 175, Decision Making for Late-Phase Recovery from Major Nuclear or Radiological Incidents. Historically this Committee addressed emerging issues of the nation pertaining to radioactivity or radiation in the environment or radioactive waste issues due either to natural origins or to manmade activities.

Natural radiation, radioactive waste and chemical risk determinants

International Nuclear Information System (INIS)

Christensen, T.; Mustonen, R.; Edhwall, H.; Hansen, H.; Soerensen, A.; Stranden, E.

1990-01-01

Doses from natural radiation to the population in the Nordic countries are summarized, and man-made modifications of the natural radiation environment are discussed. An account is given for the radiological concequences of energy concervation by reduced ventilation. Risks from possible future releases of radioactivity from final depositories of spent nuclear fuel are compared to the risks from present natural radioactivity in the environment. The possibilities for comparison between chemical and radiological risks are discussed. 104 refs., 36 figs., 47 tabs

Balancing requirements for radioactive waste management and radiation protection

International Nuclear Information System (INIS)

Lafuma, J.; Lefevre, J.

1985-01-01

The authors recall the principles of radiation protection and their application to radioactive waste management. The dose limitation system applies to every stage in management. The accepted risk limits should be compared with the level of risk from other sources, particularly from natural radiation. The uncertainties associated with long-term estimates should not lead to unrealistic requirements. The optimum rules are to be obtained by discussion among those responsible for radiation protection, nuclear safety and radioactive waste management. Satisfactory, applicable rules can be worked out in the present state of the art [fr

Radiation protection programmes for the transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2007-01-01

This Safety Guide provides guidance on meeting the requirements for the establishment of radiation protection programmes (RPPs) for the transport of radioactive material, to optimize radiation protection in order to meet the requirements for radiation protection that underlie the Regulations for the Safe Transport of Radioactive Material. This Guide covers general aspects of meeting the requirements for radiation protection, but does not cover criticality safety or other possible hazardous properties of radioactive material. The annexes of this Guide include examples of RPPs, relevant excerpts from the Transport Regulations, examples of total dose per transport index handled, a checklist for road transport, specific segregation distances and emergency instructions for vehicle operators

Ambient radioactivity levels and radiation doses. Annual report 2013; Umweltradioaktivitaet und Strahlenbelastung. Jahresbreicht 2013

Energy Technology Data Exchange (ETDEWEB)

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

2015-04-15

The report on environmental radioactivity and radiation exposure 2013 includes data concerning the following issues: sources of natural and artificial radioactivity, radon in buildings, radioactive materials in construction materials and industrial products, nuclear weapon tests, the consequences of reactor accidents in Chernobyl and Fukushima, nuclear facilities, occupational exposure, radiation exposure from medical applications, handling of radioactive materials in research and technology, radioactive wastes, radiation accidents and specific incidents.

Regulatory requirements of radiation and radioactive sources in India

International Nuclear Information System (INIS)

Sundara Rao, I.S.

1993-01-01

Manufacture and supply of radiation sources, their use and the disposal of radioactive materials are regulated through the application of Safe Disposal Radioactive Wastes Rules 1987. Salient aspects of these are discussed

Safety of radiation sources and other radioactive materials in Jordan

International Nuclear Information System (INIS)

Majali, M.M.

2001-01-01

Since joining the IAEA Model Project for upgrading radiation protection infrastructure in countries of West Asia, Jordan has amended its radiation safety legislation. The Regulatory Authority is improving its inventory system for radiation sources and other radioactive materials and also its notification, registration, licensing, inspection and enforcement systems. It has established national provisions for the management of orphan sources after they have been found. The system for the control of the radiation sources and other radioactive materials entering the country has been improved by the Regulatory Authority. (author)

Prospective Physics Teachers' Awareness of Radiation and Radioactivity

Science.gov (United States)

Tasoglu, Aslihan Kartal; Ates, Özlem; Bakaç, Mustafa

2015-01-01

The purpose of this study is to investigate prospective physics teachers' knowledge of and attitude towards radiation and radioactivity. Participants of this study are 56 prospective physics teachers. A questionnaire related with the knowledge about radiation and radiation fear was conducted. The results of this study showed that most of the…

Disposal of high-level radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Costello, J M [Australian Atomic Energy Commission Research Establishment, Lucas Heights

1982-03-01

The aims and options for the management and disposal of highly radioactive wastes contained in spent fuel from the generation of nuclear power are outlined. The status of developments in reprocessing, waste solidification and geologic burial in major countries is reviewed. Some generic assessments of the potential radiological impacts from geologic repositories are discussed, and a perspective is suggested on risks from radiation.

A proposed classification system for high-level and other radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Croff, A.G.

1987-06-01

This report presents a proposal for quantitative and generally applicable risk-based definitions of high-level and other radioactive wastes. On the basis of historical descriptions and definitions of high-level waste (HLW), in which HLW has been defined in terms of its source as waste from reprocessing of spent nuclear fuel, we propose a more general definition based on the concept that HLW has two distinct attributes: HLW is (1) highly radioactive and (2) requires permanent isolation. This concept leads to a two-dimensional waste classification system in which one axis, related to ''requires permanent isolation,'' is associated with long-term risks from waste disposal and the other axis, related to ''highly radioactive,'' is associated with shorter-term risks due to high levels of decay heat and external radiation. We define wastes that require permanent isolation as wastes with concentrations of radionuclides exceeding the Class-C limits that are generally acceptable for near-surface land disposal, as specified in the US Nuclear Regulatory Commission's rulemaking 10 CFR Part 61 and its supporting documentation. HLW then is waste requiring permanent isolation that also is highly radioactive, and we define ''highly radioactive'' as a decay heat (power density) in the waste greater than 50 W/m 3 or an external radiation dose rate at a distance of 1 m from the waste greater than 100 rem/h (1 Sv/h), whichever is the more restrictive. This proposal also results in a definition of Transuranic (TRU) Waste and Equivalent as waste that requires permanent isolation but is not highly radioactive and a definition of low-level waste (LLW) as waste that does not require permanent isolation without regard to whether or not it is highly radioactive

Environmental radioactivity and radiation exposure in Switzerland 1995; Umweltradioaktivitaet und Strahlendosen in der Schweiz 1995

Energy Technology Data Exchange (ETDEWEB)

Voelkle, H; Gobet, M

1997-12-31

Switzerland has been performing systematic monitoring of radioactivity in the environment and in food for forty years. This report contains the results of measurements made in the course of 1995 and the consequential radiation doses for the population. The monitoring programme deals with radioactivity in the atmosphere, precipitation, aquatic systems, soil, grass, foodstuffs and the human body, but also includes natural radiation, doses due to radon inside dwellings, emissions from nuclear power stations and other operations using radionuclides, as well as miscellaneous radiation sources. All the nuclear power plants and other facilities licensed to handle radioactive substances remained within their annual release limits in 1995, and environmental measurements revealed no inadmissible immission or dose values. The population`s mean annual radiation dose totals 4 mSv, with some 40% of this due to radon in the home (but with extreme values as high as 100 mSv), another 30% coming from natural radiation, a quarter from medical applications and less than 5% from artificial radiation. (author) figs., tabs., refs.

Environmental radioactivity and radiation exposure in Switzerland 1995; Umweltradioaktivitaet und Strahlendosen in der Schweiz 1995

Energy Technology Data Exchange (ETDEWEB)

Voelkle, H.; Gobet, M.

1996-12-31

Switzerland has been performing systematic monitoring of radioactivity in the environment and in food for forty years. This report contains the results of measurements made in the course of 1995 and the consequential radiation doses for the population. The monitoring programme deals with radioactivity in the atmosphere, precipitation, aquatic systems, soil, grass, foodstuffs and the human body, but also includes natural radiation, doses due to radon inside dwellings, emissions from nuclear power stations and other operations using radionuclides, as well as miscellaneous radiation sources. All the nuclear power plants and other facilities licensed to handle radioactive substances remained within their annual release limits in 1995, and environmental measurements revealed no inadmissible immission or dose values. The population`s mean annual radiation dose totals 4 mSv, with some 40% of this due to radon in the home (but with extreme values as high as 100 mSv), another 30% coming from natural radiation, a quarter from medical applications and less than 5% from artificial radiation. (author) figs., tabs., refs.

Induced radioactivity in Bevatron concrete radiation shielding blocks

International Nuclear Information System (INIS)

Moeller, G.C.; Donahue, R.J.

1994-07-01

The Bevatron accelerated protons up to 6.2 GeV and heavy ions up to 2.1 GeV/amu. It operated from 1954 to 1993. Radioactivity was induced in some concrete radiation shielding blocks by prompt radiation. Prompt radiation is primarily neutrons and protons that were generated by the Bevatron's primary beam interactions with targets and other materials. The goal was to identify the gamma-ray emitting nuclides (t 1/2 > 0.5 yr) that could be present in the concrete blocks and estimate the depth at which the maximum radioactivity presently occurs. It is shown that the majority of radioactivity was produced via thermal neutron capture by trace elements present in concrete. The depth of maximum thermal neutron flux, in theory, corresponds with the depth of maximum induced activity. To estimate the depth at which maximum activity occurs in the concrete blocks, the LAHET Code System was used to calculate the depth of maximum thermal neutron flux. The primary beam interactions that generate the neutrons are also modeled by the LAHET Code System

Environmental policy. Ambient radioactivity levels and radiation doses in 1998

International Nuclear Information System (INIS)

1999-11-01

The report contains information on the natural (background) radiation exposure (chapter II), the natural radiation exposure as influenced by anthropogenic effects (chapter III), the anthropogenic radiation exposure (chapter IV), and the radiation doses to the environment and the population emanating from the Chernobyl fallout (chapter V). The natural radiation exposure is specified referring to the contributions from cosmic and terrestrial background radiation and intake of natural radioactive substances. Changes of the natural environment resulting from anthropogenic effects (technology applications) inducing an increase in concentration of natural radioactive substances accordingly increase the anthropogenic radiation exposure. Indoor air radon concentration in buildings for instance is one typical example of anthropogenic increase of concentration of natural radioactivity, primarily caused by the mining industry or by various materials processing activities, which may cause an increase in the average radiation dose to the population. Measurements so far show that indoor air concentration of radon exceeds a level of 200 Bq/m 3 in less than 2% of the residential buildings; the EUropean Commission therefore recommends to use this concentration value as a maximum value for new residential buildings. Higher concentrations are primarily measured in areas with relevant geological conditions and abundance of radon, or eg. in mining areas. (orig./CB) [de

Categorization of radioactive sources. Revision of IAEA-TECDOC-1191, Categorization of radiation sources

International Nuclear Information System (INIS)

2003-07-01

Radioactive sources are used throughout the world for a wide variety of peaceful purposes in industry, medicine, agriculture, research and education; and they are also used in military applications. The International Basic Safety Standards provide an internationally harmonized basis for ensuring the safe and secure use of sources of ionizing radiation. Because of the wide variety of uses and activities of radiation sources, a categorization system is necessary so that the controls that are applied to the sources are commensurate with the radiological risks. In September 1998, following an assessment of the major findings of the first International Conference on the Safety of Radiation Sources and the Security of Radioactive Materials, held in Dijon, France, from 14 to 18 September 1998 (the Dijon Conference), the IAEA's General Conference (in resolution GC(42)/RES/12), inter alia, encouraged all governments 'to take steps to ensure the existence within their territories of effective national systems of control for ensuring the safety of radiation sources and the security of radioactive materials' and requested the Secretariat 'to prepare for the consideration of the Board of Governors a report on: (i) how national systems for ensuring the safety of radiation sources and the security of radioactive materials can be operated at a high level of effectiveness; and, (ii) whether international undertakings concerned with the effective operation of such systems and attracting broad adherence could be formulated'. In February 1999, the Secretariat submitted to the IAEA Board of Governors a report prepared in response to the request made of it by the General Conference. The Board took up the report at its March 1999 session and, inter alia, requested the Secretariat to prepare an action plan that took into account the conclusions and recommendations in the report, and the Board's discussion of the report. In August 1999, the Secretariat circulated a proposed Action Plan for

Radioactive clearance discharge of effluent from nuclear and radiation facilities

International Nuclear Information System (INIS)

Liu Xinhua; Xu Chunyan

2013-01-01

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

Recoil separators for radiative capture using radioactive ion beams. Recent advances and detection techniques

Energy Technology Data Exchange (ETDEWEB)

Ruiz, Chris [TRIUMF, Vancouver, BC (Canada); Greife, Uwe; Hager, Ulrike [Colorado School of Mines, Golden, CO (United States)

2014-06-15

Radiative capture reactions involving the fusion of hydrogen or helium are ubiquitous in the stellar history of the universe, and are some of the most important reactions in the processes that govern nucleosynthesis and energy generation in both static and explosive scenarios. However, radiative capture reactions pose some of the most difficult experimental challenges due to extremely small cross sections. With the advent of recoil separators and techniques in inverse kinematics, it is now possible to measure radiative capture reactions on very short-lived radioactive nuclei, and in the presence of high experimental backgrounds. In this paper we review the experimental needs for making measurements of astrophysical importance on radiative capture reactions. We also review some of the important historical advances in the field of recoil separators as well as describe current techniques and performance milestones, including descriptions of some of the separators most recently working at radioactive ion beam facilities, such as DRAGON at TRIUMF and the DRS at the Holifield Radioactive Ion Beam Facility. We will also summarize some of the scientific highlight measurements at the RIB facilities. (orig.)

Fire simulation in radioactive waste disposal and the radiation risk associated

International Nuclear Information System (INIS)

Domingos, Érica Nascimento

2018-01-01

An atmospheric dispersion of radioactive material is one of the possible consequences of an accident scenario in nuclear installations, radiative and radioactive waste deposit. Taking into account a possibility of this release of radioactive material into the atmosphere this work proposes a modeling of the atmospheric dispersion from a fire scenario in a deposit of radioactive waste of low and middle level of radiation varying the amount of inventory released in the fire. For this simulation was adopted the software of physical codes of medical health, the HotSpot Health Physics Codes which uses the Gaussian model to calculate an atmospheric dispersion based on the Pasquill atmospheric stability classes. This software calculates a total effective dose in relation to distance, such as a compromised dose in a list of specific organs, among them the lung, object of work study for calculating the risk of cancer associated with a low dose of radiation. The radiological risk calculation is held by the BEIR V model, Biological Effects of Ionizing Radiations, one of the models to estimate the relative risk of cancer induced by ionizing radiation. (author)

Environmental radioactivity and radiation exposure in 2015; Umweltradioaktivitaet und Strahlenbelastung im Jahr 2015

Energy Technology Data Exchange (ETDEWEB)

NONE

2017-07-20

The information of the German Federal Government on the environmental radioactivity and radiation exposure in 2015 covers the following issues: selected topics of radiation protection, natural radiation exposure; civilizing (artificial) radiation exposure: nuclear power plants and other nuclear facilities, uranium mine recultivation, radioactive materials in industry and households, fallout from nuclear weapon testing and reactor accidents; occupational radiation exposure: exposed personnel in nuclear facilities, aviation personnel, radiation accidents; medical radiation exposure: nuclear medical diagnostics and therapy; non-ionizing radiation: electromagnetic fields, UV radiation, optical radiation.

Environmental radioactivity and radiation exposure in Switzerland 1994; Umweltradioaktivitaet und Strahlendosen in der Schweiz 1994

Energy Technology Data Exchange (ETDEWEB)

Voelkle, H.; Gobet, M. [eds.

1995-12-31

Systematic monitoring of radioactivity in the environment and food has been going on in Switzerland since the mid 1950s. This report contains a summary of the values measured in 1994, along with the interpretation of the data and the resultant radiation doses for the population. The monitoring programme deals with radioactivity in the atmosphere, precipitation, aquatic systems, grass, foodstuffs and the human body, but also includes natural radiation, doses due to radon inside dwellings, emissions from nuclear power stations and other installations using radionuclides and also miscellaneous radiation sources. With only one exception, the nuclear power plants and other facilities licensed to handle radioactive substances remained within their annual emission limits in 1994, and measurements carried out in the environment revealed no inadmissible immission or dose values. The population`s mean annual radiation dose totals 4 mSv. Some 40% of this is due to radon in the home, with extreme values as high as 100 mSr; 30% may be ascribed to natural radiation, roughly 25% to medical applications of ionising radiation, leaving less than 5% ascribable to man-made sources. (author) figs., tabs., refs.

Environmental radioactivity and radiation exposure in Switzerland 1994; Umweltradioaktivitaet und Strahlendosen in der Schweiz 1994

Energy Technology Data Exchange (ETDEWEB)

Voelkle, H; Gobet, M [eds.

1996-12-31

Systematic monitoring of radioactivity in the environment and food has been going on in Switzerland since the mid 1950s. This report contains a summary of the values measured in 1994, along with the interpretation of the data and the resultant radiation doses for the population. The monitoring programme deals with radioactivity in the atmosphere, precipitation, aquatic systems, grass, foodstuffs and the human body, but also includes natural radiation, doses due to radon inside dwellings, emissions from nuclear power stations and other installations using radionuclides and also miscellaneous radiation sources. With only one exception, the nuclear power plants and other facilities licensed to handle radioactive substances remained within their annual emission limits in 1994, and measurements carried out in the environment revealed no inadmissible immission or dose values. The population`s mean annual radiation dose totals 4 mSv. Some 40% of this is due to radon in the home, with extreme values as high as 100 mSr; 30% may be ascribed to natural radiation, roughly 25% to medical applications of ionising radiation, leaving less than 5% ascribable to man-made sources. (author) figs., tabs., refs.

Radiation environmental impact assessment of radioactive substances of an airport transit storage construction projects

International Nuclear Information System (INIS)

Zhang Baozeng; Xia Zitong; Zou Zhaozhuang

2014-01-01

Radioactive substances belong to dangerous goods transport aviation. Radioactive substances impoundments construction purpose is to ensure that the radioactive material during transport to transport and the public to achieve full or isolation, the effects of radiation on the human body, property and the environment caused by the control to an acceptable level. According to the relevant national standards and norms, for radiation protection evaluation of project construction of an airport radioactive impoundments, feasibility of the construction project radiation environment. (authors)

Radiation safety management system in a radioactive facility

International Nuclear Information System (INIS)

Amador, Zayda H.

2008-01-01

Full text: This paper illustrates the Cuban experience in implementing and promoting an effective radiation safety system for the Centre of Isotopes, the biggest radioactive facility of our country. Current management practice demands that an organization inculcate culture of safety in preventing radiation hazard. The aforementioned objectives of radiation protection can only be met when it is implemented and evaluated continuously. Commitment from the workforce to treat safety as a priority and the ability to turn a requirement into a practical language is also important to implement radiation safety policy efficiently. Maintaining and improving safety culture is a continuous process. There is a need to establish a program to measure, review and audit health and safety performance against predetermined standards. All those areas of the radiation protection program are considered (e.g. licensing and training of the staff, occupational exposure, authorization of the practices, control of the radioactive material, radiological occurrences, monitoring equipment, radioactive waste management, public exposure due to airborne effluents, audits and safety costs). A set of indicators designed to monitor key aspects of operational safety performance are used. Their trends over a period of time are analyzed with the modern information technologies, because this can provide an early warning to plant management for searching causes behind the observed changes. In addition to analyze the changes and trends, these indicators are compared against identified targets and goals to evaluate performance strengths and weaknesses. A structured and proper radiation self-auditing system is seen as a basic requirement to meet the current and future needs in sustainability of radiation safety. The integrated safety management system establishment has been identified as a goal and way for the continuous improvement. (author)

Natural radioactivity and associated radiation characteristic of the new high background radiation area of lambwe east southern Kenya

International Nuclear Information System (INIS)

Achola, S.O.; Patel, J.P.; Angeyo, H.K.; Mustapha, A.O.

2010-01-01

Rocks and soils from a number of areas underlined by carbonatite rocks in Kenya have been associated with high levels of natural background radioactivity. People in such high background radiation areas (HBRA), are exposed to abnormally high annual absorbed dose (that have health implications) than the global normal 1 mSvyr-1. In this paper, results of field background radiation measurements, activity concentrations of primordial radionuclides in (mainly carbonatite rock and soil) matrices, and estimated annual external effective dose rates are presented for South and North Ruri hills in Lambwe East location of Suba District, which lies roughly between latitudes 0°30'S and 1°00'S, bounded on the east by longitude 34°30'E and on the west by the shores of Lake Victoria 16 and Winnam Gulf. Altitudes in the region range from about 1000 m on the shores of Lake Victoria to above 1800 m on top of the Ruri hills. The main geological features are carbonatite formations. Twenty one samples were analyzed using high-purity germanium (HPGe) gamma-ray spectrometer. The activity concentrations ranged 14.18 - 6559.99 Bqkg-1 (average: 1396.85 Bqkg-1) for Th-232; 2.73 - 499.24 Bqkg-1 (average: 178.69 Bqkg-1) for U-238; and 56.67 - 1454.73 Bqkg-1 (average: 508.67 Bqkg-1) for K-40. The variability in Th distribution could be due to another contributing factor apart from carbonatite: Homa hills geothermal field fluids might be responsible for delivery of Th to surface rocks; some hot spots have travertine deposits. Measured absorbed dose rates in air outdoors range 700 - 6000.00 nGyh-1 (mean: 2325.84 nGy h-1); assuming 0.4 occupancy factor, these values correspond to individual annual effective dose rates of 1.717 - 14.717 mSvyr-1 (mean: 5.705 mSv yr-1). Measured absorbed dose rates are higher than calculated values since they include the contribution of cosmic rays. The natural radioactivity is fractionated with higher levels in the soils than carbonatite rocks

Topical issues in nuclear, radiation and radioactive waste safety. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-08-01

The IAEA International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety was held in Vienna, Austria, 30 August - 4 September 1998 with the objective to foster the exchange of information on topical issues in nuclear, radiation and radioactive waste safety, with the aim of consolidating an international consensus on: the present status of these issues; priorities for future work; and needs for strengthening international co-operation, including recommendations for the IAEA`s future activities. The document includes 43 papers presented at the Conference dealing with the following topical issues: Safety Management; Backfitting, Upgrading and Modernization of NPPs; Regulatory Strategies; Occupational Radiation Protection: Trends and Developments; Situations of Chronic Exposure to Residual Radioactive Materials: Decommissioning and Rehabilitation and Reclamation of Land; Radiation Safety in the Far Future: The Issue of Long Term Waste Disposal. A separate abstract and indexing were provided for each paper. Refs, figs, tabs

Topical issues in nuclear, radiation and radioactive waste safety. Contributed papers

International Nuclear Information System (INIS)

1998-08-01

The IAEA International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety was held in Vienna, Austria, 30 August - 4 September 1998 with the objective to foster the exchange of information on topical issues in nuclear, radiation and radioactive waste safety, with the aim of consolidating an international consensus on: the present status of these issues; priorities for future work; and needs for strengthening international co-operation, including recommendations for the IAEA's future activities. The document includes 43 papers presented at the Conference dealing with the following topical issues: Safety Management; Backfitting, Upgrading and Modernization of NPPs; Regulatory Strategies; Occupational Radiation Protection: Trends and Developments; Situations of Chronic Exposure to Residual Radioactive Materials: Decommissioning and Rehabilitation and Reclamation of Land; Radiation Safety in the Far Future: The Issue of Long Term Waste Disposal. A separate abstract and indexing were provided for each paper

Radiation safety in sea transport of radioactive material in Japan

International Nuclear Information System (INIS)

Odano, N.; Yanagi, H.

2004-01-01

Radiation safety for sea transport of radioactive material in Japan has been discussed based on records of the exposed dose of sea transport workers and measured data of dose rate equivalents distribution inboard exclusive radioactive material shipping vessels. Recent surveyed records of the exposed doses of workers who engaged in sea transport operation indicate that exposed doses of transport workers are significantly low. Measured distribution of the exposed dose equivalents inboard those vessels indicates that dose rate equivalents inside those vessels are lower than levels regulated by the transport regulations of Japan. These facts clarify that radiation safety of inboard environment and handling of transport casks in sea transport of radioactive material in Japan are assured

Radiation safety in sea transport of radioactive material in Japan

Energy Technology Data Exchange (ETDEWEB)

Odano, N. [National Maritime Research Inst., Tokyo (Japan); Yanagi, H. [Nuclear Fuel Transport Co., Ltd., Tokyo (Japan)

2004-07-01

Radiation safety for sea transport of radioactive material in Japan has been discussed based on records of the exposed dose of sea transport workers and measured data of dose rate equivalents distribution inboard exclusive radioactive material shipping vessels. Recent surveyed records of the exposed doses of workers who engaged in sea transport operation indicate that exposed doses of transport workers are significantly low. Measured distribution of the exposed dose equivalents inboard those vessels indicates that dose rate equivalents inside those vessels are lower than levels regulated by the transport regulations of Japan. These facts clarify that radiation safety of inboard environment and handling of transport casks in sea transport of radioactive material in Japan are assured.

The radiation monitoring of environment around place of treatment and storage of radioactive wastes

International Nuclear Information System (INIS)

Vdovina, E.D.

2001-01-01

Full text: Large success was attained in the field of radiation protection of research nuclear center, but it is necessary to carry out works in this way around place of treatment and storage of radioactive wastes too. Moreover, for protection of environment it is necessary to control radiation condition of system (radioactive wastes of nuclear center - environment). There is large amount of natural and man-made radionuclides in environment and it is important to solve problem to control individual radionuclides, polluting natural environment. Also, it is necessary to control concentrations of specific radionuclides, which are marks of definite radioactive source. The radionuclides 137 Cs, 90 Sr, 60 Co, 141 Ce, 144 Ce, 95 Zr, 95 Nb, 131 I and natural radionuclides of uranium, thorium and their products of decay are basic radionuclides. The 57 Co, 35 S, 32 P are considered also basic radionuclides taking into consideration specialization of our Institute. The basic problems of control of environment are following: observation of radioactive pollution level of environment objects; estimation of radioactive pollution level with the purpose of warning of possible negative consequences; investigation of dynamics of radioactivity and prognosis of radioactive pollution of environment objects; influence on sources of radioactive pollution. There is large volume information, characterizing radiation condition of environment around research nuclear center and around place of treatment and storage of radioactive wastes. The bank of environment object analysis result date was build for investigation of information. The system of protection around location of treatment and storage of radioactive wastes and around nuclear center consists of control of radioactive wastes, superficial and underground water, soil, plants, atmospheric precipitation. There are analysis of total β- activity, α-activity and γ-spectrometry. This control includes estimation of throw down values

Radioactivity and radiation what they are, what they do, and how to harness them

CERN Document Server

Grupen, Claus

2016-01-01

This book lays the foundations for you to understand all that you always wanted to know about radioactivity. It begins by setting out essential information about the structure of matter, how radiation occurs and how it can be measured. It goes on to explore the substantial benefits of radioactivity through its many applications, and also the possible risks associated with its use. The field of radioactivity is explained in layman’s terms, so that everybody who is interested can improve their understanding of issues such as nuclear power, radiation accidents, medical applications of radiation and radioactivity from the environment. Everything is radioactive. There is natural radioactivity in the homes that we live in, the food that we eat and the air that we breath. For over 100 years, people have recognised the potential for radioactivity to help solve problems and improve our standard of living. This has led to the creation of radioactivity levels in some places that are much higher than naturally-occurr...

Key scientific challenges in geological disposal of high level radioactive waste

International Nuclear Information System (INIS)

Wang Ju

2007-01-01

The geological disposal of high radioactive waste is a challenging task facing the scientific and technical world. This paper introduces the latest progress of high level radioactive disposal programs in the latest progress of high level radioactive disposal programs in the world, and discusses the following key scientific challenges: (1) precise prediction of the evolution of a repository site; (2) characteristics of deep geological environment; (3) behaviour of deep rock mass, groundwater and engineering material under coupled con-ditions (intermediate to high temperature, geostress, hydraulic, chemical, biological and radiation process, etc); (4) geo-chemical behaviour of transuranic radionuclides with low concentration and its migration with groundwater; and (5) safety assessment of disposal system. Several large-scale research projects and several hot topics related with high-level waste disposal are also introduced. (authors)

Predicting Induced Radioactivity at High Energy Accelerators

Energy Technology Data Exchange (ETDEWEB)

Fasso, Alberto

1999-08-27

Radioactive nuclides are produced at high-energy electron accelerators by different kinds of particle interactions with accelerator components and shielding structures. Radioactivity can also be induced in air, cooling fluids, soil and groundwater. The physical reactions involved include spallations due to the hadronic component of electromagnetic showers, photonuclear reactions by intermediate energy photons and low-energy neutron capture. Although the amount of induced radioactivity is less important than that of proton accelerators by about two orders of magnitude, reliable methods to predict induced radioactivity distributions are essential in order to assess the environmental impact of a facility and to plan its decommissioning. Conventional techniques used so far are reviewed, and a new integrated approach is presented, based on an extension of methods used at proton accelerators and on the unique capability of the FLUKA Monte Carlo code to handle the whole joint electromagnetic and hadronic cascade, scoring residual nuclei produced by all relevant particles. The radiation aspects related to the operation of superconducting RF cavities are also addressed.

Environmental policy. Ambient radioactivity levels and radiation doses in 1996

International Nuclear Information System (INIS)

1997-10-01

The report is intended as information for the German Bundestag and Bundesrat as well as for the general population interested in issues of radiological protection. The information presented in the report shows that in 1996, the radiation dose to the population was low and amounted to an average of 4 millisievert (mSv), with 60% contributed by natural radiation sources, and 40% by artificial sources. The major natural source was the radioactive gas radon in buildings. Anthropogenic radiation exposure almost exclusively resulted from application of radioactive substances and ionizing radiation in the medical field, for diagnostic purposes. There still is a potential for reducing radiation doses due to these applications. In the reporting year, there were 340 000 persons occupationally exposed to ionizing radiation. Only 15% of these received a dose different from zero, the average dose was 1.8 mSv. The data show that the anthropogenic radiation exposure emanating from the uses of atomic energy or applications of ionizing radiation in technology is very low. (orig./CB) [de

Development of FOODSEYE, a high-speed screening system for radioactivity in foods

International Nuclear Information System (INIS)

Mizuta, Tetsuro; Tachibana, Kazushige; Kobayashi, Susumu

2012-01-01

We employed the radiation measurement technology utilized for positron emission tomography in nuclear medicine to develop FOODSEYE, a high-speed screening system for radioactivity in food. FOODSEYE enables high-speed screening designed to measure the concentration of radioactive cesium (Bq/kg) in food and determine with a certainty of at least 99% whether a given test article conforms to safety standards established by the Ministry of Health, Labour and Welfare of Japan. The system is comprised of BGO detectors that detect gamma rays with high sensitivity, a shielded construction to reduce noise components from outside sources of radiation (background radiation), a conveyor belt for efficient conveyance of test articles, and a touch screen panel for easy operation and display of results. This design allows the FOODSEYE system to measure trace amounts of radioactivity with high precision. The precision of the system was verified using 30-kg bags of rice tested in Nihonmatsu City in Fukushima Prefecture, Japan. The measurements results obtained with FOODSEYE correlated with, and were within the range of measurement error of, measurement results obtained using a germanium semiconductor detector. The system was also capable of screening one test article per 5 seconds at a standard value of 100 Bq/kg. This article details the system structure, performance and results of verification tests performed using the FOODSEYE high-speed screening system. (author)

Radioactive Waste Management Strategy

International Nuclear Information System (INIS)

2002-01-01

This strategy defines methods and means how collect, transport and bury radioactive waste safely. It includes low level radiation waste and high level radiation waste. In the strategy are foreseen main principles and ways of storage radioactive waste

Regulatory control and safety of radiation and radioactive sources in Bangladesh

International Nuclear Information System (INIS)

Mollah, A.S.

2001-01-01

The application of ionizing radiation and radioactive sources in different fields such as, medicine, industry, agriculture, research and teaching is constantly increasing in Bangladesh. Any system enacted to control exposure to ionizing radiation has as primary objective the protection of health of people against the deleterious effects of radiation. Establishing the appropriate level of radiological protection and safety of radiation sources used in practice or intervention attains this objective. The regulatory program governing the safe use of radioactive and radiation sources in Bangladesh is based on the legislation enacted as Nuclear Safety and Radiation Control (NSRC) Act-93 and NSRC Rules-97 and its implementation by the competent authority. The radiation control infrastructures and procedure are described as well as their functioning for the implementation of relevant activities such as licensing, regular inspection, personal dose monitoring, emergency preparedness, etc. The issue of security of radiation source is dealt in close relation with the preparation and use of the inventory of all radiation sources in the country

Disposal of high level and intermediate level radioactive wastes

International Nuclear Information System (INIS)

Flowers, R.H.

1991-01-01

The waste products from the nuclear industry are relatively small in volume. Apart from a few minor gaseous and liquid waste streams, containing readily dispersible elements of low radiotoxicity, all these products are processed into stable solid packages for disposal in underground repositories. Because the volumes are small, and because radioactive wastes are latecomers on the industrial scene, a whole new industry with a world-wide technological infrastructure has grown up alongside the nuclear power industry to carry out the waste processing and disposal to very high standards. Some of the technical approaches used, and the Regulatory controls which have been developed, will undoubtedly find application in the future to the management of non-radioactive toxic wastes. The repository site outlined would contain even high-level radioactive wastes and spent fuels being contained without significant radiation dose rates to the public. Water pathway dose rates are likely to be lowest for vitrified high-level wastes with spent PWR fuel and intermediate level wastes being somewhat higher. (author)

Information about activity, status and radiation conditions of Republic radioactive waste repository

International Nuclear Information System (INIS)

Saidumarov, P.

2000-01-01

All radioactive wastes in the Republic of Uzbekistan are stored in the Republic Radioactive Waste Repository in Parkent district of Tashkent region. In the facility there are 2 tanks for solid radioactive waste, each of 800 m 3 , one of them is full, second is in operation; 2 tanks for liquid radioactive waste each tank of 200 m 3 , both of them are empty; 6 storages, each of 3 m 3 all of them are empty; 3 storages for spent radioactive sources, one of them is full, 2 of them are in operation; 4 storages for high level radioactive waste, each storage of 3.5 m 3 , one of them is in operation, 3 are empty; one sealed storage containing 135 m 3 of concrete blocks with waste from electronic industry. According to conclusions of a few competent examinations RRWR does not cause damage to the environment. Geographic location and technical conditions of the repository are satisfactory. Low deposition of underground water (62 m) excludes penetration of radioisotopes. There were no radiation accidents during the repository operation

29 CFR 570.57 - Exposure to radioactive substances and to ionizing radiations (Order 6).

Science.gov (United States)

2010-07-01

... to Their Health or Well-Being § 570.57 Exposure to radioactive substances and to ionizing radiations... radioactive substances and to ionizing radiations are particularly hazardous and detrimental to health for... involves exposure to ionizing radiations in excess of 0.5 rem per year. (b) Definitions. As used in this...

Radiation Dose for Self-Disposal due to the Quantity of Radioactive Waste

Energy Technology Data Exchange (ETDEWEB)

Koo, Daeseo; Sung, Hyun-Hee; Kim, Seung-Soo; Kim, Gye-Nam; Choi, Jong-Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

In this study, we evaluated resident radiation dose due to cover depth on contaminated zone such as uranium contaminated soil and concrete wastes under radiation dose limit using RESRAD Version 7.0. The uranium concentration of contaminated zone due to the cover depth are also analyzed. Possibility for self-disposal of uranium contaminated soil and concrete wastes is evaluated from these calculating data. There are several radioactive material disposal methods such as regulation exemption, decontamination and long term storage. To acquire radiation dose under self-disposal from them, the study on decontamination of some uranium contaminated soil and concrete wastes was performed using electrokinectic-electrodialytic. We evaluated radiation dose due to cover depth on contaminated zone such as uranium contaminated soil and concrete wastes under radiation dose limit using RESRAD Version 7.0. As cover depth increases, the tolerable uranium concentration increases up to cover depth (1.5 m) and then it showed saturated uranium concentration above cover depth (1.5 m). Therefore, to carry out self-disposal on the quantity (1000 drums≒300,000 kg) of radioactive waste is easier than to carry out on the quantity (2000 drums≒600,000 kg) of radioactive waste owing to the large tolerable uranium concentration for self-disposal of radioactive waste. As cover depth increases, the individual radiation dose rate decreased up to cover depth (1.5 m) and then it showed saturated individual radiation dose rate above cover depth (1.5 m)

Radiation Dose for Self-Disposal due to the Quantity of Radioactive Waste

International Nuclear Information System (INIS)

Koo, Daeseo; Sung, Hyun-Hee; Kim, Seung-Soo; Kim, Gye-Nam; Choi, Jong-Won

2016-01-01

In this study, we evaluated resident radiation dose due to cover depth on contaminated zone such as uranium contaminated soil and concrete wastes under radiation dose limit using RESRAD Version 7.0. The uranium concentration of contaminated zone due to the cover depth are also analyzed. Possibility for self-disposal of uranium contaminated soil and concrete wastes is evaluated from these calculating data. There are several radioactive material disposal methods such as regulation exemption, decontamination and long term storage. To acquire radiation dose under self-disposal from them, the study on decontamination of some uranium contaminated soil and concrete wastes was performed using electrokinectic-electrodialytic. We evaluated radiation dose due to cover depth on contaminated zone such as uranium contaminated soil and concrete wastes under radiation dose limit using RESRAD Version 7.0. As cover depth increases, the tolerable uranium concentration increases up to cover depth (1.5 m) and then it showed saturated uranium concentration above cover depth (1.5 m). Therefore, to carry out self-disposal on the quantity (1000 drums≒300,000 kg) of radioactive waste is easier than to carry out on the quantity (2000 drums≒600,000 kg) of radioactive waste owing to the large tolerable uranium concentration for self-disposal of radioactive waste. As cover depth increases, the individual radiation dose rate decreased up to cover depth (1.5 m) and then it showed saturated individual radiation dose rate above cover depth (1.5 m)

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

International Nuclear Information System (INIS)

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

2010-01-01

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

Study of casks shielded with heavy metal to transport highly radioactive substances

International Nuclear Information System (INIS)

Lucchesi, R.F.; Hara, D.H.S.; Martinez, L.G.; Mucsi, C.S.; Rossi, J.L.

2014-01-01

Nowadays, Brazil relies on casks produced abroad for transportation in its territory of substances that are sources of high radioactivity, especially the Mo-99. The product of the radioactive decay of the Mo-99 is the Tc-99m, which is used in nuclear medicine for administration to humans in the form of injectable radioactive drugs for the image diagnosis of numerous pathologies. This paper aims to study the existing casks in order to propose materials for the construction of the core part as shielding against gamma radiation. To this purpose, the existing literature on the subject was studied, as well as evaluation of existing and available casks. The study was focused on the core of which is made of heavy metals, especially depleted uranium for shielding the emitted radiation. (author)

Approaches to assign security levels for radioactive substances and radiation sources

International Nuclear Information System (INIS)

Ivanov, M.V.; Petrovskij, N.P.; Pinchuk, G.N.; Telkov, S.N.; Kuzin, V.V.

2011-01-01

The article contains analyzed provisions on categorization of radioactive substances and radiation sources according to the extent of their potential danger. Above provisions are used in the IAEA documents and in Russian regulatory documents for differentiation of regulatory requirements to physical security. It is demonstrated that with the account of possible threats of violators, rules of physical protection of radiation sources and radioactive substances should be amended as regards the approaches to assign their categories and security levels [ru

Understanding radioactive waste

International Nuclear Information System (INIS)

Murray, R.L.

1981-12-01

This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes)

Understanding radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Murray, R.L.

1981-12-01

This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

Regulatory control of radiation sources and radioactive materials: The UK position

International Nuclear Information System (INIS)

Englefield, C.; Holyoak, B.; Ledgerwood, K.; Littlewood, K.

2001-01-01

The paper presents the organizations involved in the regulation of the safety of radiation sources and the security of radioactive materials across the UK. The safety of radiation sources is within the regulatory remit of the Health and Safety Executive, under the Health and safety of Work Act 1974 and associated regulations. Any employer using radiation sources has a statutory duty to comply with this legislation, thereby protecting workers and the public from undue risk. From a radioactive waste management perspective, the storage and use of radioactive materials and the accumulation and disposal of radioactive waste are regulated by the environment agencies of England and Wales, Scotland, and Northern Ireland, under the Radioactive Substances Act 1993. Special regulatory arrangements apply to nuclear sites, such as power stations and fuel cycle plants, and some additional bodies are involved in the regulation of the security of fissile materials. An explanation is given in the paper as to how these organizations to work together to provide a comprehensive and effective regulatory regime. An overview of how these regulators have recently started to work more closely with other enforcement bodies, such as the Police and Customs and Excise is also given, to illustrate the approach that is being applied in the UK to deal with orphan sources and illicit trafficking. (author)

Morsleben repository for radioactive waste (ERAM). Operational safety, radiation protection and environmental monitoring. Release: December 2009

International Nuclear Information System (INIS)

2010-01-01

The report overviews the monitoring activities of the Federal Office for Radiation Protection at the Morsleben repository for radioactive waste (ERAM), focussing the ERAM inventory of radioactive waste and the measures and results of geomechanical and hydrogeological monitoring, operational radiation protection, the monitoring of discharges of radioactive substances, environmental monitoring, and the dose levels expected from discharges of radioactive substances. (orig.)

Radioactivity levels in the mostly local foodstuff consumed by residents of the high level natural radiation areas of Ramsar, Iran.

Science.gov (United States)

Fathabadi, Nasrin; Salehi, Ali Akbar; Naddafi, Kazem; Kardan, Mohammad Reza; Yunesian, Masud; Nodehi, Ramin Nabizadeh; Deevband, Mohammad Reza; Shooshtari, Molood Gooniband; Hosseini, Saeedeh Sadat; Karimi, Mahtab

2017-04-01

Among High Level Natural Radiation Areas (HLNRAs) all over the world, the northern coastal city of Ramsar has been considered enormously important. Many studies have measured environmental radioactivity in Ramsar, however, no survey has been undertaken to measure concentrations in the diets of residents. This study determined the 226 Ra activity concentration in the daily diet of people of Ramsar. The samples were chosen from both normal and high level natural radiation areas and based on the daily consumption patterns of residents. About 150 different samples, which all are local and have the highest consumption, were collected during the four seasons. In these samples, after washing and drying and pretreatment, the radionuclide was determined by α-spectrometry. The mean radioactivity concentration of 226 Ra ranged between 5 ± 1 mBq kg -1 wet weight (chino and meat) to 725 ± 480 mBq kg -1 for tea dry leaves. The 226 Ra activity concentrations compared with the reference values of UNSCEAR appear to be higher in leafy vegetables, milk and meat product. Of the total daily dietary 226 Ra exposure for adults in Ramsar, the largest percentage was from eggs. The residents consuming eggs from household chickens may receive an elevated dose in the diet. Copyright © 2016. Published by Elsevier Ltd.

The dress and the cloud. Stories about X-rays, radioactivity and radiation protection

International Nuclear Information System (INIS)

Lochard, Jacques; Repussard, Jacques; Tabare, Mireille

2013-01-01

This bibliographical note presents a book in which the authors recall the history of X-rays, of radioactivity and of radiation protection. It describes the almost simultaneous discovery of X-rays and radioactivity, the concern created by the Hiroshima and Nagasaki bombings, the importance given back to civil society by the Chernobyl and Fukushima accidents. They comment the various applications of X-rays and radioactivity in the fields of research, medicine, energy, weapons. They describe the progressive development of radiation protection in a context of large political, economic and social evolutions during the past century

Evaluation of S-type fiberglass composites for use in high-level radioactive waste environments

International Nuclear Information System (INIS)

Parra, S.A.

1996-01-01

Two types of S-type fiberglass materials were evaluated for use in a high-level radioactive waste environment. The S-type fiberglass composites tested were in the form of tubes and were exposed to a simulated high-level radioactive waste environment consisting of corrosive chemicals, high gamma radiation, and elevated temperatures. The physical properties of the exposed and unexposed tube samples were compared to determine the effects of the simulated environment on the S-type fiberglass composites

Human genetics studies in areas of high natural radiation. IV. Research in radioactive areas

Energy Technology Data Exchange (ETDEWEB)

Freire-Maia, A [Faculdade de Ciencias Medicas e Biologicas de Botucatu (Brazil). Departamento de Genetica

1974-01-01

A review is made on researches performed in areas with high levels of natural radioactivity. Some considerations are made on the importance and difficulties involved in projects of this kind. Although there is no doubt that natural radioactivity is one of the causes of the so-called spontaneous mutations, the practical demonstration of this assertion is extremely complex. Projects trying to correlate high levels of natural radioactivity with the occurrence of cancer (in general, or specific), leukemia, congenital malformations (in general or specific), neuro-vegetative disturbs, sex ratio, mortality, and physical development, as well as other characteristics. Some researches with animals are also mentioned, and references are given for plant studies. A critical analysis is made of some works relating to human populations.

Human genetics studies in areas of high natural radiation.IV. Research in radioactive areas

International Nuclear Information System (INIS)

Freire-Maia, A.

1974-01-01

A review is made on researches performed in areas with high levels of natural radioactivity. Some considerations are made on the importance and difficulties involved in projects of this kind. Although there is no doubt that natural radioactivity is one of the causes of the so-called spontaneous mutations, the practical demonstration of this assertion is extremely complex. Projects trying to correlate high levels of natural radioactivity with the occurrence of cancer (in general, or specific), leukemia, congenital malformations (in general or specific), neuro-vegetative disturbs, sex ratio, mortality, and physical development, as well as other characteristics. Some researches with animals are also mentioned, and references are given for plant studies. A critical analysis is made of some works relating to human populations [pt

Significance of radiation effects in solid radioactive waste

International Nuclear Information System (INIS)

Permar, P.H.; McDonell, W.R.

1980-01-01

Proposed NRC criteria for disposal of high-level nuclear waste require development of waste packages to contain radionuclide for at least 1000 years, and design of repositories to prevent radionuclide release at an annual rate greater than 1 part in 100,000 of the total activity. The high-level wastes that are now temporarily stored as aqueous salts, sludges, and calcines must be converted to high-integrity solid forms that resist deterioration from radiation and other effects of long-term storage. Spent fuel may be encapsulated for similar long-term storage. Candidate waste forms beside the spent fuel elements themselves, include borosilicate and related glasses, mineral-like crystalline ceramics, concrete formulations, and metal-matrix glass or ceramic composites. these waste forms will sustain damage produced by beta-gamma radiation up to 10 12 rads, by alpha radiation up to 10 19 particles/g, by internal helium generation greater than about 0.1 atom percent, and by the atom transmutations accompanying radioactive decay. Current data indicate that under these conditions the glass forms suffer only minor volume changes, stored energy deposition, and leachability effects. The crystalline ceramics appear susceptible to the potentially more severe alterations accompanying metamictization and natural analogs of candidate materials are being examined to establish their suitability as waste forms. Helium concentrations in the waste forms are generally below thresholds for severe damage in either glass or crystalline ceramics at low temperatures, but microstructural effects are not well characterized. Transmutation effects remain to be established

Dose for background radioactivity in areas with high radioactivity levels in the Pinar del Rio province

International Nuclear Information System (INIS)

Alcaide Orpi, J.; Oliveira Acosta, J.; Valdes Hernadez, G.M.; Leal Ramirez, M.R.; Blanco Jorrin, N.

1998-01-01

The objective the work is to know the areas with high natural radiation doses, for they were used it the data obtained by the studies it has more than enough favorability for radioactive minerals carried out in different regions to the Pinar del Rio province in the 1986 to 1993 years and the doses calculations they were carried out according to the effective methodology

Radiation doses from the transport of radioactive materials

International Nuclear Information System (INIS)

Shaw, K.B.; Holyoak, B.

1983-01-01

A summary is given of a study on radiation exposure resulting from the transport of radioactive materials within the United Kingdom. It was concluded that the transport of technetium generators for hospital use accounts for about 49% of the occupational exposure for the normal transport of radioactive materials. Other isotopes for medical and industrial use contribute about 38% of the occupational exposure and the remainder can be attributed to transportation as a result of the nuclear fuel cycle including the transport of irradiated nuclear fuel. The occupational collective dose for all modes of transport is estimated at 1 man Sv y -1 . (UK)

Environmental radioactivity and radiation exposure in 2013; Umweltradioaktivitaet und Strahlenbelastung im Jahr 2013

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-01

The report on the environmental radioactivity and radiation exposure in 2013 covers the natural radiation exposure due to radon, food, cosmic and terrestric radiation and the radiation exposure due to nuclear medicine nuclear facilities, mining, industry household and fallout. Special issues are the occupational radiation exposure the medical radiation exposure and the exposure to non-ionizing radiation.

Developing procedures for the handling of highly radioactive materials

International Nuclear Information System (INIS)

Wagner, M.L.

1994-01-01

Handling procedures for highly radioactive materials must be analyzed for the reduction of radiation dose. In keeping with ALARA principles, time, distance, and shielding must be used to maximum benefit during the job. After an initial risk assessment is accomplished, job pre-planning meetings and cold open-quotes walk-throughsclose quotes are held in order to engineer the best workable procedure given allocated resources, and to reduce personnel exposure. This paper shows the relationship between each step in the job development, over a number of actual jobs, drawing out how subtle changes in practice can affect the individual and team radiation dose

Remote sampling and analysis of highly radioactive samples in shielded boxes

International Nuclear Information System (INIS)

Kirpikov, D.A.; Miroshnichenko, I.V.; Pykhteev, O.Yu.

2010-01-01

The sampling procedure used for highly radioactive coolant water is associated with high risk of personnel irradiation and uncontrolled radioactive contamination. Remote sample manipulation with provision for proper radiation shielding is intended for safety enhancement of the sampling procedure. The sampling lines are located in an isolated compartment, a shielded box. Various equipment which enables remote or automatic sample manipulation is used for this purpose. The main issues of development of the shielded box equipment intended for a wider ranger of remote chemical analyses and manipulation techniques for highly radioactive water samples are considered in the paper. There were three principal directions of work: Transfer of chemical analysis performed in the laboratory inside the shielded box; Prevalence of computer-aided and remote techniques of highly radioactive sample manipulation inside the shielded box; and, Increase in control over sampling and determination of thermal-hydraulic parameters of the coolant water in the sampling lines. The developed equipment and solutions enable remote chemical analysis in the restricted volume of the shielded box by using ion-chromatographic, amperometrical, fluorimetric, flow injection, phototurbidimetric, conductometric and potentiometric methods. Extent of control performed in the shielded box is determined taking into account the requirements of the regulatory documents as well as feasibility and cost of the technical adaptation of various methods to the shielded box conditions. The work resulted in highly precise determination of more than 15 indexes of the coolant water quality performed in on-line mode in the shielded box. It averages to 80% of the total extent of control performed at the prototype reactor plants. The novel solutions for highly radioactive sample handling are implemented in the shielded box (for example, packaging, sample transportation to the laboratory, volume measurement). The shielded box is

Status of radiation dose and radioactive contamination due to the Fukushima accident

International Nuclear Information System (INIS)

Baba, Mamoru

2016-01-01

The accident at Fukushima Daiichi Nuclear Power Plant (NPP), March 2011, caused serious radioactive contamination over wide area in east Japan. Therefore, it is important to know the effect of the accident and the status of NPP. This paper provides a review on the status of radiation dose and radioactive contamination caused by the accident on the basis of publicized information. Monitoring of radiation dose and exposure dose of residents has been conducted extensively by the governments and various organizations. The effective dose of general residents due to the accident proved to be less than a mSv both for external and internal dose. The equivalent committed dose of thyroid was evaluated to be a few mSv in mean value and less than 50 mSv even for children. Monitoring of radioactivity concentration has been carried out on food ingredients, milk and tap water, and actual meal. These studies indicated the percentage of foods above the regulation standard was over 10% in 2011 but decreasing steadily with time. The internal dose due to foods proved to be tens of μSv and much less than that due to natural 40 K even in the Fukushima area and decreasing steadily, although high level concentration is still observed in wild plants, wild mushrooms, animals and some kind of fishes. According to extensive studies, not only the effect of the accident but also the pathway and countermeasures against radioactive contamination have been revealed, and they are applied very effectively for restoration of environment and reconstruction of the area

Status of radiation dose and radioactive contamination due to the Fukushima accident

Energy Technology Data Exchange (ETDEWEB)

Baba, Mamoru [Tohoku Univeristy, Sendai (Japan)

2016-06-15

The accident at Fukushima Daiichi Nuclear Power Plant (NPP), March 2011, caused serious radioactive contamination over wide area in east Japan. Therefore, it is important to know the effect of the accident and the status of NPP. This paper provides a review on the status of radiation dose and radioactive contamination caused by the accident on the basis of publicized information. Monitoring of radiation dose and exposure dose of residents has been conducted extensively by the governments and various organizations. The effective dose of general residents due to the accident proved to be less than a mSv both for external and internal dose. The equivalent committed dose of thyroid was evaluated to be a few mSv in mean value and less than 50 mSv even for children. Monitoring of radioactivity concentration has been carried out on food ingredients, milk and tap water, and actual meal. These studies indicated the percentage of foods above the regulation standard was over 10% in 2011 but decreasing steadily with time. The internal dose due to foods proved to be tens of μSv and much less than that due to natural {sup 40}K even in the Fukushima area and decreasing steadily, although high level concentration is still observed in wild plants, wild mushrooms, animals and some kind of fishes. According to extensive studies, not only the effect of the accident but also the pathway and countermeasures against radioactive contamination have been revealed, and they are applied very effectively for restoration of environment and reconstruction of the area.

Environmental radiation control and quality management system in design and operation of sealed radioactive sources

International Nuclear Information System (INIS)

Hussein, A.Z.

2007-01-01

New environmental regulations and radiation safety standards are being implemented almost daily to ensure radiation safety, in particular for practices causing exposures to undue radiation doses. A particular emphasis of real challenge for organizations and users of radiation sources has to be for proper radiological safety assessment and is becoming cost effectively to be prepared for auditing. Special concern for the environment is of global . nature, and hence environmental auditing has been and will continue to be an essential practice for improving the environment and for meeting the relevant regulations and standards. In general, most facilities that deal with radioactive sources undertake strict safety measures in terms of personnel radiation protection, handling procedures and security. Hence, those measures should comply with the requirements of the environmental protection standards. Accordingly, a successful quality management system must balance realities of organization and personnel in achieving quality objectives. Organizational principles are found in the technical aspects of' quality management, such as, charting, requirements, measurements, procedures, ... , etc. Human principles are found in the communication side of quality management (e.g. meetings, ,decision making, ,teams, ... , etc). The quality management must understand and balance skills needed to blend them together. Large gamma irradiators present a high potential radiation hazard to the surrounding environment, since the amount of radioactivity is of the order of (P Bq) and a very high dose rates are produced during irradiation. Application of environmental radiation control deemed by regulatory authority and a proper quality management system by the utility would serve public health and safety

Teaching about radioactivity and ionising radiation: an alternative approach

International Nuclear Information System (INIS)

Millar, R.; Klaassen, K.; Eijkelhof, H.

1990-01-01

This article reviews children's ideas about radiation and radioactivity and identifies several common areas of misunderstanding. A new approach to teaching the topic at school level, which seeks specifically to address these known difficulties, is then proposed and outlined. (author)

The Role of Automatic Radiation Monitoring in Control of Illicit Trafficking of Radioactive Materials in Slovenia

International Nuclear Information System (INIS)

Mitic, D.

2003-01-01

Automatic radiation monitoring in Slovenia comprises monitoring of external gamma radiation, aerosol radioactivity, radon progeny concentration, and radioactive deposition measurements. The officer on duty has an important part in assuring proper and undisturbed functioning of our automatic radiation monitoring. He is the one who gets the first alert message on radiation levels when exceeded pre-set values in the territory of Slovenia. Together with continuous control over the functioning of automatic radiation monitoring, the officer on duty has been also assigned for receiving messages from users, who carry the 'Radiation pager' (it is a trade mark for Sensor Technology Engineering, inc. from USA). All valuable experiences of the officer on duty who has been accepting reports from customs officers, police officers, from Slovenian radiation and nuclear safety inspectors, are described in this article. The officer on duty with his new role contributes to prevention of the illicit trafficking and inadvertent movement of radioactive materials over the territory of Slovenia. In the last year there where many different causes of emergency calls: from many cases of patient after radioisotopes medical treatment to serious rejected shipment with exceeded radiation. This is only a beginning of responsible task how to introduce and assure the control of the inadvertent movement of radioactive materials in Slovenia. (author)

Safety of radiation sources and security of radioactive materials. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

The International Atomic Energy Agency (IAEA) in co-operation with the European Commission (EC), International Criminal Police Organization (INTERPOL) and the World Customs Organization (WCO) organized an International Conference on the Safety of Radiation Sources and the Security of Radioactive Materials, in Dijon, France, from 14 to 18 September 1998. The Government of France hosted this Conference through the Commissariat a l`energie atomique, Direction des applications militaires (CEA/DAM). This TECDOC contains the contributed papers dealing with the topics of this Conference which were accepted by the Conference Programme Committee for presentation. The papers written in one of the two working languages of the Conference, English or French are presented here each by a separate abstract. Ten technical sessions covered the following subjects: the regulatory control of radiation sources, including systems for notification, authorization and inspection; safety assessment techniques applied to radiation sources and design and technological measures including defense in depth and good engineering practice; managerial measures, including safety culture, human factors, quality assurance, qualified experts, training and education; learning from operational experience; international co-operation, including reporting systems and databases; verification of compliance, monitoring of compliance and assessment of the effectiveness of national programmes for the safety of sources; measures to prevent breaches in the security of radioactive materials, experience with criminal acts involving radioactive materials; detection and identification technologies for illicitly trafficked radioactive materials; response to detected cases and seized radioactive materials, strengthening of the awareness, training and exchange of information. The IAEA plans to issue the proceedings of this Conference containing the invited presentations, rapporteurs and Chairpersons overviews and summaries

Safety of radiation sources and security of radioactive materials. Contributed papers

International Nuclear Information System (INIS)

1998-09-01

The International Atomic Energy Agency (IAEA) in co-operation with the European Commission (EC), International Criminal Police Organization (INTERPOL) and the World Customs Organization (WCO) organized an International Conference on the Safety of Radiation Sources and the Security of Radioactive Materials, in Dijon, France, from 14 to 18 September 1998. The Government of France hosted this Conference through the Commissariat a l'energie atomique, Direction des applications militaires (CEA/DAM). This TECDOC contains the contributed papers dealing with the topics of this Conference which were accepted by the Conference Programme Committee for presentation. The papers written in one of the two working languages of the Conference, English or French are presented here each by a separate abstract. Ten technical sessions covered the following subjects: the regulatory control of radiation sources, including systems for notification, authorization and inspection; safety assessment techniques applied to radiation sources and design and technological measures including defense in depth and good engineering practice; managerial measures, including safety culture, human factors, quality assurance, qualified experts, training and education; learning from operational experience; international co-operation, including reporting systems and databases; verification of compliance, monitoring of compliance and assessment of the effectiveness of national programmes for the safety of sources; measures to prevent breaches in the security of radioactive materials, experience with criminal acts involving radioactive materials; detection and identification technologies for illicitly trafficked radioactive materials; response to detected cases and seized radioactive materials, strengthening of the awareness, training and exchange of information. The IAEA plans to issue the proceedings of this Conference containing the invited presentations, rapporteurs and Chairpersons overviews and summaries

Comparison of the measured radiation dose-rate by the ionization chamber and G (Geiger-Mueller) counter after radioactive lodine therapy in differentiated thyroid cancer patients

Energy Technology Data Exchange (ETDEWEB)

Park, Kwang Hun [Dept. of Nuclear Medicine, Kyungbuk National University Hospital, Daegu (Korea, Republic of); Kim, Kgu Hwan [Dept. of Radiological Technology, Daegu Health College, Daegu (Korea, Republic of)

2016-12-15

Radioactive iodine(131I) treatment reduces recurrence and increases survival in patients with differentiated thyroid cancer. However, it is important in terms of radiation safety management to measure the radiation dose rate generated from the patient because the radiation emitted from the patient may cause the exposure. Research methods, it measured radiation dose-rate according to the elapsed time from 1 m from the upper abdomen of the patient by intake of radioactive iodine. Directly comparing the changes over time, high dose rate sensitivity and efficiency is statistically significant, and higher chamber than GM counter(p<0.05). Low dose rate sensitivity and efficiency in the chamber had lower levels than gm counter, but not statistically significant(p>0.05). In this study confirmed the characteristics of calibrated ionization chamber and GM counter according to the radiation intensity during high-dose radioactive iodine therapy by measuring the accurate and rapid radiation dose rate to the patient explains, discharged patients will be reduced to worry about radiation hazard of family and others person.

Safety of radiation sources and security of radioactive materials. Proceedings of an international conference

International Nuclear Information System (INIS)

1999-01-01

This International Conference, hosted by the Government of France and co-sponsored by the European Commission, the International Criminal Police Organization (Interpol) and the World Customs Organization (WCO), was the first one devoted to the safety of radiation sources and the security of radioactive materials and - for the first time - brought together radiation safety experts, regulators, and customs and police officers, who need to closely co-operate for solving the problem of illicit trafficking. The technical sessions reviewed the state of the art of twelve major topics, divided into two groups: the safety of radiation sources and the security of radioactive materials. The safety part comprised regulatory control, safety assessment techniques, engineering and managerial measures, lessons from experience, international cooperation through reporting systems and databases, verification of safety through inspection and the use of performance indicators for a regulatory programme. The security part comprised measures to prevent breaches in the security of radioactive materials, detection and identification techniques for illicit trafficking, response to detected cases and seized radioactive materials, strengthening awareness, training and exchange of information. The Conference was a success in fostering information exchange through the reviews of the state of the art and the frank and open discussions. It raised awareness of the need for Member States to ensure effective systems of control and for preventing, detecting and responding to illicit trafficking in radioactive materials. The Conference finished by recommending investigating whether international undertakings concerned with an effective operation of national systems for ensuring the safety of radiation sources and security of radioactive materials

A proposed classification system for high-level and other radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Croff, A.G.

1989-01-01

On the basis of the definition of high-level wastes (HLW) in the Nuclear Waste Policy Act of 1982 and previous descriptions of reprocessing wastes, a definition is proposed based on the concept that HLW is any waste which is highly radioactive and requires permanent isolation. This conceptual definition of HLW leads to a two-dimensional waste classification system in which one axis, related to 'highly radioactive', is associated with shorter-term risks from waste management and disposal due to high levels of decay heat and external radiation, and the other axis, related to 'requires permanent isolation', is associated with longer-term risks from waste disposal. Wastes that are highly radioactive are defined quantitatively as wastes with a decay heat (power density) greater than 50 W/m 3 or an external dose-equivalent rate greater than 100 rem/h (1 Sv/h) at a distance of 1 m from the waste, whichever is more restrictive. Wastes that require permanent isolation are defined quantitatively as wastes with concentrations of radionuclides greater than the Class-C limits that are generally acceptable for near-surface land disposal, as obtained from the Nuclear Regulatory Commission's 10 CFR Part 61 and its associated methodology. This proposal leads to similar definitions of two other waste classes: transuranic (TRU) waste and equivalent is any waste that requires permanent isolation but is not highly radioactive; and low-level waste (LLW) is any waste that does not require permanent isolation, without regard to whether or not it is highly radioactive. 31 refs.; 3 figs.; 4 tabs

Radiation Protection and the Management of Radioactive Waste in the Oil and Gas Industry

International Nuclear Information System (INIS)

2010-01-01

The oil and gas industry, a global industry operating in many Member States, makes extensive use of radiation generators and sealed and unsealed radioactive sources, some of which are potentially dangerous to human health and the environment if not properly controlled. In addition, significant quantities of naturally occurring radioactive material (NORM) originating from the reservoir rock are encountered during production, maintenance and decommissioning. The oil and gas industry operates in all climates and environments, including the most arduous conditions, and is continuously challenged to achieve high efficiency of operation while maintaining a high standard of safety and control - this includes the need to maintain control over occupational exposures to radiation, as well as to protect the public and the environment through proper management of wastes that may be radiologically and chemically hazardous. The oil and gas industry is organizationally and technically complex, and relies heavily on specialized service and supply companies to provide the necessary equipment and expertise, including expertise in radiation safety. This training manual is used by the IAEA as the basis for delivering its training course on radiation protection and the management of radioactive waste in the oil and gas industry. Enclosed with this manual is a CD-ROM that contains the presentational material used in the training course, the course syllabus and additional notes for course presenters. The course material is based principally on IAEA Safety Reports Series No. 34 Radiation Protection and the Management of Radioactive Waste in the Oil and Gas Industry, published by the IAEA in 2003. The training course is aimed at regulatory bodies; oil and gas field operators and support companies; workers and their representatives; health, safety and environmental professionals; and health and safety training officers. A pilot training course was held in the Syrian Arab Republic in 2000 as

Investigation of radioactive pollution on land at Thule and assessment of radiation doses

International Nuclear Information System (INIS)

2011-12-01

Risoe National Laboratory at the Technical University of Denmark has carried out research on the terrestrial contamination in the Thule area, Greenland, after the radioactive contents of four nuclear weapons were dispersed following the crash of an American B-52 bomber in 1968. The results of this research are described in the report ''Thule-2007 - Investigation of radioactive pollution on land''. Based on this report, the National Board of Health made an assessment of radiation doses and the risk for individuals in the Thule area. The results of the assessment are described in the report ''The Thule accident. Assessment of radiation doses from terrestrial radioactive contamination''. The present report is a summary of these two reports. (ln)

Radiation safety requirements for radioactive waste management in the framework of a quality management system

International Nuclear Information System (INIS)

Salgado, M.M.; Benitez, J.C.; Pernas, R.; Gonzalez, N.

2007-01-01

The Center for Radiation Protection and Hygiene (CPHR) is the institution responsible for the management of radioactive wastes generated from nuclear applications in medicine, industry and research in Cuba. Radioactive Waste Management Service is provided at a national level and it includes the collection and transportation of radioactive wastes to the Centralized Waste Management Facilities, where they are characterized, segregated, treated, conditioned and stored. A Quality Management System, according to the ISO 9001 Standard has been implemented for the RWM Service at CPHR. The Management System includes the radiation safety requirements established for RWM in national regulations and in the Licence's conditions. The role of the Regulatory Body and the Radiation Protection Officer in the Quality Management System, the authorization of practices, training and personal qualification, record keeping, inspections of the Regulatory Body and internal inspection of the Radiation Protection Officer, among other aspects, are described in this paper. The Quality Management System has shown to be an efficient tool to demonstrate that adequate measures are in place to ensure the safety in radioactive waste management activities and their continual improvement. (authors)

Ionization profile of beta radiation from radioactive cloud; Jonizacioni profil beta zracenja radioaktivnog oblaka

Energy Technology Data Exchange (ETDEWEB)

Vujovic, M [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia); Vojvodic, V [VTI Belgrade (Yugoslavia)

1978-07-01

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

Study of the radiation and radioactivity in dairy formulas

International Nuclear Information System (INIS)

Mireles G, F.; Pinedo V, J.L.; Quirino T, L.L.; Davila R, J.I.; Rios M, C.; Leal A, B.; Lopez del Rio, H.

2006-01-01

The radiation and natural radioactivity is present in the man's food chain, like it is the case of the milk, and it comes from the natural series of radioactive decay of the 238 U, 235 U and 232 Th, and of the 40 K radioisotope. Since the radioisotopes can be found in floor of where its are transferred to the grasses and in the water that serve as food and of drinking to the cows, then to enter the milk and its derived to the human consumption. In this work it is presented the study of the radiation and gamma radioactivity of 40 samples of dairy formulas of the trademarks and presentations more sold in the market of the private and public sectors. The measurements of the gamma ray spectra were carried out with a spectrometry system based on an Hyper pure Germanium detector (HPGe). The detector has a resolution (FWHM) of 1.9 keV for an energy of the gamma ray of 1.332 keV of the 60 Co. This study presents the results of the concentration in activity of dairy formulations of the radioisotopes of interest. Also, the results are related with possible damages to the health. (Author)

On risk assessment of high level radioactive waste disposal

International Nuclear Information System (INIS)

Smith, C.F.; Kastenberg, W.E.

1976-01-01

One of the major concerns with the continued growth of the nuclear power industry is the production of the high level radioactive wastes. The risks associated with the disposal of these wastes derives from the potential for release of radioactive materials into the environment. The development of a methodology for risk analysis is carried out. The methodology suggested involves the probabilistic analysis of a general accident consequence distribution. In this analysis, the frequency aspect of the distribution is treated separately from the normalized probability function. In the final stage of the analysis, the frequency and probability characteristics of the distribution are recombined to provide an estimate of the risk. The characterization of the radioactive source term is accomplished using the ORIGEN computer code. Calculations are carried out for various reactor types and fuel cycles, and the overall waste hazard for a projected 35 year nuclear power program is determined. An index of relative nuclide hazard appropriate to problems involving the management of high level radioactive wastes is developed. As an illustration of the methodology, risk analyses are made for two proposed methods for waste management: extraterrestrial disposal and interim surface storage. The results of these analyses indicate that, within the assumptions used, the risks of these management schemes are small compared with natural background radiation doses. (Auth.)

Radioactive materials' transportation main routes in Brazil. Radiation protection aspects about radioactive materials transportation

International Nuclear Information System (INIS)

Vaz, Solange dos Reis e; Andrade, Fernando de Menezes; Aleixo, Luiz Claudio Martins

2007-01-01

The heavy transportation in Brazil is generally done by highways. The radioactive material transportation follow this same rule. Whenever a radioactive material is carried by the road, by the sea or by the air, in some cases, a kind of combination of those transportation ways, the transport manager has to create a Transportation Plan and submit it to CNEN. Only after CNEN's approval, the transportation can be done. The plan must have the main action on Radiation Protection, giving responsibilities and showing all the directing that will be take. Although, the Brazilian's highways are not in good conditions, one could say that some of them are not good enough for any kind of transportation. But we are facing radioactive material use increase but the hospitals and industries, that the reason it's much more common that kind of transportation nowadays. So, because of that, a special attention by the governments must be provide to those activities. This paper goal is to show the real conditions of some important highways in Brazil in a radioactive protection's perspective and give some suggestions to adjust some of those roads to this new reality. (author)

Evaluation of management of radioactive waste in nuclear medicine department of radiation and isotopes center, Khartoum

International Nuclear Information System (INIS)

Ahmed, Amel Bushra Abaker

2001-01-01

Evaluation of management of radioactive waste in nuclear medicine department of radiation and isotopes center in Khartoum, Sudan, was conducted using radiation survey meter. The purpose of this study is to provide protection of workers, patients, co patients, an the environment by introducing good practice in management of radioactive waste generated in this lab. In this work measurement of radiation effective dose at different locations in the department were carried out. These locations were selected around the radioactive liquid and solid waste disposal position. It was found that the effective doses per year from radioactive wastes obtained through this work using the survey meter RDS-120 at these locations, are 1.47 mSv/y at the neighbouring patients room, 5.47 mSv/y at the hot lab., 0.09 mSv/y at the neighbouring toilet, 0.321 mSv/y at the water closet, and 1.4 mSv/y at the place down water closet. The results obtained shows that the dose levels waste at the location not exceed the recommended dose limits for workers 20 mSv/y, that set by basic safety standards (Bss 115) which published by the international atomic energy agency. Also it s comply with the national regulation, regulation on basic radiation protection requirement and dose limits 1996, issued by sudan atomic energy commission act 1996. The annual dose calculated for the patients and co-patients at rooms around the nuclear medicine department, the results shows that dose are fairly high. Measure should taken to improve the waste management in the department for better protection of workers, patients and co patients. (Author)

Safety and radiation protection aspects of the management of radioactive wastes of high level activity

International Nuclear Information System (INIS)

Candes, P.; Pradel, J.

1977-01-01

Appropriate consideration is given in France to safety and protection problems to be solved from the production up to the final disposal of radioactive wastes of high level activity. The first stage of the work consisted in emphasizing the various technical options. Different strategies appear to be possible, taking into account technical, political, and psychological difficulties. This results in evaluating the safety problems to be solved in the framework of those strategies. In this field, the main safety and protection principles do not differ from those which apply to other nuclear facilities. Nevertheless, duration is in most cases a quite different factor (thousands or millions of years). The question is then raised of evaluating the importance to be given to very remote consequences, both at philosophical and scientific levels. As a first result of those considerations, the application of the ''barrier'' concept is recommended. This concept is familiar to safety specialists. Different barriers for which particular problems are listed and evaluated, are defined. Another results with regard to radiation protection principles is to consider that if safety provisions should lead to a containment of radioactive products as efficient as possible, it would not be realistic to consider such a containment as absolute, in particular for disposal durations arising to thousands of years. It is therefore assumed that a limited radioactivity transfer should be taken into account, and its consequences for environment and man be calculated. This is especially true in the study of an appropriate site for final storage, and the study should necessarily include a detailed investigation of the retention characteristics of soil layers, and the implementation of appropriate models giving a sufficiently accurate evaluation of the consequences of transfers, including those related to the effect of various elements after their arrival into the biosphere. The authors review the

An analysis of the awareness and performance of radiation workers' radiation/radioactivity protection in medical institutions : Focused on Busan regional medical institutions

International Nuclear Information System (INIS)

Park, Cheol Koo; Hwang, Chul Hwan; Kim, Dong Hyun

2017-01-01

The purpose of this study was to investigate safety management awareness and behavioral investigation of radiation/radioactivity performance defenses of radiation workers' in medical institutions. Data collection consisted of 267 radiation workers working in medical institutions using structured questionnaires. As a result, it was analyzed that radiation safety management awareness and performance were high in 40s, 50s group and higher education group. The analysis according to the radiation safety management knowledge was analyzed that the 'Know very well' group had higher scores on awareness and performance scores. The analysis according to the degree of safety management effort showed the high awareness scale and the performance scale in the group 'Receiving various education or studying the safety management contents through book'. The correlations between the sub-factors showed the highest positive correlation between perceived practician and personal perspective and perceived by patient and patient's caretaker perspective. Therefore, radiation safety management for workers, patients, and patient's caretaker should be conducted through continuous education of radiation safety management through various routes of radiation workers working at medical institutions

Comparative effect of radioactive radiation on roots in a coastal and ...

African Journals Online (AJOL)

The detection of the radiation levels in root crops from Ibeno (an oil producing area) and Uyo, (a non oil producing area) in Akwa Ibom state was carried out. The radioactivity level in Cassava, Potato, Sweet yam, water yam and cocoyam was investigated. Result shows that the radiation level in root samples in Uyo ranges ...

Radioactivity. Centenary of radioactivity discovery

International Nuclear Information System (INIS)

Charpak, G.; Tubiana, M.; Bimbot, R.

1997-01-01

This small booklet was edited for the occasion of the exhibitions of the celebration of the centenary of radioactivity discovery which took place in various locations in France from 1996 to 1998. It recalls some basic knowledge concerning radioactivity and its applications: history of discovery, atoms and isotopes, radiations, measurement of ionizing radiations, natural and artificial radioactivity, isotope dating and labelling, radiotherapy, nuclear power and reactors, fission and fusion, nuclear wastes, dosimetry, effects and radioprotection. (J.S.)

A general description of the Swedish radiation protection regulations of radioactive sources

International Nuclear Information System (INIS)

Staalnacke, C.-G.

2001-01-01

The regulation of ionizing radiation in Sweden is based on both the Radiation Protection Act and Ordinance from 1998. The Swedish Radiation Protection Institute (SSI) acts as the regulatory authority for radiation safety and issues detailed regulations in specific areas. The report summarizes how the SSI controls radiation sources, including orphan sources for which a process for analyzing their occurrence has started in Sweden. A number of proposed procedures for the control and follow-up of sealed radioactive sources is provided. (author)

Radiation protection with regard to sea dumping of radioactive waste

International Nuclear Information System (INIS)

Sanderse, R.W.; Worst, J.

1980-01-01

The Netherlands Energy Research Foundation (ECN) has been dumping into the Atlantic Ocean radioactive waste cast into concrete since 1965. In the report the Health Physics problems with regard to the transport and dumping of the radioactive waste are discussed. In particular to the following points has been paid attention: tasks and working methods of the radiation protection service, dose evaluation for the people involved by two different kinds of dumping methods, doses received by the personal involved, some contamination problems caused by leaking drums. (orig.) [de

Your radioactive garden

International Nuclear Information System (INIS)

Marshall, W.G.

1986-01-01

The booklet on radiation risks from nuclear waste is based on lectures given by the author at Westminster School (United Kingdom) and elsewhere during 1986. A description is given of naturally-occurring radioactivity, and the health risks due to this radiation. The types of radioactive wastes produced by the nuclear industry are described, including low-level wastes, short-lived and long-lived intermediate-level wastes, and high level wastes. These wastes are discussed with respect to their potential health risks and their disposal underground. (U.K.)

World high background natural radiation areas: Need to protect public from radiation exposure

International Nuclear Information System (INIS)

Sohrabi, Mehdi

2013-01-01

Highlights of findings on radiological measurements, radiobiological and epidemiological studies in some main world high background natural radiation (HBNR) areas such as in Brazil, China, India and Iran are presented and discussed with special regard to remediation of radiation exposure of inhabitants in such areas. The current radiation protection philosophy and recommendations applied to workers and public from operation of radiation and nuclear applications are based on the linear non-threshold (LNT) model. The inhabitants of HBNR and radon prone areas receive relatively high radiation doses. Therefore, according to the LNT concept, the inhabitants in HBNR areas and in particular those in Ramsar are considered at risk and their exposure should be regulated. The HBNR areas in the world have different conditions in terms of dose and population. In particular, the inhabitants in HBNR areas of Ramsar receive very high internal and external exposures. This author believes that the public in such areas should be protected and proposes a plan to remedy high exposure of the inhabitants of the HBNR areas of Ramsar, while maintaining these areas as they stand to establish a national environmental radioactivity park which can be provisionally called “Ramsar Research Natural Radioactivity Park” (RRNRP). The major HBNR areas, the public exposure and the need to remedy exposures of inhabitants are reviewed and discussed. - Highlights: ► Highlights of findings on studies in HBNR areas are reviewed and discussed. ► The need to protect HBNR area inhabitants and remedy public exposure is emphasized. ► A collective approach is proposed to remedy exposure of Ramsar HBNR area inhabitants. ► Relocation of HBNR area inhabitants and establishing a park at the location is proposed. ► The advantages and disadvantages of the methods are discussed and recommendations are made

Ultra Secure High Reliability Wireless Radiation Monitor

International Nuclear Information System (INIS)

Cordaro, J.; Shull, D.; Farrar, M.; Reeves, G.

2011-01-01

Radiation monitoring in nuclear facilities is essential to safe operation of the equipment as well as protecting personnel. In specific, typical air monitoring of radioactive gases or particulate involves complex systems of valves, pumps, piping and electronics. The challenge is to measure a representative sample in areas that are radioactively contaminated. Running cables and piping to these locations is very expensive due to the containment requirements. Penetration into and out of an airborne or containment area is complex and costly. The process rooms are built with thick rebar-enforced concrete walls with glove box containment chambers inside. Figure 1 shows high temperature radiation resistance cabling entering the top of a typical glove box. In some case, the entire processing area must be contained in a 'hot cell' where the only access into the chamber is via manipulators. An example is shown in Figure 2. A short range wireless network provides an ideal communication link for transmitting the data from the radiation sensor to a 'clean area', or area absent of any radiation fields or radioactive contamination. Radiation monitoring systems that protect personnel and equipment must meet stringent codes and standards due to the consequences of failure. At first glance a wired system would seem more desirable. Concerns with wireless communication include latency, jamming, spoofing, man in the middle attacks, and hacking. The Department of Energy's Savannah River National Laboratory (SRNL) has developed a prototype wireless radiation air monitoring system that address many of the concerns with wireless and allows quick deployment in radiation and contamination areas. It is stand alone and only requires a standard 120 VAC, 60 Hz power source. It is designed to be mounted or portable. The wireless link uses a National Security Agency (NSA) Suite B compliant wireless network from Fortress Technologies that is considered robust enough to be used for classified data

ULTRA SECURE HIGH RELIABILITY WIRELESS RADIATION MONITOR

Energy Technology Data Exchange (ETDEWEB)

Cordaro, J.; Shull, D.; Farrar, M.; Reeves, G.

2011-08-03

Radiation monitoring in nuclear facilities is essential to safe operation of the equipment as well as protecting personnel. In specific, typical air monitoring of radioactive gases or particulate involves complex systems of valves, pumps, piping and electronics. The challenge is to measure a representative sample in areas that are radioactively contaminated. Running cables and piping to these locations is very expensive due to the containment requirements. Penetration into and out of an airborne or containment area is complex and costly. The process rooms are built with thick rebar-enforced concrete walls with glove box containment chambers inside. Figure 1 shows high temperature radiation resistance cabling entering the top of a typical glove box. In some case, the entire processing area must be contained in a 'hot cell' where the only access into the chamber is via manipulators. An example is shown in Figure 2. A short range wireless network provides an ideal communication link for transmitting the data from the radiation sensor to a 'clean area', or area absent of any radiation fields or radioactive contamination. Radiation monitoring systems that protect personnel and equipment must meet stringent codes and standards due to the consequences of failure. At first glance a wired system would seem more desirable. Concerns with wireless communication include latency, jamming, spoofing, man in the middle attacks, and hacking. The Department of Energy's Savannah River National Laboratory (SRNL) has developed a prototype wireless radiation air monitoring system that address many of the concerns with wireless and allows quick deployment in radiation and contamination areas. It is stand alone and only requires a standard 120 VAC, 60 Hz power source. It is designed to be mounted or portable. The wireless link uses a National Security Agency (NSA) Suite B compliant wireless network from Fortress Technologies that is considered robust enough to be

Regulatory control of radiation sources and radioactive materials in Ireland

International Nuclear Information System (INIS)

McGarry, A.T.; Fenton, D.; O'Flaherty, T.

2001-01-01

The primary legislation governing safety in uses of ionizing radiation in Ireland is the Radiological Protection Act, 1991. This Act provided for the establishment in 1992 of the Radiological Protection Institute of Ireland, and gives the Institute the functions and powers which enable it to be the regulatory body for all matters relating to ionizing radiation. A Ministerial Order made under the Act in 2000 consolidates previous regulations and, in particular, provides for the implementation in Irish law of the 1996 European Union Directive which lays down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionizing radiation. Under the legislation, the custody, use and a number of other activities involving radioactive substances and irradiating apparatus require a licence issued by the Institute. Currently some 1260 licences are in force. Of these, some 850 are in respect of irradiating apparatus only and are issued principally to dentists and veterinary surgeons. The remaining licences involve sealed radiation sources and/or unsealed radioactive substances used in medicine, industry or education. A schedule attached to each licence fully lists the sealed sources to which the licence applies, and also the quantities of radioactive substances which may be acquired or held under the licence. It is an offence to dispose of, or otherwise relinquish possession of, any licensable material other than in accordance with terms and conditions of the licence. Disused sources are returned to the original supplier or, where this is not possible, stored under licence by the licensee who used them. Enforcement of the licensing provisions relies primarily on the programme of inspection of licensees, carried out by the Institute's inspectors. The Institute's Regulatory Service has a complement of four inspectors, one of whom is the Manager of the Service. The Manager reports to one of the Institute's Principal

Training system in radiation protection of workers of a radioactive facility

International Nuclear Information System (INIS)

Amador Balbona, Zayda; Perez Pijuan, Saul; Ayra Pardo, Fernando E.; Soria Guevara, Miguel A.

2013-01-01

The following topics are addressed: the state of the art of the studies on the biological effects of ionizing radiation, the new national regulations, operational experiences and in the transportation of radioactive materials and those obtained from the radiological events, radioactive waste management and the analysis of culture of safety in the installation. It evaluates the effectiveness of the training system through the analysis of the occurrence of radiological incidents and behavior of occupational exposure

Recovery of Cs from high level radioactive waste

International Nuclear Information System (INIS)

Kumar, Amar; Kaushik, C.P.; Raj, K.; Varshney, Lalit

2008-01-01

Separation of Cs + from HLW restricts the personal radiation exposure during the vitrification and prevents thermal deformation of conditioned waste matrix during storage because of the high calorific power of 134 Cs (13.18 W/g) and 137 Cs (0.417 W/g) which would markedly reduce the storage cost. Separation will also reduce its volatility during vitrification and extent of migration from the vitrified mass in repository. In addition 137 Cs has enormous applications as radiation sources in food preservation, sterilization of medical products, brachy therapy, blood irradiation, hygienization of sewage sludge etc. The use of 137 Cs (T 1/2 = 30 years) in place of 60 Co (T 1/2 = 5.2 years) will also reduce the shielding requirement and frequency of source replenishment which will ease the handling/transportation of radioactive source

Concentrating Radioactivity

Science.gov (United States)

Herrmann, Richard A.

1974-01-01

By concentrating radioactivity contained on luminous dials, a teacher can make a high reading source for classroom experiments on radiation. The preparation of the source and its uses are described. (DT)

Radioactive hospital wastes. Radiations under control

International Nuclear Information System (INIS)

Bondeelle, A.; Delmotte, H.; Gauron, C.

2006-07-01

A set of articles proposes an overview of legal and regulatory evolutions regarding radioactive hospital wastes. These legal measures and evolutions are notably present in the Public Health code, in the Labour code. An article outlines the role of the radiation protection expert in the process of elimination of contaminated wastes (four major steps for this elimination are indicated; peculiarities of the hospital are outlined, as well as control procedures and the importance of training and information). An article describes the specific activity of the Creteil incinerator which comprises a unit for the incineration of care activity wastes under a very constraining regulation

Gamma radiation and gamma ray protection factors of ships in various situations of radioactive fall-out

International Nuclear Information System (INIS)

Brehm, E.H.; Holst, T.

1975-01-01

In this report the development of methods of evaluating gamma ray protection factors (GSF) of ships for various situations of radioactive fall-out is described. The joining calculations of gamma ray protection factors are performed by the newly developed computer procedure GASUFA. These protection factors determine - in connection with a measured gamma radiation dose at a given detector point - the gamma radiation in different compartments of the ships. The computer program GASUFA is able to perform calculations considering the dependence of energy, place and time for the following situations: - the ship is under a radioactive cloud without fall-out; - the ship is under a radioactive cloud with fall-out; - the ship is contaminated by radioactive fall-out; - the clean or decontaminated ship is going through a zone, which is contaminated by radioactive fall-out; - the ship and the surrounding water surface are contaminated by radioactive fall-out. (orig.) [de

Preliminary studies into profiling DNA recovered from a radiation or radioactivity incident

International Nuclear Information System (INIS)

Hodgson, A.; Baxter, A.

2013-01-01

The examination and profiling of human DNA recovered from a scene of crime is an essential aspect of criminal investigations. However, it is currently not known whether DNA recovered from a scene where an ionising radiation source or radioactive contamination is present can be successfully profiled. The direct examination and analysis of radioactively contaminated DNA has not been widely explored using the current procedures employed by forensic service providers. As a result, AWE is putting in place an extensive research and development programme to better understand the effects that radiation has on the ability to profile human DNA, and assess the associated retention of different radioactive contaminants within each step of the profiling procedure. A summary will be provided on the aims of this project and progress that has been made to date; together with a discussion of the lessons that have been learnt during the course of the programme's development. (author)

Location iron-Mantua an area with high securities gives natural radioactivity

International Nuclear Information System (INIS)

Alcaide Orpi, J.; Oliveira Acosta, J.; Valdes Hernadez, G.M.; Leal Ramirez, M.R.; Blanco Jorrin, N.

1998-01-01

The work shows the high natural radioactivity and the concentration to the natural radioelements (U,Th, Ra, K) it is exists in the sulfurous Hierro Mantua location. The objective is to know the possible radiological risk to that would be subjected the workers during the mining exploitation, because the high gamma radiation doses that could receive and to the risks product the internal contamination due to the inhalation the radon 222 and uranium aerosols and particles

Code of practice on radiation protection in the mining and milling of radioactive ores 1987

International Nuclear Information System (INIS)

1987-01-01

This Code was formulated under provisions of the Environment Protection (Nuclear Codes) Act 1978 in close consultation with the Governments of the States and the Northern Territory. It is a major revision of the Code of Practice on Radiation Protection in the Mining and Milling of Radioactive Ores (1980), incorporating changes flowing from advances in internationally agreed radiation protection philosophy, and experience gained in Australia in uranium mining and milling operations and the extraction of monazite from mineral sands. The Code specifies the standards, practices, procedures, and measures to prevent or limit risk to employees and to the public from uranium mining and milling, mineral sands operations and extraction of radioactive ores. To assist the industry in meeting the requirements and responsibilities imposed by the Code, guidelines to the former Code will be reviewed and, if appropriate, revised. New guidelines to assist compliance with changed requirements will also be prepared. The Act provides for the revision of codes of practice. The Code of Practice on Radiation Protection in the Mining and Milling of Radioactive Ores (1987) will be reviewed from time to time and revised if necessary to ensure that the highest standards of radiation protection in the mining and milling of radioactive ores are maintained

Code of practice on radiation protection in the mining and milling of radioactive ores 1987

Energy Technology Data Exchange (ETDEWEB)

1987-01-01

This Code was formulated under provisions of the Environment Protection (Nuclear Codes) Act 1978 in close consultation with the Governments of the States and the Northern Territory. It is a major revision of the Code of Practice on Radiation Protection in the Mining and Milling of Radioactive Ores (1980), incorporating changes flowing from advances in internationally agreed radiation protection philosophy, and experience gained in Australia in uranium mining and milling operations and the extraction of monazite from mineral sands. The Code specifies the standards, practices, procedures, and measures to prevent or limit risk to employees and to the public from uranium mining and milling, mineral sands operations and extraction of radioactive ores. To assist the industry in meeting the requirements and responsibilities imposed by the Code, guidelines to the former Code will be reviewed and, if appropriate, revised. New guidelines to assist compliance with changed requirements will also be prepared. The Act provides for the revision of codes of practice. The Code of Practice on Radiation Protection in the Mining and Milling of Radioactive Ores (1987) will be reviewed from time to time and revised if necessary to ensure that the highest standards of radiation protection in the mining and milling of radioactive ores are maintained.

Radiation exposure to skin following radioactive contamination

International Nuclear Information System (INIS)

Baumann, H.; Beyermann, M.; Kraus, W.

1989-01-01

In the case of skin contamination intensive decontamination measures should not be carried out until the potential radiation exposure to the basal cell layer of the epidermis was assessed. Dose equivalent rates from alpha-, beta- or photon-emitting contaminants were calculated with reference to the surface activity for different skin regions as a function of radiation energy on the condition that the skin was healthy and uninjured and the penetration of contaminants through the epidermis negligible. The results have been presented in the form of figures and tables. In the assessment of potential skin doses, both radioactive decay and practical experience as to the decrease in the level of surface contamination by natural desquamation of the stratum corneum were taken into account. 9 figs., 5 tabs., 46 refs. (author)

Radioactivity in the environment

International Nuclear Information System (INIS)

2006-01-01

In this report different aspects of the radioactivity in the environment of the Slovak Republic for the period of 2004 - 2006 years are reported. This report is published only on the Enviroportal.sk. The following aspects of the radioactivity in the environment are reviewed there: Electricity production in nuclear power plants and their consumption; Natural sources of ionisation radiation; Man-made sources of ionisation radiation; Safety of exploitation of the nuclear power plants on the territory of the Slovak Republic; International Nuclear Event Scale; Basic information about influence of radiation on health of population and about evaluation methods; Influence of physical risk factors (including of ionisation radiation) in the working environment on formation of occupation diseases; Collective doses of occupation in NPPs; Health state of population in the locality of the NPP Mochovce; Food contamination by ionisation radiation; Radiation monitoring network; Legislative directives about population health protection against ionisation radiation action; Decommissioning of the NPP Jaslovske Bohunice (EBO V-1); Conception of the back fuel cycle and treatment of spent fuels and high-level radioactive wastes; Project of territorial-economic development of the Trnava region after decommissioning of the Jaslovske Bohunice NPP

MONITORING OF RADIOACTIVITY AT DNURT CAMPUS

Directory of Open Access Journals (Sweden)

L. F. Dolina

2016-06-01

Full Text Available Purpose. The research paper aims to determine radioactive contamination on the territory of campus of Dnipropetrovsk National University of Railway Transport named after Academician V. Lazaryan (DNURT. Methodology. The dosimeters measured the radioactive contamination in different places (points of DNURT campus, focusing on public places. The centres of measurements became dormitories, monuments, stops, main entrances of the new and the old buildings, classrooms, basements, a swimming pool, boiler room and others. Findings. The conducted radiation monitoring for the first time in the history of the University discovered the source of radioactive contamination on DNURT territory and campus. The highest radiation background is observed on three points, namely: the pedestal of the monument, the monument to students-soldiers, the main entrance of the new building (columns. This can be explained by granite materials, which the pedestals and the stairs are made of. Originality. The largest contribution to the total value of annual effective dose of human exposure is made by ionizing radiation sources (IRS of building materials (65 - 70%. The radioactivity level of building materials is determined by the content of natural radionuclides that are included in uranium-radium and thorium decay series (18 and 12 radionuclides as well as potassium-40. Radioactivity of building materials is evaluated by the content of dominant radionuclides radium-226, thorium-232 and potassium-40. Their dominant role is explained by the fact that these long-lived high-energy - emitters are the products of decay of radium-226 in uranium series of and radium-224 in thorium series, exposing radioactive gases (radon-222 and radon-220. Radioactive gases are accumulated in the basements of educational buildings; their decay is accompanied by 100% alpha radiation, which is the most dangerous. Practical value. It is necessary to set radioactivity signs near the objects with high

Environmental radioactivity and radiation exposure by radioactive emissions of coal-fired power plants

International Nuclear Information System (INIS)

Jacobi, W.

1981-03-01

On the basis of measurements of the radioactive emissions of a 300 MW coal-fired power plant and of a 600 MW lignite-fired power plant the expected activity increase in air and soil in the environment of both plants is estimated and compared with the normal, natural activity level. Due to these emissions it results for the point of maximum immission a committed effective dose equivalent per GW x a of about 0.2 mrem = 0.002 mSv for the coal-fired plant and of about 0.04 mrem = 0.0004 mSv for the lignite-fired plant. This dose is caused to nearly equal parts by inhalation, ingestion and external γ-radiation. The normalized effective dose equivalent in the environment of the modern coal-fired power plant is in the same order of magnitude like that of a modern pressurized water reactor. The total, collective effective dose equivalent commitment by the annual radioactive emissions of coal-fired power plants in the F.R.Germany is estimated to 2000-6000 Man x rem = 20-60 Man x Sv. This corresponds to a mean per caput-dose in the population of the F.R.Germany of about 0.03-0.1 mrem = 0.0003-0.001 mSv; this is about 0.02-0.06% of the mean normal natural radiation exposure of the population. (orig.) [de

Radioactive wastes

International Nuclear Information System (INIS)

Teillac, J.

1988-01-01

This study of general interest is an evaluation of the safety of radioactive waste management and consequently the preservation of the environment for the protection of man against ionizing radiations. The following topics were developed: radiation effects on man; radioactive waste inventory; radioactive waste processing, disposal and storage; the present state and future prospects [fr

Accident with radioactive substances in laboratory. An exercise during the education of persons in radiation protection, who are working with open radioactive sources

International Nuclear Information System (INIS)

Stolze, B.

2003-01-01

In spite of carefulness it is possible,that contamination occur by handling unscaled radioactive sources or in case of an accident. It is demonstrated in an exercise managing an accident with unscaled radioactive sources. The persons, who are educated in radiation protection for handling unsealed radioactive sources, must have knowledge of theoretical regulations of the radiation protection law and of the limits in radiation protection. Also they have to know the handling to reduce possible contamination. They have to be able to calculate the dose of skin contamination. In my lecture I give some information on regulations of accidents with radioactive sources in Germany and a scenario of an accident and I explain, what is to do to manage this event. A person opened an ampoule. The activity splashed and contaminated the person's hand, arm and face. Also in the room there was a contamination. The desk and the floor were contaminated. There were 50 MBq P-32 as NaH 2 P''32O 3 in water solution, I give a report on practices in our courses, which the participants have to do. The radiological experts have to decontaminate the skin and they have to calculate the skin-dose and to give the information to the authorities. (Author) 4 refs

Radiation Protection and the Management of Radioactive Waste in the Oil and Gas Industry. Additional Information

International Nuclear Information System (INIS)

2010-01-01

The oil and gas industry, a global industry operating in many Member States, makes extensive use of radiation generators and sealed and unsealed radioactive sources, some of which are potentially dangerous to human health and the environment if not properly controlled. In addition, significant quantities of naturally occurring radioactive material (NORM) originating from the reservoir rock are encountered during production, maintenance and decommissioning. The oil and gas industry operates in all climates and environments, including the most arduous conditions, and is continuously challenged to achieve high efficiency of operation while maintaining a high standard of safety and control - this includes the need to maintain control over occupational exposures to radiation, as well as to protect the public and the environment through proper management of wastes that may be radiologically and chemically hazardous. The oil and gas industry is organizationally and technically complex, and relies heavily on specialized service and supply companies to provide the necessary equipment and expertise, including expertise in radiation safety. This training manual is used by the IAEA as the basis for delivering its training course on radiation protection and the management of radioactive waste in the oil and gas industry. Enclosed with this manual is a CD-ROM that contains the presentational material used in the training course, the course syllabus and additional notes for course presenters. The course material is based principally on IAEA Safety Reports Series No. 34 Radiation Protection and the Management of Radioactive Waste in the Oil and Gas Industry, published by the IAEA in 2003. The training course is aimed at regulatory bodies; oil and gas field operators and support companies; workers and their representatives; health, safety and environmental professionals; and health and safety training officers. A pilot training course was held in the Syrian Arab Republic in 2000 as

Legal and governmental infrastructure for nuclear, radiation, radioactive waste and transport safety. Safety requirements

International Nuclear Information System (INIS)

2000-01-01

This publication establishes requirements for legal and governmental responsibilities in respect of the safety of nuclear facilities, the safe use of sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material. Thus, it covers development of the legal framework for establishing a regulatory body and other actions to achieve effective regulatory control of facilities and activities. Other responsibilities are also covered, such as those for developing the necessary support for safety, involvement in securing third party liability and emergency preparedness

Legal and governmental infrastructure for nuclear, radiation, radioactive waste and transport safety. Safety requirements

International Nuclear Information System (INIS)

2004-01-01

This publication establishes requirements for legal and governmental responsibilities in respect of the safety of nuclear facilities, the safe use of sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material. Thus, it covers development of the legal framework for establishing a regulatory body and other actions to achieve effective regulatory control of facilities and activities. Other responsibilities are also covered, such as those for developing the necessary support for safety, involvement in securing third party liability and emergency preparedness

Radiation doses from residual radioactivity

International Nuclear Information System (INIS)

Okajima, Shunzo; Fujita, Shoichiro; Harley, John H.

1987-01-01

In this chapter available data and calculations for assessing the exposure of survivors of the Hiroshima and Nagasaki bombs and persons who entered the cities after the bombings have been presented. It appears that it is possible to produce firm estimates only for external radiation and, while the internal contribution for long-lived fission products appears small, there is no way to evaluate potential exposures to the short-lived fission products. The radiation exposure in the most highly contaminated fallout area of a few hectares at Nishiyama, Nagasaki, is estimated as 20 to 40 R when integrated from one hour to infinity using a decay exponent of -1.2. For the Hiroshima Koi-Takasu area, the corresponding exposure is estimated as 1 to 3 R. The falloff with distance for Nagasaki is not steep and an exposure of one-fifth of the maximum is spread over an area of perhaps 1000 ha. With the assumption stated above, the potential maximum exposures to external radiation from induced radioactivity at the hypocenter is estimated to be about 80 R fir Hiroshima and 30 to 40 R for Nagasaki with the assumptions stated above. These exposures fall off with both time and distance. The cumulative exposure would be about one-third as large after a day and only a few percent after a week. The falloff with distance is less striking, but can be estimated from the areas listed or from the curves shown in Gritzner and Woolson. Unlike the fallout, which exposed individuals in their living areas, exposures to induced activity came from reentry of individuals into the area around the hypocenter. As an example, an individual entering the Hiroshima hypocenter area after one day and working 10 or 20 hours a day for a week would have been exposed to about 10 R. If the person had been working at a distance of 500 m, the exposure would have been about 1 R and, at 1000 m, about 20 mR. The exposure described apply to the specified areas in the two cities. Application of these values to individuals

The HAW-Project: Test disposal of highly radioactive radiation sources in the Asse salt mine

International Nuclear Information System (INIS)

1992-04-01

Two electrical heater tests were already started in November 1988 and are continuously surveyed in respect of the thermomechanical and geochemical response of the rock mass. Also the handling system necessary for the emplacement of 30 radioactive canisters (Sr-90 and Cs-137 sources) was developed and succesfully tested. This system consists of six multiple transport and storage casks of the type Castor-GSF-5, two above ground/below ground shuttle transport casks of the type Asse TB1, an above ground transfer station, an underground transport vehicle, a disposal machine, and a borehole slider. A laboratory investigation program on radiation effects in salt is being performed in advance to the radioactive canister emplacement. This program includes the investigation of thermally and radiolytically induced water and gas release from the rock salt and the radiolytical decomposition of salt minerals. For gamma dose and dose rate measurements in the test field measuring systems consisting of ionisation chambers as well as solid state dosemeters were developed and tested. Thermomechanical computer code validation is performed by calculational predictions and parallel investigation of the stress and displacement fields in the underground test field. (orig./HP)

Cementification for radioactive waste including high-concentration sodium sulfate and high-concentration radioactive nuclide

International Nuclear Information System (INIS)

Miyamoto, Shinya; Sato, Tatsuaki; Sasoh, Michitaka; Sakurai, Jiro; Takada, Takao

2005-01-01

For the cementification of radioactive waste that has large concentrations of sodium sulfate and radioactive nuclide, a way of fixation for sulfate ion was studied comprising the pH control of water in contact with the cement solid, and the removal of the excess water from the cement matrix to prevent hydrogen gas generation with radiolysis. It was confirmed that the sulfate ion concentration in the contacted water with the cement solid is decreased with the formation of ettringite or barium sulfate before solidification, the pH value of the pore water in the cement solid can control less than 12.5 by the application of zeolite and a low-alkali cement such as alumina cement or fly ash mixed cement, and removal of the excess water from the cement matrix by heating is possible with aggregate addition. Consequently, radioactive waste including high-concentration sodium sulfate and high-concentration radioactive nuclide can be solidified with cementitious materials. (author)

Particle size of radioactive aerosols generated during machine operation in high-energy proton accelerators

International Nuclear Information System (INIS)

Oki, Yuichi; Kanda, Yukio; Kondo, Kenjiro; Endo, Akira

2000-01-01

In high-energy accelerators, non-radioactive aerosols are abundantly generated due to high radiation doses during machine operation. Under such a condition, radioactive atoms, which are produced through various nuclear reactions in the air of accelerator tunnels, form radioactive aerosols. These aerosols might be inhaled by workers who enter the tunnel just after the beam stop. Their particle size is very important information for estimation of internal exposure doses. In this work, focusing on typical radionuclides such as 7 Be and 24 Na, their particle size distributions are studied. An aluminum chamber was placed in the EP2 beam line of the 12-GeV proton synchrotron at High Energy Accelerator Research Organization (KEK). Aerosol-free air was introduced to the chamber, and aerosols formed in the chamber were sampled during machine operation. A screen-type diffusion battery was employed in the aerosol-size analysis. Assuming that the aerosols have log-normal size distributions, their size distributions were obtained from the radioactivity concentrations at the entrance and exit of the diffusion battery. Radioactivity of the aerosols was measured with Ge detector system, and concentrations of non-radioactive aerosols were obtained using condensation particle counter (CPC). The aerosol size (radius) for 7 Be and 24 Na was found to be 0.01-0.04 μm, and was always larger than that for non-radioactive aerosols. The concentration of non-radioactive aerosols was found to be 10 6 - 10 7 particles/cm 3 . The size for radioactive aerosols was much smaller than ordinary atmospheric aerosols. Internal doses due to inhalation of the radioactive aerosols were estimated, based on the respiratory tract model of ICRP Pub. 66. (author)

Radiation monitoring in the mining and milling of radioactive ores

International Nuclear Information System (INIS)

1989-01-01

The present Guide is a revision of IAEA Safety Series No. 43. It explains the recommendations on administrative requirements for the organization of radiation protection in the mining and milling of radioactive ores, and the monitoring requirements, including methods, techniques, instrumentation and strategy. 146 refs, 9 figs, 14 tabs

Monte Carlo simulation of radiation streaming from a radioactive material shipping cask

International Nuclear Information System (INIS)

Liu, Y.Y.; Schwarz, R.A.; Tang, J.S.

1996-01-01

Simulated detection of gamma radiation streaming from a radioactive material shipping cask have been performed with the Monte Carlo codes MCNP4A and MORSE-SGC/S. Despite inherent difficulties in simulating deep penetration of radiation and streaming, the simulations have yielded results that agree within one order of magnitude with the radiation survey data, with reasonable statistics. These simulations have also provided insight into modeling radiation detection, notably on location and orientation of the radiation detector with respect to photon streaming paths, and on techniques used to reduce variance in the Monte Carlo calculations. 13 refs., 4 figs., 2 tabs

Exposure to natural radiation from the earth's crust, atmosphere and outer space - the natural radioactivity of the earth's crust

International Nuclear Information System (INIS)

Schwab, R.G.

1987-01-01

Any conclusions to be drawn from the geochemical distribution pattern of radioactive elements for one's own conduct require to study their distribution in soil, earth crust, magmatic differentiation, rock disintegration zone and biosphere. The author notes that high activities in soils and rocks are contrasted by relatively low radiation dose levels absorbed by the human body. This is different for incorporated radiation. (DG) [de

Handbook of high-level radioactive waste transportation

International Nuclear Information System (INIS)

Sattler, L.R.

1992-10-01

The High-Level Radioactive Waste Transportation Handbook serves as a reference to which state officials and members of the general public may turn for information on radioactive waste transportation and on the federal government's system for transporting this waste under the Civilian Radioactive Waste Management Program. The Handbook condenses and updates information contained in the Midwestern High-Level Radioactive Waste Transportation Primer. It is intended primarily to assist legislators who, in the future, may be called upon to enact legislation pertaining to the transportation of radioactive waste through their jurisdictions. The Handbook is divided into two sections. The first section places the federal government's program for transporting radioactive waste in context. It provides background information on nuclear waste production in the United States and traces the emergence of federal policy for disposing of radioactive waste. The second section covers the history of radioactive waste transportation; summarizes major pieces of legislation pertaining to the transportation of radioactive waste; and provides an overview of the radioactive waste transportation program developed by the US Department of Energy (DOE). To supplement this information, a summary of pertinent federal and state legislation and a glossary of terms are included as appendices, as is a list of publications produced by the Midwestern Office of The Council of State Governments (CSG-MW) as part of the Midwestern High-Level Radioactive Waste Transportation Project

An analysis of the awareness and performance of radiation workers' radiation/radioactivity protection in medical institutions : Focused on Busan regional medical institutions

Energy Technology Data Exchange (ETDEWEB)

Park, Cheol Koo [Dept. of Radiological Science, Graduate School of Catholic University of Pusan, Busan (Korea, Republic of); Hwang, Chul Hwan [Dept. of Radiation Oncology, Pusan National University Hospital, Busan (Korea, Republic of); Kim, Dong Hyun [Dept. of Radiological Science, College of Health Sciences, Catholic University of Pusan, Busan (Korea, Republic of)

2017-03-15

The purpose of this study was to investigate safety management awareness and behavioral investigation of radiation/radioactivity performance defenses of radiation workers' in medical institutions. Data collection consisted of 267 radiation workers working in medical institutions using structured questionnaires. As a result, it was analyzed that radiation safety management awareness and performance were high in 40s, 50s group and higher education group. The analysis according to the radiation safety management knowledge was analyzed that the 'Know very well' group had higher scores on awareness and performance scores. The analysis according to the degree of safety management effort showed the high awareness scale and the performance scale in the group 'Receiving various education or studying the safety management contents through book'. The correlations between the sub-factors showed the highest positive correlation between perceived practician and personal perspective and perceived by patient and patient's caretaker perspective. Therefore, radiation safety management for workers, patients, and patient's caretaker should be conducted through continuous education of radiation safety management through various routes of radiation workers working at medical institutions.

The effects of high nautal radioactivity on the bone marrow activities of Rattus-rattus in Ramsar: A chromosomal study

International Nuclear Information System (INIS)

Jamali, M.; Sahabi, Z.

1993-01-01

The area under study is Ramsar known as one of the high level natural radioactive areas in the world with radiation levels ranging from 0.8 to 5.5 mR.h -1 . The radioactivity of the area is due to 226 Ra and its daughters which have been brought up to the earth surface by the water of the warm springs. It is necessary to say that the radioactive area of Ramsar is divided into three parts: with high, medium and low radiation areas. The control area is Babol with a radius of 10 kilometers. The area has natural background radiation. In the control area thirty Rattus-rattus and in the area of study sixty Rattus-rattus were trapped. It was tried that the Rattuses chosen be from a distance of maximum 500 meters, and from the three different parts of the radioactive areas. Then all the ninety Rattuses were transported to Tehran for experiment. An average of 10-30 Rattuses were trapped for one week, and the maximum time between the trapping and the dissection was one month. The chromosomal study was followed by the Ford technique. The staining was routine and G. banding. No chromosomal disorders and morphological anomalies were considered. (author). 5 refs, 1 fig

Health effects in residents of high background radiation regions

International Nuclear Information System (INIS)

Hanson, G.P.

1984-01-01

Although the health effects of radiation doses in occupationally exposed persons had received attention, it was not until the 1950s, when the atmospheric atom bomb tests of the United States and the Soviet Union had raised the level of environmental radioactivity, that the long-term effects of low-level radiation dosage became a matter of popular concern throughout the world. The United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) was created, and the World Health Organization (WHO) appointed an expert committee to provide advice concerning radiation and human health. In its first report, the WHO expert committee identified several areas of high natural radiation where studies of the exposed population might possibly provide information concerning the effects of chromic low-level radiation dosage

Study of radiation dose from radioactive shipments to cargo handlers at O'Hare Field

International Nuclear Information System (INIS)

1975-06-01

The relationship between the amount of radioactive materials that pass through the cargo areas at O'Hare Field, Chicago, and the resulting radiation dose to the workers handling the packages was determined. Measurements of radiation exposure rates at various distances from the radioactive packages were made. Handling or exposure times for personnel during several unit operations were measured with a watch. These data were used to determine the body dose from the unit operation. In randomly selected cases workers were assigned TLD dosimeters in the form of a ring to be worn on the hand or in the form of a clip to be attached to the clothing for measurement of the hand or body dose from a unit operation. During each survey, several workers were given TLDs that were worn for the duration of the shift, and some workers, in addition, were given dosimeters to be worn for the duration of the study. Results showed that the workers who handled the radioactive packages did not receive any significant radiation exposure. (U.S.)

Recovering method for high level radioactive material

International Nuclear Information System (INIS)

Fukui, Toshiki

1998-01-01

Offgas filters such as of nuclear fuel reprocessing facilities and waste control facilities are burnt, and the burnt ash is melted by heating, and then the molten ashes are brought into contact with a molten metal having a low boiling point to transfer the high level radioactive materials in the molten ash to the molten metal. Then, only the molten metal is evaporated and solidified by drying, and residual high level radioactive materials are recovered. According to this method, the high level radioactive materials in the molten ashes are transferred to the molten metal and separated by the difference of the distribution rate of the molten ash and the molten metal. Subsequently, the molten metal to which the high level radioactive materials are transferred is heated to a temperature higher than the boiling point so that only the molten metal is evaporated and dried to be removed, and residual high level radioactive materials are recovered easily. On the other hand, the molten ash from which the high level radioactive material is removed can be discarded as ordinary industrial wastes as they are. (T.M.)

The Thule accident: Assessment of radiation doses from terrestrial radioactive contamination

International Nuclear Information System (INIS)

Ulbak, K.

2011-12-01

Risoe DTU has carried out research on the terrestrial contamination in the Thule area after the radioactive contents of four nuclear weapons were dispersed following the crash of an American B-52 bomber in 1968. The results of Risoe DTU's studies are described in the report Thule-2007 - Investigation of radioactive pollution on land, which covers all measurements that were carried out on land in Thule in the years 2003, 2006, 2007 and 2008. The present report uses Risoe DTU's report as a basis for assessing radiation doses and consequently the risk for individuals as a result of terrestrial radioactive contamination in the Thule area. The assessment of radiation doses involves a number of conservative assumptions, estimates, and measurements, all of which are subject to considerable uncertainty. In some cases, models have been used based on experiences from other contaminated areas elsewhere in the world, which are subject to climatic and other conditions that diverge from those in the Thule area. The calculated doses are thus associated with considerable uncertainty, which must be taken into account when the results are used for comparison and when the risks of staying in the Thule area are assessed. It has therefore been chosen to provide the assessed radiation doses in the form of indicative orders of magnitude, which are applicable to everyone who might stay in the area, across various age groups. If the estimated doses in this report are combined with the National Institute of Radiation Protections recommended reference level for contamination as a result of the Thule Accident of 1 mSv/year, the assessed magnitudes of radiation doses for inhalation and ingestion as exposure pathways are many orders of magnitude below the reference level (10,00010 million times smaller). The wound contamination exposure pathway has a magnitude of radiation dose that is smaller than the reference level by a factor of 101000, and it should be recalled that the probability of this

The Thule accident: Assessment of radiation doses from terrestrial radioactive contamination

Energy Technology Data Exchange (ETDEWEB)

Ulbak, K. (National Institute of Radiation Protection, Herlev (Denmark))

2011-12-15

Risoe DTU has carried out research on the terrestrial contamination in the Thule area after the radioactive contents of four nuclear weapons were dispersed following the crash of an American B-52 bomber in 1968. The results of Risoe DTU's studies are described in the report Thule-2007 - Investigation of radioactive pollution on land, which covers all measurements that were carried out on land in Thule in the years 2003, 2006, 2007 and 2008. The present report uses Risoe DTU's report as a basis for assessing radiation doses and consequently the risk for individuals as a result of terrestrial radioactive contamination in the Thule area. The assessment of radiation doses involves a number of conservative assumptions, estimates, and measurements, all of which are subject to considerable uncertainty. In some cases, models have been used based on experiences from other contaminated areas elsewhere in the world, which are subject to climatic and other conditions that diverge from those in the Thule area. The calculated doses are thus associated with considerable uncertainty, which must be taken into account when the results are used for comparison and when the risks of staying in the Thule area are assessed. It has therefore been chosen to provide the assessed radiation doses in the form of indicative orders of magnitude, which are applicable to everyone who might stay in the area, across various age groups. If the estimated doses in this report are combined with the National Institute of Radiation Protection's recommended reference level for contamination as a result of the Thule Accident of 1 mSv/year, the assessed magnitudes of radiation doses for inhalation and ingestion as exposure pathways are many orders of magnitude below the reference level (10,000-10 million times smaller). The wound contamination exposure pathway has a magnitude of radiation dose that is smaller than the reference level by a factor of 10-1000, and it should be recalled that the

Radioactivity, radiation protection and monitoring during dismantling of light-water reactors

International Nuclear Information System (INIS)

Hummel, L.; Zech, J.B.

2005-01-01

Based on the radioactivity inventory in the systems and components of light-water reactors observed during operation, the impact of actions during plant emptying after the conclusion of power operation and possible subsequent long-term safe enclosure concerning the composition of the nuclide inventory of the plant to be dismantled will be described. Derived from this will be the effects on radioactivity monitoring in the plant, physical radiation protection monitoring, and the measured characterization of the residual materials resulting from the dismantling. The impact of long-term interim storage will also be addressed in the discussion. The talk should provide an overview of the interrelationships between source terms, decay times and the radioactivity monitoring requirements of the various dismantling concepts for commercial light-water reactors. (orig.)

The radiation protection and the radioactive wastes management; La radioprotection et la gestion des dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

Servais, F. [CHR Hopital de Warquignies, Service de Medecine Nucleaire (Belgium); Woiche, Ch. [Universite Libre de Bruxelles, Service Interne et de Prevention et Protection (Belgium); Hunin, Ch. [Agence Federale de Controle Nucleaire, Service Controle Etablissements Classes, Brexelles (Belgium)] [and others

2003-07-01

This chapter concerns the radiation protection in relation with the radioactive waste management. Three articles make the matter of this file, the management of radioactive medical waste into hospitals, a new concept of waste storage on site, the protection devices on the long term with some lessons for the radioactive waste management. (N.C.)

The Winfrith lecturers' demonstration kits for radiation and radioactivity

International Nuclear Information System (INIS)

Woffinden, G.B.

1981-01-01

During the early part of the 1970s a need arose for suitable aids to assist lecturers in giving talks on radioactivity and radiation to employees and occasionally to science students in local schools and colleges. A kit capable of demonstrating the basic properties of alpha, beta and gamma radiation was assembled for these purposes. During the latter half of the decade a demand arose for talks to non-scientific groups of the general public on nuclear power and radiation and some of the items in the original demonstration kit were found to be appropriate for these talks. The items used, now constitute the Basic Demonstration Kit. Meanwhile, a few changes or additions were made to the original kit which is now known as the Comprehensive Demonstration Kit. (author)

Avoiding radiation exposure while training to locate a radioactive source: a virtual reality exercise

International Nuclear Information System (INIS)

Marins, E.R.; Cotelli do Espírito Santo, A.; Abreu Mól, A. C. de; Cunha, G.; Landau, L.

2015-01-01

A technician undergoing radioprotection training must learn to use radiation detectors. Practical exercises involve being near to radiation sources. The work here presented reduces the exposure to individuals using a virtual environment to achieve preliminary apprenticeship prior using real radioactive sources. (authors)

Radiation risk from natural radioactivity in oil and gas production industry. Vol. 4

Energy Technology Data Exchange (ETDEWEB)

Eid, M A [National Center for Radiation Research and Technology, Atomic Energy Authority, Cairo, (Egypt)

1996-03-01

This paper throws light on the natural radioactive materials as well as the radiation background level in Egypt and other global areas. It also describes the deposition of naturally occurring radioactivity as well as the gamma-ray exposure rate primarily due to {sub 226} Ra and daughters which concentrate as scale or sludge in oil field piping and equipment. The potential hazards arising during normal operation, maintenance, and cleaning are considered. Occupational annual personnel doses are estimated and examined relative to work function. The measures to reduce occupational radiation exposure and radioactive contamination were investigated. The data indicated that relatively higher exposure rates are associated with areas around water discharge system, separator and descaling operations where the dose rates varying between 0.02-6 m R/h. The annual collective effective dose equivalent was estimated about 4.58 man-Rem, and the mean annual dose equivalent of about 120 mrem were measured. 3 tabs.

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

International Nuclear Information System (INIS)

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

2014-01-01

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

High Level Radioactive Waste Management

International Nuclear Information System (INIS)

1991-01-01

The proceedings of the second annual international conference on High Level Radioactive Waste Management, held on April 28--May 3, 1991, Las Vegas, Nevada, provides information on the current technical issue related to international high level radioactive waste management activities and how they relate to society as a whole. Besides discussing such technical topics as the best form of the waste, the integrity of storage containers, design and construction of a repository, the broader social aspects of these issues are explored in papers on such subjects as conformance to regulations, transportation safety, and public education. By providing this wider perspective of high level radioactive waste management, it becomes apparent that the various disciplines involved in this field are interrelated and that they should work to integrate their waste management activities. Individual records are processed separately for the data bases

Concerns on the health effects of low-dose ionizing radiations from naturally occurring radioactive materials (NORM)

International Nuclear Information System (INIS)

Mohankumar, Mary N.

2005-01-01

It is a widely known fact that man evolved in a naturally radioactive environment. Even today life exists in an atmosphere of cosmic and terrestrial radiation. Radionuclides are found naturally in air, water and soil. They are even found in us, we being the products of our environment. Every day, we ingest and inhale radionuclides in our air and food and the water. Natural radioactivity is common in the rocks and soil that makes up our planet, in water and oceans, and in our building materials and homes. There is nowhere on earth that one cannot find natural radioactivity. Radioactive materials which occur naturally and expose people to radiation occur widely, and are known by the acronym 'NORM' (Naturally Occurring Radioactive Materials). Besides, around the globe there are some areas with an elevated background radiation. These areas include parts of Brazil, Iran, India and China. The sources of radiation in these areas include monazite containing beach sands and radium from hot springs. On the southwest coast of India, there are large deposits of thorium bearing monazite sands that contribute to an external radiation dose of about 5 - 6 mGy/yr, but in some parts doses up to 32.6 mGy/yr have been reported. Nevertheless, most general public associate ionising radiations only with the nuclear industry. Antinuclear activists often fail to accept the fact that coal-fired power stations and the oil and gas exploration operations may emit more radioactivity than an operating nuclear reactor. Another NORM issue relates to radon exposure in homes, particularly those built on granite grounds. The solid airborne Rn-222 progeny, particularly Po-218, Pb-214 and Bi-214 are of health importance because they can be inspired and retained in the lung causing cancer. Man-made operations like oil and gas production and processing operations result in technologically enhanced naturally occurring radioactive materials (TENORM) to accumulate at elevated concentrations in by

Radon adsorbed in activated charcoal—a simple and safe radiation source for teaching practical radioactivity in schools and colleges

Science.gov (United States)

Al-Azmi, Darwish; Mustapha, Amidu O.; Karunakara, N.

2012-07-01

Simple procedures for teaching practical radioactivity are presented in a way that attracts students' attention and does not make them apprehensive about their safety. The radiation source is derived from the natural environment. It is based on the radioactivity of radon, a ubiquitous inert gas, and the adsorptive property of activated charcoal. Radon gas from ambient air in the laboratory was adsorbed into about 70 g of activated charcoal inside metallic canisters. Gamma radiation was subsequently emitted from the canisters, following the radioactive decay of radon and its progenies. The intensities of the emitted gamma-rays were measured at suitable intervals using a NaI gamma-ray detector. The counts obtained were analysed and used to demonstrate the radioactive decay law and determine the half-life of radon. In addition to learning the basic properties of radioactivity the students also get practical experience about the existence of natural sources of radiation in the environment.

Radon adsorbed in activated charcoal- a simple and safe radiation source for teaching practical radioactivity in schools and colleges

International Nuclear Information System (INIS)

Al-Azmi, D.S.

2014-01-01

Simple procedures for teaching practical radioactivity are presented in a way that attracts students' attention and does not make them apprehensive about their safety. The radiation source is derived from the natural environment. It is based on the radioactivity of radon, an ubiquitous inert gas, and the adsorptive property of activated charcoal. Radon gas from ambient air in the laboratory was adsorbed into about 70 gram of activated charcoal inside metallic canisters. Gamma radiation was subsequently emitted from the canisters, following the radioactive decay of radon and its progenies. The intensities of the emitted gamma-rays were measured at suitable intervals using a NaI gamma-ray detector. The counts obtained were analysed and used to demonstrate the radioactive decay law and determine the half-life of radon. In addition to learning the basic properties of radioactivity, the students also get practical experience about the existence of natural sources of radiation in the environment. (author)

Equipment of high sensitivity to detect smuggled radioactive materials transported across the ''east-west'' border

International Nuclear Information System (INIS)

Antonovski, A.; Kagan, L.; Stavrov, A.

1998-01-01

An equipment specially developed for the customs radiation control is described. Its sensitivity is higher than requirements of western countries. The equipment ensures an alarm when a radioactive source (both shielded or not) is found in the controlled area, localizes and identifies the source detected, and provides the radiation protection of customs personnel. Most of devices have a non-volatile memory where the radiation situation history is stored and then transferred to PC. The equipment may be used by personnel of special services for secret detection of radioactive materials. Some Belarussian and Russian documents specifying measures to prevent an unauthorized transportation of radioactive materials are discussed. (author)

Transport of radioactive materials: the need for radiation protection programmes

International Nuclear Information System (INIS)

Masinza, S.A.

2004-01-01

The increase in the use of radioactive materials worldwide requires that these materials be moved from production sites to the end user or in the case of radioactive waste, from the waste generator to the repository. Tens of millions of packages containing radioactive material are consigned for transport each year throughout the world. The amount of radioactive material in these packages varies from negligible quantities in shipments of consumer products to very large quantities of shipments of irradiated nuclear fuel. Transport is the main way in which the radioactive materials being moved get into the public domain. The public is generally unaware of the lurking danger when transporting these hazardous goods. Thus radiation protection programmes are important to assure the public of the certainty of their safety during conveyance of these materials. Radioactive material is transported by land (road and rail), inland waterways, sea/ocean and air. These modes of transport are regulated by international 'modal' regulations. The international community has formulated controls to reduce the number of accidents and mitigate their consequences should they happen. When accidents involving the transport of radioactive material occur, it could result in injury, loss of life and pollution of the environment. In order to ensure the safety of people, property and the environment, national and international transport regulations have been developed. The appropriate authorities in each state utilise them to control the transport of radioactive material. Stringent measures are required in these regulations to ensure adequate containment, shielding and the prevention of criticality in all spheres of transport, i.e. routine, minor incidents and accident conditions. Despite the extensive application of these stringent safety controls, transport accidents involving packages containing radioactive material have occurred and will continue to occur. When a transport accident occurs, it

The management of high-level radioactive wastes

International Nuclear Information System (INIS)

Lennemann, Wm.L.

1979-01-01

The definition of high-level radioactive wastes is given. The following aspects of high-level radioactive wastes' management are discussed: fuel reprocessing and high-level waste; storage of high-level liquid waste; solidification of high-level waste; interim storage of solidified high-level waste; disposal of high-level waste; disposal of irradiated fuel elements as a waste

Radiation protection of workers in the mining and milling of radioactive ores. Code of practice and technical addendum. 1983 ed

International Nuclear Information System (INIS)

1983-01-01

This Code of Practice sets forth the means of ensuring protection against ionizing radiation for workers engaged in mining and milling of radioactive ores: general provisions outlining the responsibilities of the employer and the worker, limits of radiation exposure, administrative organization of radiation protection, radiation surveillance, engineering and administrative protective measures and medical surveillance. It is designed to facilitate the preparation and adoption of national and local regulations and factory rules for radiation protection in mining and milling of radioactive ores.

Natural radioactivity levels and estimation of radiation exposure from soils in Bahi and Manyoni Districts in Tanzania

International Nuclear Information System (INIS)

Nkuba, Leonid L.; Nyanda, Pendo B.

2017-01-01

Soils from Bahi and Manyoni districts in Tanzania were analyzed for radioactivity. The radioactivity levels of 226 Ra, 232 Th and 40 K were measured by direct γ‐ray spectrometry using HPGe detector by Compton suppression method. The radioactivity concentration in soil were computed in arithmetic mean. The results from this study have been compared with those from other areas in Tanzania, different countries of the world and the world average radioactivity in the soil. To assess the radiological effects and hazards indices from natural radionuclides ( 226 Ra, 232 Th and 40 K), the absorbed dose rate (DR), the annual effective dose equivalent (AEDE), Excess Lifetime Cancer Risk (ELCR), the radium equivalent activity (Raeq), the external (Hex), the alpha index (Iα) and the radioactivity level index (Iγ) were calculated. Except for DR in all the soil samples; Raeq, Hex and Iα exceeds the recommended limits due to high activity of 226 Ra in Membeta soils. Also Iγ was above the limits due to higher 226 Ra in soils from Membeta and 232 Th in Ilindi and Nala. Whilst the other radiological parameters (AEDE and ELCR) as well as the Raeq, Hex, Iα and Iγ in same areas were far below the recommended limits. However, this does not guarantee the safety. Therefore the probability of occurrence of the health effects from radiation is significant. The study recommends that the soils from Membeta should not be used as building material because they might expose the population to radiation. (author)

Natural radioactivity levels and estimation of radiation exposure from soils in Bahi and Manyoni Districts in Tanzania

Energy Technology Data Exchange (ETDEWEB)

Nkuba, Leonid L.; Nyanda, Pendo B., E-mail: leonid_nkuba@yahoo.co.uk [Tanzania Atomic Energy Commission, Directorate of Radiation Control, Dar es Salaam (Tanzania, United Republic of)

2017-07-01

Soils from Bahi and Manyoni districts in Tanzania were analyzed for radioactivity. The radioactivity levels of {sup 226}Ra, {sup 232}Th and {sup 40}K were measured by direct γ‐ray spectrometry using HPGe detector by Compton suppression method. The radioactivity concentration in soil were computed in arithmetic mean. The results from this study have been compared with those from other areas in Tanzania, different countries of the world and the world average radioactivity in the soil. To assess the radiological effects and hazards indices from natural radionuclides ({sup 226}Ra, {sup 232}Th and {sup 40}K), the absorbed dose rate (DR), the annual effective dose equivalent (AEDE), Excess Lifetime Cancer Risk (ELCR), the radium equivalent activity (Raeq), the external (Hex), the alpha index (Iα) and the radioactivity level index (Iγ) were calculated. Except for DR in all the soil samples; Raeq, Hex and Iα exceeds the recommended limits due to high activity of {sup 226}Ra in Membeta soils. Also Iγ was above the limits due to higher {sup 226}Ra in soils from Membeta and {sup 232}Th in Ilindi and Nala. Whilst the other radiological parameters (AEDE and ELCR) as well as the Raeq, Hex, Iα and Iγ in same areas were far below the recommended limits. However, this does not guarantee the safety. Therefore the probability of occurrence of the health effects from radiation is significant. The study recommends that the soils from Membeta should not be used as building material because they might expose the population to radiation. (author)

Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 1997

International Nuclear Information System (INIS)

Meyer, H.; Stippler, R.

1998-01-01

The number of annual sampling and measurements performed in compliance with the operator's monitoring duties have been the same as last year: 364. All measured radioactivity values were at the level of natural environmental radioactivity. Some samples and measurements reflected the fallout from former atmospheric nuclear weapons tests and the accident at the Chernobyl reactor. Personnel dosimetry was performed according to legal requirements of the Radiation Protection Ordinance, as were measurements for the monitoring of ambient doses, dose rates and radioactivity levels in the air of the mine structures. All measured values were below the maximum permissible personal doses and occupational dose limits. Ambient air measurements in the salt mine as in the preceding years detected low amounts of the nuclides H 3, C 14, Pb 210, and the short-lived daughter products of Rn 222 and Rn 220. The calculated radioactivity concentrations in the vicinity of the mine, derived from averaged annual effluents, to some part were below the average natural concentrations of the nuclides. The effluent-induced radiation dose at the most affected location was far below the limits set by the Radiation Protection Ordinance. (orig./CB) [de

Development of simple and rapid radioactivity analysis for thorium series in the products containing naturally occurring radioactive materials (NORM)

Energy Technology Data Exchange (ETDEWEB)

Yoo, Jae Ryong; Park, Se Young; Yoon, Seok Won; Ha, Wi Ho [Korea Institute of Radiological and Medical Sciences, Seoul (Korea, Republic of); Lee, Jae Kook; Kim, Kwang Pyo [Kyung Hee University, Seoul (Korea, Republic of)

2016-05-15

It is necessary to analyze radioactivity of naturally occurring radioactive materials (NORM) in products to ensure radiological safety required by Natural Radiation Safety Management Act. The pretreatments for the existing analysis methods require high technology and time. Such destructive pretreatments including grinding and dissolution of samples make impossible to reuse products. We developed a rapid and simple procedure of radioactivity analysis for thorium series in the products containing NORM. The developed method requires non-destructive or minimized pretreatment. Radioactivity of the product without pretreatment is initially measured using gamma spectroscopy and then the measured radioactivity is adjusted by considering material composition, mass density, and geometrical shape of the product. The radioactivity adjustment can be made using scaling factors, which is derived by radiation transport Monte Carlo simulation. Necklace, bracelet, male health care product, and tile for health mat were selected as representative products for this study. The products are commonly used by the public and directly contacted with human body and thus resulting in high radiation exposure to the user. The scaling factors were derived using MCNPX code and the values ranged from 0.31 to 0.47. If radioactivity of the products is measured without pretreatment, the thorium series may be overestimated by up to 2.8 times. If scaling factors are applied, the difference in radioactivity estimates are reduced to 3-24%. The developed procedure in this study can be used for other products with various materials and shapes and thus ensuring radiological safety.

Radiation protection measures for the handling of unsealed radioactive materials

International Nuclear Information System (INIS)

Moehrle, G.

1975-03-01

The radiation protective medical measures are described which are required after contamination by radioactive materials or their incorporation. In the case of skin contamination, penetration by diffusion is explained and the maximum permissible value with regard to the various types of radiation is given. A detailed description of the decontamination measures including the necessary equipment follows. Indications for the treatment of injuries are given. In addition, incorporation due to inhalation, ingestion with intake through the skin are described, direct and indirect incorporation detection are explained, and the therapeutical possibilities and measures are gone into. (ORU/LH) [de

Safety measures to address the year 2000 issue at medical facilities which use radiation generators and radioactive materials

International Nuclear Information System (INIS)

1999-03-01

In resolution GC(42)/RES/11 on 'Measures to Address the Year 2000 (Y2K) Issue', adopted on 25 September 1998, the General Conference of the International Atomic Energy Agency (IAEA) - inter alia - urged Member States 'to share information with the Secretariat regarding diagnostic and corrective actions being planned or implemented by operating and regulatory organizations at their ... medical facilities which use radioactive materials to make those facilities Year 2000 ready', encouraged the Secretariat 'within existing resources to act as a clearing-house and central point of contact for Member States to exchange information regarding diagnostic and remediation actions being taken at ... medical facilities which use radioactive materials to make these facilities Year 2000 ready', urged the Secretariat 'to handle the information provided by Member States carefully' and requested the Director General to report to it at its next (1999) regular session on the implementation of that resolution. The IAEA Secretariat convened a group of consultants who met in Vienna from 14 to 18 December 1998 and produced this report. The consultants decided that the report should cover not just 'medical facilities which use radioactive materials' but also medical facilities which, while perhaps not using radioactive materials, use ionizing radiation produced by radiation generators such as accelerators. The reports issued together are: Achieving Year 2000 Readiness: Basic Processes; Safety Measures to Address the Year 2000 Issue at Medical Facilities Which Use Radiation Generators and Radioactive Materials; and Safety Measures to Address the Year 2000 Issue at Radioactive Waste Management Facilities. This report addresses means of dealing with the Y2K problem at medical facilities which use radiation generators and radioactive materials

Radioactive Decay

Science.gov (United States)

Radioactive decay is the emission of energy in the form of ionizing radiation. Example decay chains illustrate how radioactive atoms can go through many transformations as they become stable and no longer radioactive.

Development of a high speed three-dimensional radiation detecting system for the emergency response robot

Energy Technology Data Exchange (ETDEWEB)

Lee, Nam Ho; Lee, Yong Duk; Choi, Chang Whan; Jung, Kyung Min; Moon, Myung Kook; Kim, Hee Moon

2007-02-15

Technologies for managing the emergency leak accident of radioactive materials have been developed actively in USA, Japan, and Russia, since the Chernobyl nuclear disaster in Russia and nuclear fuel accident in Japan Nuclear fuel Conversion cooperation had occurred. A robot (Pioneer) for managing radioactive materials have been developed in co-operation of USA(CMU), Japan, and Russia. The pioneer is recently examined its performance through exploring test in the Chernobyl nuclear reactor. The exploring function of these system is quite different with a dosimeter for a worker in operation, installation, and radiation measurement. So, it is inevitable to develop a new system. The developed system from now is so expensive and slow in operation. So this problem is pending and must be improved. In this research, instead of an existing expensive system, a CCD(or CMOS) sensor, which has high resolution (640 X 480) and high signal process (30 frame/sec), is used for exploring radioactive materials as economical view and image consideration. The connection with image processing, 3D imaging technology, and radioactive exploring can visualize imaginary radiation source and can improve exploring and managing radioactive materials.

Radioactive waste management

International Nuclear Information System (INIS)

Balek, V.

1994-01-01

This booklet is a publication by International Atomic Energy Agency for general awareness of citizens and policy-makers to clarify their concept of nuclear wastes. In a very simple way it tells what is radioactivity, radiations and radioactive wastes. It further hints on various medial and industrial uses of radiations. It discusses about different types of radioactive wastes and radioactive waste management. Status of nuclear power plants in Central and Eastern European countries are also discussed

Radioactive elements and ionizing radiation in the environment of the alternative sites for the final disposal of nuclear waste

International Nuclear Information System (INIS)

Voutilainen, A.

1998-09-01

This report summarises a short review of the origin of earth's natural radioactivity and concentrations of radioactive elements in ground and water. The radiation doses of natural and artificial sources are examined and presented for population of both Finland and the whole world. The report includes data on the radioactivity of indoor and outdoor air, rainwater, surface and groundwater, soil and bedrock in Eurajoki, Kuhmo, Loviisa and Aeaenekoski. The radiation doses from natural sources are also estimated in each municipality separately. Natural radiation is the most significant source of radiation exposure in the world. We eat, drink and breathe radioactive elements. The most radiation dose to man comes from indoor radon. We get cosmic radiation from space and terrestrial gamma radiation from ground. Indoor radon and radon in drilled wells causes the largest variation in radiation doses between municipalities or individuals. The radiation doses in Loviisa and Aeaenekoski are bigger and in Eurajoki and Kuhmo smaller than the average in Finland. The average radiation dose from natural radiation and Chernobyl fallout is 3,5 milli-sievert per year (mSv/a) for a Finn who lives in a detached house and uses household water from waterworks. The corresponding radiation dose in Eurajoki is 3,3, in Kuhmo 2,6, in Loviisa 8,3 and in Aeaenekoski 4,2 mSv/a The average doses for persons who use household water from drilled wells are respectively 5,4 (all Finns), 4,1 (Eurajoki), 3,5 (Kuhmo), 12 (Loviisa) and 5,4 mSv/a (Aeaenekoski). The other sources of radiation, excluding indoor radon and household water, cause together less than 1 mSv per year, although these doses vary in different municipalities, too. (orig.)

Radioactive action code

International Nuclear Information System (INIS)

Anon.

1988-01-01

A new coding system, 'Hazrad', for buildings and transportation containers for alerting emergency services personnel to the presence of radioactive materials has been developed in the United Kingdom. The hazards of materials in the buildings or transport container, together with the recommended emergency action, are represented by a number of codes which are marked on the building or container and interpreted from a chart carried as a pocket-size guide. Buildings would be marked with the familiar yellow 'radioactive' trefoil, the written information 'Radioactive materials' and a list of isotopes. Under this the 'Hazrad' code would be written - three symbols to denote the relative radioactive risk (low, medium or high), the biological risk (also low, medium or high) and the third showing the type of radiation emitted, alpha, beta or gamma. The response cards indicate appropriate measures to take, eg for a high biological risk, Bio3, the wearing of a gas-tight protection suit is advised. The code and its uses are explained. (U.K.)

40 CFR 227.30 - High-level radioactive waste.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 24 2010-07-01 2010-07-01 false High-level radioactive waste. 227.30...-level radioactive waste. High-level radioactive waste means the aqueous waste resulting from the operation of the first cycle solvent extraction system, or equivalent, and the concentrated waste from...

Factories Act 1961, Ionizing Radiations (Unsealed Radioactive Substances) Regulations 1968, Certificate of Approval No.1 (General)

International Nuclear Information System (INIS)

1969-01-01

Under the Ionising Radiations (Unsealed Radioactive Substances) Regulations No. 780 of 1968, the Chief Inspector of Factories has wide powers to ensure the protection of workers. By this Certificate he approved, for the purpose of measuring radiation doses, any radiation dosemeter, based on the phenomenon of radiation-induced thermoluminescence, supplied by an approved laboratory. (NEA) [fr

Radiation monitoring in the NPP environment, control of radioactivity in NPP-environment system

International Nuclear Information System (INIS)

Egorov, Yu.A.

1987-01-01

Problems of radiation monitoring and control of the NPP-environment system (NPPES) are considered. Radiation control system at the NPP and in the environment provides for the control of the NPP, considered as the source of radioactive releases in the environment and for the environmental radiation climate control. It is shown, that the radiation control of the NPP-environment system must be based on the ecological normalization principles of the NPP environmental impacts. Ecological normalization should be individual for the NPP region of each ecosystem. The necessity to organize and conduct radiation ecological monitoring in the NPP regions is pointed out. Radiation ecological monitoring will provide for both environmental current radiation control and information for mathematical models, used in the NPPES radiation control

Radioactive whey concentrate - a case to apply section 3 of the Radiation Protection Ordinance

International Nuclear Information System (INIS)

Sauer, G.W.; Zypries, B.

1988-01-01

According to the authors, section 4 StrlSchV does not apply, the case has to be handled applying section 3 StrlSchV (Radiation Protection Ordinance). This means that the storage, treatment and disposal of the radioactive whey concentrate is subject to licensing. Disposal as radioactive waste, however, will require a licence only if the limit given in section 4 IV, No. 2 lit. e, the 10 -4 -fold of the allowed radioactivity per gramme (i.e. 3700 Bq/kg) is exceeded. The averaged radioactivity data measured do exceed this limit. Only the transport of the radioactive whey concentrate does not fall under the provisions of the ordinances on road transport or rail transport of hazardons substances, as the limit given there is 74 Bq/g of specific activity. (orig./HP) [de

Radiation exposure as a result of radioactivity in the vicinity of nuclear installations

International Nuclear Information System (INIS)

Van As, Deodandus.

1975-11-01

The nuclear industry in South Africa is expected to expand dramatically and, as a result, the effects of radioactive effluent from these installations on the environment will be of great practical and scientific importance. The long-term effects of low-level radiation cannot be clinically predicted; physical determination and prediction is therefore the accepted measure of radiation exposure. This study includes a survey of all forms of natural and man-made radiation to which the general public is constantly exposed. An intensive study was made of radioactive fallout over South Africa from nuclear bomb tests. From this the general radiation exposure of the South African public could be calculated. It also led to valuable scientific information on mesometeorology and health physics. The latter includes the relationship between air concentration and deposition, the transfer of airborne iodine-131 to milk, and the accumulation of strontium-90 and cesium-137 in human beings as a result of their diets. Thorough environmental studies were conducted at existing nuclear installation sites i.e. Pelinbada which is the site of the National Nuclear Research Centre and Dynefontein which is the proposed site of South Africa's first nuclear power station. These included meso-meteorology, atmospheric dispersion by means of neutron-activable tracers, accumulation factors for important radionuclides in edible marine species by means of stable element tracers, population surveys, background radioactivity surveys etc. From these results critical exposure pathways were established for both sites and the relationship between effluent release and radiation dose to the public was determined. This has lead to the establishment of maximum permissible releases for the operation of the SAFARI-1 research reactor by the Atomic Energy Board and for the specifications of the proposed Koeberg power reactors to be operated by the Electricity Supply Commission at Dynefontein [af

Radiation exposures of workers and the public associated with the transport of radioactive material in Germany

International Nuclear Information System (INIS)

Schwarz, G.; Fett, H.J.; Lange, F.

2004-01-01

Most radioactive material packages transported emit penetrating ionising radiation and radiation exposures of transport workers and the public may occur during their transport. The radiation exposures incurred by transport workers and members of the public can vary significantly depending on a number of factors: most important is the type of radiation emitted (primarily gamma and neutron radiation), the radiation field intensity in the surrounding of a package and conveyance and the duration of exposure to ionising radiation. The information and guidance material on occupational exposures has primarily been derived from a survey and analysis of personal monitoring data provided by a number of commercial transport operators in Germany known as major carrier and handler organisations of fuel cycle and non-fuel cycle material (in terms of the number of pack-ages and the activity carriaged). To some extent advantage was taken of compilations of statistical transport and exposure data collated within other transport safety analysis studies including research projects funded by the European Commission. The exposure data collected cover the time period of the last 4 - 8 years and are most representative for routine transport operations closely related to the movement phase of packaged radioactive material, i.e. receipt, vehicle loading, carriage, in-transit storage, intra-/intermodal transfer, vehicle unloading and delivery at the final destination of loads of radioactive material and packages and the related supervisory and health physics functions. Radiation dose monitoring of members of the public, however, is generally impracticable and, consequently, the information available relies on employing dose assessment models and reflects radiation exposures incurred by hypothetical or critical group individuals of members of the public under normal conditions of transport

Radiation Education Activities | RadTown USA | | US EPA

Science.gov (United States)

2018-03-12

EPA's Radiation Education Activities are designed to help increase awareness and understanding of radiation concepts among middle and high school students. The activities introduce basic concepts of radiation, non-ionizing and ionizing radiation, radiation protection, radioactive atoms and radioactive decay.

ISCORS ASSESSMENT OF RADIOACTIVITY IN SEWAGE SLUDGE: MODELING TO ASSESS RADIATION DOSES

Science.gov (United States)

The Interagency Steering Committee on Radiation Standards (ISCORS) has recently completed a study of the occurrence within the United States of radioactive materials in sewage sludge and sewage incineration ash. One component of that effort was an examination of the possible tran...

Safety and security of radioactive sources in Taiwan

International Nuclear Information System (INIS)

Tsay Yeousong; Guan Channan; Cheng Yungfu

2008-01-01

In Taiwan, the safety and security of radioactive sources is a high priority issue. Ionizing Radiation Protection Act (IRPA) and correlating regulations had been in place for effective control of the safety and security of radioactive sources since 2003. For increased control of sealed radioactive sources, Atomic Energy Council (AEC) established in March 2004 an online reporting system through the Internet, assisting source owners in reporting their sources every month. To conform to the Code of Conduct on the Safety and Security of Radioactive Sources and the Categorization of radioactive sources, published by the International Atomic Energy Agency (IAEA), AEC has taken the following actions: 1. Established an inventory of Categories 1 and 2 radioactive sources, and implemented the Import/Export Provisions of the Code. 2. Required that each licensee shall control access to Categories 1 and 2 radioactive sources, and AEC will conduct project inspection on Categories 1 and 2 radioactive sources. 3. Using a new radiation warning symbol by ISO for Categories 1 and 2 radioactive sources. The reinforcement of orphaned source control was implemented as early as 1995. All steel mills have installed radiation detectors to scan incoming metal scrap to prevent accidental smelting of radioactive sources. The results of this effort will be discussed in the paper. The above measures are examples for demonstrating AEC's commitment to reinforced control of radioactive sources. AEC will continue to protect public safety and security, ensuring that Taiwan's regulatory system in radiation protection conforms to international standards. (author)

Strengthening the safety of radiation sources and the security of radioactive materials: Timely action

International Nuclear Information System (INIS)

Gonzalez, A.J.

1999-01-01

When used as they should be, commercial radiation sources and radioactive materials are useful tools that pose no unacceptable risks to people or environment. In fact, their applications in fields such as medicine, industry, agriculture, and environmental research help countries to achieve sizeable social and economic benefits important to global goals of sustainable development. For most of the past half century, the IAEA has been instrumental in advancing the application of techniques that constructively make use of ionizing radiation properties, particularly in developing countries. But though global standards are in place, and being strengthened, a disturbing picture is emerging. It is regrettably framed by tragic consequences from accidents that involved unsafe, abandoned, lost, or uncontrolled radiation sources, including illicit trafficking of radioactive materials, notably in the 1990s. A turning point in global awareness of serious problems came in 1998, at an international conference in France. In March 1999, the IAEA Board of Governors discussed the issue, and a multi faced Action Plan is being submitted to the general Conference. This edition of IAEA Bulletin looks closely at the problems and issues the international community is facing, and the steps States are taking to reinforce the safety and security of radioactive materials

Natural radioactivity in soil samples of Yelagiri Hills, Tamil Nadu, India and the associated radiation hazards

International Nuclear Information System (INIS)

Ravisankar, R.; Chandrasekaran, A.; Vijayagopal, P.; Venkatraman, B.; Senthilkumar, G.; Eswaran, P.; Rajalakshmi, A.

2012-01-01

The natural radioactivity of soils at Yelagiri hills has been studied in this paper. The radioactivities of 25 samples have been measured with a NaI(Tl) detector. The radioactivity concentrations of 238 U, 232 Th and 40 K ranged from ≤2.17 to 53.23, 13.54 to 89.89 and from 625.09 to 2207.3 Bq kg −1 , respectively. The measured activity concentrations for these radionuclides were compared with world average activity of soil. The average activity concentration of 232 Th in the present study is 1.19 times higher than world median value while the activity of 238 U and 40 K is found to be lower. In order to evaluate the radiological hazard of the natural radioactivity, the radium equivalent activity Ra eq , the absorbed dose rate D R , the annual effective dose rate and the external hazard index (H ex ) have been calculated and compared with the internationally approved values. The study provides background radioactivity concentrations in Yelagiri hills. - Highlights: ► Soil radioactivity is used for base line data in future impact assessment. ► We report the results of radiation hazard parameters in soils of Yelagiri hills. ► The level of the natural radiation in the studied area does not exceed the norm.

Study of particle size distribution and formation mechanism of radioactive aerosols generated in high-energy neutron fields

CERN Document Server

Endo, A; Noguchi, H; Tanaka, S; Iida, T; Furuichi, S; Kanda, Y; Oki, Y

2003-01-01

The size distributions of sup 3 sup 8 Cl, sup 3 sup 9 Cl, sup 8 sup 2 Br and sup 8 sup 4 Br aerosols generated by irradiations of argon and krypton gases containing di-octyl phthalate (DOP) aerosols with 45 MeV and 65 MeV quasi-monoenergetic neutrons were measured in order to study the formation mechanism of radioactive particles in high energy radiation fields. The effects of the size distribution of the radioactive aerosols on the size of the added DOP aerosols, the energy of the neutrons and the kinds of nuclides were studied. The observed size distributions of the radioactive particles were explained by attachment of the radioactive atoms generated by the neutron-induced reactions to the DOP aerosols. (author)

In situ-experiments on the disposal of high-level radioactive wastes (HAW) at the Asse salt mine Federal Republic of Germany

International Nuclear Information System (INIS)

Kuhn, K.; Rothfuchs, T.

1989-01-01

Deep geological salt formations are considered as being the most suitable medium for the disposal of radioactive wastes in the Federal Republic of Germany (FRG). This paper reports how, in order to develop and to prove the necessary disposal techniques, the Asse Salt Mine in the northern part of Germany is being used as a national R and D facility for the execution of representative in situ-tests. Besides the test-wise disposal of low-and medium-level radioactive waste, a series of in situ experiments was performed on the disposal of high-level radioactive waste (HAW). The so-called HAW repository is being performed from 1983 through 1994 will be the most important pilot test for the HAW repository in the FRG. During this experiment, 30 vitrified high-level radioactive heat and radiation sources will be emplaced in six underground boreholes. The duration of testing will be approximately five years. In addition to the investigations of the interactions of the heat and radiation sources and the host rock, a complete handling system for HAW-canisters is being developed and proved

Radioactive waste interim storage in Germany

International Nuclear Information System (INIS)

2015-12-01

The short summary on the radioactive waste interim storage in Germany covers the following issues: importance of interim storage in the frame of radioactive waste management, responsibilities and regulations, waste forms, storage containers, transport of vitrified high-level radioactive wastes from the reprocessing plants, central interim storage facilities (Gorleben, Ahaus, Nord/Lubmin), local interim storage facilities at nuclear power plant sites, federal state collecting facilities, safety, radiation exposure in Germany.

Safety and security of radiation sources and radioactive materials: A case of Zambia - least developed country

International Nuclear Information System (INIS)

Banda, S.C.

1998-01-01

In Zambia, which is current (1998) classified as a Least Developed Country has applications of nuclear science and technology that cover the medical, industrial, education and research. However, the application is mainly in medical and industry. Through the responsibility of radiation source is within the mandate of the Radiation Protection Board. The aspects involving security fall on different stake holders some that have no technical knowledge on what radiation is about. The stake holders in this category include customs clearing and forwarding agents, state security/defence agencies and the operators. Such a situation demands a national system that should be instituted to meet the safety and security requirements but takes into account the involvement of the diverse stake holders. In addition such system should avoid unnecessary exposure, ensure safety of radioactive materials and sources, detect illicit trade and maintain integrity of such materials or sources. This paper will provide the status on issue in Zambia and the challenges that exist to ensure further development in application of Nuclear Science and Technology (S and T) in the country takes into account the safety and security requirements that avoid deliberate and accidental loss of radiation sources and radioactive materials. The Government has a responsibility to ensure that effective system is established and operated to protect radiation sources and radioactive materials from theft, sabotage and ensure safety. (author)

Occupational radiation protection experience in radioactive waste management at Bhabha Atomic Research Centre, Trombay, Mumbai, India

International Nuclear Information System (INIS)

Ramchandran, V.; Jauhri, G.S.

2000-01-01

Waste Management Facilities, Trombay (WMFT) comprises Radioactive Solid waste Management Site (RSMS), an Effluent Treatment Plant (ETP), and a Decontamination Centre (DC). Radioactive wastes from the plants and laboratories in Mumbai are handled here. The wastes are categorized and classified as per International Atomic Energy Agency (IAEA) and Atomic Energy Regulatory Board (AERB) guidelines. RSMS is a near surface disposal facility, where assorted beta gamma solid waste is disposed off in appropriate disposal facilities. ETP is a centralized low level liquid waste treatment facility, where liquid effluent is chemically treated to remove the radionuclides present in it, monitored for radioactivity, and discharged into the Mumbai Harbour Bay. In DC, plant and laboratory used clothings and personnel protective wears are decontaminated, monitored and sent for reuse. A comprehensive radiation monitoring programme is in place in these facilities from the beginning of radioactive waste management operations at BARC. The per capita radiation dose of the occupational workers and individual maximum dose has been low. Radioactivity release through liquid effluent from ETP has been kept well below Authorized Limits (AL). There has been no safety related unusual occurrences during the facility operation, that had any significant radiological impact. (author)

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

International Nuclear Information System (INIS)

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

1985-01-01

metabolism kinetics of radioactive iodine in the critical organ. Experimental result indicate that such factors as vaccine, alcohol and environmental temperature can essentially affect a function of the thyroid and its ability to accumulate radioactive iodine. It is found that the accumulation level of radioactive iodine and the dose of thyroid irradiation are increased by 1,3-1,5 times when radionuclide is administered: at late periods after vaccination (5-14 days); after a single administration of ethanol (20,0% concentration). A decrease of radionuclide accumulation level in the thyroid by 1,3-1,5 times and of the absorbed dose created by this radionuclide about 2 times is observed when iodine is administered: at early periods after vaccination (up to 5 days); after a long, during 2 months, exposure to ethanol (20,0% concentration); in the conditions of high environmental temperature (43-45 deg C). Therefore, the degree of critical organ (thyroid) irradiation by radioactive iodine will be essentially decreased under the influence of most of the investigated factors. When estimating the risk of exposure to radioactive isotopes of iodine the change of functional activity of the thyroid under the influence of modifying factors can be of principle value due to the possible summation of non-radiation and radiation effects if iodine is administered in the amount inducing hypofunction of the thyroid. In order to make a final conclusion about the significance of non-radiation factors for the problem of normalization of radioactive isotopes of iodine it is necessary to perform further studies of biological effects induced by the radionuclide and non-radiation factors. (author)

Using radioactivity

International Nuclear Information System (INIS)

1982-10-01

The leaflet discusses the following: radioactivity; radioisotopes; uses of ionising radiations; radioactivity from (a) naturally occurring radioactive elements, and (b) artificially produced radioisotopes; uses of radioactivity in medicine, (a) clinical diagnostic, (b) therapeutic (c) sterilization of medical equipment and materials; environmental uses as tracers; industrial applications, e.g. tracers and radiography; ensuring safety. (U.K.)

Engineering Deinococcus geothermailis for Bioremediation of High-Temperature Radioactive Waste Environments

International Nuclear Information System (INIS)

Brim, Hassan; Venkateswaran, Amudhan; Kostandarithes, Heather M.; Fredrickson, Jim K.; Daly, Michael J.

2003-01-01

Deinococcus geothermalis is an extremely radiation-resistant thermophilic bacterium closely related to the mesophile Deinococcus radiodurans, which is being engineered for in situ bioremediation of radioactive wastes

Emergency Response to Radioactive Material Transport Accidents

International Nuclear Information System (INIS)

EL-shinawy, R.M.K.

2009-01-01

Although transport regulations issued by IAEA is providing a high degree of safety during transport opertions,transport accidents involving packages containing radioactive material have occurred and will occur at any time. Whenever a transport accident involving radioactive material accurs, and many will pose no radiation safety problems, emergency respnose actioms are meeded to ensure that radiation safety is maintained. In case of transport accident that result in a significant relesae of radioactive material , loss of shielding or loss of criticality control , that consequences should be controlled or mitigated by proper emergency response actions safety guide, Emergency Response Plamming and Prepardness for transport accidents involving radioactive material, was published by IAEA. This guide reflected all requirememts of IAEA, regulations for safe transport of radioactive material this guide provide guidance to the publicauthorites and other interested organziation who are responsible for establishing such emergency arrangements

The role of the Gosatomnadzor of Russia in national regulating of safety of radiation sources and security of radioactive materials

International Nuclear Information System (INIS)

Mikhailov, M.V.; Sitnikov, S.A.

2001-01-01

As at the end of 1999, the Gosatomnadzor of Russia supervised 6551 radiation sources, including 1285 unsealed sources with individual activity from a minimal level to 1x10 12 Bq and a total activity of 585x10 12 Bq, and also 5266 sealed sources with individual activity from 30 to 1x10 17 Bq and the total activity of more than 11x10 17 Bq. A national infrastructure has been created in the Russian Federation in order to regulate the safety of nuclear energy use. The infrastructure includes the legal system and the regulatory authorities based on and acting according to it. The regulation of radiation safety, including assurance of radiation source safety and radioactive material security (management of disused sources, planning, preparedness and response to abnormal events and emergencies, recovery of control over orphan sources, informing users and others who might be affected by lost source, and education and training in the safety of radiation sources and the security of radioactive materials), is realized within this infrastructure. The legal system includes federal laws ('On the Use of Nuclear Energy' and 'On Public Radiation Safety'), a number of decrees and resolutions of the President and the Government of the Russian Federation, federal standards and rules for nuclear energy use, and also departmental and industrial manuals and rules, State standards, construction standards and rules and other documents. The safety regulation tasks have been defined by these laws, according to which regulatory authorities are entrusted with the development, approval and putting into force of standards and rules in the nuclear energy use, with issuing licenses for carrying out nuclear activities, with safety supervision assurance, with review and inspection implementation, with control over development and realization of protective measures for workers, population and environment in emergencies at nuclear and radiation hazardous facilities. Russian national regulatory

Engineering materials for high level radioactive waste repository

International Nuclear Information System (INIS)

Wen Zhijian

2009-01-01

Radioactive wastes can arise from a wide range of human activities and have different physical and chemical forms with various radioactivity. The high level radioactive wastes (HLW)are characterized by nuclides of very high initial radioactivity, large thermal emissivity and the long life-term. The HLW disposal is highly concerned by the scientists and the public in the world. At present, the deep geological disposal is regarded as the most reasonable and effective way to safely dispose high-level radioactive wastes in the world. The conceptual model of HLW geological disposal in China is based on a multi-barrier system that combines an isolating geological environment with an engineering barrier system(EBS). The engineering materials in EBS include the vitrified HLW, canister, overpack, buffer materials and backfill materials. Referring to progress in the world, this paper presents the function, the requirement for material selection and design, and main scientific projects of R and D of engineering materials in HLW repository. (authors)

S.I. No 249 of 1972, Factories Ionising Radiations (Unsealed Radioactive Substances) Regulations, 1972

International Nuclear Information System (INIS)

1972-12-01

The Regulations which entered into force on 1 December 1972 apply to factories in which a process involving the use of unsealed radioactive substances is carried on and where the total activity of the unsealed radioactive substances exceeds specified levels, or where there are objects contaminated in excess of certain levels. The Schedules specify the maximum radiation doses and the maximum permissible levels of contamination and provide for a classification of radionuclides [fr

Multilayer bimetallic media as protection method of radioactive radiation

International Nuclear Information System (INIS)

Borts, B.V.; Tkachenko, V.I.; Tkachenko, I.V.

2010-01-01

Multilayer bimetallic media as means of protection of the earth's space vehicle from radioactive space radiation is described in the proposed paper. Evaluation of radiation losses of electron energy in inhomogeneous media is carried out; these media may be formed by layers of materials with different dielectric constants or they may be simulated by dielectric permittivity varying in space by harmonic law. It is shown that in such media the radiation losses of electron are proportional to the square of parameter of inhomogeneity, that is the losses are low. In the case when in periodic laminar medium with sharp boundaries the conditions of parametric union of self-waves of medium are satisfied, the losses of electron are proportional to the inhomogeneity parameter to first power and are comparable with losses that are caused by elementary events of scattering. The mean length of radiation losses of electron with energy 2(6) MeV in multilayer bimetallic medium tungsten-aluminum with period L ∼ 0,3 ·10 -6 cm is comparable with mean path of electron in such medium. The characteristic angles of radiation have the discrete character and are directed from 0 to 180 degree C. The power of losses increases with the radiation angle increase and is maximal for characteristic angles approaching 90 degree C.

Procurement and use of radioactive sources

International Nuclear Information System (INIS)

Prasad, S.S.; Sumathi, E.

2017-01-01

Radioactive sources are used throughout the world for a wide variety of peaceful purposes in industry, medicine, agriculture, research and education. It has been recognized that unsecured radioactive sources can cause serious radiological accidents involving radiation injuries and fatalities. Radioactive source after its useful life, although considered waste, can still pose a security threat if not managed properly. Today, there is a growing concern that terrorist or criminal groups could gain access to disused high activity radioactive sources and use it with harmful intent. Consequently, there has been a global trend towards increased control, accounting, and security measures to prevent such incidents. Particular concern is expressed regarding radioactive sources that have become orphaned (not under regulatory control) or vulnerable (under weak regulatory control and about to be orphaned). The International Basic Safety Standards published by International Atomic Energy Agency (IAEA) provide an internationally harmonized basis for ensuring the safe and secure use of sources of ionizing radiation

Radiation survey and management on the reconstructed radioactive work-site

International Nuclear Information System (INIS)

Yu Tao; Liang Shiqiang; Wang Youmei

2004-12-01

The experiences of radiation survey and administration in the prophase on reconstructed radioactive work-site are summarized. The advance works are to investigate the reconstructed work-site, settle working plans, devise inspecting flow charts, deal with something in time in the local and train the staffers. The works about prophasic decontaminating, removing and cleaning up the site have been finished, which have established the deep foundation to develop later task. (authors)

Influence of radiation on the system liquid radioactive wastes: geologic formation

International Nuclear Information System (INIS)

Spitsyn, V.I.; Balukova, V.D.; Kabakchi, S.A.; Medvedeva, M.L.

1979-01-01

Introduction of liquid radioactive wastes into deep strata-collectors results in a number of physical-chemical processes: precipitation, dissolution, complex formation, sorption, etc. The area occupied by the injected waste and changes in the nature of the liquid phase depend primarily on radiolysis processes in the heterogeneous system of liquid waste-stratal material occurring at elevated temperatures and pressures. Experiments that simulate actual conditions of temperature, pressure and high radiation levels on this system have been performed. Results are presented for radiolytic gas formation and for changes in the liquid phase and sorption capacity of stratal minerals. It is shown that the temperature increase in the stratum-collector significantly enhances waste decomposition processes, promotes sorption of radionuclides and decreases the mobility of the waste in the formation

Conditioning of low level radioactive wastes, spent radiation sources and their transport at the interim storage building of the Institute of Nuclear Physics in Albania

International Nuclear Information System (INIS)

Qafmolla, L.

2000-01-01

Aspects of treatment and management of radioactive wastes resulting from the use of radiation sources and radioisotopes in research, medicine and industry, are described. The methods applied for the conditioning of low-level radioactive wastes and spent radiation sources are simple. Solid radioactive wastes with low-level activity, after accumulation, minimization, segregation and measurement, are burned or compressed in a simple compactor of the PGS type. Spent radiation sources are placed into 200 l drums, are cemented and conditioned. Conditioned drums from the Radiation Protection Division of the Institute of Nuclear Physics (INP), which is the responsible Institution for the treatment and management of radioactive wastes in Albania, are transported to the interim storage building of the Institute of Nuclear Physics in Tirana. Work to construct a new building for treatment and management of radioactive wastes and spent radiation sources within the territory of INP is underway. Funds have been allocated accordingly: based on the Law No. 8025 of 25.11.1995, it is the Albanian Government's responsibility to finance activities concerned with the treatment and management of radioactive wastes generating from the use of ionizing radiation in science, medicine and industry in the country. (author)

Actions of radiation protection in the collection of discarded radioactive material; Ações de proteção radiológica no recolhimento de material radioativo descartado

Energy Technology Data Exchange (ETDEWEB)

Neri, E.P.M.; Silva, F.C.A. da, E-mail: dasilva@ird.gov.br [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Riode Janeiro, RJ (Brazil)

2017-07-01

Brazil has approximately 2000 radiative facilities that use radiation sources in their processes and are controlled by The Brazilian Nuclear Energy Commission - CNEN through standards, authorizations and inspections. These radioactive materials, whether in the form of waste or radioactive source, used in medical, industrial, research, etc. are sometimes discarded and found in inappropriate places, such as garbage dumps, industrial waste, streets, squares, etc. found by urban cleaning professionals without the proper knowledge of them. The work presents the radiation protection actions required for the safe collection of radioactive material to be performed by these professionals. According to the type of radioactive material the main actions of radiation protection are, among others: recognition of a radioactive material; correct use of personal protective equipment to contain possible radiation contamination; implementation of an area control etc. In order for the actions of recognition and collection of discarded radioactive material to be effective, there is a need to implement a training program in radiation protection for urban cleaning professionals.

Kalman filtration of radiation monitoring data from atmospheric dispersion of radioactive materials

DEFF Research Database (Denmark)

Drews, M.; Lauritzen, B.; Madsen, H.

2004-01-01

A Kalman filter method using off-site radiation monitoring data is proposed as a tool for on-line estimation of the source term for short-range atmospheric dispersion of radioactive materials. The method is based on the Gaussian plume model, in which the plume parameters including the source term...

Radioactive Plumes Monitoring Simulator

International Nuclear Information System (INIS)

Kapelushnik, I.; Sheinfeld, M.; Avida, R.; Kadmon, Y.; Ellenbogen, M.; Tirosh, D.

1999-01-01

The Airborne Radiation Monitoring System (ARMS) monitors air or ground radioactive contamination. The contamination source can be a radioactive plume or an area contaminated with radionuclides. The system is based on two major parts, an airborne unit carried by a helicopter and a ground station carried by a truck. The system enables real time measurement and analysis of radioactive plumes as well as post flight processing. The Radioactive Plumes Monitoring Simulator purpose is to create a virtual space where the trained operators experience full radiation field conditions, without real radiation hazard. The ARMS is based on a flying platform and hence the simulator allows a significant reduction of flight time costs

Present status and problems of radiation education in Japanese high school

International Nuclear Information System (INIS)

Hiroi, Tadashi; Muraishi, Yukimasa; Mikado, Shogo; Watanabe, Tomohiro

1999-01-01

Radiations always exist in nature and are necessary in various fields of our daily life. Radiations are utilized for nondestructive inspection in industrial uses, diagnosis and medical treatment, tracers in agricultural research, and so on. Researchers make good use of radioactivity. However, the fears of radioactivity remain in the public due to reports by mass media, accidents of nuclear power station, treatment of nuclear waste, and atomic bomb. Therefore the public tend to see the negative images of the radiation. Radioactivity can be dangerous. But it is hard to say that radiations are always elevated appropriately. To solve the problems of misunderstanding, we focused the study on the radiation education curriculum. In this research, we studied the radiation education from the following four points: 'physics field', 'physical experiment', 'chemistry field', and 'comprehensive study time'. Two themes of the former were performed in the actual lessons. Two themes of the latter were the investigation of the current state and the tentative plan. The research have to be continued in the future. (author)

Low-level radioactive waste management: French and foreign regulations

International Nuclear Information System (INIS)

Coulon, R.

1991-01-01

This paper describes radioactive waste management regulations applied in USA, CANADA, SCANDINAVIA and FRANCE. For low level radioactive wastes, it is necessary to adapt waste management regulations which were firt definite for high level radioactive wastes. So the exemption concept is a simplification method of regulations applied to low radiation sources

Radioactivity in the environment

International Nuclear Information System (INIS)

Costello, J.M.

1983-01-01

Radioactivity is a natural phenomenon. Out of 1700 known isotopes of 104 chemical elements, only about 16 per cent are stable. Seventy-three radioactive isotopes of 39 elements occur naturally in the terrestrial environment. The significance of environmental radioactivity lies in the contribution to the annual exposure of the general population to ionising radiation. This exposure results largely from natural sources of radioactivity and radiation together with applications of radiation in medicine. Minor contributions are from nuclear weapons tests, nuclear power production and the nuclear fuel cycle, and consumer products including luminous clocks and watches, television receivers and smoke detectors. The natural background radiation level varies substantially with altitude and geographic location. Although no satisfactory evidence is available that natural variations in background radiation levels are detrimental to humans, upper limits of risk have been estimated for possible somatic and genetic effects from these levels of radiation. Contributory sources of and variability in the radiation background are reviewed and the relation between effective dose equivalent and associated detriment outlined. The risk from exposure to an average level of background radiation is compared with risks from other human activities

Radiation Attenuation and Stability of ClearView Radiation Shielding TM-A Transparent Liquid High Radiation Shield.

Science.gov (United States)

Bakshi, Jayeesh

2018-04-01

Radiation exposure is a limiting factor to work in sensitive environments seen in nuclear power and test reactors, medical isotope production facilities, spent fuel handling, etc. The established choice for high radiation shielding is lead (Pb), which is toxic, heavy, and abidance by RoHS. Concrete, leaded (Pb) bricks are used as construction materials in nuclear facilities, vaults, and hot cells for radioisotope production. Existing transparent shielding such as leaded glass provides minimal shielding attenuation in radiotherapy procedures, which in some cases is not sufficient. To make working in radioactive environments more practicable while resolving the lead (Pb) issue, a transparent, lightweight, liquid, and lead-free high radiation shield-ClearView Radiation Shielding-(Radium Incorporated, 463 Dinwiddie Ave, Waynesboro, VA). was developed. This paper presents the motivation for developing ClearView, characterization of certain aspects of its use and performance, and its specific attenuation testing. Gamma attenuation testing was done using a 1.11 × 10 Bq Co source and ANSI/HPS-N 13.11 standard. Transparency with increasing thickness, time stability of liquid state, measurements of physical properties, and performance in freezing temperatures are reported. This paper also presents a comparison of ClearView with existing radiation shields. Excerpts from LaSalle nuclear power plant are included, giving additional validation. Results demonstrated and strengthened the expected performance of ClearView as a radiation shield. Due to the proprietary nature of the work, some information is withheld.

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

International Nuclear Information System (INIS)

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

1998-01-01

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

Radioactivity of tobacco

International Nuclear Information System (INIS)

Nashawati, A.; Al-Dalal, Z.; Al-Akel, B.; Al-Masri, M. S.

2002-04-01

This report shows the results of studies related to radioactivity in tobacco and its pathways to human being. Tobacco contains high concentrations of natural radioactive materials especially polonium 210 and lead 210, which may reach a value of 27 mBq/g. The amount of polonium 210 in tobacco is related to the concentration of radon (the main source of polonium 210 in the agricultural areas) in addition to the over use of phosphate fertilizers for tobacco plantation. Radioactive materials present in tobacco enter the human body through smoking where 210 Po concentrates in the Alveolar lung; this may cause health risks including lung cancer. In addition, radiation doses due to smoking have been reported and some results of the studies carried out for radioactivity in tobacco at the Syrian Atomic Energy Commission. (author)

Users manual. Pursuit program of use licenses of radioactive material or generator equipment of ionizing radiations

International Nuclear Information System (INIS)

Becerril M, V.M.; Villarreal, J.E.

1992-05-01

The objective of the program 'Databases for the pursuit of licenses of use of radioactive material', it consists on the application of a computer system carried out in dbase IV that it allows the control of the all the information related with those licenses for use, possession and storage of radioactive material or generator equipment of ionizing radiations. (Author)

Determining the Knowledge Level of Pre-Service Teachers' on Radioactivity and Radiation

Science.gov (United States)

Ergul, N. Remziye

2012-01-01

This study investigated the basic knowledge levels of teacher candidates' from different branches regarding the subjects of radiation and radioactivity. 42 variables were determined in relation to the specified titles. In the preparation stage of determining the variables, all the related programs were examined, and attention was paid to include…

Information by the Federal Government. Report of the Federal Governement on 'Environmental radioactivity and radiation load in 1975'

International Nuclear Information System (INIS)

1977-01-01

The report on environmental radioactivity and radiation load, to be published annually by the Federal government, contains data on artificial exposure from nuclear facilities, data on the application of radioactive substances and ionizing rays in research and technology, on occupational activities, medical application and special occurrences. Not only the annual release of radioactive substances from nuclear fcilities is presented but also data on the maximum permissible radiation exposures and the average gonadal exposure within the vicinity of plants. Furthermore, data is presented on the influence of X-ray investigations on the genetically significant dose as well as on the proportion in percent of the various radionuclides when applied in nuclear medicine. (ORU) [de

Natural radioactivity and radiation situation in Mangystau Oblast and Western Kazakhstan

International Nuclear Information System (INIS)

Kadyrzhanov, K. K.; Kuterbekov, K. A.; Lukashenko, S. N.; Glushchenko, V. N.; Kijatkina, N. G.; Morenko, V. S.; Poleshko, A. N.

2004-01-01

When performing radio-ecological investigations and developing measures for lowering radiation risks for inhabited localities and territories subjected to impact of radiation-hazardous objects (RHO) one should pay special attention to the cases when several RHO's of different type contribute simultaneously into radiation situation in a region. A prominent example is the Aktau city in Mangystau oblast of Western Kazakhstan; radiation situation there has been formed under such factors as presence of Mangyshlak Atomic Energy Combine with BN-350 reactor facilities, sites of underground nuclear explosions at Plato Ustyurt, uranium extracting and processing facilities and a bunch of operating there oil extracting companies. Previous investigations showed that situation in the city and its vicinity is quite complex and requires vast corrective measures to be immediately introduced. At the same time, separate narrow-scale programs related to improvement of radio-ecological situation in the region funded from different sources are uncoordinated and are not very effective for they have been developed without taking into account all the possible sources and mechanisms of radioactive contamination of the environment. In order to improve effectiveness of the measures aimed at lowering radiation risks it is necessary to perform preliminary investigations and estimate contributions from each RHO in the region. Institute of Nuclear Physics of National Nuclear Center (INP NNC RK) has been actively involved in a set of research and environment-preventing measures in Mangystau oblast for many years. Among the most noticeable projects on investigation of radiation situation at the territory of Mangystau oblast where INP took part or leaded are the following: assessment of radiation situation in places of underground nuclear explosions at Plato Ustyurt; over all investigation of sanitary-protection zone and monitoring zone of BN-350 reactor facilities; over-all investigation of

Production of high intensity radioactive beams

International Nuclear Information System (INIS)

Nitschke, J.M.

1990-04-01

The production of radioactive nuclear beams world-wide is reviewed. The projectile fragmentation and the ISOL approaches are discussed in detail, and the luminosity parameter is used throughout to compare different production methods. In the ISOL approach a thin and a thick target option are distinguished. The role of storage rings in radioactive beam research is evaluated. It is concluded that radioactive beams produced by the projectile fragmentation and the ISOL methods have complementary characteristics and can serve to answer different scientific questions. The decision which kind of facility to build has to depend on the significance and breadth of these questions. Finally a facility for producing a high intensity radioactive beams near the Coulomb barrier is proposed, with an expected luminosity of ∼10 39 cm -2 s -1 , which would yield radioactive beams in excess of 10 11 s -1 . 9 refs., 3 figs., 7 tabs

Modern technical and technological solutions of radiation control to combat illicit trafficking of nuclear and radioactive materials across borders

International Nuclear Information System (INIS)

Frymire, A.; Kagan, L.; Stavrov, A.

2006-01-01

Full text: Preventing the illicit nuclear and radioactive materials transportation across the state borders has recently taken on a special significance due to ongoing threat of utilizing these materials for terrorist purposes. Currently more and more countries are gaining better understanding of the importance of creating the national security system. It is obvious that the threat of nuclear terrorism is not the only reason to stimulate these efforts and actions. Another reason is existence of 'orphan' sources which number in the world is approaching to 200 000 including the ones with a very high activity. Uncontrolled presence of such sources and materials in the human environment can be hazardous to human health and it may cause significant economical losses. Radiation control at the borders of the countries in this case is the first line of defense on the route of illicit nuclear and radioactive material movement and therefore vitally important for country/state radiation protection. Radiation control at the borders of the states requires three steps: 1) primary control or detecting the presence of radioactive sources on a controlled object; 2) additional radiation control or locating the exact place of the radioactive source on the person, within the vehicle or inside the container; 3) identification of the nature of the radioactive source. To accomplish the first and the main step of radiation control process the high sensitive gamma-neutron portal monitors operating in automatic mode are utilized. They are used to alert authorities to the appearance of any radioactive source in the controlled area. These monitors are developed and manufactured in some countries and currently deployed at the borders of the countries and also in areas where the radioactive sources may appear. However, the experience of deploying the portal monitors in various countries (Poland, Russia, Belarus) (1-3) has proved that the installation even the best of the best monitors is just

NATURAL RADIOACTIVITY LEVEL AND ELEMENTAL COMPOSITION OF SOIL SAMPLES FROM A HIGH BACKGROUND RADIATION AREA ON EASTERN COAST OF INDIA (ODISHA).

Science.gov (United States)

Sahoo, S K; Kierepko, R; Sorimachi, A; Omori, Y; Ishikawa, T; Tokonami, S; Prasad, G; Gusain, G S; Ramola, R C

2016-10-01

A comprehensive study was carried out to determine the radioactivity concentration of soil samples from different sites of a high background radiation area in the eastern coast of India, Odisha state. The dose rate measured in situ varied from 0.25 to 1.2 µSv h -1 The gamma spectrometry measurements indicated Th series elements as the main contributors to the enhanced level of radiation and allowed the authors to find the mean level of the activity concentration (±SD) for 226 Ra, 228 Th and 40 K as 130±97, 1110±890 and 360±140 Bq kg -1 , respectively. Human exposure from radionuclides occurring outdoor was estimated based on the effective dose rate, which ranged from 0.14±0.02 to 2.15±0.26 mSv and was higher than the UNSCEAR annual worldwide average value 0.07 mSv. Additionally, X-ray fluorescence analysis provided information about the content of major elements in samples and indicated the significant amount of Ti (7.4±4.9 %) in soils. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Canada: Living with radiation

International Nuclear Information System (INIS)

1995-01-01

Canadians are exposed daily to a variety of naturally occurring radiation. Heat and light from the sun, are familiar examples. Radium and uranium are naturally occurring materials which have been found to emit radiation and so have been called radioactive. There are also various types of artificially produced forms of radiation that are employed routinely in modern living, such as radio and television waves and microwaves. X-rays, another common type of radiation, are widely used in medicine as are some man-made radioactive substances. These emit radiation just like naturally occurring radioactive materials. Surveys have shown that many people have a poor understanding of the risks associated with the activities of modern living. Exposure to ionizing radiation from radioactive materials is also considered by many persons to have a high risk, This booklet attempts to inform the readers about ionizing radiation, its uses and the risks associated with it, and to put these risks in perspective with the risks of other activities and practices. A range of topics from medical uses of radiation to emergency planning, from biological effects of radiation to nuclear power, each topic is explained to relate radiation to our everyday lives. 44 figs

Canada: Living with radiation

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

Canadians are exposed daily to a variety of naturally occurring radiation. Heat and light from the sun, are familiar examples. Radium and uranium are naturally occurring materials which have been found to emit radiation and so have been called radioactive. There are also various types of artificially produced forms of radiation that are employed routinely in modern living, such as radio and television waves and microwaves. X-rays, another common type of radiation, are widely used in medicine as are some man-made radioactive substances. These emit radiation just like naturally occurring radioactive materials. Surveys have shown that many people have a poor understanding of the risks associated with the activities of modern living. Exposure to ionizing radiation from radioactive materials is also considered by many persons to have a high risk, This booklet attempts to inform the readers about ionizing radiation, its uses and the risks associated with it, and to put these risks in perspective with the risks of other activities and practices. A range of topics from medical uses of radiation to emergency planning, from biological effects of radiation to nuclear power, each topic is explained to relate radiation to our everyday lives. 44 figs.

The planning, construction, and operation of a radioactive waste storage facility for an Australian state radiation regulatory authority

Energy Technology Data Exchange (ETDEWEB)

Wallace, J.D.; Kleinschmidt, R.; Veevers, P. [Radiation Health, Queensland (Australia)

1995-12-31

Radiation regulatory authorities have a responsibility for the management of radioactive waste. This, more often than not, includes the collection and safe storage of radioactive sources in disused radiation devices and devices seized by the regulatory authority following an accident, abandonment or unauthorised use. The public aversion to all things radioactive, regardless of the safety controls, together with the Not In My Back Yard (NIMBY) syndrome combine to make the establishment of a radioactive materials store a near impossible task, despite the fact that such a facility is a fundamental tool for regulatory authorities to provide for the radiation safety of the public. In Queensland the successful completion and operational use of such a storage facility has taken a total of 8 years of concerted effort by the staff of the regulatory authority, the expenditure of over $2 million (AUS) not including regulatory staff costs and the cost of construction of an earlier separate facility. This paper is a summary of the major developments in the planning, construction and eventual operation of the facility including technical and administrative details, together with the lessons learned from the perspective of the overall project.

Strengthening of safety and security of radioactive sources: new regulatory challenges

Energy Technology Data Exchange (ETDEWEB)

El Messaoudi, M.; Essadki M Lferde, H.; Moutia, Z. [Faculte des Sciences, Dept. de Physique, Rabat (Morocco)

2006-07-01

The answer to these new regulatory challenges was given by implementation of divers measures aimed at strengthening of safety and security of radioactive sources and to prevent the malevolent use of radioactive sources. The international basic safety standards for protection against ionizing radiation and for the safety of radiation sources (B.S.S.) require the establishment and implementation of security measures of radioactive sources to ensure that protection and safety requirements are met. The IAEA has engaged in an extensive effort to establish and/or strengthen national radiation protection and radiological safety infrastructure, including legislation and regulation, a regulatory authority empowered to authorize and inspect regulated activities, an adequate number of trained personnel and technical services that are beyond the capabilities required of the authorized legal persons. The Moroccan authority makes steady efforts to strengthen national radiation safety infrastructure by participating in IAEA model project for upgrading radiation protection infrastructure, to implement the revised version of code of conduct on the safety and security of radioactive sources. Indeed, Morocco expressed its adhesion with the technical assistance project of the IAEA in 2001, carrying on the reinforcement of the national infrastructure of regulation and control of the radioactive materials. The control over radioactive sources is an essential element for maintaining high level of security and safety of radioactive sources. The IAEA T.E.C.-D.O.C.-1388 serves as reference document to implement the control culture. The security problems with which the world is confronted showed that the uses of radioactive sources should subject reinforcements of safety, of control and of security of the radioactive sources. For this purpose, the IAEA launched an action plan for the safety and security of radioactive sources. The IAEA guide Security of radioactive sources will help the

Strengthening of safety and security of radioactive sources: new regulatory challenges

International Nuclear Information System (INIS)

El Messaoudi, M.; Essadki M Lferde, H.; Moutia, Z.

2006-01-01

The answer to these new regulatory challenges was given by implementation of divers measures aimed at strengthening of safety and security of radioactive sources and to prevent the malevolent use of radioactive sources. The international basic safety standards for protection against ionizing radiation and for the safety of radiation sources (B.S.S.) require the establishment and implementation of security measures of radioactive sources to ensure that protection and safety requirements are met. The IAEA has engaged in an extensive effort to establish and/or strengthen national radiation protection and radiological safety infrastructure, including legislation and regulation, a regulatory authority empowered to authorize and inspect regulated activities, an adequate number of trained personnel and technical services that are beyond the capabilities required of the authorized legal persons. The Moroccan authority makes steady efforts to strengthen national radiation safety infrastructure by participating in IAEA model project for upgrading radiation protection infrastructure, to implement the revised version of code of conduct on the safety and security of radioactive sources. Indeed, Morocco expressed its adhesion with the technical assistance project of the IAEA in 2001, carrying on the reinforcement of the national infrastructure of regulation and control of the radioactive materials. The control over radioactive sources is an essential element for maintaining high level of security and safety of radioactive sources. The IAEA T.E.C.-D.O.C.-1388 serves as reference document to implement the control culture. The security problems with which the world is confronted showed that the uses of radioactive sources should subject reinforcements of safety, of control and of security of the radioactive sources. For this purpose, the IAEA launched an action plan for the safety and security of radioactive sources. The IAEA guide Security of radioactive sources will help the

Radiation and radiation protection; Strahlung und Strahlenschutz

Energy Technology Data Exchange (ETDEWEB)

Bartholomaeus, Melanie (comp.)

2017-04-15

The publication of the Bundesamt fuer Strahlenschutz covers the following issues: (i) Human beings in natural and artificial radiation fields; (ii) ionizing radiation: radioactivity and radiation, radiation exposure and doses; measurement of ionizing radiation, natural radiation sources, artificial radiation sources, ionizing radiation effects on human beings, applied radiation protection, radiation exposure of the German population, radiation doses in comparison; (iii) non-ionizing radiation; low-frequency electric and magnetic fields, high-frequency electromagnetic fields, optical radiation; (iiii) glossary, (iv) units and conversion.

Survey of radiation protection programmes for transport; Etude des programmes de radioprotection pour les transports de matieres radioactives

Energy Technology Data Exchange (ETDEWEB)

Lizot, M.T.; Perrin, M.L.; Sert, G. [CEA Fontenay-aux-Roses, Inst. de Protection et de Surete Nucleaire, Dept. de Protection et de Surete Nucleaire, 92 (France); Lange, F.; Schwarz, G.; Feet, H.J.; Christ, R. [Gesellschaft fur Anlagen-und Reaktorsicherheit, GRS, mbH, Cologne (Germany); Shaw, K.B.; Hughes, J.S.; Gelder, R. [National Radiological Protection Board (NRPB), Oxon, OX (United Kingdom)

2001-07-01

The survey of radiation protection programmes for transport has been jointly performed by three scientific organisations I.P.S.N. (France), G.R.S. ( Germany), and N.R.P.B. (United kingdom) on behalf of the European Commission and the pertaining documentation summarises the findings and conclusions of the work that was undertaken with the principal objectives to provide guidance on the establishment, implementation and application of radiation protection programmes for the transport of radioactive materials by operators and the assessment and evaluation of such programmes by the competent authority and to review currently existing radiation protection programmes for the transport of radioactive materials. (N.C.)

Top soil radioactivity assessment in a high natural radiation background area: the case of Vinaninkarena, Antsirabe-Madagascar.

Science.gov (United States)

Rabesiranana, Naivo; Rasolonirina, Martin; Terina, Franck; Solonjara, Asivelo F; Andriambololona, Raoelina

2008-11-01

The village of Vinaninkarena, Antsirabe, Madagascar (47 degrees 02'40''E, 19 degrees 57'17''S) is located in a high natural radioactivity area. In order to evaluate the natural radionuclide content in soil, sampling was done on-site by the transect method (85 soil samples) and off-site through transects across and beyond the region (up to a range of 100 km), to determine the natural radioactivity variation within vs. outside the region, and to detect significant differences, taking into account spatial variability.

Radioactive wastes and discharges

International Nuclear Information System (INIS)

1993-01-01

According to the Section 24 of the Finnish Radiation Decree (1512/91), the Finnish Centre for Radiation and Nuclear Safety shall specify the concentration and activity limits and principles for the determination whether a waste can be defined as a radioactive waste or not. The radiation safety requirements and limits for the disposal of radioactive waste are given in the guide. They must be observed when discharging radioactive waste into the atmosphere or sewer system, or when delivering solid low-activity waste to a landfill site without a separate waste disposal plan. The guide does not apply to the radioactive waste resulting from the utilization of nuclear energy of natural resources. (4 refs., 1 tab.)

Final repositories for high-level radioactive waste; Endlagerung hochradioaktiver Abfaelle

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-10-15

The brochure on final repositories for high-level radioactive waste covers the following issues: What is the origin of radioactive wastes? How large are the waste amounts? What is going to happen with the wastes? What is the solution for the Waste disposal? A new site search is started. Safety requirements for the final disposal of high-level radioactive wastes. Comparison of host rocks. Who is responsible and who will pay? Final disposal of high-level radioactive wastes worldwide. Short summary: History of the search for a final repository for high-level radioactive wastes in Germany.

High technology for radiation application

International Nuclear Information System (INIS)

Iida, Toshiyuki

2005-03-01

Fundamentals of radiations, radioactivity, and their applications in recent industrial, medical, agricultural and various research fields are reviewed. The book begins with historical description regarding to discovery of radiation at the end of 19th century and the exploration into the inside of an atom utilizing the radiation discovered, discovery of the neutron which finally leaded to nuclear energy liberation. Developments of radiation sources, including nuclear reactors, and charged-particle accelerators follow with simultaneous description on radiation measurement or detection technology. In medical fields, X-ray diagnosis, interventional radiology (IVR), nuclear medicine (PET and others), and radiation therapy are introduced. In pharmaceutical field, synthesis of labeled compounds and tracer techniques are explained. In industrial application, radiation-reinforced wires and heat-resistant cables whose economic effect can be estimated to amount to more than 10 12 yen, radiation mutation, food irradiation, and applied accelerators such as polymer modifications, decomposition of environmentally harmful substances, and ion-implantations important in semiconductor device fabrication. Finally, problems relating to general public such as radiation education and safety concept are also discussed. (S. Ohno)

Assessment of radiation exposure of personnel during clinical application of radioactive iridium

Energy Technology Data Exchange (ETDEWEB)

Dworakowski, M; Krystman-Mazgajska, E; Wysopolski, J [Instytut Onkologii, Warsaw (Poland); Centralne Lab. Ochrony Radiologicznej, Warsaw (Poland))

1975-01-01

The authors describe the results of measurements of doses and the evaluation of radiation exposure of the personnel of the Department of General Oncology working with application of radioactive iridium for interstitial and superficial treatment of neoplasma. The doses were measured by the photographic method simultaneously at six sites of the body: on the forehead, left side of the chest, 4th fingers of both hands, and on the left and right sides of the trunk at the level of gonads. The authors believe that introduction of iridium in place of radium will improve the conditions of work from the standpoint of protection against radioactivity.

Soil radioactivity levels and radiation hazard assessment around a Thermal Power Plant

International Nuclear Information System (INIS)

Kumar, Mukesh; Kumar, Pankaj; Sharma, Somdutt; Agrawal, Anshu; Kumar, Rajesh; Prajith, Rama; Sahoo, B.K.

2016-01-01

Coal based thermal power plants further enhance the level of radioactivity in the environment, as burning of coal produces fly ash that can be released into the environment containing traces of 238 U, 232 Th and their decay products. Therefore, coal fired power plants are one of the major contributor towards the Technologically Enhanced Natural Radiation (TENR). Keeping this in view, a study of natural radioactivity in the soil of twenty five villages within 5 km radius around the Harduaganj Thermal Power Plant, Aligarh, UP, India is going on under a BRNS major project, to know the radiological implications on general population living around this plant

Regulatory control of radiation sources and radioactive materials in the Czech Republic

International Nuclear Information System (INIS)

Drabova, D.; Prouza, Z.

2001-01-01

The paper describes legal and regulatory provisions for radiation protection and safe use of sources of ionizing radiation in the Czech Republic with special emphasis on aspects of bringing activities under regulatory control and releasing them from it. It covers the development of a new legal framework, the work of the regulatory body, an overview of sources in use and provisions to achieve effective regulatory control of facilities and releases of radioactive material into the environment. Also, it describes reported unusual events with a proposed scheme for their classification and evaluation. (author)

Study of radioactivity and radiation attenuation of a new heavy weight concrete

International Nuclear Information System (INIS)

Ramadan, A.B.; Fouda, S.; EL-Mongy, S.; Hodhod, O.; Yousef, M.

2005-01-01

The present study is concerned with studying the radioactivity levels and efficiency of proposed heavy weight concrete as a shielding material for low and intermediate level radioactive wastes. Effect of elevated temperatures on radiation attenuation characteristics of proposed materials was also studied. Three types of local natural aggregates (iron ores) namely magnetite, limonite and hematite have been prepared, analyzed for their radioactivity and tested to determine their suitability for the manufacture of heavy weight concrete, which can be used for shielding. Hematite was excluded and two types of concrete have been prepared by using magnetite and limonite. The gamma spectrometry and neutron activation have been used to determine both uranium and thorium contents in the investigated materials. The results obtained by the two methods showed that uranium and thorium were within the acceptable low levels. It was observed that the two types of concrete have good attenuation properties

Natural radioactivity distribution images and their educational uses

International Nuclear Information System (INIS)

Mori, Chizuo; Sumi, Tetsuo; Miyahara, Hiroshi; Uritani, Akira; Nishina, Kojiro

1999-01-01

Distribution images of natural radioactivities in vegetables, meat and porcelain works were obtained by use of Imaging Plate with very high sensitivity to radiations. A brochure titled 'Natural Radiations through Naked Eyes' was published in both Japanese and English which included the images mentioned above. In this paper, the method to obtain the distribution images of extremely low level natural radioactivity, the content of the brochure and the effect of it to the public are described. (author)

Natural radioactivity distribution images and their educational uses

Energy Technology Data Exchange (ETDEWEB)

Mori, Chizuo; Sumi, Tetsuo [Aichi Institute of Technology, Toyota, Aichi (Japan); Miyahara, Hiroshi; Uritani, Akira; Nishina, Kojiro

1999-09-01

Distribution images of natural radioactivities in vegetables, meat and porcelain works were obtained by use of Imaging Plate with very high sensitivity to radiations. A brochure titled 'Natural Radiations through Naked Eyes' was published in both Japanese and English which included the images mentioned above. In this paper, the method to obtain the distribution images of extremely low level natural radioactivity, the content of the brochure and the effect of it to the public are described. (author)

Radioactivity in the environment

International Nuclear Information System (INIS)

Fernandez Niello, Jorge

2005-01-01

The book summarizes general concepts on radiation, nuclear structure, radioactivity and the interaction of the nuclear radiation with matter. It describes also the basic principles of radio dosimetry. Natural and artificial sources of radiation are reviewed as well as the effects of radiation in man. Medical and industrial applications of ionizing radiation and the pollution produced by the discharge of radioactive materials are outlined. A short review is made of the safety rules and the regulations concerning the protection of the environment [es

Assessment of temporal trend of radiation dose to the public living in the large area contaminated with radioactive materials after a nuclear power plant accident

Energy Technology Data Exchange (ETDEWEB)

Go, A Ra; Kim, Min Jun; Kim, Kwang Pyo [Dept. of Nuclear Engineering, Kyung Hee University, Seoul (Korea, Republic of); Cho, Nam Chan; Seol, Jeung Gun [Radiation Safety Team, Korea Electric Power Corporation Nuclear Fuel, Seoul (Korea, Republic of)

2015-12-15

It has been about 5 years since the Fukushima nuclear power plant accident, which contaminated large area with radioactive materials. It is necessary to assess radiation dose to establish evacuation areas and to set decontamination goal for the large contaminated area. In this study, we assessed temporal trend of radiation dose to the public living in the large area contaminated with radioactive materials after the Fukushima nuclear power plant accident. The dose assessment was performed based on Chernobyl model and RESRAD model for two evacuation lift areas, Kawauchi and Naraha. It was reported that deposition densities in the areas were 4.3-96 kBq m{sup -2} for {sup 134}Cs, 1.4-300 kBq m{sup -2} for {sup 137}Cs, respectively. Radiation dose to the residents depended on radioactive cesium concentrations in the soil, ranging 0.11-2.4 mSv y{sup -1} at Kawauchi area and 0.69-1.1 mSv y{sup -1} at Naraha area in July 2014. The difference was less than 5% in radiation doses estimated by two different models. Radiation dose decreased with calendar time and the decreasing slope varied depending on dose assessment models. Based on the Chernobyl dosimetry model, radiation doses decreased with calendar time to about 65% level of the radiation dose in 2014 after 1 year, 11% level after 10 years, and 5.6% level after 30 years. RESRAD dosimetry model more slowly decreased radiation dose with time to about 85% level after 1 year, 40% level after 10 years, and 15% level after 30 years. The decrease of radiation dose can be mainly attributed into radioactive decays and environmental transport of the radioactive cesium. Only environmental transports of radioactive cesium without consideration of radioactive decays decreased radiation dose additionally 43% after 1 year, 72% after 3 years, 80% after 10 years, and 83% after 30 years. Radiation doses estimated with cesium concentration in the soil based on Chernobyl dosimetry model were compared with directly measured radiation doses

Radioactive PTT as part of screening protocol for prospecting radiation workers

International Nuclear Information System (INIS)

Nato, Alejandro Q. Jr.; Deocaris, Custer; Sajise, Sheila C.

2002-04-01

Heterozygous mutations in BRCA1 or BRCA2 (breast cancer)have been found to be associated with enhanced cellular radiosensitivity with impaired proliferative capacity after irradiation and could predispose increased risk of radiation-induced mutagenesis and carcinogenesis (1,2). Deficient repair mechanism exhibited by lymphocytes from breast cancer patients provides associated vulnerability to genotoxicity of ionizing radiation. Other genes ay also play a role in terms o clinical radiation hypersensitivity needed in predicting response to radiotherapy. However, relaxation of cell cycle checkpoints, production of micronuclei, and loss of proliferative capacity which have been exhibited by impairment of irradiated cells lacking functional BRCA1 and BRCA2, accentuate the notion that heterozygous women may respond differently to radiation. The radioactive protein truncation test (PTT), utilized as screening procedures to detect frameshift mutations, can be employed to clarify radiosensitivity of individuals carrying a mutated BRCA1 gene. It can therefore, be incorporated in the series of clinical assays used in standard screening protocols for prospective nuclear facility workers. (author)

Experimental studies on the possibility of using a ceramic matrix for fixing the high level radioactive wastes

International Nuclear Information System (INIS)

Husain, S.R.; Rudolph, G.; Hild, W.

1975-06-01

A ceramic product has been developed to fix high level radioactive wastes for storage and final disposal. In the present experiments some of the properties, e.g. visual change, change in size or shape, change in weight, change in structure, density and leachability, are studied for the long term stability of the product under heat and radiation treatment. The properties are not severely affected by radiation or by heat treatment. The leaching property is slightly affected due to heating. From the results it appears that the heating has a dominant effect over the radiation on the properties of the ceramic product. (orig.) [de

The status of safety of radiation sources and security of radioactive materials in Ethiopia

International Nuclear Information System (INIS)

Gebeyehu Wolde, G.

2001-01-01

Since 1993, the National Radiation Protection Authority (NRPA) has been empowered by the 'Radiation Protection Proclamation no. 79/1993' to authorize and inspect regulated activities, issue guidelines and standards and enforce the legislation and regulations. The report describes the status of the safety of radiation sources and the security of radioactive materials in Ethiopia and the progress made towards building a sound and effective national regulatory infrastructure. Also, the report highlights the challenges and difficulties encountered and concludes by indicating the way forward towards the strategic goals. (author)

Application of radiation protection programmes to transport of radioactive material

International Nuclear Information System (INIS)

Lopez Vietri, Jorge; Capadona, Nancy; Barenghi, Leonardo

2008-01-01

Full text: The principles for implementing radiation protection programmes (RPP) are detailed in the draft IAEA safety guide TS-G-1.5 'Radiation protection programmes for transport of radioactive material'. The document is described in this paper and analysis is made for typical applications to current operations carried out by consignors, carriers and consignees. Systematic establishment and application of RPPs is a way to control radiological protection during different steps of transport activity. The most widely transported packages in the world are radiopharmaceuticals by road. It is described an application of RPP for an organization involved in road transport of Type A packages containing radiopharmaceuticals. Considerations based on the radionuclides, quantities and activities transported are the basis to design and establish the scope of the RPP for the organizations involved in transport. Next stage is the determination of roles and responsibilities for each activity related to transport of radioactive materials. An approach to the dose received by workers is evaluated considering the type, category and quantity of packages, the radionuclides, the frequency of consignments and how long are the storages. The average of transports made in the last years must be taken into account and special measures intended to optimize the protection are evaluated. Tasks like monitoring, control of surface contamination and segregation measures, are designed based on the dose evaluation and optimization. The RPP also indicates main measures to follow in case of emergency during transport taking account of radionuclides, activities and category of packages for different accident scenarios. Basis for training personnel involved in handling of radioactive materials to insure they have appropriate knowledge about preparing packages, measuring dose rates, calculating transport index, labelling, marking and placarding, transport documents, etc, are considered. The RPP is a part

Radiation safety ensuring and environment protection dealing with radioactive waste management in the system of the special plants ''Radon''

International Nuclear Information System (INIS)

Zenkina, Lidia

1999-01-01

This presentation deals with the Russian special plants ''Radon'', a system of 16 regional plants devoted to radioactive waste management. The plants are intended to receive solid radioactive wastes and liquid radioactive wastes of low and medium levels of activity for reprocessing and final disposal. The following topics are discussed: (1) waste characterization, (2) storage construction, (3) preparation of waste for burial, (4) site selection, (5) tasks of the plant, (6) division of plant territory into zones, (7) radiation monitoring, (8) prevention of accidents and elimination of their consequences, (10) training of staff, (11) sanitary treatment of staff and equipment decontamination. Lack of financial means is a major problem. The closure of the Murmansk special plant Radon has caused great problems for the North-European District. The Leningrad special plant Radon has been forced to accept radioactive waste from the Arkhangelsk region. The exhaustion of reserve volumes for solid radioactive waste acceptance at this plant affects the entire North-Western Russia. At present, spent sources of ionising radiation are buried in shallow land-based storage facilities of well type. It was found on inspection that such burial of sources containing nuclides with half-life of more than 30 years must be stopped. Existing storages are inadequate for safe storage of such sources throughout their hazardous period, and are not adjusted for extraction of such sources in the future. The spent sources containing long-lived nuclides must be temporarily stored in transport containers in separate sections of solid waste storage facilities. In 1997, analysis of radiation state parameters for radioactive waste burial at special plants Radon showed that the radiation dose rate at working places and the average annual volumetric activity of radionuclides in the environment were within the admissible limits

Soil radioactivity levels and radiation hazard assessment for some populated areas, Cairo, Egypt

International Nuclear Information System (INIS)

Abu-Zeid, H.M; Abd-ElMaksoud, T.M; Nada, A; Awad, S; El-Nagar, T.

2011-01-01

Determination of the natural radioactivity has been carried out, by means of gamma ray spectrometry system ,on sixty two surface soil samples collected from different localities in Nasr City and Heliopolis for measuring the activity concentrations for 238 U, 232 Th, and 40 K. The evaluation of environmental radioactivity and estimating the current radiation hazards to the population make this study an interesting issue. The output results referred to all these localities indicated that these regions are not hazardous from the environmental point of view.The results of the present study were discussed and compared with internationally recommended values.

The functionalities of the Darwin radioactivity calculation form and the radiation protection studies

International Nuclear Information System (INIS)

Tsilanizara, A.; Huynh, T.D.; Luneville, L.; Diop, C.M.; Eid, M.

2003-01-01

The characterisation of the radioactive sources relative to the evolution of nuclear fuels or to the activation under particles flux (generally neutrons) of structures of a nuclear equipment or a simple isotope decay is a step in the radiation protection studies. This characterisation needs to know a fundamental knowledge: the radionuclides concentration. This one changes with time, and follows the coupled differential equations of first order in time, the generalised Bateman equations. The objective of this paper is to present the functionalities of the Darwin form, developed by the Cea and dedicated to the study of radioactivity. (N.C.)

Release of the radioactive patient following radiation therapy

International Nuclear Information System (INIS)

Powers, J.; Cancer Board, A.

2004-01-01

Patients walk out of medical facilities containing as much as a complete therapeutic dose of radiation on a daily basis. This presents a significant challenge to the radiation protection community, as most patients have no prior education related to radiation and may not have the aptitude to assimilate such knowledge. In the case of targeted radiation therapy in which radionuclides are used to selectively target the cancer, patients are typically released only after adequate elimination and decay of the radionuclide administered. Established modalities of targeted radiotherapy include the use of iodine for thyroid cancer, strontium for bone pain, phosphorous for haematological diseases, 131I-mIBG for neuroblastoma, and most recently Y-90 labelled monoclonal antibodies for lymphoma. In the case of permanent implants, implants of encapsulated radioactive sources are left permanently in the tissues, thus patients are released containing their complete therapeutic dose. Isotopes used in permanent implants include I-125, Pd-103 and Au-198. Radiation safety considerations for both cases, the release of a patient who has received targeted radiotherapy, and the release of a patient who has received a permanent implant, will be discussed. A summary of applicable regulations will serve as a starting point for each of the following considerations; i) Security and source control ii) Instructions to patient and family members iii) Risk to the public As the incidence of cancer increases, and the popularity of targeted radiotherapy and permanent seed implants grows, the event of having an untrained person in possession of a therapeutic dose of radiation becomes more and more common. It is essential to stop and examine the risk of this practice, whether current strategies to reduce the risk to an acceptable level are indeed effective, and whether control over these sources is even feasible. (Author)

Release of the radioactive patient following radiation therapy

Energy Technology Data Exchange (ETDEWEB)

Powers, J.; Cancer Board, A.

2004-07-01

Patients walk out of medical facilities containing as much as a complete therapeutic dose of radiation on a daily basis. This presents a significant challenge to the radiation protection community, as most patients have no prior education related to radiation and may not have the aptitude to assimilate such knowledge. In the case of targeted radiation therapy in which radionuclides are used to selectively target the cancer, patients are typically released only after adequate elimination and decay of the radionuclide administered. Established modalities of targeted radiotherapy include the use of iodine for thyroid cancer, strontium for bone pain, phosphorous for haematological diseases, 131I-mIBG for neuroblastoma, and most recently Y-90 labelled monoclonal antibodies for lymphoma. In the case of permanent implants, implants of encapsulated radioactive sources are left permanently in the tissues, thus patients are released containing their complete therapeutic dose. Isotopes used in permanent implants include I-125, Pd-103 and Au-198. Radiation safety considerations for both cases, the release of a patient who has received targeted radiotherapy, and the release of a patient who has received a permanent implant, will be discussed. A summary of applicable regulations will serve as a starting point for each of the following considerations; i) Security and source control ii) Instructions to patient and family members iii) Risk to the public As the incidence of cancer increases, and the popularity of targeted radiotherapy and permanent seed implants grows, the event of having an untrained person in possession of a therapeutic dose of radiation becomes more and more common. It is essential to stop and examine the risk of this practice, whether current strategies to reduce the risk to an acceptable level are indeed effective, and whether control over these sources is even feasible. (Author)

CITON involvement in CETRAD project on 'Education and training in radiation protection and radioactive waste'

International Nuclear Information System (INIS)

Comsa, Olivia; Meglea, Claudia; Banutoiu, Marina; Paraschiva, M. V.; Meglea, S.

2003-01-01

Within the European Community and world-wide there is extensive experience in the principles and practice of radiation protection and radioactive waste management. Nuclear skills and capabilities have grown and evolved since the inception of nuclear technology in the 1940s. However, with the current stagnation of the nuclear industry it is increasingly acknowledged that the skills and expertise held by the generation who grew up with nuclear technology are being passed on to new generations of experts. This poses a significant risk to the community who will need to manage nuclear liabilities for long times into the future in order to protect future society from radiological hazards. Notwithstanding that the state of the art in nuclear waste management is undoubtedly high in many organizations, it is very clear that there is continuous need for the provision of education and training in this area. The various training and education programmes throughout Europe are at different stages of development. There is undoubtedly a need for harmonization of the numerous programmes and there would be great benefit to countries at early stages of development due to the learning experiences from the more developed organizations. The objective of CETRAD is to develop proposals for structuring and delivering both education and training in the management of the geological disposal of long-lived radioactive waste and radiation protection across Europe. This proposal is seen as a forerunner of a more comprehensive pan-European Network in this area, which it is planned, will emerge from this work. The project activities will be carried out in two phases. Phase 1 will involve national evaluations of both the needs for education and training and the existing infrastructure and resources in the field of radiation protection and radioactive waste management. Phase 2 will involve development of specific proposals for education and training based on the needs identified in Phase 1. (authors)

Disposal of high level radioactive waste consideration of some basic criteria

International Nuclear Information System (INIS)

1993-01-01

The series of Nordic documents on radiation protection principles present the joint views of the Nordic authorities on radiation protection issues. These views are to be regarded as recommendations to the same Nordic authorities to be considered in their work on national regulations and applications. This document deals with the principles of disposal of high level radioactive waste, including spent fuels, and is therefore intended for authorities in nuclear safety as well as radiation protection. The emphasis is on radiation protection criteria, and the document is primarily directed to the authorities but can also be of interest to the nuclear power industry in its planning of disposal facilities. It can also be used as a source of information on the problems associated with high level waste and on the principles by which these problems would be solved. The main emphasis has been placed on the long-term aspects. The recommendations given by ICRP and the ideas and discussions presented by NEA and IAEA in various publications were the main documents taken into account. The discussions concentrate on the deep geological repository which is the main disposal concept currently being considered in the Nordic countries. The plans in Finland and Sweden include the selection of a disposal site around the year 2000 and a construction period in the early part of the next century. 32 refs, 3 figs

Natural radiation environment

International Nuclear Information System (INIS)

Vohra, K.G.; Mishra, U.C.; Pillai, K.C.; Sadasivan, S.

1982-01-01

The volume presented contains papers presented at the Second Special Symposium on Natural Radiation Environment held at Bombay, India, during January 1981. The papers deal with such topics as : 1)high natural radiation background areas; 2)environmental natural radioactivity; 3)measurement techniques; 4)technologically enhanced radioactivity; 5)indoor radiation environment; 6)radon and daughters in ambient air, and 7)applications in Geosciences. Each of the 87 papers presented has been abstracted and indexed for the U.S. Department of Energy Technical Information Center's Energy Data Base

Development of Radioactive Inventory Evaluation System using 3D Shape and Multiple Radiation Measurement

International Nuclear Information System (INIS)

Lee, Sang Chul; Kim, Won Seok; Han, Byong Su; Moon, Joo Hyun

2013-01-01

The increase of the operating NPPs and the superannuation of the equipment in NPPs cause a large amount of the metal radioactive waste. Presently the metal radioactive wastes are stored in the temporary storage facility in NPPs because of the delay of the construction of the final disposal facility. The radioactive level of general metal radioactive wastes is low, and the radioactive level can be lowered by the simple decontamination process. If the radioactive wastes are disposed as the industry waste, the disposal cost is diminished largely. For the disposal of the radioactive wastes as the industrial wastes, the radioactive level of the target wastes are evaluated. It is difficult to know the position of the source term for most of the metal radioactive and the source term is distributed non-homogeneously. And the self-shielding effect of the metal material makes the evaluation more difficult. In this study, the radioactive inventory evaluation system for the metal radioactive waste is developed. For the correction of the uncertainty of the position and the non-homogeneity of the source term, the 3D shape and multiple radiation measurement are used. The existing gamma-ray measurement system for the metal radioactive waste cannot reflect the position and the distribution of the source term and the effect of self-shielding. This evaluation system suggested in this system can calculate the reasonable value regarding to the position and the distribution of the source term and the effect of self-shielding. By the calculation of the partial inventory of the target metal waste, the advantage in the application of the clearance criteria can be obtained

High energy radiation in cancer treatment

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-10-15

Certain basic recommendations on the use of supervoltage radiation and radioisotope teletherapy in the treatment of malignant growths have been made by an expert study group which met in Vienna in August this y ear. The group, convened jointly by the International Atomic Energy Agency and the World Health Organization, was composed of 20 radiotherapists and radiation physicists from 12 countries. High energy radiation, used in the treatment of malignant tumours, can be either in the form of gamma- or X-rays or in the form of beams of accelerated electrons. The source of radiation is kept at a certain distance from the patient. The study group was agreed on the value of supervoltage radiotherapy, including gamma-ray and high voltage x-ray therapy as well as electron beam therapy. The required gamma radiation can be obtained from large sources of radioactive materials like cobalt 60 or caesium 137, while electron beams are produced by high voltage accelerators. The experts considered the sources in four broad categories: large supervoltage units, intermediate units, small isotope units and units of electron beams or very high energy x-rays. Each group of source was described including its usage. The experts made it clear that while supervoltage radiation should be a part of an organized radiotherapy department, the radiation facilities at any particular establishment should not be of the supervoltage type alone. The high energy facilities could be fruitfully used only when there was a background of general radiotherapy. The group emphasized that supervoltage radiotherapy, in common with other forms of radiotherapy, should be conducted only by adequately trained and qualified personnel, including radiation physicists, and specified the training and qualifications required of such personnel. It was felt that specialized training was one of the main requirements at the present stage and the training programmes of IAEA and WHO should be utilized extensively for this

High energy radiation in cancer treatment

International Nuclear Information System (INIS)

1959-01-01

Certain basic recommendations on the use of supervoltage radiation and radioisotope teletherapy in the treatment of malignant growths have been made by an expert study group which met in Vienna in August this y ear. The group, convened jointly by the International Atomic Energy Agency and the World Health Organization, was composed of 20 radiotherapists and radiation physicists from 12 countries. High energy radiation, used in the treatment of malignant tumours, can be either in the form of gamma- or X-rays or in the form of beams of accelerated electrons. The source of radiation is kept at a certain distance from the patient. The study group was agreed on the value of supervoltage radiotherapy, including gamma-ray and high voltage x-ray therapy as well as electron beam therapy. The required gamma radiation can be obtained from large sources of radioactive materials like cobalt 60 or caesium 137, while electron beams are produced by high voltage accelerators. The experts considered the sources in four broad categories: large supervoltage units, intermediate units, small isotope units and units of electron beams or very high energy x-rays. Each group of source was described including its usage. The experts made it clear that while supervoltage radiation should be a part of an organized radiotherapy department, the radiation facilities at any particular establishment should not be of the supervoltage type alone. The high energy facilities could be fruitfully used only when there was a background of general radiotherapy. The group emphasized that supervoltage radiotherapy, in common with other forms of radiotherapy, should be conducted only by adequately trained and qualified personnel, including radiation physicists, and specified the training and qualifications required of such personnel. It was felt that specialized training was one of the main requirements at the present stage and the training programmes of IAEA and WHO should be utilized extensively for this

Development of radioactive materials inspection system

International Nuclear Information System (INIS)

Yang Lu; Wang Guobao; Chen Yuhua; Li Latu; Zhang Sujing

2005-01-01

Radioactive materials inspection system which is applied to inspect the horror activities of radioactive materials and its illegal transfer. The detector sections are made of highly stable and credible material. It has high sensitivity to radioactive materials. The inspect lowest limit of inspection is the 2-3 times to the background, the energy range is 30 keV-2.5 MeV and the response time is 0.5 s. Inspection message can be transmitted through wired or wireless web to implement remote control. The structure of the system is small, light and convenient. It is ideal for protecting society and public from the harm of the radiation. (authors)

Prospective study in the management of high-dose radioactive iodine therapy induced gastritis

International Nuclear Information System (INIS)

Carbonell, C.; Ogbac, R.V.

2007-01-01

Full text: Gastritis is simply defined as inflammation of the gastric mucosa. In post-RAI patients, this is one of the most common complications that are encountered. Some patients may even require repetitive administration of high doses of radioactive iodine (I-131). Small doses of radiation (up to 1500 R) cause reversible mucosal damage, whereas higher radiation doses cause irreversible damage with atrophy and ischemic-related ulceration. Reversible changes consist of degenerative changes in epithelial cells and nonspecific chronic inflammatory infiltrate in the lamina propria. Higher amounts of radiation cause permanent mucosal damage, with atrophy of fundic glands, mucosal erosions, and capillary hemorrhage. Associated submucosal endarteritis results in mucosal ischemia and secondary ulcer development. Recurrent gastritis, if left untreated, may be a predisposing factor for gastric malignancy. Methods:A total of thirty post-RAI subjects were evaluated for signs and symptoms of gastritis and were divided into 3 groups which were given drugs for gastritis (H2-receptor antagonist, proton pump inhibitor, and sucralfate). Survey forms were distributed to evaluate the presence of nausea, vomiting, epigastric pain (graded according to severity of pain), and gastrointestinal bleeding. Results were tallied accordingly. Results and Discussion: In a total of 3 subjects who were given sucralfate, all of them did not experience any nausea and vomiting. One subject experienced mild epigastric discomfort and another subject was able to experience a non-specific symptom of abdominal bloatedness. (Note: Subjects are still for completion) In theory, radiation irritates the mucosa causing inflammation and mucosal damage which is further irritated by gastric acid secretion. The administration of H2-receptor blockers and proton pump inhibitors only inhibit gastric acid secretion while existing inflammation of mucosa due to high doses of radiation is left untreated. However

Radiation safety program in high dose rate brachytherapy facility at INHS Asvini

Directory of Open Access Journals (Sweden)

Kirti Tyagi

2014-01-01

Full Text Available Brachytherapy concerns primarily the use of radioactive sealed sources which are inserted into catheters or applicators and placed directly into tissue either inside or very close to the target volume. The use of radiation in treatment of patients involves both benefits and risks. It has been reported that early radiation workers had developed radiation induced cancers. These incidents lead to continuous work for the improvement of radiation safety of patients and personnel The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. The widespread adoption of high dose rate brachytherapy needs appropriate quality assurance measures to minimize the risks to both patients and medical staff. The radiation safety program covers five major aspects: quality control, quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. This paper will discuss the radiation safety program developedfor a high dose rate brachytherapy facility at our centre which may serve as a guideline for other centres intending to install a similar facility.

Radioactive waste management in a hospital.

Science.gov (United States)

Khan, Shoukat; Syed, At; Ahmad, Reyaz; Rather, Tanveer A; Ajaz, M; Jan, Fa

2010-01-01

Most of the tertiary care hospitals use radioisotopes for diagnostic and therapeutic applications. Safe disposal of the radioactive waste is a vital component of the overall management of the hospital waste. An important objective in radioactive waste management is to ensure that the radiation exposure to an individual (Public, Radiation worker, Patient) and the environment does not exceed the prescribed safe limits. Disposal of Radioactive waste in public domain is undertaken in accordance with the Atomic Energy (Safe disposal of radioactive waste) rules of 1987 promulgated by the Indian Central Government Atomic Energy Act 1962. Any prospective plan of a hospital that intends using radioisotopes for diagnostic and therapeutic procedures needs to have sufficient infrastructural and manpower resources to keep its ambient radiation levels within specified safe limits. Regular monitoring of hospital area and radiation workers is mandatory to assess the quality of radiation safety. Records should be maintained to identify the quality and quantity of radioactive waste generated and the mode of its disposal. Radiation Safety officer plays a key role in the waste disposal operations.

Radioactive Waste Management in A Hospital

Science.gov (United States)

Khan, Shoukat; Syed, AT; Ahmad, Reyaz; Rather, Tanveer A.; Ajaz, M; Jan, FA

2010-01-01

Most of the tertiary care hospitals use radioisotopes for diagnostic and therapeutic applications. Safe disposal of the radioactive waste is a vital component of the overall management of the hospital waste. An important objective in radioactive waste management is to ensure that the radiation exposure to an individual (Public, Radiation worker, Patient) and the environment does not exceed the prescribed safe limits. Disposal of Radioactive waste in public domain is undertaken in accordance with the Atomic Energy (Safe disposal of radioactive waste) rules of 1987 promulgated by the Indian Central Government Atomic Energy Act 1962. Any prospective plan of a hospital that intends using radioisotopes for diagnostic and therapeutic procedures needs to have sufficient infrastructural and manpower resources to keep its ambient radiation levels within specified safe limits. Regular monitoring of hospital area and radiation workers is mandatory to assess the quality of radiation safety. Records should be maintained to identify the quality and quantity of radioactive waste generated and the mode of its disposal. Radiation Safety officer plays a key role in the waste disposal operations. PMID:21475524

Customs control over the transportation of radiation sources and radioactive materials through the frontier of the Republic of Belarus

International Nuclear Information System (INIS)

Derevyashko, A.

1998-01-01

1. As it is shown in the name the main purpose of this Paper is to describe system of customs control over transportation of radiation sources and radioactive materials through the frontier of the Republic of Belarus, clarifying herewith influence of global situation on the creation of this system and noting technical needs of Customs Administration of Belarus in its activities aimed at strengthening the control system. 2. The Republic of Belarus has not the enterprises of atomic-industrial complex and does not produce radioactive and nuclear materials, so, control over them is largely connected with their transit through frontiers of Belarus and its territory. It is necessary to note, that the frontier of Belarus with the Ukraine, Poland and Baltic States is an external frontier of a Custom Union between Belarus, Russia, Kazakhstan and Kirghizia. On the territory of the last three states are concentrated extraction and production of radioactive and nuclear materials, part of which can be transported by the shortest way to the European countries through the territory and frontiers of the Republic of Belarus. 3. The significant part of the republic territory suffered from Chernobyl catastrophe. In a number of the polluted regions of Belarus there were created the zones of >, the residing on them is prohibited by legislation. On those territories there were created numerous burial grounds for the conditionally radioactive and low radioactive wastes. In this connection, there is also a danger of illegal importation of various radioactive wastes from contiguous countries to these zones and burial them there. On the other hand, there are known the numerous cases of exportation of various materials, subjects, food from the polluted zones even out of Belarus. 4. Taking into account the aforesaid the Customs Administration of the Republic of Belarus as well as other public authorities, clearly recognizes the necessity of organization of an effective radiation control on

Measurement of radioactivity in Norway

International Nuclear Information System (INIS)

Berg, T.C.

1988-05-01

A nation-wide network of seven monitoring stations for continuous registration of radioactivity in the air has been established in Norway. Via the telecommunication network, collected data are dayly automatically transmitted to the Norwegian Institute for Air Research (NILU). High radiation levels will trigger an alarm for immediate transmission. The monitoring system and field experiences in connection with its operation are described. NILU's directions in the event of radiation alarm are specified and radiation measurements for 1987 are presented

Application of laser cutting technology to high radiation environments

International Nuclear Information System (INIS)

Pauley, K.A.; Mitchell, M.R.; Saget, S.N.

1996-01-01

A 2 kW Nd:YAG laser system manufactured by the Lumonics Corporation will be used to cut various metals during the fall of 1996 as part of a United States Department of Energy (DOE)-funded technology demonstration at the Hanford Site. The laser cutting demonstration will focus on an evaluation of two issues as the technology applies to the decontamination and decommissioning (D ampersand D) of aging nuclear facilities. An assessment will be made as to the ability of laser end effectors to be operated using electromechanical remote manipulators and the ability of both end effector and fiber optics to withstand the damage created by a high radiation field. The laser cutting demonstration will be conducted in two phases. The first phase will be a non-radioactive test to ensure the ability of hot cell remote manipulators to use the laser end effector to successfully cut the types of materials and geometries found in the hot cell. The second phase will introduce the laser end effector and the associated fiber optic cable into the hot cell radiation environment. The testing in the hot cell will investigate the degradation of the optical portions of the end effector and transmission cable in the high radiation field. The objective of the demonstration is to assess the cutting efficiency and life limitations of a laser cutting system for radioactive D ampersand D operations. A successful demonstration will, therefore, allow the laser cutting technology to be integrated into the baseline planning for the D ampersand D of DOE facilities throughout the nation

mtDNA point and length heteroplasmy in high- and low radiation areas of Kerala

International Nuclear Information System (INIS)

Forster, L.; Forster, P.; Gurney, S.M.; Spencer, M.; Huang, C.; Röhl, A.; Brinkmann, B.

2010-01-01

A coastal peninsula in Kerala (India) contains the world's highest level of natural radioactivity in a densely populated area, offering an opportunity to characterize radiation-associated DNA mutations. Here, we focus on mitochondrial DNA (mtDNA) mutations, which are passed exclusively from the mother to her children. To analyse point mutations, we sampled 248 pedigrees (988 individuals) in the high-radiation peninsula and in nearby low-radiation islands as a control population. Then, in an extended sample of 1,172 mtDNA sequences (containing some non-Indians for comparison), we also analysed length mutations, which in mtDNA can lead to the phenomenon of length heteroplasmy, i.e. the existence of different DNA types in the same cell. We wished to find out how fast mtDNA mutates between generations, and whether the mutation rate is increased in radioactive conditions compared to the low-irradiation sample

Teaching of radiation for elementary and junior high students in Kagoshima and its effects on their radiation literacy

International Nuclear Information System (INIS)

Fukutoku, Yasuo

2009-01-01

Teaching of radiation-related subjects for school children takes an important part in promotion of social radiation literacy; however, the effect of school education on radiation literacy of students, as well as the current status regarding how and when children acquire their knowledge on radiation, have not been elucidated in Japan. In 2005 and 2006, a written surveillance on radiation education was conducted twice in Kagoshima prefecture targeting elementary and junior-high students under the consent of school teachers. Based on the results of these surveillances, the followings were revealed; (1) The elementary and junior-high students receive the information on radiation mainly by the conventional media, including books, television and radio, rather than by school education. (2) More than a half of all junior-high schools are teaching radiation-related subjects, in classes called 'Integrated study', 'Social studies', and 'Science'. (3) The cross tabulation analysis revealed that among the Novel Prize winners on radiation-related fields, 'Pierre and Marie Curie', 'Yukawa' and 'Tomonaga' were recognized by junior-high students by the conventional media, whereas 'Roentgen' and 'Koshiba' appeared to be recognized by school education. (4) Among the scientific terms, junior-high education seems to have some effect on recognition of 'radiation', 'radioactivity' and 'natural radiation'. 'X-rays' was highly recognized, however, the contribution of school education to the recognition was not significant. (5) Among the application examples of radiation, sources other than school education had a large effect on recognition of 'food irradiation', 'sterilization' of medical instruments, 'research on cultural assets' and 'dating', although the recognition was marginal. In contrast, the 'cancer treatment

Proposed classification scheme for high-level and other radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Croff, A.G.

1986-01-01

The Nuclear Waste Policy Act (NWPA) of 1982 defines high-level (radioactive) waste (HLW) as (A) the highly radioactive material resulting from the reprocessing of spent nuclear fuel...that contains fission products in sufficient concentrations; and (B) other highly radioactive material that the Commission...determines...requires permanent isolation. This paper presents a generally applicable quantitative definition of HLW that addresses the description in paragraph B. The approach also results in definitions of other wastes classes, i.e., transuranic (TRU) and low-level waste (LLW). The basic waste classification scheme that results from the quantitative definitions of highly radioactive and requires permanent isolation is depicted. The concentrations of radionuclides that correspond to these two boundaries, and that may be used to classify radioactive wastes, are given

Alternative high-level radiation sources for sewage and waste-water treatment

International Nuclear Information System (INIS)

Ballantine, D.S.

1975-01-01

The choice of an energy source for the radiation treatment of waste-water or sludge is between an electron accelerator or a gamma-ray source of radioactive cobalt or caesium. A number of factors will affect the ultimate choice and the potential future adoption of radiation as a treatment technique. The present and future availability of radioactive sources of cobalt and caesium is closely linked to the rate of nuclear power development and the assumption by uranium fuel reprocessors of a role as radioactive caesium suppliers. Accelerators are industrial machines which could be readily produced to meet any conceivable market demand. For energy sources in the 20-30 kW range, electron accelerators appear to have an initial capital cost advantage of about seven and an operating cost advantage of two. While radioisotope sources are inherently more reliable, accelerators at voltages to 3 MeV have achieved a reliability level adequate to meet the demands of essentially continuous operations with moderate maintenance requirements. The application of either energy source to waste-water treatment will be significantly influenced by considerations of the relative penetration capability, energy density and physical geometrical constraints of each option. The greater range of the gamma rays and the lower energy density of the isotopic sources permit irradiation of a variety of target geometrics. The low penetration of electrons and the high-energy density of accelerators limit application of the latter to targets presented as thin films of several centimetres thickness. Any potential use of radiation must proceed from a clear definition of process objectives and critical comparison of the radiation energy options for that specific objective. (Author)

Radiation doses arising from the air transport of radioactive materials

International Nuclear Information System (INIS)

Gelder, R.; Shaw, K.B.; Wilson, C.K.

1989-01-01

There is a compelling need for the transport of radioactive material by air because of the requirement by hospitals throughout the world for urgent delivery for medical purposes. Many countries have no radionuclide-producing capabilities and depend on imports: a range of such products is supplied from the United Kingdom. Many of these are short lived, which explains the need for urgent delivery. The only satisfactory method of delivery on a particular day to a particular destination is often by the use of scheduled passenger air service. The International Civil Aviation Organization's Technical Instructions for the Safe Transport of Dangerous Goods by Air (ICAO 1987-1988), prescribe the detailed requirements applicable to the international transport of dangerous goods by air. Radioactive materials are required to be separated from persons and from undeveloped photographic films or plates: minimum distances as a function of the total sum of transport indexes are given in the Instructions. A study, which included the measurement and assessment of the radiation doses resulting from the transport of radioactive materials by air from the UK, has been performed by the National Radiological Protection Board (NRPB) on behalf of the Civil Aviation Authority (CAA) and the Department of Transport (DTp)

Radioactivity and foods

International Nuclear Information System (INIS)

Olszyna-Marzys, A.E.

1991-01-01

The purpose of this article is to describe and contrast two relationships between radiation and food on the one hand, beneficial preservation of food by controlled exposure to ionizing radiation; and, on the other, contamination of food by accidental incorporation of radioactive nuclides within the food itself. In food irradiation, electrons or electromagnetic radiation is used to destroy microorganisms and insects or prevent seed germination. The economic advantages and health benefits of sterilizing food in this manner are clear, and numerous studies have confirmed that under strictly controlled conditions no undesirable changes or induced radioactivity is produced in the irradiated food. An altogether different situation is presented by exposure of food animals and farming areas to radioactive materials, as occurred after the major Soviet nuclear reactor accident at Chernobyl. This article furnishes the basic information needed to understand the nature of food contamination associated with that event and describes the work of international organizations seeking to establish appropriate safe limits for levels of radioactivity in foods

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

International Nuclear Information System (INIS)

2002-01-01

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

Risks and management of radiation exposure.

Science.gov (United States)

Yamamoto, Loren G

2013-09-01

High-energy ionizing radiation is harmful. Low-level exposure sources include background, occupational, and medical diagnostics. Radiation disaster incidents include radioactive substance accidents and nuclear power plant accidents. Terrorism and international conflict could trigger intentional radiation disasters that include radiation dispersion devices (RDD) (a radioactive dirty bomb), deliberate exposure to industrial radioactive substances, nuclear power plant sabotage, and nuclear weapon detonation. Nuclear fissioning events such as nuclear power plant incidents and nuclear weapon detonation release radioactive fallout that include radioactive iodine 131, cesium 137, strontium 90, uranium, plutonium, and many other radioactive isotopes. An RDD dirty bomb is likely to spread only one radioactive substance, with the most likely substance being cesium 137. Cobalt 60 and strontium 90 are other RDD dirty bomb possibilities. In a radiation disaster, stable patients should be decontaminated to minimize further radiation exposure. Potassium iodide (KI) is useful for iodine 131 exposure. Prussian blue (ferric hexacyanoferrate) enhances the fecal excretion of cesium via ion exchange. Ca-DTPA (diethylenetriaminepentaacetic acid) and Zn-DTPA form stable ionic complexes with plutonium, americium, and curium, which are excreted in the urine. Amifostine enhances chemical and enzymatic repair of damaged DNA. Acute radiation sickness ranges in severity from mild to lethal, which can be assessed by the nausea/vomiting onset/duration, complete blood cell count findings, and neurologic symptoms.

A low power high speed radiation hard serializer for High Energy Physics experiments

CERN Document Server

AUTHOR|(CDS)2080243; Marchioro, Alessandro; Ottavi, Marco

This Ph.D. thesis focuses on the development and the characterization of novel solutions for electronic systems for high-speed data transmission in extremely high radio-active environment (e.g. high energy physics application). The text proposes two alternative full-custom solutions for a fundamental enabling block for a lowpower serial data transmission system, the serializer. This block will find place in a future transceiver conceived for the future upgraded phase of the Large Hadron Collider, or LHC, at CERN. The first solution proposed, called “triple module redundancy”, is based on hardware redundancy, a well-known solution, to obtain protection against the temporary malfunctioning induced by radiation. In the second case a new architecture, called “code protected”, is proposed. This architecture takes advantage of the error correction code present in the data word to obtain radiation robustness on data and some parts of the control logic and to further reduce the power consumption. A test chip ...

Radiation Protection and Radioactive Waste Management in the Operation of Nuclear Power Plants. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

The purpose of this Safety Guide is to provide recommendations to the regulatory body, focused on the operational aspects of radiation protection and radioactive waste management in nuclear power plants, and on how to ensure the fulfilment of the requirements established in the relevant Safety Requirements publications. It will also be useful for senior managers in licensee or contractor organizations who are responsible for establishing and managing programmes for radiation protection and for the management of radioactive waste. This Safety Guide gives general recommendations for the development of radiation protection programmes at nuclear power plants. The issues are then elaborated by defining the main elements of a radiation protection programme. Particular attention is paid to area classification, workplace monitoring and supervision, application of the principle of optimization of protection (also termed the 'as low as reasonably achievable' (ALARA) principle), and facilities and equipment. This Safety Guide covers all the safety related aspects of a programme for the management of radioactive waste at a nuclear power plant. Emphasis is placed on the minimization of waste in terms of both activity and volume. The various steps in predisposal waste management are covered, namely processing (pretreatment, treatment and conditioning), storage and transport. Releases of effluents, the application of authorized limits and reference levels are discussed, together with the main elements of an environmental monitoring programme

Report on the legislation in the field of nuclear safety and regulatory control of radiation sources and radioactive materials in Yugoslavia

International Nuclear Information System (INIS)

Kolundzija, V.

2001-01-01

The national regulatory infrastructure in Yugoslavia is described in the report, including the legal framework governing the safety of radiation sources and the security of radioactive materials. The organization and competencies of the Yugoslav Nuclear Safety Administration are explained, in particular regarding the national system of notification, registration, licensing, inspection and enforcement of radiation sources and radioactive materials, where the Federal Ministry of Economy and the Federal Ministry of Labour, Health and Social Policy are sharing competencies. Finally, the report refers to the national provisions on the management of disused sources; on planning, preparedness and response to abnormal events and emergencies; on the recovery of control over orphan sources; and on the education and training in the safety of radiation sources and the security of radioactive materials. (author)

The research status of induced radioactivity in accelerator facilities

International Nuclear Information System (INIS)

Lu Feng; Deng Daping

2005-01-01

The hazards of subsequent-radiation produced by high-energy accelerator must be no ignore. The principle of induced radioactivity and the hazards to the people were introduced in this article. The radiation levels around the treatment head and in the air of the treatment room were discussed thor-oughly. Some effects of the induced radioactivity were also mentioned. At last, the article talks about some problems in present researches and some directions for the following study. (authors)

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

International Nuclear Information System (INIS)

Klevinskas, G.; Mastauskas, A.

2001-01-01

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

Determination of 90Sr in radioactive liquid waste-a comparative study using 'SrCO3 precipitation, extraction chromatography and Cerenkov radiation counting' techniques

International Nuclear Information System (INIS)

Mani, A.G.S.; Renganathan, K.; Rao, S.V.S.; Sinha, P.K.

2007-01-01

In the wastes generated at nuclear power plants, 90 Sr and 90 Y are responsible for approximately 7% and 38% of the total fission product activity after 1 year and 10 years respectively. Monitoring of the liquid waste produced in nuclear facilities for 90 Sr before and after releasing to the aquatic environment is essential, as it can cause a long term biological hazard due to its chemical similarity with Ca, high fission yield (5.9%) and long radioactive and biological half lives of 28 and 49.3 years respectively. As conventional carbonate precipitation method for 90 Sr- 90 Y estimation is laborious and time consuming, the other methods like extraction chromatography technique using strontium selective crown ether and Cerenkov radiation counting by liquid scintillation analyser (LSA) were also investigated. This paper describe procedures involved in the estimation of strontium in low-level radioactive liquid effluent by using above methods and deals with the comparison of results. Cerenkov radiation counting by LSA has an edge over the other methods in the determination of 90 Sr as it is a simple and rapid technique. Experiences gained in the estimation of 90 Sr in low-level radioactive liquid effluent using Cerenkov radiation counting technique is discussed in detail in this paper. (author)

High polymer-based composites for the fabrication of containers for the long-term storage or disposal of high-level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Miedema, I.; Bonin, H.W.; Bui, V.T. [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)

2002-07-01

This study considers the application of PEEK and continuous graphite fibre composite as the principal component in a high level nuclear waste disposal container. The ultimate radioactive environment to which the containers will be exposed has been simulated using a SLOWPOKE-2 research nuclear reactor and a specialized heated irradiation chamber. Doses of up to 1 MGy were given to samples in combination with elevated temperatures (15{sup o}C to 75{sup o}C), which induced mechanical and chemical changes in the material. Mechanically, the composite and virgin polymer samples were minimally affected, rarely deviating beyond one standard deviation of the properties of unirradiated samples. Molecularly, crosslinking between adjacent polymer chains in the amorphous region is the primary observed phenomenon as a consequence of the radiation treatment. This effect is diminished with the application of heat during irradiation. Slight changes in crystallinity were also noted through molecular rearrangement, beginning with slight increases at lower radiation doses, and then minor decreases are noted with larger doses ({approx}10{sup 6} Gy). It is also shown in this study that the rate of radiation effects that is typical in this polymer is dependent on the temperature of irradiation. The results confirm that polymer-based composite materials, such as the PEEK/graphite fibre material studied here, are excellent candidates for the fabrication of the containers for the disposal of high-level radioactive waste. (author)

A study on radiation shield design of storage facility for low and intermediate level radioactive waste in Bangladesh

International Nuclear Information System (INIS)

Khan, JJahirul Haque

2005-02-01

Bangladesh has no nuclear power reactor but has only one 3 MW TRIGA Mark-II Research Reactor. The Bangladesh Atomic Energy commission (BAEC) operates a 3 MW TRIGA Mark-II Research Reactor and maintains not only the nuclear facilities at its Atomic Energy Research Establishment (AERE) at Savar (near Dhaka) but also the related radiation facilities the whole country. The main sources of radioactive wastes result from the use of sealed and unsealed radiation sources in medicine industry, research, agriculture, etc as well as from operation and maintenance of the nuclear facilities the whole country. As a result radioactive wastes are increasing day by day and these wastes are classified as low and intermediate level radioactive waste (LILW) following the radiation safety philosophy of IAEA recommendations in Bangladesh. Radioactive waste is very sensitive issue to public and environment from the hazardous standpoint of ionizing radiation. Therefore, storage facility of LILW is very essential for safe radioactive waste management in Bangladesh and in parallel: this study is of a great importance due to new installation of this storage facility in future. The basic objective of this study is to recommend the radiation shield design parameters of the installation of storage facility for low and intermediate level radioactive waste from the points of view of radiation safety and sensitivity analysis. The shield design of this installation has been carried out with the Monte Carlo Code MCNP4C and the point Kernel Code Micro Shield 5.05 respectively considering the ICRP-60 (1990) recommendations for occupational exposure limit (10 μ Sv/hr). For more safety purpose every equivalent dose rate at different positions of this installation is considered below 9 μ Sv/hr in this study. The radiation shield design parameters are recommended based on MCNP4C calculated results than those of Micro Shield due to more credible results and these parameters are: (I) 51 cm thickness of

Radiation safety for incineration of radioactive waste contaminated by cesium

International Nuclear Information System (INIS)

Veryuzhs'kij, Yu.V.; Gryin'ko, O.M.; Tokarevs'kij, V.V.

2016-01-01

Problems in the treatment of radioactive waste contaminated by cesium nuclides are considered in the paper. Chornobyl experience in the management of contaminated soil and contaminated forests is analyzed in relation to the accident at Fukushima-1. The minimization of release of cesium aerosols into atmosphere is very important. Radiation influence of inhaling atmosphere aerosols polluted by cesium has damage effect for humans. The research focuses on the treatment of forests contaminated by big volumes of cesium. One of the most important technologies is a pyro-gasification incineration with chemical reactions of cesium paying attention to gas purification problems. Requirements for process, physical and chemical properties of treatment of radioactive waste based on the dry pyro-gasification incineration facilities are considered in the paper together with the discussion of details related to incineration facilities. General similarities and discrepancies in the environmental pollution caused by the accidents at Chornobyl NPP and Fukushima-1 NPP in Japan are analyzed

Testing of Air Pulse Agitators to Support Design of Savannah River Site Highly Radioactive Processing at the Salt Waste Processing Facility

International Nuclear Information System (INIS)

Gallego, R.M.; Stephens, A.B.; Wilkinson, R.H.; Dev, H.; Suggs, P.C.

2006-01-01

The Salt Waste Processing Facility (SWPF) is intended to concentrate the highly radioactive constituents from waste salt solutions at the Savannah River Site (SRS). Air Pulse Agitators (APAs) were selected for process mixing in high-radiation locations at the SWPF. This technology has the advantage of no moving parts within the hot cell, eliminating potential failure modes and the need for maintenance within the high-radiation environment. This paper describes the results of APA tests performed to gain operational and performance data for the SWPF design. (authors)

Attainment of radiation equivalency in nuclear power plant radioactive product management

International Nuclear Information System (INIS)

Adamov, E.O.; Ganev, I.Kh.; Orlov, V.V.

1992-01-01

Basic provisions for radiation equivalent radioactive waste disposal are formulated and conditions for its realization are considered. They include simultaneous removal of uranium and long-living products of its decay from the ore, separation of actinides from the fuel in the course of chemical reprocessing for burning in reactors, and possibly strontium and cesium with the purpose of their useful utilization and long-term controlled waste storage in the near-surface facilities

Spotting Radioactive Sources Buried Underground Using an Airborne Radiation Monitoring System

International Nuclear Information System (INIS)

Sheinfeld, M.; Wengrowicz, U.; Beck, A.; Marcus, E.; Tirosh, D.

2002-01-01

This article provides theoretical background concerning the capability of the Airborne Radiation Monitoring System [1]to detect fission products buried at 1-meter depth under the ground surface,at a flight altitude of 100 meters above ground.The 137 Cs source was used as a typical fission product. The System monitors radioactive contamination in the air or on the ground using two 2 inch NaI(Tl) scintillation detectors and computerized accessories for analysis purposes

Radioactivity measurement

International Nuclear Information System (INIS)

Bohme, R.F.; Lazerson, M.M.

1984-01-01

A problem with ore sorting arrangements is that radiation is difficult to measure accurately while particles are moving at speed past the detector. This is particulary so when dealing with ores such as gold ores which have weak emissions. A method of measuring radioactive emissions from moving radioactive material includes the steps of shielding the radiation detector(s) so that the angle of acceptance of the receptor surface is restricted, and further shielding the shielded portion of the detector with a second material which is less radiation emissive than the material of the first shield. This second shield is between the first shield and the detector

Radioactive material accidents in the transport

International Nuclear Information System (INIS)

Rodrigues, D.L.; Magalhaes, M.H.; Sanches, M.P.; Sordi, G.M.A.A.

2008-01-01

Transport is an important part of the worldwide nuclear industry and the safety record for nuclear transport across the world is excellent. The increase in the use of radioactive materials in our country requires that these materials be moved from production sites to the end user. Despite the number of packages transported, the number of incidents and accidents in which they are involved is low. In Brazil, do not be records of victims of the radiation as a result of the transport of radioactive materials and either due to the accidents happened during the transports. The absence of victims of the radiation as result of accidents during the transports is a highly significant fact, mainly to consider that annually approximately two hundred a thousand packages containing radioactive material are consigned for transport throughout the country, of which eighty a thousand are for a medical use. This is due to well-founded regulations developed by governmental and intergovernmental organizations and to the professionalism of those in the industry. In this paper, an overview is presented of the activities related to the transport of radioactive material in the state of Sao Paulo. The applicable legislation, the responsibilities and tasks of the competent authorities are discussed. The categories of radioactive materials transported and the packaging requirements for the safe transport of these radioactive materials are also described. It also presents the packages amounts of carried and the accidents occurred during the transport of radioactive materials, in the last five years. The main occurred events are argued, demonstrating that the demanded requirements of security for any transport of radioactive material are enough to guarantee the necessary control of ionizing radiation expositions to transport workers, members of general public and the environment. (author)

Radioactivity

International Nuclear Information System (INIS)

2002-01-01

This pedagogical document presents the origin, effects and uses of radioactivity: where does radioactivity comes from, effects on the body, measurement, protection against radiations, uses in the medical field, in the electric power industry, in the food (ionization, radio-mutagenesis, irradiations) and other industries (radiography, gauges, detectors, irradiations, tracers), and in research activities (dating, preservation of cultural objects). The document ends with some examples of irradiation levels (examples of natural radioactivity, distribution of the various sources of exposure in France). (J.S.)

New challenge for the radiation protection: devices for the radioactivity dispersion

International Nuclear Information System (INIS)

Mora, J. C.; Robles, B.; Cancio, C.

2006-01-01

In recent years the terrorist attacks produced in several countries have changed the mind of the security experts. This has also included the Radiation Protection aspects. Newly considered features have required the update of emergency response and preparedness, ad well as a greater emphasis on security. Within the Radiation Protection field has been introduced the radiological and nuclear terrorism definition. almost every organism and research centre involved in Radiation Protection is nowadays working on. The possible terrorist attack scenarios have already been defined and the use of an explosive to disperse radioactive material, known as a Radiation Dispersion Devices (RDD), has been specified as the most probable one. Studies to mitigate against the chance of attack and to mitigate the consequences of any attack with a RDD are complex, due to the innovation that introduce. This leads to a need to take some immediate preventative actions and to carry out additional R and D efforts. This document presents some considerations on the possible RDD design and behaviour in order to prevent and prepare against a possible attack. (Author) 17 refs

Doses of radiation from natural and artificial radioactive sources. [In German

Energy Technology Data Exchange (ETDEWEB)

Franzen, L F; Myszynski, G; Wiesenack, G

1957-01-01

Only since quite recently has man been subjected to irradiation which, as the result of medical and industrial development has been added to the radiation from natural sources. According to the investigations quoted artificial radiation accounts for 20 to 25 per cent of the total radiation level. Atomic test explosions have so far only made an insignificant contribution. The same can still be said of the industrial application of nuclear energy which is still in its infancy. It has been estimated that people living in Europe will over a period of 30 years be subjected to a total dose of radiation from 2500 to 4000 mr. Of this total dose received in 30 years about 750 to 850 mr will be contributed by medical and industrial appurtenances, the overwhelming share of 600 to 700 mr being the result of medical x-ray diagnosis. The atmospheric radioactivity has been estimated (incl. rainfall, etc.) at 20 to 30 mr over a period of 30 years and will therefore not represent any hazards as far as external, direct radiation is concerned. The possible absorption by and accumulation of radiation substances in the body must, however, be carefully studied and special consideration must be given to fission products with a long half-life.

Radioactivity and Environment

International Nuclear Information System (INIS)

Sanchez Leon, J.G.

1993-01-01

Radioactivity is one of the most studied natural phenomena. Most of irradiation suffered by the human being is produced by natural sources. The second source in order of importance is nuclear medicine. The average level of radiation received by the man is 2.4 mSv/year and this value can be modified naturally in 20-30%. The author provides a review on radioactivity sources like natural (cosmic rays, extraterrestrial radiation, internal earth radiation, radon) and artificial (Nuclear explosions, professional exposure, nuclear medicine, nuclear power plants and accidents)

Natural radioactivity in mining and hydrocarbon extraction industry. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

Testa, C; Desideri, D; Meli, M A; Roselli, C [General Chemistry Institute, Urbino University, 61029 Urbino, (Italy)

1996-03-01

Water and soil natural radioactivity is a well known phenomenon which can produced by variable concentrations of uranium and thorium series radionuclides. Generally, the relevant radiological hazard is not important; however, some radiation protection problems can occur in particular industrial processes involving the treatment of large quantities of materials. In this case a high concentration of radioactive substance (NORM: nationally occurring radioactive materials) can be found at special points of the plant, in the manufacture by-products and in the waters. Sometimes the national radioactivity concentration can be so high to raise radiation protection problems which can be assimilated in a sense to the ones faced in the presence, handling, and disposal of non-sealed radioactive sources. In this paper the following mining and hydrocarbon extraction plants were particularly taken into account: (a) industries using zircon sands to produce refractory and ceramic materials; (b) phosphorites manufacture to prepare phosphoric acids, plasters and fertilizers (c) hydrocarbon extraction and treatment processes where formations of low specific activity (L.S.A.) scales and sludges are produced. The relevant results and the possible radiation protection risks for the professional exposed staff will be reported. A special emphasis will be given to some african phosphorites (boucraa, togo, morocco), and L.S.A. scales (tunisia, congo, Egypt). 4 figs., 5 tabs.

Natural radioactivity in mining and hydrocarbon extraction industry. Vol. 1

International Nuclear Information System (INIS)

Testa, C.; Desideri, D.; Meli, M.A.; Roselli, C.

1996-01-01

Water and soil natural radioactivity is a well known phenomenon which can produced by variable concentrations of uranium and thorium series radionuclides. Generally, the relevant radiological hazard is not important; however, some radiation protection problems can occur in particular industrial processes involving the treatment of large quantities of materials. In this case a high concentration of radioactive substance (NORM: nationally occurring radioactive materials) can be found at special points of the plant, in the manufacture by-products and in the waters. Sometimes the national radioactivity concentration can be so high to raise radiation protection problems which can be assimilated in a sense to the ones faced in the presence, handling, and disposal of non-sealed radioactive sources. In this paper the following mining and hydrocarbon extraction plants were particularly taken into account: a) industries using zircon sands to produce refractory and ceramic materials; b) phosphorites manufacture to prepare phosphoric acids, plasters and fertilizers c) hydrocarbon extraction and treatment processes where formations of low specific activity (L.S.A.) scales and sludges are produced. The relevant results and the possible radiation protection risks for the professional exposed staff will be reported. A special emphasis will be given to some african phosphorites (boucraa, togo, morocco), and L.S.A. scales (tunisia, congo, Egypt). 4 figs., 5 tabs

Measuring radioactivity in the body

Energy Technology Data Exchange (ETDEWEB)

NONE

1961-09-15

Techniques of measuring the total amount of radioactivity in the body of a living person as well as the principal applications of such measurements were reviewed at a Symposium on Whole Body Counting held in Vienna from 12 to 16 June 1961. The whole body counters can be divided into two broad groups: (a) counters for the radiation protection surveillance of the general public and radiation workers, capable of detecting extremely low levels of radioactivity in the human body, and (b) counters for medical research and diagnosis, designed to check the retention and excretion of radioactive substances administered to patients for metabolic and pathological studies. In both cases, the primary requirement is that the counter must be able to measure the total activity in the body. In recent years, there has been a remarkable development of the instruments and techniques for such measurements. One of the main purposes of the symposium in Vienna was to discuss how best to use these highly sophisticated instruments.

Studies of high-level radioactive waste form performance at Japan Atomic Energy Research Institute

International Nuclear Information System (INIS)

Banba, Tsunetaka; Kamizono, Hiroshi; Mitamura, Hisayoshi

1992-02-01

The recent studies of high-level radioactive waste form at Japan Atomic Energy Research Institute can be classified into the following three categories; (1) Study on the leaching behavior of the nuclear waste glass placing the focus on the alteration layer and the chemical composition of leachant for the prediction of the long-term corrosion of the waste glass. (2) Study on the radiation (alpha-radiation) effects which have relation to the long-term stability of the nuclear waste glass. (3) Study on the long-term self-irradiation damage of a SYNROC waste form using a curium-doped sample. In the present report, the recent results corresponding to the above categories are described. (author)

Exposure to radiation from the natural radioactivity in building materials

International Nuclear Information System (INIS)

1979-05-01

Radiation exposure of members of the public can be increased appreciably by the use of building materials containing above-normal levels of natural radioactivity. This phenomenon has attracted attention in recent years, and in this review, an attempt is made to the quantify exposures incurred under various circumstances. The second section of the review is a general survey of those building materials, mostly industrial wastes, that have aroused interest in Member countries. The probability that environmental pressures may cause such wastes to be used more and more by building industries may lead to similar situations in the future. Other review material of a relevant nature is described in the third section. Primordial radionuclides only are considered here. They are: potassium-40 (K-40); radium-226 (Ra-226) and its decay products; the series headed by thorium-232 (Th-232). The important radiological consequences of the natural radioactivity in building materials are two-fold, irradiation of the body by gamma rays and irradiation of the lung tissues by radon-222 (Rn-222) decay products or daughters. These consequences cannot be explored quantitatively except in relation to the specific activities of the nuclides of interest, and the approach adopted in this review is to assess the consequences in terms of the incremental radiation exposures that would be incurred by occupants of substantial dwellings entirely constructed of materials with various specific activities or combinations thereof. Gamma rays are dealt with in the fourth section and radon daughters in the fifth

Understanding radioactive waste

International Nuclear Information System (INIS)

Murray, R.L.

1989-01-01

This book discusses the sources and health effects of radioactive wastes. It reveals the techniques to concentrate and immobilize radioactivity and examines the merits of various disposal ideas. The book, which is designed for the lay reader, explains the basic science of atoms,nuclear particles,radioactivity, radiation and health effects

Assessment of natural radioactivity and associated radiation indices in soil samples from the high background radiation area, Kanyakumari district, Tamil Nadu, India

Directory of Open Access Journals (Sweden)

A K Ajithra

2017-01-01

Full Text Available Assessment of natural radioactivity is very important from different points of view, especially for assessment of radiation exposure to human. In the present study, natural radionuclide concentrations of 238U, 232Th, and 40K were measured by gamma spectrometry using HPGe detector in soil samples collected from Southwest coast of Kanyakumari district, Tamil Nadu. The radiological index parameters due to natural radionuclides such as radium equivalent activity, absorbed dose rate, annual effective dose rate, external hazard index, internal hazard index, and gamma index were calculated for the soil samples. All the calculated radiological index values are higher than world average values and the recommended safety limits. Multivariate statistical techniques such as Pearson correlation, principal component analysis, and cluster analysis were applied to know the relation between radionuclides and radiological parameters and to study the spatial distribution of radionuclides.

In situ investigations on the impact of heat production and gamma radiation with regard to high-level radioactive waste disposal in rock salt formations

International Nuclear Information System (INIS)

Rothfuchs, T.

1986-01-01

Deep geological formations especially rock salt formations, are considered worldwide as suitable media for the final disposal of radioactive high-level waste (HLW). In the Federal Republic of Germany, the Institut fur Tieflagerung of the Gesellschaft fur Strahlen- und Umweltforschung mbH Munchen operates the Asse Salt Mine as a pilot facility for testing the behavior of an underground nuclear waste repository. The tests are performed using heat and radiation sources to simulate disposed HLW canisters. The measured data obtained since 1965 show that the thermomechanical response of the salt formation and the physical/chemical changes in the vicinity of disposal boreholes are not a serious concern and that their long-term consequences can be estimated based on theoretical considerations and in-situ investigations

Radiation protection. Scientific fundamentals, legal regulations, practical applications. Compendium

International Nuclear Information System (INIS)

Buchert, Guido; Gay, Juergen; Kirchner, Gerald; Michel, Rolf; Niggemann, Guenter; Schumann, Joerg; Wust, Peter; Jaehnert, Susanne; Strilek, Ralf; Martini, Ekkehard

2011-06-01

The compendium on radiation protection, scientific fundamentals, legal regulations and practical applications includes contributions to the following issues: (1) Effects and risk of ionizing radiation: fundamentals on effects and risk of ionizing radiation, news in radiation biology, advantages and disadvantages of screening investigations; (2) trends and legal regulations concerning radiation protection: development of European and national radiation protection laws, new regulations concerning X-rays, culture and ethics of radiation protection; (3) dosimetry and radiation measuring techniques: personal scanning using GHz radiation, new ''dose characteristics'' in practice, measuring techniques for the nuclear danger prevention and emergency hazard control; (4) radiation exposure in medicine: radiation exposure of modern medical techniques, heavy ion radiotherapy, deterministic and stochastic risks of the high-conformal photon radiotherapy, STEMO project - mobile CT for apoplectic stroke patients; (5) radiation exposure in technology: legal control of high-level radioactive sources, technical and public safety using enclosed radioactive sources for materials testing, radiation exposure in aviation, radon in Bavaria, NPP Fukushima-Daiichi - a status report; (6) radiation exposure in nuclear engineering: The Chernobyl accident - historical experiences or sustaining problem? European standards for radioactive waste disposal, radioactive material disposal in Germany risk assessment of ionizing and non-ionizing radiation (7) Case studies.

Radioactive decay data tables: A handbook of decay data for application to radiation dosimetry and radiological assessments

Science.gov (United States)

Kocher, D. C.; Smith, J. S.

Decay data are presented for approximately 500 radionuclides including those occurring naturally in the environment, those of potential importance in routine or accidental releases from the nuclear fuel cycle, those of current interest in nuclear medicine and fusion reactor technology, and some of those of interest to Committee 2 of the International Commission on Radiological Protection for the estimation of annual limits on intake via inhalation and ingestion for occupationally exposed individuals. Physical processes involved in radioactive decay which produce the different types of radiation observed, methods used to prepare the decay data sets for each radionuclide in the format of the computerized evaluated nuclear structure data file, the tables of radioactive decay data, and the computer code MEDLIST used to produce the tables are described. Applications of the data to problems of interest in radiation dosimetry and radiological assessments are considered as well as the calculations of the activity of a daughter radionuclide relative to the activity of its parent in a radioactive decay chain.

Proposal for basic safety requirements regarding the disposal of high-level radioactive waste

International Nuclear Information System (INIS)

1980-04-01

A working group commissioned to prepare proposals for basic safety requirements for the storage and transport of radioactive waste prepared its report to the Danish Agency of Environmental Protection. The proposals include: radiation protection requirements, requirements concerning the properties of high-level waste units, the geological conditions of the waste disposal location, the supervision of waste disposal areas. The proposed primary requirements for safety evaluation of the disposal of high-level waste in deep geological formations are of a general nature, not being tied to specific assumptions regarding the waste itself, the geological and other conditions at the place of disposal, and the technical methods of disposal. It was impossible to test the proposals for requirements on a working repository. As no country has, to the knowledge of the working group, actually disposed of hifg-level radioactive waste or approved of plans for such disposal. Methods for evaluating the suitability of geological formations for waste disposal, and background material concerning the preparation of these proposals for basic safety requirements relating to radiation, waste handling and geological conditions are reviewed. Appended to the report is a description of the phases of the fuel cycle that are related to the storage of spent fuel and the disposal of high-level reprocessing waste in a salt formation. It should be noted that the proposals of the working group are not limited to the disposal of reprocessed fuel, but also include the direct disposal of spent fuel as well as disposal in geological formations other than salt. (EG)

Radioactive waste management from nuclear facilities

International Nuclear Information System (INIS)

2005-06-01

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

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

International Nuclear Information System (INIS)

Moriyama, Yoshinori

1998-01-01

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

High-Level Radioactive Waste.

Science.gov (United States)

Hayden, Howard C.

1995-01-01

Presents a method to calculate the amount of high-level radioactive waste by taking into consideration the following factors: the fission process that yields the waste, identification of the waste, the energy required to run a 1-GWe plant for one year, and the uranium mass required to produce that energy. Briefly discusses waste disposal and…

High-level radioactive wastes

International Nuclear Information System (INIS)

Grissom, M.C.

1982-10-01

This bibliography contains 812 citations on high-level radioactive wastes included in the Department of Energy's Energy Data Base from January 1981 through July 1982. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

The radioactive materials decree and the radiation apparatus decree in the nuclear energy law

International Nuclear Information System (INIS)

Vlaskamp, L.

1982-01-01

A short introduction is presented to the new sets of regulations concerning the use of radioactive materials and work with apparatuses producing ionising radiations, which were drawn up to bring the Netherlands' Regulations in agreement with the Euratom basic standards. Appendices contain a survey of the new units to be used, the regulations as proposed, the Euratom category classification, a global Dutch one, a list of concepts and notions, and a table of old and new units in radiation protection programmes. (Auth.)

Radiation in everyday life

International Nuclear Information System (INIS)

Wahlstroem, B.

1994-01-01

The world is radioactive. Radioactive substances and radiation existed on Earth before the first man was born. Radiation reaches man from the cosmos and is also emitted from radioactive substances in the ground, in construction material, in the food and the air. All people are radioactive, too. For instance, all people have got radioactive Radium and Polonium in their skeleton, radioactive Carbon and Potassium in their muscles and radioactive noble gases and Tritium in their lungs. The radiation emitted by the body can be measured by a very sensitive radiation meter called a Whole Body Counter. This paper is a discussion of natural radioactivity and the increased exposure to radiations released by energy production and medical testing

Outlook of the accident at Fukushima No.1 Nuclear Power Plants and issues concerning radioactive materials in environments

International Nuclear Information System (INIS)

Tanaka, Shun-ichi

2011-01-01

Fukushima No.1 Nuclear Power Plants (NPPs) affected by a great earthquake finally suffered reactor core meltdown with loss of all cooling capability and discharged a large amount of radioactive materials to the environment. Local areas in the northwest direction from NPPs were highly contaminated with radioactive materials. In order to reduce radiation exposure, several kinds of decontamination works had been tested in contaminated areas of primary school and kindergarten or residential houses with no evacuation. Radiation mini-hotspots were scattered. Contaminated soils and rubbles having cesium of high concentration in the order of several ten or hundreds kBq/kg were accumulated in large amounts of radioactive wastes and their disposal became a big issue. Related safety guidelines were proposed based on radioactive waste disposal for nuclear facilities as well as radiation dose control of neighboring residents and disposal workers, which would not be applicable to current state of Fukushima in a high radiation background. Establishment of new radiation protection rule was highly needed to deal with this emergency based on reality within and outside the Fukushima NPPs. (T. Tanaka)

Environmental radioactivity survey in Andong

Energy Technology Data Exchange (ETDEWEB)

Yoon, Zi Hong; Jo, Kum Ju [Andong Regional Radioactivity Monitoring Station, Andong National Univ., Andong (Korea, Republic of)

2003-12-15

The objectives of the project are to monitor an abnormal level in Andong area and to provide a base line data on environmental radiation/radioactivity levels in case of any radiological emergency situation. The project is important in view of protecting the public health from the potential hazards of radiation and keeping up the clean environment. This report simonizes and interprets environmental radiation/radioactivity monitoring samples : Gamma exposure rates, airborne dust, precipitation, fall out and drinking-water. Environmental samples 2 kinds of indicator plant, 4 kinds of mushroom, 7 kinds of nut and seeds, and drinking waters. Among the all 2003 radiological monitoring and environmental data in Andong area were not found the extraordinary data. And a nation-wide environmental radiation/radioactivity level survey results were all background levels attributed to terrestrial and cosmic radiation.

Environmental radioactivity survey in Andong

Energy Technology Data Exchange (ETDEWEB)

Yoon, Zi Hong; Jo, Kum Ju [Andong Regional Radioactivity Monitoring Station, Andong National Univ., Andong (Korea, Republic of)

2002-12-15

The objectives of the project are to monitor an abnormal level in Andong area and to provide a base-line data on environmental radiation/radioactivity levels in case of any radiological emergency situation. The project is important in view of protecting the public health from the potential hazards of radiation and keeping up the clean environment. This report summarizes and interprets environmental radiation/radioactivity monitoring samples Gamma exposure rates, airborne dust, precipitation, fall-out and drinking-water. Environmental samples 2 kinds of indicator plant, 4 kinds of mushroom, 7 kinds of nut and seeds, and drinking waters. Among the all 2002 radiological monitoring and environmental data in Andong area were not found the extraordinary data. And a nation-wide environmental radiation/radioactivity level survey results were all background levels attributed to terrestrial and cosmic radiation.

Radiation hygienic annual report 2012. General environmental radioactivity and radiation surveillance in the vicinity of nuclear facilities in Bavaria

International Nuclear Information System (INIS)

Pfau, T.; Bernkopf, J.; Klement, R.; Bayerisches Landesamt fuer Umwelt, Augsburg

2013-01-01

The radiation hygienic annual report 2012 includes the following issues: (1) Introduction: Legal aspects of the surveillance, implementation of the radiation protection law, nuclear facility sites in Bavaria, interim storage facilities in Bavaria. (2) Natural radioactivity surveillance: measured data for the exposure paths air, water, food chain land, food chain water, residuals and waste. (3) Radiation surveillance in the vicinity of nuclear facilities in Bavaria: measures for air, precipitation, soils, plants, food chain land, milk and milk products, surface water, food chain water, drinking and ground water; measured data in the vicinity of NNP Isar 1 bd Isar 2 (KKI1/KKI2), NPP Gundremmingen (KGG), NPP Grafenrheinfeld (KKG), research neutron source Muenchen FRM II; emissions, meteorological conditions, spreading calculations.

Radioactivity content of books

International Nuclear Information System (INIS)

Lalit, B.Y.; Shukla, V.K.; Ramachandran, T.V.

1981-01-01

The natural and fallout radioactivity was measured in a large number of books produced in various countries after 1955. Results of these measurements showed that the books contained radioactivity due to fallout 137 Cs and 226 Ra, 228 Th and 40 K radioisotopes of primordial origin. Books printed in the U.S.A. had low radioactivity of 40K and 226 Ra origin compared to books printed in the European subcontinent. Books printed during high fallout rate (1962-64) or thereafter did not exhibit any significantly higher 137 Cs levels. The maximum radiation dose to the eyes calculated for the radioactivity content of the books was 0.8 μR/hr and the minimum was 0.07 μR/hr; most of the books were in the range 0.3-0.5 μR/hr. (U.K.)

Radioactive Materials in Medical Institutions as a Potential Threat

International Nuclear Information System (INIS)

Radalj, Z.

2007-01-01

In numerous health institutions ionizing sources are used in everyday practice. Most of these sources are Roentgen machines and accelerators which produce radiation only when in use. However, there are many institutions, e.g., Nuclear medicine units, where radioactive materials are used for diagnostic and therapeutic purposes. This institutions store a significant amount of radioactive materials in form of open and closed sources of radiation. Overall activity of open radiation sources can reach over a few hundred GBq. Open sources of radiation are usually so called short-living isotopes. Since they are used on daily basis, a need for a continuous supply of the radioactive materials exists (on weekly basis). Transportation phase is probably the most sensitive phase because of possible accidents or sabotage. Radiological terrorism is a new term. Legislation in the area of radiological safety is considered complete and well defined, and based on the present regulatory mechanism, work safety with radiation sources is considered relatively high. However, from time to time smaller accidents do happen due to mishandling, loose of material (possible stealing), etc. Lately, the safety issue of ionizing sources is becoming more important. In this matter we can expect activities in two directions, one which is going towards stealing and 'smuggling' of radioactive materials, and the other which would work or provoke accidents at the location where the radiation sources are.(author)

Radioactivity and foods

International Nuclear Information System (INIS)

Olszyna Marzys, A.E.

1991-01-01

The purpose of this article is to describe and contrast two relationships between radiation and food-on the one hand, beneficial preservation of food by controlled exposure to ionizing radiation; and, on the other, contamination of food by accidental incorporation of radioactive nuclides within the food itself. In food irradiation, electrons or electromagnetic radiation is used to destroy microorganisms and insects or prevent seed germination. The economic advantages and health benefits of sterilizing food in this manner are clear, and numerous studies have confirmed that under strictly controlled conditions no undesirable changes or induced radioactivity is produced in the irradiated food. An altogether different situation is presented by exposure of food animals and farming areas to radioactive materials, as occurred after the major Soviet nuclear reactor accident at Chernobyl. This article furnishes the basic information needed to understand the nature of food contamination associated with that event and describes the work of international organizations seeking to establish appropriate safe limits for levels of radioactivity in foods. 14 refs, 4 tabs

Working safely with radioactive materials

International Nuclear Information System (INIS)

Davies, Wynne

1993-01-01

In common with exposure to many other laboratory chemicals, exposure to ionising radiations and to radioactive materials carries a small risk of causing harm. Because of this, there are legal limits to the amount of exposure to ionising radiations at work and special rules for working with radioactive materials. Although radiation protection is a complex subject it is possible to simplify to 10 basic things you should do -the Golden Rules. They are: 1) understand the nature of the hazard and get practical training; 2) plan ahead to minimise time spent handling radioactivity; 3) distance yourself appropriately from sources of radiation; 4) use appropriate shielding for the radiation; 5) contain radioactive materials in defined work areas; 6) wear appropriate protective clothing and dosimeters; 7) monitor the work area frequently for contamination control; 8) follow the local rules and safe ways of working; 9) minimise accumulation of waste and dispose of it by appropriate routes, and 10) after completion of work, monitor, wash, and monitor yourself again. These rules are expanded in this article. (author)

Radioactive waste treatment and handling in France

International Nuclear Information System (INIS)

Sivintsev, Yu.V.

1984-01-01

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

An assessment of overseas developments in methods for treatment and disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Costello, J.M.

1982-10-01

The principles of management and disposal of highly radioactive wastes contained in spent fuel from nuclear power generation are described. The status of developments in spent fuel reprocessing, high-level waste solidificaton and geologic isolation is reviewed. Some generic studies on the possible range of annual radiological doses to individuals from waste repositories are discussed and compared with doses from some existing nuclear power and fuel cycle operations, and with the dose received annually from an average background of naturally occurring radiation

Simulation of decay processes and radiation transport times in radioactivity measurements

Energy Technology Data Exchange (ETDEWEB)

García-Toraño, E., E-mail: e.garciatorano@ciemat.es [Laboratorio de Metrología de Radiaciones Ionizantes, CIEMAT, Avda. Complutense 22, 28040 Madrid (Spain); Peyres, V. [Laboratorio de Metrología de Radiaciones Ionizantes, CIEMAT, Avda. Complutense 22, 28040 Madrid (Spain); Bé, M.-M.; Dulieu, C.; Lépy, M.-C. [CEA, LIST, Laboratoire National Henri Becquerel (LNE-LNHB), Bldg 602, PC111, 91191 Gif-sur-Yvette Cedex (France); Salvat, F. [Facultat de Física (FQA and ICC), Universitat de Barcelona, Diagonal 647, 08028 Barcelona (Spain)

2017-04-01

The Fortran subroutine package PENNUC, which simulates random decay pathways of radioactive nuclides, is described. The decay scheme of the active nuclide is obtained from the NUCLEIDE database, whose web application has been complemented with the option of exporting nuclear decay data (possible nuclear transitions, branching ratios, type and energy of emitted particles) in a format that is readable by the simulation subroutines. In the case of beta emitters, the initial energy of the electron or positron is sampled from the theoretical Fermi spectrum. De-excitation of the atomic electron cloud following electron capture and internal conversion is described using transition probabilities from the LLNL Evaluated Atomic Data Library and empirical or calculated energies of released X rays and Auger electrons. The time evolution of radiation showers is determined by considering the lifetimes of nuclear and atomic levels, as well as radiation propagation times. Although PENNUC is designed to operate independently, here it is used in conjunction with the electron-photon transport code PENELOPE, and both together allow the simulation of experiments with radioactive sources in complex material structures consisting of homogeneous bodies limited by quadric surfaces. The reliability of these simulation tools is demonstrated through comparisons of simulated and measured energy spectra from radionuclides with complex multi-gamma spectra, nuclides with metastable levels in their decay pathways, nuclides with two daughters, and beta plus emitters.

Some Experience with Illicit Trafficking of Radioactive Materials in Tanzania

International Nuclear Information System (INIS)

Ngaile, J.E.; Banzi, F.P.; Kifanga, L.D.

2008-01-01

Illicit trafficking of radioactive materials (orphan sources or disuse sources) is of global concern. Reports on the IAEA Illicit Trafficking Data Base (ITDB) indicates increasing trend of incidents recorded in more than 40 countries on six continents[1]. It is suspected that nuclear trafficking is fueled by nuclear terrorism and is a threat for increasing illegal trade in nuclear and radioactive materials to manufacture Radiological Disposal Devices (RDD)- dirty bombs. As such, the international co-operative efforts are needed to uncover and combat nuclear trafficking in order to minimize its consequences such as external radiation exposure of persons from source to various radiation levels during illicit movement and after seizure; rupture of source leading to internal exposure of persons and environmental contamination. Although accidents with radioactive materials have not occurred in the United Republic of Tanzania (URT), incidents of illicit trafficking and unauthorized possession of radioactive materials has occurred thus prompting the Tanzania Atomic Energy Commission (TAEC) to strengthen its nuclear security of nuclear and radioactive material in the URT. Nuclear faclities and radioactive sources lacks adequate physical protection against theft, fire or different forms of unauthorized access. Tanzaniaia has recorded about thirteen (13) illicit trafficking incidents of radioactive between 1996-2006. Caesium-137, Uranium-238; and Uranium oxide standard and Radium-226 with activity ranging from low to significantly high were among the radiounuclides which were intercepted. Most of these incidents had their original outside Tanzania. The incidents were uncovered by informers in cooperation with the police. Despite the fact that the management of these incidents by the police were adequate, it was observed that there is an inadequate radiation protection arrangements during transport of seized sources; lack of precautions for safety when handling seized

Method for evaluating building materials with a high content of radioactivity

International Nuclear Information System (INIS)

Stranden, E.

1979-01-01

In order to avoid increased radiation doses to the population due to the introduction of building materials with an unusually high content of radioactivity, a method for evaluating building materials has been developed. An expression for the gamma radiation due to radium, thorium and potassium 40 has been proposed by a Scandinavian group. When this value for a given material does not exceed 1, then no restriction is placed. Should it exceed 1, then the material is subjected to further investigation. Similarly, since the radon concentration depends on the radium content, an expression for this is proposed. Should this be less than unity the material may be sold freely. Should it exceed unity, further investigations must be made. Measurements have also been made on the exhalation of radon from concrete, and the results are given. An expression including this exhalation rate and the ventilation rate, giving the radon concentration is given. (JIW)

Distinguishing method for contamination/radio-activation of radioactive wastes

International Nuclear Information System (INIS)

Fukazawa, Takuji; Kato, Keiichiro; Koda, Satoshi.

1994-01-01

The present invention concerns a method of distinguishing the contamination/radio-activation of radioactive wastes used in processing wastes generated upon dismantling of exhausted nuclear reactors. Especially, contaminated/radio-activation is distinguished for wastes having openings such as pipes and valves, by utilizing scattering of γ-rays or γ-ray to β-ray ratio. That is, ratio of scattered γ-rays and direct γ-rays or ratio of β-rays and γ-rays from radioactive wastes are measured and compared by a radiation detector, to distinguish whether the radioactive wastes contaminated materials or radio-activated materials. For example, when an object to be measured having an opening is contaminated at the inner side, the radiation detector facing to the opening mainly detects high direct γ-rays emitted from the object to be measured while a radiation detector not facing the opening mainly detects high scattered γ-rays relatively. On the other hand, when the object is a radio-activated material, any of the detectors detect scattered γ-rays, so that they can be distinguished by these ratios. (I.S.)

Radon Adsorbed in Activated Charcoal--A Simple and Safe Radiation Source for Teaching Practical Radioactivity in Schools and Colleges

Science.gov (United States)

Al-Azmi, Darwish; Mustapha, Amidu O.; Karunakara, N.

2012-01-01

Simple procedures for teaching practical radioactivity are presented in a way that attracts students' attention and does not make them apprehensive about their safety. The radiation source is derived from the natural environment. It is based on the radioactivity of radon, a ubiquitous inert gas, and the adsorptive property of activated charcoal.…

Radioactivity Handbook

International Nuclear Information System (INIS)

Firestone, R.B.; Browne, E.

1985-01-01

The Radioactivity Handbook will be published in 1985. This handbook is intended primarily for applied users of nuclear data. It will contain recommended radiation data for all radioactive isotopes. Pages from the Radioactivity Handbook for A = 221 are shown as examples. These have been produced from the LBL Isotopes Project extended ENDSF data-base. The skeleton schemes have been manually updated from the Table of Isotopes and the tabular data are prepared using UNIX with a phototypesetter. Some of the features of the Radioactivity Handbook are discussed here

The current state of radiation education in schools and results of the opinion survey on radiation

International Nuclear Information System (INIS)

Murai, Kenji

2013-01-01

In 2008, a new guideline about radioactivity was added to the government guidelines for teaching junior high school science. Since then people involved with school education have been trying to spread correct information about radioactivity. On the other hand, people's confusion in the aftermath of the Fukushima Daiichi Nuclear Power Plant accident has clearly shown that people do not know much about radioactivity. Considering the situation, the author conducted an investigation about the current state of radiation education and carried out an opinion survey about radioactivity among adults. The investigation about education showed the following: (1) the nature of radiation, such as its permeability, and its uses were described in the government-approved textbooks; (2) basic knowledge, such as what are radiation effects, were described comprehensively in the supplementary reading recommendations made by the Ministry of Education, Culture, Sports, Science, and Technology; and (3) locale education committees created teaching materials such as guidance to present topics. The opinion survey had questions to judge: (1) current public understanding of radioactivity; (2) the degree of general information that people collected for themselves; (3) the degree of specific knowledge about radioactivity that people had; and (4) people's attitudes toward various problems with radioactivity in the environment. The results suggested that for radiation education the following items are important: (1) to learn that radioactivity exists in people's daily lives and is used safely in various field; (2) to get basic knowledge and better quantitative understanding of such things as radioactivity units, radiation dose and radiation effects; and (3) to acquire practical experience to use the information effectively. (author)

State of radioactive waste management is power reactor facilities and state of radiation exposure of workers who engaged in radiation works in fiscal 1993

International Nuclear Information System (INIS)

1994-01-01

This report is the summary of the reports on radiation control and others submitted by those who installed practical power reactor facilities based on the relevant law in fiscal 1993. The amounts of release of radioactive gaseous and liquid wastes were sufficiently smaller than the target value of the yearly release control for attaining the target value of dose that the public around the facilities receive. As to the state of control of radioactive solid waste, the amount of drum generation tended to decrease year by year, and the cumulative amount to be preserved tended to level off. The dose equivalent that the individuals who engaged in radiation works received was smaller than the limit value in all nuclear power stations. The total dose equivalent for those workers in fiscal 1993 was 86.65 man Sv. Hereafter, the automation and remote operation of works, the water quality control for reducing crud and so on will be promoted to reduce radiation exposure. The reference data on the state of control of gaseous, liquid and solid wastes, and the state of control of radiation exposure of workers are attached. (K.I.)

The state of radioactive waste management and of personnel radiation exposure in nuclear power generating facilities in fiscal 1983

International Nuclear Information System (INIS)

1985-01-01

(1) The state of radioactive waste management in nuclear power generating facilities: In the nuclear power stations, the released quantities of radioactive gaseous and liquid wastes are all below the control objective levels. For the respective nuclear power stations, the released quantities of radioactive gaseous and liquid wastes in fiscal 1983 and the objective levels are given in table. And, the quantities of solid wastes taken into storage and the cumulative amounts are given. For reference, the results each year since fiscal 1974 are shown. (2) The state of personnel radiation exposure in nuclear power generating facilities: In the nuclear power stations, the personnel radiation exposures are all below the permissible levels. The dose distribution etc. in the respective nuclear power stations are given in table. For reference, the results each year since fiscal 1974 are shown. (Mori, K.)

Radioactivity and geophysics

International Nuclear Information System (INIS)

Radvanyi, P.

1992-01-01

The paper recalls a few steps of the introduction of radioactivity in geophysics and astrophysics: contribution of radioelements to energy balance of the Earth, age of the Earth based on radioactive disintegration and the discovery of cosmic radiations

Radioactivity in the environment

International Nuclear Information System (INIS)

Valkovic, V.

2000-01-01

Numerous sources of ionizing radiation can lead to human exposure: natural sources, nuclear explosions, nuclear power generation, use of radiation in medical, industrial and research purposes, and radiation emitting consumer products. Before assessing the radiation dose to a population one requires a precise knowledge of the activity of a number of radionuclides. The basis for the assessment of the dose to a population from a release of radioactivity to the environment, the estimation of the potential clinical heath effects due to the dose received and, ultimately, the implementation of countermeasures to protect the population, is the measurement of radioactive contamination in the environment after the release. It is the purpose of this book to present the facts about the presence of radionuclides in the environment, natural and man made. There is no aspect of radioactivity, which has marked the passing century, not mentioned or discussed in this book. refs

Natural gamma radioactivity in the villages of Kanyakumari District, Tamil Nadu, India.

Science.gov (United States)

Padua, Jeni Chandar; Basil Rose, M R

2013-01-01

In situ radiometric survey carried out in 81 revenue villages of Kanyakumari District, Tamil Nadu, India, using a portable radiation dosemeter/detector, revealed the existence of radiation hotspots along the coastal belt. A close observation of the coastal villages specifically revealed high background radioactivity in 14 coastal villages. A very high intrinsic anomalous radioactivity of 41.03 μSv h(-1) was observed, in a famous tourist spot in the coastal belt of Kanyakumari District. This is the highest level of radiation registered in South India, which is extremely higher than the permissible world average and is suggestive of causing severe clinical problems on continuous and prolonged exposure.

Natural gamma radioactivity in the villages of Kanyakumari district, Tamil Nadu, India

International Nuclear Information System (INIS)

Padua, J. C.; Basil Rose, M. R.

2013-01-01

In situ radiometric survey carried out in 81 revenue villages of Kanyakumari District, Tamil Nadu (India), using a portable radiation dosemeter/detector, revealed the existence of radiation hotspots along the coastal belt. A close observation of the coastal villages specifically revealed high background radioactivity in 14 coastal villages. A very high intrinsic anomalous radioactivity of 41.03 μSv h -1 was observed, in a famous tourist spot in the coastal belt of Kanyakumari District. This is the highest level of radiation registered in South India, which is extremely higher than the permissible world average and is suggestive of causing severe clinical problems on continuous and prolonged exposure. (authors)

Physics of radiation

International Nuclear Information System (INIS)

Abd Nasir Ibrahim; Azali Muhammad; Ab Razak Hamzah; Abd Aziz Mohamed; Mohammad Pauzi Ismail

2004-01-01

This chapter discusses the following topics: concept of atom and elements; molecules and compounds; basic principles of radiation; types of radiations; radioactivity, unit of radioactivity, specific activity, radioactive decay, ionisation and ions, interaction of radiation with matters, modes of interaction: photoelectric absorption: Compton scattering, pair-production; attenuation of x and gamma radiation; build-up factors

Spent fuel and high-level radioactive waste storage

International Nuclear Information System (INIS)

Trigerman, S.

1988-06-01

The subject of spent fuel and high-level radioactive waste storage, is bibliographically reviewed. The review shows that in the majority of the countries, spent fuels and high-level radioactive wastes are planned to be stored for tens of years. Sites for final disposal of high-level radioactive wastes have not yet been found. A first final disposal facility is expected to come into operation in the United States of America by the year 2010. Other final disposal facilities are expected to come into operation in Germany, Sweden, Switzerland and Japan by the year 2020. Meanwhile , stress is placed upon the 'dry storage' method which is carried out successfully in a number of countries (Britain and France). In the United States of America spent fuels are stored in water pools while the 'dry storage' method is still being investigated. (Author)

Health effects of ionizing radiation

International Nuclear Information System (INIS)

Pathak, B.

1989-12-01

Ionizing radiation is energy that travels through space as electromagnetic waves or a stream of fast moving particles. In the workplace, the sources of ionizing radiation are radioactive substances, nuclear power plants, x-ray machines and nuclear devices used in medicine, research and industry. Commonly encountered types of radiation are alpha particles, beta particles and gamma rays. Alpha particles have very little penetrating power and pose a risk only when the radioactive substance is deposited inside the body. Beta particles are more penetrating than alpha particles and can penetrate the outer body tissues causing damage to the skin and the eyes. Gamma rays are highly penetrating and can cause radiation damage to the whole body. The probability of radiation-induced disease depends on the accumulated amount of radiation dose. The main health effects of ionizing radiation are cancers in exposed persons and genetic disorders in the children, grandchildren and subsequent generations of the exposed parents. The fetus is highly sensitive to radiation-induced abnormalities. At high doses, radiation can cause cataracts in the eyes. There is no firm evidence that ionizing radiation causes premature aging. Radiation-induced sterility is highly unlikely for occupational doses. The data on the combined effect of ionizing radiation and other cancer-causing physical and chemical agents are inconclusive

Environmental monitoring and radiation protection programs of Novi Han radioactive waste repository

International Nuclear Information System (INIS)

Christoskova, M.; Kostova, M.; Sheherov, L.; Bekiarov, P.; Iovtchev, M.

2000-01-01

The system for monitoring and control as an important part of the safety management of the Novi Han Radioactive Waste Repository contains two independent programs: environmental monitoring of the site (controlled area), the restricted access area and the surveillance area (supervised area) of the repository and radiation protection program including personal dosimetric control and indoor dosimetric control of workplaces in the buildings of the repository. The main activities related to the programs implementation are presented

The IAEA and Control of Radioactive Sources

International Nuclear Information System (INIS)

Dodd, B.

2004-01-01

The presentation discusses the authoritative functions and the departments of the IAEA, especially the Department of Nuclear Safety and Security and its Safety and Security of Radiation Sources Unit. IAEA safety series and IAEA safety standards series inform about international standards, provide underlying principles, specify obligations and responsibilities and give recommendations to support requirements. Other IAEA relevant publications comprise safety reports, technical documents (TECDOCs), conferences and symposium papers series and accident reports. Impacts of loss of source control is discussed, definitions of orphan sources and vulnerable sources is given. Accidents with orphan sources, radiological accidents statistic (1944-2000) and its consequences are discussed. These incidents lead to development of the IAEA guidance. The IAEA's action plan for the safety of radiation sources and the security of radioactive material was approved by the IAEA Board of Governors and the General Conference in September 1999. This led to the 'Categorization of Radiation Sources' and the 'Code of Conduct on the Safety and Security of Radioactive Sources'. After 0911 the IAEA developed a nuclear security plan of activities including physical protection of nuclear material and nuclear facilities, detection of malicious activities involving nuclear and other radioactive materials, state systems for nuclear material accountancy and control, security of radioactive material other than nuclear material, assessment of safety and security related vulnerability of nuclear facilities, response to malicious acts, or threats thereof, adherence to and implementation of international agreements, guidelines and recommendations and nuclear security co-ordination and information management. The remediation of past problems comprised collection and disposal of known disused sources, securing vulnerable sources and especially high-risk sources (Tripartite initiative), searching for

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

Science.gov (United States)

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

2012-08-01

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

Modification of catalase and MAPK in Vicia faba cultivated in soil with high natural radioactivity and treated with a static magnetic field.

Science.gov (United States)

Haghighat, Nazanin; Abdolmaleki, Parviz; Ghanati, Faezeh; Behmanesh, Mehrdad; Payez, Atefeh

2014-03-01

The effects of a static magnetic field (SMF) and high natural radioactivity (HR) on catalase and MAPK genes in Vicia faba were investigated. Soil samples with high natural radioactivity were collected from Ramsar in north Iran where the annual radiation absorbed dose from background radiation is higher than 20mSv/year. The specific activity of the radionuclides of (232)Th, (236)Ra, and (40)K was measured using gamma spectrometry. The seeds were planted either in the soil with high natural radioactivity or in the control soils and were then exposed to a SMF of 30mT for 8 days; 8h/day. Levels of expression of catalase and MAPK genes, catalase activity and H2O2 content were evaluated. The results demonstrated significant differences in the expression of catalase and MAPK genes in SMF- and HR-treated plants compared to the controls. An increase in catalase activity was accompanied by increased expression of its gene and accumulation of H2O2. Relative expression of the MAPK gene in treated plants, however, was lower than those of the controls. The results suggest that the response of V. faba plants to SMF and HR may be mediated by modification of catalase and MAPK. Copyright © 2013 Elsevier GmbH. All rights reserved.

Radioactive waste management in Tanzania

International Nuclear Information System (INIS)

Banzi, F.P.; Bundala, F.M.; Nyanda, A.M.; Msaki, P.

2002-01-01

Radioactive waste, like many other hazardous wastes, is of great concern in Tanzania because of its undesirable health effects. The stochastic effects due to prolonged exposure to ionizing radiation produce cancer and hereditary effects. The deterministic effects due to higher doses cause vomiting, skin reddening, leukemia, and death to exposed victims. The aim of this paper is to give an overview of the status of radioactive wastes in Tanzania, how they are generated and managed to protect humans and the environment. As Tanzania develops, it is bound to increase the use of ionizing radiation in research and teaching, industry, health and agriculture. Already there are more than 42 Centers which use one form of radioisotopes or another for these purposes: Teletherapy (Co-60), Brach-therapy (Cs-137, Sr-89), Nuclear Medicine (P-32, Tc-99m, 1-131, 1-125, Ga-67, In-111, Tl-206), Nuclear gauge (Am-241, Cs- 137, Sr-90, Kr-85), Industrial radiography (Am-241, C-137, Co-60, lr-92), Research and Teaching (1-125, Am241/Be, Co-60, Cs-137, H-3 etc). According to IAEA definition, these radioactive sources become radioactive waste if they meet the following criteria: if they have outlived their usefulness, if they have been abandoned, if they have been displaced without authorization, and if they contaminate other substances. Besides the origin of radioactive wastes, special emphasis will also be placed on the existing radiation regulations that guide disposal of radioactive waste, and the radioactive infrastructure Tanzania needs for ultimate radioactive waste management. Specific examples of incidences (theft, loss, abandonment and illegal possession) of radioactive waste that could have led to serious deterministic radiation effects to humans will also be presented. (author)

Radioactivities (dose rates) of rocks in Japan

International Nuclear Information System (INIS)

Matsuda, Hideharu; Minato, Susumu

1995-01-01

The radioactive distribution (radiation doses) of major rocks in Japan was monitored to clarify the factors influencing terrestrial gamma-ray absorbed dose rates. The rock samples were reduced to powder and analyzed by well-type NaI(Tl) scintillation detector and pulse height analyzer. Terrestrial gamma-ray dose rates were estimated in terms of gamma radiation dose rate 1 m above the ground. The radioactivity concentration was highest in acidic rock which contains much SiO 2 among igneous rock, followed by neutral rock, basic rock, and ultrabasic rock. The radioactive concentration was 30-40% lower in acidic and clastic rocks than those of the world average concentration. Higher radioactive concentration was observed in soils than the parent rocks of sedimentary rock and metamorphic rock. The gamma radiation dose rate was in proportion to the radioactive concentration of the rocks. To clarify the radioactive effect in the change course of rocks into soils, comparative measurement of outcrop and soil radioactive concentrations is important. (S.Y.)

Handling of radioactive sources in Ecuador

International Nuclear Information System (INIS)

Benitez, Manuel

2000-01-01

This document describes the following aspects: sealed and unsealed radioactive sources, radiation detectors, personnel and area monitoring, surface pollution, radioactive wastes control and radioactive sources transferring. (The author)

Current status of control of radiation sources and radioactive materials in the United Republic of Tanzania

International Nuclear Information System (INIS)

Nyaruba, M.M.; Mompome, W.K.

2001-01-01

A Protection from Radiation Act was enacted in Tanzania in 1983 to regulate the use of ionizing radiation and protect people against its danger. The Act established a regulatory authority known as National Radiation Commission (NRC), which is the corporate body to enforce the law and regulations. From the beginning of 2000, the NRC has kept inventory of 200 and 324 radiation installations, and radiation sources and radioactive materials in the country, respectively; and has provided personnel monitoring services to 665 radiation workers. However, due to the trade liberalization that is currently being experienced in the country, the increase in the number of radiation practices is observed yearly. To cope with the situation, the whole system of notification, authorization, registration and licensing needs to be improved. The improvement has now started by amending the existing Protection from Radiation Act. (author)

Living with radiation. The hazards and the potentials of radioactivity. Leben mit Strahlen. Risiken und Chancen der Radioaktivitaet

Energy Technology Data Exchange (ETDEWEB)

Moedder, G

1988-01-01

The author is an expert in nuclear medicine and with this book intends to illustrate for the general reader the hazards and the potentials of radioactivity. The book first presents the fundamentals of atomic physics and radiobiology and explains the terminology and concepts used in the discussions about radiation exposure and effects, and puts them into the overall context. The following chapters discuss natural radioactivity and its effects and the nuclear energy technology together with the safety engineering aspects, as well as the medical applications of ionizing radiation, and nuclear energy as a weapon. 'How dangerous is low-dose irradiation' is a main topic dealt with in detail. The material is presented on a sound scientific basis, taking into account the latest developments and knowledge available, so that the reader will be able to form his own opinion on the risks of ionizing radiation. (orig./HSCH).

The conceptual design of waste repository for radioactive waste from medical, industrial and research facilities containing comparatively high radioactivity

International Nuclear Information System (INIS)

Yamamoto, Masayuki; Hashimoto, Naro

2002-02-01

Advisory Committee on Nuclear Fuel Cycle Backend Policy reported the basic approach to the RI and Institute etc. wastes on March 2002. According to it, radioactive waste form medical, industrial and research facilities should be classified by their radioactivity properties and physical and chemical properties, and should be disposed in the appropriate types of repository with that classification. For the radioactive waste containing comparatively high radioactivity generated from reactors, NSC has established the Concentration limit for disposal. NSC is now discussing about the limit for the radioactive waste from medical, industrial and research facilities containing comparatively high radioactivity. Japan Nuclear Cycle Development Institute (JNC) preliminary studied about the repository for radioactive waste from medical, industrial and research facilities and discussed about the problems for design on H12. This study was started to consider those problems, and to develop the conceptual design of the repository for radioactive waste from medical, industrial and research facilities. Safety assessment for that repository is also performed. The result of this study showed that radioactive waste from medical, industrial and research facilities of high activity should be disposed in the repository that has higher performance of barrier system comparing with the vault type near surface facility. If the conditions of the natural barrier and the engineering barrier are clearer, optimization of the design will be possible. (author)

Proposed classification scheme for high-level and other radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Croff, A.G.

1986-01-01

The Nuclear Waste Policy Act (NWPA) of 1982 defines high-level radioactive waste (HLW) as: (A) the highly radioactive material resulting from the reprocessing of spent nuclear fuel....that contains fission products in sufficient concentrations; and (B) other highly radioactive material that the Commission....determines....requires permanent isolation. This paper presents a generally applicable quantitative definition of HLW that addresses the description in paragraph (B). The approach also results in definitions of other waste classes, i.e., transuranic (TRU) and low-level waste (LLW). A basic waste classification scheme results from the quantitative definitions

Environmental radioactivity survey in Andong area

Energy Technology Data Exchange (ETDEWEB)

Yoon, Zi Hong; Jo, Kum Ju [Andong Regional Radioactivity Monitoring Station, Andong National Univ., Andong (Korea, Republic of)

2001-12-15

The objectives of the project are to monitor an abnormal level in Andong area and to provide a base-line data on environmental radiation/radioactivity levels in case of any radiological emergency situation. The project is important in view of protecting the public health from the potential hazards of radiation and keeping up the clean environment. This report summarizes and interprets environmental radiation/radioactivity monitoring samples Gamma exposure rates, airborne dust, precipitation, fall-out and drinking-water. Environmental samples : vegetables, fishes/shellfishes, fruits, starch and starch roots and drinking waters. Among the all 2001 radiological monitoring and environmental data in Andong area were not found the extraordinary data. And a nation-wide environmental radiation/radioactivity level survey results were all background levels attributed to terrestrial and cosmic radiation.

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

International Nuclear Information System (INIS)

Ogawa, Tateo; Sato, Kohei

1988-01-01

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

Radioactivity and you

International Nuclear Information System (INIS)

1987-01-01

What does it mean when radiation levels are said to have risen? How do we measure radioactivity? Where do we get our exposure to radiation from? This programme, examines the risks we incur through radiation exposure, explains the basic science of radiation measurement, looks at the contributions of natural and man made sources. (author)

Radioactive waste isolation in salt: geochemistry of brine in rock salt in temperature gradients and gamma-radiation fields - a selective annotated bibliography

International Nuclear Information System (INIS)

Hull, A.B.; Williams, L.B.

1985-07-01

Evaluation of the extensive research concerning brine geochemistry and transport is critically important to successful exploitation of a salt formation for isolating high-level radioactive waste. This annotated bibliography has been compiled from documents considered to provide classic background material on the interactions between brine and rock salt, as well as the most important results from more recent research. Each summary elucidates the information or data most pertinent to situations encountered in siting, constructing, and operating a mined repository in salt for high-level radioactive waste. The research topics covered include the basic geology, depositional environment, mineralogy, and structure of evaporite and domal salts, as well as fluid inclusions, brine chemistry, thermal and gamma-radiation effects, radionuclide migration, and thermodynamic properties of salts and brines. 4 figs., 6 tabs

Radioactive waste isolation in salt: geochemistry of brine in rock salt in temperature gradients and gamma-radiation fields - a selective annotated bibliography

Energy Technology Data Exchange (ETDEWEB)

Hull, A.B.; Williams, L.B.

1985-07-01

Evaluation of the extensive research concerning brine geochemistry and transport is critically important to successful exploitation of a salt formation for isolating high-level radioactive waste. This annotated bibliography has been compiled from documents considered to provide classic background material on the interactions between brine and rock salt, as well as the most important results from more recent research. Each summary elucidates the information or data most pertinent to situations encountered in siting, constructing, and operating a mined repository in salt for high-level radioactive waste. The research topics covered include the basic geology, depositional environment, mineralogy, and structure of evaporite and domal salts, as well as fluid inclusions, brine chemistry, thermal and gamma-radiation effects, radionuclide migration, and thermodynamic properties of salts and brines. 4 figs., 6 tabs.

Radioactivity in the Rhine - the LWA controls North-Rhine-Westphalian surface waters

International Nuclear Information System (INIS)

Kloes, H.

1985-01-01

The State Authority for Water and Waste Management has been testing the Rhine and the most important surface waters of North-Rhine Westphalia for radioactivity ever since it was founded in 1969. Radiation exposure of human beings who use Rhine water is far below the permitted maximum values of the 'radiation protection ordinance'. Pollution of the Rhine and its tributaries in North-Rhine Westphalia with artificial radioactive substances has even slightly decreased over the past ten years; pollution of the River Emscher with natural radioactive material remained high, the Lippe River now contains less radium than before. (orig./PW) [de

The high pH chemical and radiation compatibility of various liner materials

International Nuclear Information System (INIS)

Whyatt, G.A.; Farnsworth, R.K.

1990-01-01

This paper reports on a flexible membrane liner that has been proposed to line a concrete vault in which liquid low-level radioactive waste will be solidified. High-density polyethylene (HDPE) and polypropylene liners were tested at the Pacific Northwest Laboratory in an EPA method 9090 format to determine their chemical compatibility with the waste. Radiation effects were also investigated. The liners were immersed in a highly caustic (pH>14), primarily inorganic solution at 90 degrees C. The liners were subjected to radiation doses up to 38.9 Mrad, which was the expected dose the liner would receive over a 30-year life inside the vault. Recent changes have placed the liner outside the vault. The acceptance criteria for judging the compatibility of the liner with radiation would be different that those used for judging chemical compatibility. The radiation damage over the life of the liner can be simulated in a short-term test. Both HDPE and polypropylene liners were judged to be acceptable from a chemical and radiation standpoint when placed outside of the vault, while several other liners were not compatible. Radiation did not have a significant effect on chemical degradation rates

The high pH chemical and radiation compatibility of various liner materials

International Nuclear Information System (INIS)

Whyatt, G.; Farnsworth, R.

1990-01-01

A flexible membrane liner has been proposed to line a concrete vault in which liquid low-level radioactive waste will be solidified. High-density polyethylene (HDPE) and polypropylene liners were tested at the Pacific Northwest Laboratory in an EPA method 9090 format to determine their chemical compatibility with the waste. Radiation effects were also investigated. The liners were immersed in a highly caustic (pH>14), primarily inorganic solution at 90 degrees C. The liners were subjected to radiation doses up to 38.9 Mrad, which was the expected dose the liner would receive over a 30-year life inside the vault. Recent changes have placed the liner outside the vault. The acceptance criteria for judging the compatibility of the liner with radiation should be different than those used for judging chemical compatibility. The radiation damage over the life of the liner can be simulated in a short-term test. Both HDPE and polypropylene liners were judged to be acceptable from a chemical and radiation standpoint when placed outside of the vault, while several other liners were not compatible. Radiation did not have a significant effect on chemical degradation rates

Survey monitoring of environmental radioactivity in Daejeon area

Energy Technology Data Exchange (ETDEWEB)

Jun, Jae Shik.; Noh, Hyung Ah [Taejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

2000-12-15

Systematic understanding of the distribution of environmental radioactivity and radiation level in Taejon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Taejon Radiation Monitoring Station in 2000. In conclusion, the natural environmental radiation level in Taejon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

Survey monitoring of environmental radioactivity in Daejeon area

Energy Technology Data Exchange (ETDEWEB)

Jun, Jae Sik; Noh, Hyung Ah [Daejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

2001-12-15

Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2001. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

Survey monitoring of environmental radioactivity in Daejeon area

Energy Technology Data Exchange (ETDEWEB)

Jun, Jae Shik; Noh, Hyung Ah [Daejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

2002-12-15

Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2002. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

Survey monitoring of environmental radioactivity in Daejeon area

Energy Technology Data Exchange (ETDEWEB)

Jun, Jae Shik; Noh, Hyung Ah [Daejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

2003-12-15

Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2002. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

Survey monitoring of environmental radioactivity in Daejeon area

International Nuclear Information System (INIS)

Jun, J. S.; Kim, K. S.

1998-01-01

Systematic understanding of the distribution of environmental radioactivity and radiation level in Taejon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Taejon Radiation Monitoring Station in 1998. In conclusion, the natural environmental radiation level in Taejon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period

Survey monitoring of environmental radioactivity in Daejeon area

International Nuclear Information System (INIS)

Jun, Jae Sik; Noh, Hyung Ah

2001-12-01

Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2001. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period

Radiation monitor

International Nuclear Information System (INIS)

Pao, C.T.; Green, W.K.

1978-01-01

A system for indicating radiation from a radioactive fluid such as a gas wherein simultaneous indications of the activity concentration of radioactivity of the gas, the radiation dose rate and average energy of the radiation are provided

Applications of ionizing radiations

International Nuclear Information System (INIS)

2014-01-01

Developments in standard applications and brand new nuclear technologies, with high impact on the future of the agriculture, medicine, industry and the environmental preservation. The Radiation Technology Center (CTR) mission is to apply the radiation and radioisotope technologies in Industry, Health, Agriculture, and Environmental Protection, expanding the scientific knowledge, improving human power resources, transferring technology, generating products and offering services for the Brazilian society. The CTR main R and D activities are in consonance with the IPEN Director Plan (2011-2013) and the Applications of Ionizing Radiation Program, with four subprograms: Irradiation of Food and Agricultural Products; Radiation and Radioisotopes Applications in Industry and Environment; Radioactive Sources and Radiation Applications in Human Health; and Radioactive Facilities and Equipment for the Applications of Nuclear Techniques

Applications of ionizing radiations

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-01

Developments in standard applications and brand new nuclear technologies, with high impact on the future of the agriculture, medicine, industry and the environmental preservation. The Radiation Technology Center (CTR) mission is to apply the radiation and radioisotope technologies in Industry, Health, Agriculture, and Environmental Protection, expanding the scientific knowledge, improving human power resources, transferring technology, generating products and offering services for the Brazilian society. The CTR main R and D activities are in consonance with the IPEN Director Plan (2011-2013) and the Applications of Ionizing Radiation Program, with four subprograms: Irradiation of Food and Agricultural Products; Radiation and Radioisotopes Applications in Industry and Environment; Radioactive Sources and Radiation Applications in Human Health; and Radioactive Facilities and Equipment for the Applications of Nuclear Techniques.

An assessment of the natural radioactivity distribution and radiation hazard in soil samples from Qatar using high-resolution gamma-ray spectrometry