Regulation on the transport of nuclear fuel materials by vehicles

International Nuclear Information System (INIS)

1984-01-01

The regulations applying to the transport of nuclear fuel materials by vehicles, mentioned in the law for the regulations of nuclear source materials, nuclear fuel materials and reactors. The transport is for outside of the factories and the site of enterprises by such modes of transport as rail, trucks, etc. Covered are the following: definitions of terms, places of fuel materials handling, loading methods, limitations on mix loading with other cargo, radiation dose rates concerning the containers and the vehicles, transport indexes, signs and indications, limitations on train linkage during transport by rail, security guards, transport of empty containers, etc. together with ordinary rail cargo and so on. (Mori, K.)

Radiation protection in nuclear medicine

International Nuclear Information System (INIS)

Chougule, Arun

2014-01-01

The branch of medical science that utilizes the nuclear properties of the radioactivity and stable nuclides to make diagnostic evaluation of anatomical and/or physiological conditions of the body and provide therapy with unsealed radioactive sources is called Nuclear Medicine (NM). The use of unsealed radionuclides in medicine is increasing throughout the world for diagnosis and treatment. As per UNSCEAR report more than 6 million nuclear medicine procedures are conducted in a year. However we know that radiation is double edged sword and if not used carefully will be harmful to patient as well as staff and therefore a nuclear medicine procedure should be undertaken only after proper justification and optimization. Nuclear medicine procedures are different than the X-ray diagnostic procedures as in NM, radioisotope is administered to patient and patient becomes radioactive. The NM staff is involved in unpacking radioactive material, activity measurements, storage of sources, internal transports of sources, preparation of radiopharmaceuticals, administration of radiopharmaceutical, examination of the patient, care of the radioactive patient, handling of radioactive waste and therefore receives radiation dose. This talk will discuss the various steps for radiation safety of patient, staff and public during Nuclear Medicine procedures so as to implementing the ALARA concept. (author)

Measures to strengthen international co-operation in nuclear, radiation and transport safety and waste management. Nuclear safety review for the year 2003

International Nuclear Information System (INIS)

2004-01-01

The Nuclear Safety Review for the Year 2003 presents an overview of the current issues and trends in nuclear, radiation, transport and radioactive waste safety during 2003. As in 2002 the overview is supported by more detailed Notes by the Secretariat: Safety Related Events and Issues Worldwide during 2003 (document 2004/Note 6), The Agency's Safety Standards: Activities during 2003 (document 2004/Note 7) and Providing for the Application of the Safety Standards (document 2004/Note 8). In January 2003, the Agency implemented an organization change and developed an integrated approach to reflect a broader assignment of nuclear safety and nuclear security and to better exploit synergy between them. The Office of Physical Protection and Material Security renamed to Office of Nuclear Security was transferred from the Department of Safeguards to the Department of Nuclear Safety, which became the Department of Nuclear Safety and Security to reflect the change. This Review provides information primarily on nuclear safety, and nuclear security will be addressed in a separate report

Nuclear transports. Unpopular as never before?; Nukleartransporte. Ungeliebter denn je?

Energy Technology Data Exchange (ETDEWEB)

Feldmann, Ulrike

2014-11-15

Since many years there are initiatives in cities with large German seaports to prevent nuclear transports through the cities and transshipment at these harbours. Through the reactor accident in Fukushima and the Federal Government's decision 2011 to opt out, initiatives against nuclear transports seem to have gotten fresh wind in their sails. This is indicated by initiatives in Bremen and Hamburg. Though, to protect health and material goods from hazards and harmful ionising radiation, transportation of radioactive material is regulated by nuclear law as well as traffic law, enactments, guidelines, standards and recommendations, nationally and internationally. These regulations have contributed to the fact that nuclear material has been transported worldwide routinely without harm for the past five decades with an average of roughly 20 million nuclear material transports per year. These attempts disregard that about 95 % of all nuclear transports is not caused by the nuclear energy industry. We should stop demonising nuclear transports and rather acknowledge that they are necessary part of our everyday life.

Licensing authority's control of radiation sources and nuclear materials in Brazil

International Nuclear Information System (INIS)

Binns, D.A.C.

2002-01-01

Full text: The Brazilian Nuclear Energy Commission is the national licensing authority and among its responsibilities is the control of nuclear materials and radiation sources. This control is carried out in three different ways: 1) Control of the import and export of nuclear materials and radiation sources. To be able to import or export any nuclear material or radiation source, the user has to have an explicit permission of the licensing authority. This is controlled by electronic means in which the user has to fill a special form found on the licensing authority's home page, where he has to fill in his name, license number, license number of his radiation protection officer and data of the material to be imported or exported. These data are checked with a data base that contains all the information of the licensed users and qualified personnel before authorization is emitted. The airport authorities have already installed x-ray machines to check all baggages entering or leaving the country. 2) Transport and transfer permit for radiation sources. In order to transport and/or transfer radiations sources and nuclear materials within the country, the user(s) have to submit an application to the licensing authority. The user(s) fill out an application form where he fills in his company's name, licensing I.D., radiation protection officer's name and I.D and identification of the sources involved. These information are checked with the licensing operations data before the operations is permitted. 3) Inspections and radiation monitoring systems. Routine and regulatory inspections are continuously carried out where the user's radiation sources and nuclear materials inventory are checked. Also the physical security and protection of these materials are verified. The installation of monitoring systems is an item that is being discussed with the airport authorities so as to increase the possibilities of detecting any illegal transport of these materials. (author)

Implementation and testing of a multivariate inverse radiation transport solver

International Nuclear Information System (INIS)

Mattingly, John; Mitchell, Dean J.

2012-01-01

Detection, identification, and characterization of special nuclear materials (SNM) all face the same basic challenge: to varying degrees, each must infer the presence, composition, and configuration of the SNM by analyzing a set of measured radiation signatures. Solutions to this problem implement inverse radiation transport methods. Given a set of measured radiation signatures, inverse radiation transport estimates properties of the source terms and transport media that are consistent with those signatures. This paper describes one implementation of a multivariate inverse radiation transport solver. The solver simultaneously analyzes gamma spectrometry and neutron multiplicity measurements to fit a one-dimensional radiation transport model with variable layer thicknesses using nonlinear regression. The solver's essential components are described, and its performance is illustrated by application to benchmark experiments conducted with plutonium metal. - Highlights: ► Inverse problems, specifically applied to identifying and characterizing radiation sources . ► Radiation transport. ► Analysis of gamma spectroscopy and neutron multiplicity counting measurements. ► Experimental testing of the inverse solver against measurements of plutonium.

Radiation Transport

Energy Technology Data Exchange (ETDEWEB)

Urbatsch, Todd James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-06-15

We present an overview of radiation transport, covering terminology, blackbody raditation, opacities, Boltzmann transport theory, approximations to the transport equation. Next we introduce several transport methods. We present a section on Caseology, observing transport boundary layers. We briefly broach topics of software development, including verification and validation, and we close with a section on high energy-density experiments that highlight and support radiation transport.

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 Radiation Shielding Analysis for Low-Intermediate Level Waste Transport Ship

Energy Technology Data Exchange (ETDEWEB)

Kim, Dohyung; Lee, Unjang; Song, Yangsoo; Kim, Sukhoon; Ko, Jaehoon [Korea Nuclear Engineering and Service Corporation, Seoul (Korea, Republic of)

2007-07-01

In Korea, it is planed to transport Low-Intermediate Level Radioactive Waste (LILW) from each nuclear power plant site to Kyongju LILW repository after 2009. Transport through the sea using ship is one of the most prospective ways of LILW transport for current situation in Korea. There are domestic and international regulations for radiation dose limit for radioactive material transport. In this article, radiation shielding analysis for LILW transport ship is performed using 3-D computer simulation code, MCNP. As a result, the thickness and materials for radiation shielding walls next to cargo in the LILW transport ship are determined.

Nuclear radiation in warfare

International Nuclear Information System (INIS)

Rotblat, J.

1986-01-01

The subject is covered in chapters, entitled: introduction; digest of nuclear weaponry (characteristics of nuclear weapons; effects of nuclear weapons other than ionizing radiation (fire-ball, fall-out, thermal radiation, blast wave, electromagnetic pulse); the nuclear arms race; war scenarios; biological effects of radiations on man (radiation doses; natural sources of radiation; acute effects of radiation; long-term somatic effects; genetic effects; factors affecting the biological response to radiation; internal exposure; synergistic effects; protection against radiation effects); radiations from nuclear explosions (initial radiation; fall-out; effects of fall-out on animal and plant life; contamination of water and food supplies by fall-out); radiation casualties in a nuclear war; effectiveness of civil defence; other warlike uses of radiation (attacks on civilian nuclear power installations; radiological warfare; terrorist activities); conclusion. (orig./HP) [de

Nuclear radiation in warfare

International Nuclear Information System (INIS)

Rotblat, J.

1981-01-01

The subject is covered in chapters, entitled: introduction; digest of nuclear weaponry (characteristics of nuclear weapons; effects of nuclear weapons other than ionizing radiation (fire-ball, fall-out, thermal radiation, blast wave, electromagnetic pulse); the nuclear arms race; war scenarios); biological effects of radiations on man (radiation doses; natural sources of radiation; acute effects of radiation; long-term somatic effects; genetic effects; factors affecting the biological response to radiation; internal exposure; synergistic effects; protection against radiation effects); radiations from nuclear explosions (initial radiation; fall-out; effects of fall-out on animal and plant life; contamination of water and food supplies by fall-out); radiation casualties in a nuclear war; effectiveness of civil defence; other warlike uses of radiation (attacks on civilian nuclear power installations; radiological warfare; terrorist activities); conclusion. (U.K.)

Radiological emergency: road map for radiation accident victim transport

International Nuclear Information System (INIS)

Costa, V.S.G.; Alcantara, Y.P.; Lima, C.M.A.; Silva, F. C. A. da

2017-01-01

During a radiological or nuclear emergency, a number of necessary actions are taken, both within the radiation protection of individuals and the environment, involving many institutions and highly specialized personnel. Among them it is possible to emphasize the air transportation of radiation accident victims.The procedures and measures for the safe transport of these radiation accident victims are generally the responsibility of the armed forces, specifically the Aeronautics, with the action denominated 'Aeromedical Military Evacuation of Radiation Accident Victims'. The experience with the Radiological Accident of Goiânia demonstrated the importance of adequate preparation and response during a radiological emergency and the need for procedures and measures with regard to the transport of radiation victims are clearly defined and clearly presented for the effectiveness of the actions. This work presents the necessary actions for the transport of radiation accident victim during a radiological emergency, through the road map technique, which has been widely used in scientific technical area to facilitate understanding and show the way to be followed to reach the proposed objectives

Report of the State Office for Nuclear Safety on state supervision of nuclear safety of nuclear facilities and radiation protection in 1998

International Nuclear Information System (INIS)

1999-05-01

The legislative basis of the authority of the State Office for Nuclear Safety as the Czech national regulatory body is outlined, its organizational scheme is presented, and the responsibilities of the various departments are highlighted. The operation of major Czech nuclear facilities, including the Dukovany NPP which is in operation and the Temelin NPP which is under construction, is described with respect to nuclear safety. Since the Office's responsibilities also cover radiation protection in the Czech Republic, a survey of ionizing radiation sources and their supervision is given. Other topics include, among other things, nuclear material transport, the state system for nuclear materials accountancy and control, central registries for radiation protection, nuclear waste management, the National Radiation Monitoring Network, personnel qualification and training, emergency planning, legislative activities, international cooperation, and public information. (P.A.)

A radiation monitoring system model for the Laguna Verde nuclear power training simulator

International Nuclear Information System (INIS)

Ocampo, M.H.; DeAlbornoz, B.A.

1988-01-01

A model for the Radiation Monitoring System of the Laguna Verde Boiling Water Reactor training simulator is presented. This model comprises enough definitions to assure interactions with the processes related, directly or indirectly, with the transport of radioisotopes. It is capable of following a dynamic behavior of the plant so an operator could be trained to become aware of nuclear radiation hazards. The model is composed of three parts: the electronics for the Process and Area Radiation Monitoring System; a lumped parameter transport model for the most representative radioisotopes; and the interactions with the modeled processes as well as with process not being simulated. The first part represents the radiation monitor controls in the vertical board panels of the nuclear station. The second part allows the carrying of nuclear isotopes between processes. The third part defines the way that the process interacts with the electronics at the point of release to environment or the point of detection. Each part of the model has been tested individually, and the transport model has been incorporated as a part of each process required to simulate nuclear radiation. The model parameters has been calculated using typical BWR nuclear radiation data, and Laguna Verde heat balance data at 100% design power. However, tunning will be necessary once the Simulator is integrated and tested. The tunning allows each detecting channel to behave as expected

Perspective on radiation from the nuclear power industry

International Nuclear Information System (INIS)

Cohen, B.L.

1990-01-01

Methods for estimating the risk of radiation induced cancer mortality to members of the public are outlined for each element of the nuclear power industry - reactor accidents, routine releases from nuclear plants, transport, mining and milling of uranium, and escape of buried radioactive waste (high level and low level). The results are compared with mortality risks from the air pollution and chemical carcinogens released into the ground in generating the same amount of electricity by coal burning - the latter are thousands of times larger. Radiation from nuclear power is also 1,000 times smaller than that from radon in homes. The amount of money spent to avert a death from nuclear power radiation is in the billion dollar range, whereas lives could be saved from radon in homes for 0.00001 times that cost. Medical screening and highway safety programs can save lives for a similarly low cost

The nuclear safety authority (ASN) presents its report on the status of nuclear safety and radiation protection in France in 2010

International Nuclear Information System (INIS)

2011-01-01

After a presentation of the French nuclear safety authority (ASN) and of some events which occurred in 2010, this report present the actions performed by the ASN in different fields: nuclear activities (ionizing radiations and risks for health and for the environment), principles and actors of control of nuclear safety, radiation protection and environment protection, regulation, control of nuclear activities and of exposures to ionizing radiations, emergency situations, public information and transparency, international relationship. It proposes a regional overview of nuclear safety and radiation protection in France. It addresses the activities controlled by the ASN: medical and non medical usages of ionizing radiations, transportation of radioactive materials, electronuclear power stations, installations involved in the nuclear fuel cycle, research nuclear installations and other nuclear installations, safety in basic nuclear installation dismantling, radioactive wastes and polluted sites

Nuclear radiation applications in hydrological investigations

International Nuclear Information System (INIS)

Rao, S.M.

1978-01-01

The applications of radiation sources for the determination of water and soil properties in hydrological investigations are many and varied. These include snow gauging, soil moisture and density determinations, measurement of suspended sediment concentrations in natural streams and nuclear well logging for groundwater exploitation. Besides the above, many radiation physics aspects play an important role in the development of radiotracer techniques, particularly in sediment transport studies. The article reviews the above applications with reference to their limitations and advantages. (author)

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

Energy Technology Data Exchange (ETDEWEB)

Kirk, Bernadette Lugue [ORNL

2009-01-01

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries.

The changing nature of nuclear transport

International Nuclear Information System (INIS)

Brobst, W.A.

1976-01-01

The IAEA's efforts in transport safety have been proven through 25 years of nearly accident-free transport, with no evidence of death or injury from the nuclear characteristics of those shipments. Much testing has been done over the last five years to verify the technical bases for the IAEA Regulations. Rather than being complacent with the past, we should instead see ourselves at a turning point for the solution of problems coming up in the next few years. The number of shipments will increase drastically and this will result in changes of risk levels. A number of critical problems will be discussed: (1) lack of public acceptance of nuclear shipment safety; (2) transport safeguards; (3) incompleteness in the IAEA package damage tests; (4) need for innovative technology for spent fuel casks; (5) reduction of radiation dose to the public; (6) quality assurance; (7) engineering analyses versus scale-model and full-scale testing; and (8) transport controls. A recommendation is made to the IAEA to set up immediately a study group to define these problems, list alternatives and options, and recommend corrective actions. (author)

BALTORO a general purpose code for coupling discrete ordinates and Monte-Carlo radiation transport calculations

International Nuclear Information System (INIS)

Zazula, J.M.

1983-01-01

The general purpose code BALTORO was written for coupling the three-dimensional Monte-Carlo /MC/ with the one-dimensional Discrete Ordinates /DO/ radiation transport calculations. The quantity of a radiation-induced /neutrons or gamma-rays/ nuclear effect or the score from a radiation-yielding nuclear effect can be analysed in this way. (author)

Transport Nuclear Liability Insurance

International Nuclear Information System (INIS)

Folens, M.

2006-01-01

Although transport of nuclear substances represents only a very small part of the global transport of dangerous goods, it takes place every day all over the world and it is part of our daily life. Transport of nuclear material takes also place at every stage of the nuclear fuel cycle; radioactive materials are carried out all over the world by all major modes of transport: sea, air, road and rail. Despite the large number of nuclear transports, they are not considered as posing a serious risk. A major nuclear incident is almost always associated with the operating of fixed installations such as nuclear power plants; just think about Three Mile Island and Chernobyl. This perception is strengthened by the absence so far of serious accidents in the nuclear transport sector and this finding is in fact proof of the very safe conditions of nuclear transport. But accidents can never be excluded entirely and in some cases damages could be as large as those caused by fixed installations. This means that protection of the interests of possible victims should also be covered in a correct way. That is why the special nuclear liability regime has also been developed to cover damage caused by a nuclear transport accident. As stated by Patrick Reyners, the prime motivation for originally adopting a special nuclear regime was the harmonisation of national legislation and that nowhere more than in the field of international transport operations is such harmonisation felt desirable . The international legal regime has been developed along two tracks, one based on the mode of transport and the other based on the notion of dangerous goods. The linkage between those two tracks is of permanent concern and the mode of transport is the key element to determine which international instrument should be applicable. The purpose of this paper is to briefly introduce the financial security provided by the insurance industry to cover the international nuclear liability regime for nuclear

Radiation interaction with substance and simulation of the nuclear geophysical problems

International Nuclear Information System (INIS)

Pshenichnyj, G.A.

1982-01-01

Main processes of interaction of various types of nuclear radiation (NR) with substance, NR transport theory and physical- mathematical simulation of basic problems of nuclear geophysics (NG) are considered. General classification of NG methods according to the type of the detected radiation with a more detailed division according to the physical essence of the interaction process employed is given. Direct NG problems are related to the study of space- energy radiation distribution in substance under certain cross sections of elementary interaction processes, substance properties and specified geometric conditions. The theoretical solution of the direct problems is based on using mathematical models of radiation transport in specified media. The NG inverse problems consist in determining element composition and other medium properties by data of integral or spectral characteristics of NR fields measurements. The NR in the course of its transport in substance can experience dozens of elementary interaction processes, the predominance of this or that process depending on NR energy, medium properties and geometric measurement conditions. This explains a wide NG method diversity. The Monte Carlo method application in the NR transport theory and various methods of decreasing calculations labour input are considered [ru

E-Alerts: Nuclear science and technology (radiation shielding, protection, and safety). E-mail newsletter

International Nuclear Information System (INIS)

1999-01-01

Topics include: Shielding design, nuclear radiation transport properties of materials, decontamination; Container design and transportation requirements for radioactive materials; and Fallout shelters

Radiation exposures associated with shipments of foreign research reactor spent nuclear fuel

International Nuclear Information System (INIS)

Massey, C.D.; Messick, C.E.; Mustin, T.

1999-01-01

In accordance with the Record of Decision on a Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel (ROD) (DOE, 1996a), the U.S. Department of Energy (DOE) is implementing a 13-year program under which DOE accepts foreign research reactor spent nuclear fuel (SNF) containing uranium that was enriched in the United States. The ROD required that DOE take several steps to ensure low environmental and health impacts resulting from the implementation of the program. These efforts mainly focus on transportation related activities that the analysis of potential environmental impacts in the Environmental Impact Statement on a Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel (EIS) (DOE, 1996b) identified as having the potential for exceeding current radiation protection guidelines. Consequently, DOE issued a Mitigation Action Plan to reduce the likelihood of potential adverse environmental impacts associated with the policy established in the ROD. As shown in the EIS, incident-free radiation exposures to members of the ship's crew, port workers, and ground transportation personnel due to shipments of spent nuclear fuel from foreign research reactors are expected to be below the radiation exposure limit of 100 mrem (1 mSv) per year established to protect the general public. However, the analysis in the EIS demonstrated that port and transportation workers could conceivably receive a cumulative radiation dose above the limit established for the general public if, for example, they are involved in multiple shipments within one year or if the radiation levels outside the casks are at the maximum allowable regulatory limit (10 mrem/hr [0.1 mSv/h] at 2 meters from the surface of the cask). With the program successfully underway, DOE has collected information from the shipments in accordance with the Mitigation Action Plan. The information to date has demonstrated that the analysis in

The transports of nuclear fuel cycle: An essential activity, safely managed

International Nuclear Information System (INIS)

Lenail, B.; Savornin, B.; Curtis, H.W.

1989-01-01

Transports associated with the nuclear fuel cycle normally use public means of transport by rail, road, sea and air and it might therefore be expected that they would be the Achilles heel of the cycle from a safety point of view. In fact, despite a few minor accidents, no radioactive releases resulting in a significant exposure of the public or the environment have occurred. On the other hand, during the last quarter, the news media have reported major spillages of crude oil and chemicals of high toxicity which have jeopardized the environment, the explosion of gas tankers with dozens of fatalities, and even the sinking of a nuclear submarine. All reports show that the radiation exposure to the public resulting from transports is negligible, i.e., far below 1% of that due to the whole nuclear industry. Similarly, the radiation exposure of transport workers has been lower than anticipated over several decades. The demonstrations and attacks by opponents of the nuclear industry against transports have been limited and have been used as an attempt to freeze the activity of different plants or disposal sites, and to focus public attention on the nuclear issue, rather than to question the fuel cycle transports themselves or the safety principles ruling them. When looking for explanations of such a favorable situation, which they should endeavour to perpetuate, without being surprised if any incident occurs, one finds two major reasons: First, the awareness by the fuel cycle operators, of the vital importance of a safe and reliable implementation of the necessary transports. Secondly, the results of assessments of safety conducted by international organizations and most countries, which have resulted in detailed international recommendations, as well as uniform national and modal regulations, thus establishing the necessary link between the basic rules for radioprotection and the needs of the Transport Industry

Proceedings of the 6. Argentine congress on radiation protection and nuclear safety

International Nuclear Information System (INIS)

1998-01-01

The 6th Argentine Congress on Radiation Protection and Nuclear Safety was organized by the Radioprotection Argentine Society, in Buenos Aires, between the 22 and 24 of september of 1998. In this event, were presented almost 66 papers in the following sessions, about these subjects: 1.- Safety in nuclear installations. 2.- Control of nuclear material and physical protection of nuclear installations. 3.- Programs of quality assurance. 4.- Training, technical information and public information. 5.- Physical dosimetry. 6.- Physical dosimetry and occupational radiation protection. 7.- Exposure of the natural radiation. 8.- Environmental radiological safety. 9.- Biological effects of the ionizing radiations and biological dosimetry. 10.- Radiological protection of the medical practice and the radiological emergencies. 11.- Radioactive wastes management. 12.- Transport of radioactive materials

A comparison of radiation doses and risks between spent fuel transport/storage and selected non-nuclear activities

International Nuclear Information System (INIS)

Pennington, C.W.

2003-01-01

Spent fuel transport and storage have achieved an exemplary safety record over four decades within both the United States (US) and the global community at large. This paper offers an assessment demonstrating the safety of spent fuel transport and storage packagings relative to currently accepted but unregulated non-nuclear activities and practices within society. Over the last quarter of a century, several spent fuel transport and storage packaging test programmes have produced data that allow calculation of potential releases and population doses resulting from a terrorist attack. The US Department of Energy (DOE) has used this information to develop projected worst-case, low probability population exposures as part of the Final Environmental Impact Statement (FEIS) for the Yucca Mountain repository. The paper discusses potential population exposures from these packagings based on analysis and testing under beyond-design-basis (BDB) events, including missile attacks, and then defines and defends an acceptance criterion for the bounding outcomes of these events, based upon current accepted activities within society that produce high radiation doses to the general public. These activities involve unregulated technologies and practices within society that yield population doses significantly exceeding those that would result from such hypothetical and highly improbable events as a terrorist missile attack on a spent fuel transport or storage packaging. In particular, technologically enhanced natural radiation (TENR) exposures from building materials, farming, and masonry construction are highlighted. Recent landmark work by the US National Academy of Sciences (NAS) and by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) are cited in support of this assessment, along with work from the US Environmental Protection Agency (EPA). From this compelling evidence, it is concluded that spent fuel transport and storage represent a low

Path Toward a Unified Geometry for Radiation Transport

Science.gov (United States)

Lee, Kerry

The Direct Accelerated Geometry for Radiation Analysis and Design (DAGRAD) element of the RadWorks Project under Advanced Exploration Systems (AES) within the Space Technology Mission Directorate (STMD) of NASA will enable new designs and concepts of operation for radiation risk assessment, mitigation and protection. This element is designed to produce a solution that will allow NASA to calculate the transport of space radiation through complex CAD models using the state-of-the-art analytic and Monte Carlo radiation transport codes. Due to the inherent hazard of astronaut and spacecraft exposure to ionizing radiation in low-Earth orbit (LEO) or in deep space, risk analyses must be performed for all crew vehicles and habitats. Incorporating these analyses into the design process can minimize the mass needed solely for radiation protection. Transport of the radiation fields as they pass through shielding and body materials can be simulated using Monte Carlo techniques or described by the Boltzmann equation, which is obtained by balancing changes in particle fluxes as they traverse a small volume of material with the gains and losses caused by atomic and nuclear collisions. Deterministic codes that solve the Boltzmann transport equation, such as HZETRN (high charge and energy transport code developed by NASA LaRC), are generally computationally faster than Monte Carlo codes such as FLUKA, GEANT4, MCNP(X) or PHITS; however, they are currently limited to transport in one dimension, which poorly represents the secondary light ion and neutron radiation fields. NASA currently uses HZETRN space radiation transport software, both because it is computationally efficient and because proven methods have been developed for using this software to analyze complex geometries. Although Monte Carlo codes describe the relevant physics in a fully three-dimensional manner, their computational costs have thus far prevented their widespread use for analysis of complex CAD models, leading

Post-graduate course on radiation protection and nuclear safety. Vol. 1,2

International Nuclear Information System (INIS)

1998-01-01

The course handbook on radiation protection and nuclear safety containing two parts some was prepared mainly by scientists of the Nuclear Regulatory Authority (ARN) of the Argentine Republic, under the auspices of the International Atomic Energy Agency. The contents o this handbook have the principals aspects: radiation detection, radio dosimetry, biological effects of the ionizing radiation, occupational exposure, environmental effects, contamination and decontamination, radioactive waste management, transport of radioactive materials, medical and industrial applications and the Argentine regulatory system

ASN report on the status of nuclear safety and radiation protection in France in 2011

International Nuclear Information System (INIS)

2012-01-01

The first part of this huge report proposes a detailed overview of ASN activities in different fields: ionizing radiations related to nuclear activities and risks for health and the environment, principles and actors of nuclear safety control, of radiation protection and of protection of the environment, regulation, control of nuclear activities and exposures to ionizing radiations, emergency situations, public information and transparency, international relationships, regional overview of nuclear safety and radiation protection. The second part addresses the activities controlled by the ASN: medical use of ionizing radiations, non medical use of ionizing radiations, transport of radioactive materials, electronuclear power stations, facilities involved in the nuclear fuel cycle, research facilities and other nuclear installations, the safety of dismantling of nuclear base installations, radioactive wastes and polluted sites and soils

Design analysis of various transportation package options for BN-350 SNF in terms of nuclear radiation safety in planning for long-terms dry storage

International Nuclear Information System (INIS)

Aisabekov, A.Z.; Mukenova, S.A.; Tur, E.S.; Tsyngaev, V.M.

2004-01-01

Full text: This effort is performed under the BN-350 reactor facility decommissioning project. One of the project tasks - spent nuclear fuel handling - includes the following: fuel packaging into sealed canisters, transportation of the canisters in multi-seat metallo-concrete containers and placement of the containers for a long-term dry storage. The goal of this effort is to computationally validate nuclear and radiation safety of the SNF containers placed for storage both under normal storage conditions and probable accident situations. The basic unit structure and design configurations are presented: assemblies, canisters, transportation containers. The major factors influencing nuclear and radiation safety are presented: fuel burn-up, enrichment, fabrication tolerance, types of fuel assemblies, configuration of assemblies in the canister and canisters in the container, background of assemblies placed in the reactor and cooling pool. Conditions under which the SNF containers will be stored are described and probable accident situations are listed. Proceeding from the conservatism principle, selection of the assemblies posing the greatest nuclear hazard is validated. A neutron effective multiplication factor is calculated for the SNF containers under the normal storage conditions and for the case of emergency. The effective multiplication factor is shown to be within a standard value of 0.95 in any situation. Based on the experimental data on assembly and canister dose rates, canisters posing the highest radiation threat are selected. Activities of sources and gamma-radiation spectral composition are calculated. Distribution of the dose rate outside the containers both under the normal storage conditions and accident situations are calculated. The results obtained are analyzed

Nuclear and radiation studies and environmental concerns

International Nuclear Information System (INIS)

McEwan, A.C.

1998-01-01

Over the three days 22-24 September 1998 a Science Forum was convened under the general heading of 'Nuclear technology in relation to water resources and the aquatic environment' at the International Atomic Energy Agency, Vienna. Some points of interest, or points of more particular relevance to radiation protection, are noted from the five sessions of the Forum: Session 1: water resources; Session 2: sea transport of radioactive and nuclear materials; Session 3: monitoring radioactivity in the aquatic environment; Session 4: nuclear technology in relation to waste resources and the aquatic environment, Session 5: impact assessment. (author)

Radiation shielding activities at the OECD/Nuclear Energy Agency

International Nuclear Information System (INIS)

Sartori, Enrico; Vaz, Pedro

2000-01-01

The OECD Nuclear Energy Agency (NEA) has devoted considerable effort over the years to radiation shielding issues. The issues are addressed through international working groups. These activities are carried out in close co-ordination and co-operation with the Radiation Safety Information Computational Center (RSICC). The areas of work include: basic nuclear data activities in support of radiation shielding, computer codes, shipping cask shielding applications, reactor pressure vessel dosimetry, shielding experiments database. The method of work includes organising international code comparison exercises and benchmark studies. Training courses on radiation shielding computer codes are organised regularly including hands-on experience in modelling skills. The scope of the activity covers mainly reactor shields and spent fuel transportation packages, but also fusion neutronics and in particular shielding of accelerators and irradiation facilities. (author)

Computer codes in nuclear safety, radiation transport and dosimetry

International Nuclear Information System (INIS)

Bordy, J.M.; Kodeli, I.; Menard, St.; Bouchet, J.L.; Renard, F.; Martin, E.; Blazy, L.; Voros, S.; Bochud, F.; Laedermann, J.P.; Beaugelin, K.; Makovicka, L.; Quiot, A.; Vermeersch, F.; Roche, H.; Perrin, M.C.; Laye, F.; Bardies, M.; Struelens, L.; Vanhavere, F.; Gschwind, R.; Fernandez, F.; Quesne, B.; Fritsch, P.; Lamart, St.; Crovisier, Ph.; Leservot, A.; Antoni, R.; Huet, Ch.; Thiam, Ch.; Donadille, L.; Monfort, M.; Diop, Ch.; Ricard, M.

2006-01-01

The purpose of this conference was to describe the present state of computer codes dedicated to radiation transport or radiation source assessment or dosimetry. The presentations have been parted into 2 sessions: 1) methodology and 2) uses in industrial or medical or research domains. It appears that 2 different calculation strategies are prevailing, both are based on preliminary Monte-Carlo calculations with data storage. First, quick simulations made from a database of particle histories built though a previous Monte-Carlo simulation and secondly, a neuronal approach involving a learning platform generated through a previous Monte-Carlo simulation. This document gathers the slides of the presentations

Suggestions of radiation protection instruments in ships used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants

International Nuclear Information System (INIS)

Warenmo, G.

1979-01-01

Some radiation protection measures are necessary in ships which will be used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants in order to protect the crew from unnecessarily high radiation doses and to ensure that not allowable values occur. Such measures are discussed in this report as well as suitable radiation protection instruments for such ships. (E.R.)

Transportation of spent nuclear fuels

International Nuclear Information System (INIS)

Meguro, Toshiichi

1976-01-01

The spent nuclear fuel taken out of reactors is cooled in the cooling pool in each power station for a definite time, then transported to a reprocessing plant. At present, there is no reprocessing plant in Japan, therefore the spent nuclear fuel is shipped abroad. In this paper, the experiences and the present situation in Japan are described on the transport of the spent nuclear fuel from light water reactors, centering around the works in Tsuruga Power Station, Japan Atomic Power Co. The spent nuclear fuel in Tsuruga Power Station was first transported in Apr. 1973, and since then, about 36 tons were shipped to Britain by 5 times of transport. The reprocessing plant in Japan is expected to start operation in Apr. 1977, accordingly the spent nuclear fuel used for the trial will be transported in Japan in the latter half of this year. Among the permission and approval required for the transport of spent nuclear fuel, the acquisition of the certificate for transport casks and the approval of land and sea transports are main tasks. The relevant laws are the law concerning the regulations of nuclear raw material, nuclear fuel and reactors and the law concerning the safety of ships. The casks used in Tsuruga Power Station and EXL III type, and the charging of spent nuclear fuel, the decontamination of the casks, the leak test, land transport with a self-running vehicle, loading on board an exclusive carrier and sea transport are briefly explained. The casks and the ship for domestic transport are being prepared. (Kato, I.)

Communications on nuclear, radiation, transport and waste safety: a practical handbook

International Nuclear Information System (INIS)

1999-04-01

Basic requirements to be met by national infrastructures for radiation protection and safety are stated in the International basic safety Standards for Protection against Ionizing radiation and for safety of radiation Sources. These include a requirement 'to set up appropriate means of informing the public, its representatives and the information media about the health and safety aspects of activities involving exposure to radiation and about regulatory processes.' This publication is intended for national regulatory authorities, to provide them with guidance on the principles and methods that can be applied in communicating nuclear safety to different audiences under different circumstances. This report presumes the existence of adequate national infrastructure including an independent regulatory authority with sufficient powers and resources to meet its responsibilities

Introduction to radiation transport

International Nuclear Information System (INIS)

Olson, G.L.

1998-01-01

This lecture will present time-dependent radiation transport where the radiation is coupled to a static medium, i.e., the material is not in motion. In reality, radiation exerts a pressure on the materials it propagates through and will accelerate the material in the direction of the radiation flow. This fully coupled problem with radiation transport and materials in motion is referred to as radiation-hydrodynamics (or in a shorthand notation: rad-hydro) and is beyond the scope of this lecture

Nuclear data for fusion: Validation of typical pre-processing methods for radiation transport calculations

International Nuclear Information System (INIS)

Hutton, T.; Sublet, J.C.; Morgan, L.; Leadbeater, T.W.

2015-01-01

Highlights: • We quantify the effect of processing nuclear data from ENDF to ACE format. • We consider the differences between fission and fusion angular distributions. • C-nat(n,el) at 2.0 MeV has a 0.6% deviation between original and processed data. • Fe-56(n,el) at 14.1 MeV has a 11.0% deviation between original and processed data. • Processed data do not accurately depict ENDF distributions for fusion energies. - Abstract: Nuclear data form the basis of the radiation transport codes used to design and simulate the behaviour of nuclear facilities, such as the ITER and DEMO fusion reactors. Typically these data and codes are biased towards fission and high-energy physics applications yet are still applied to fusion problems. With increasing interest in fusion applications, the lack of fusion specific codes and relevant data libraries is becoming increasingly apparent. Industry standard radiation transport codes require pre-processing of the evaluated data libraries prior to use in simulation. Historically these methods focus on speed of simulation at the cost of accurate data representation. For legacy applications this has not been a major concern, but current fusion needs differ significantly. Pre-processing reconstructs the differential and double differential interaction cross sections with a coarse binned structure, or more recently as a tabulated cumulative distribution function. This work looks at the validity of applying these processing methods to data used in fusion specific calculations in comparison to fission. The relative effects of applying this pre-processing mechanism, to both fission and fusion relevant reaction channels are demonstrated, and as such the poor representation of these distributions for the fusion energy regime. For the nat C(n,el) reaction at 2.0 MeV, the binned differential cross section deviates from the original data by 0.6% on average. For the 56 Fe(n,el) reaction at 14.1 MeV, the deviation increases to 11.0%. We

Radiological emergency: road map for radiation accident victim transport; Emergência radiológica: roadmap para o transporte de radioacidentado

Energy Technology Data Exchange (ETDEWEB)

Costa, V.S.G.; Alcantara, Y.P. [Faculdade Casa Branca, SP (Brazil); Lima, C.M.A. [MAXIM Cursos, Rio de Janeiro, RJ (Brazil); Silva, F. C. A. da, E-mail: franciscodasilva13uk@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2017-07-01

During a radiological or nuclear emergency, a number of necessary actions are taken, both within the radiation protection of individuals and the environment, involving many institutions and highly specialized personnel. Among them it is possible to emphasize the air transportation of radiation accident victims.The procedures and measures for the safe transport of these radiation accident victims are generally the responsibility of the armed forces, specifically the Aeronautics, with the action denominated 'Aeromedical Military Evacuation of Radiation Accident Victims'. The experience with the Radiological Accident of Goiânia demonstrated the importance of adequate preparation and response during a radiological emergency and the need for procedures and measures with regard to the transport of radiation victims are clearly defined and clearly presented for the effectiveness of the actions. This work presents the necessary actions for the transport of radiation accident victim during a radiological emergency, through the road map technique, which has been widely used in scientific technical area to facilitate understanding and show the way to be followed to reach the proposed objectives.

Nuclear instrumentation for radiation measurement

International Nuclear Information System (INIS)

Madan, V.K.

2012-01-01

Nuclear radiation cannot be detected by human senses. Nuclear detectors and associated electronics facilitate detection and measurement of different types of radiation like alpha particles, beta particles, gamma radiation, and detection of neutrons. Nuclear instrumentation has evolved greatly since the discovery of radioactivity. There has been tremendous advancement in detector technology, electronics, computer technology, and development of efficient algorithms and methods for spectral processing to extract precisely qualitative and quantitative information of the radiation. Various types of detectors and nuclear instruments are presently available and are used for different applications. This paper describes nuclear radiation, its detection and measurement and associated electronics, spectral information extraction, and advances in these fields. The paper also describes challenges in this field

High-order discontinuous Galerkin nonlocal transport and energy equations scheme for radiation hydrodynamics

Czech Academy of Sciences Publication Activity Database

Holec, M.; Limpouch, J.; Liska, R.; Weber, Stefan A.

2017-01-01

Roč. 83, č. 10 (2017), s. 779-797 ISSN 0271-2091 R&D Projects: GA MŠk EF15_008/0000162; GA MŠk LQ1606 Grant - others:ELI Beamlines(XE) CZ.02.1.01/0.0/0.0/15_008/0000162 Institutional support: RVO:68378271 Keywords : radiation hydrodynamics * nonlocal transport * Knudsen number * multigroup diffusion * radiation coupling Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders OBOR OECD: Nuclear physics Impact factor: 1.652, year: 2016

Informational system to assist decision making at spent nuclear fuel transportation from VVER-440, VVER-1000 and RBMK-1000 nuclear power plants

International Nuclear Information System (INIS)

Kuryndin, A.V.; Kirkin, A.M.; Stroganov, A.A.

2012-01-01

The developed informational system provides an automated estimations of nuclear and radiation safety parameters during spent nuclear fuel transportation from WWER-440 and WWER-1000 and RBMK-1000 nuclear power plants to the nuclear fuel cycle facilities, and allows us to determine the optimum cask loading from the dose rates distribution outside of protection point of view [ru

Nuclear materials transport worldwide

International Nuclear Information System (INIS)

Stellpflug, J.

1987-01-01

This Greenpeace report shows: nuclear materials transport is an extremely hazardous business. There is no safe protection against accidents, kidnapping, or sabotage. Any moment of a day, at any place, a nuclear transport accident may bring the world to disaster, releasing plutonium or radioactive fission products to the environment. Such an event is not less probable than the MCA at Chernobyl. The author of the book in hand follows the secret track of radioactive materials around the world, from uranium mines to the nuclear power plants, from reprocessing facilities to the waste repositories. He explores the routes of transport and the risks involved, he gives the names of transport firms and discloses incidents and carelessness, tells about damaged waste drums and plutonium that 'disappeared'. He also tells about worldwide, organised resistance to such nuclear transports, explaining the Greenpeace missions on the open sea, or the 'day X' operation at the Gorleben site, informing the reader about protests and actions for a world freed from the threat of nuclear energy. (orig./HP) [de

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

International Nuclear Information System (INIS)

Kirk, Bernadette Lugue

2009-01-01

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries. An important activity of RSICC is its participation in international efforts on computational and experimental benchmarks. An example is the Shielding Integral Benchmarks Archival Database (SINBAD), which includes shielding benchmarks for fission, fusion and accelerators. RSICC is funded by the United States Department of Energy, Department of Homeland Security and Nuclear Regulatory Commission.

Spectral Analysis Method of Plastic Scintillator-based Radiation Detector against Nuclear/Radiological Terrorism

International Nuclear Information System (INIS)

Kwak, Sung-Woo; Yoo, Ho-Sik; Jang, Sung Soon; Kim, Jung-Soo; Yoon, Wan-Ki

2008-01-01

In these days, the threats relating to nuclear or radioactive materials have become a matter of internationally increased grave concern. A plastic scintillation detector in radiation portal monitoring (RPM) application has been used to detect radioactive sources in steel scrap entering reprocessing facilities, and to detect illicit transport of radioactive material across border ports-of-entry. The detection systems for RPM application usually are large and can not easily be moved to a different location. For some situations, an inconspicuous and mobile system for the radioactive or nuclear material during road transport is needed. The mobile radiation detection system has employed a NaI- based radiation detector to detect and identify the material hidden in vehicle. There are some operational constraints - short measuring time, weak activity due to heavy shield of illegal source, long distance - of inspection system in such nuclear security applications. Due to these constraints, large area sensor is required to maximize its sensitivity. Large NaI material, however, is extremely expensive. In designing a radiation detector for prevention of illicit trafficking of nuclear or radioactive materials, the trade-off should be carefully optimized between performance and cost in order to achieve cost-effective inspection system. For the cost-effective mobile radiation detection system, this paper describes new spectral analysis method to use the crude spectroscopic information available from a plastic detector to discriminate other man-made radiation source from NORM

Radiation versus radiation: nuclear energy in perspective

International Nuclear Information System (INIS)

Gonzalez, A.J.; Anderer, J.

1989-01-01

This paper seeks to provide a proper perspective on radiation exposures from nuclear energy. Instead of comparing these exposures with other pollutants, natural and man-made, it assesses the radiation doses that result from the human environment and from the entire fuel cycle associated with nuclear generated electricity. It explores radiation versus radiation, not only in terms of absolute levels but, more importantly, of the enormous variability characterizing many radiation sources. The quantitative findings and their implications are meant to contribute to a balanced understanding of the radiological impact of nuclear energy, and so to help to bridge the information gap that is perceived to exist on this issue. The 1988 Unscear report and its seven scientific annexes provide an authoritative and dispassionate factual basis for examining radiation levels from all sources, natural and man-made. It is the main source for this paper. (author)

Radiation safety in nuclear medicine procedures

International Nuclear Information System (INIS)

Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun

2017-01-01

Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed

Radiation safety in nuclear medicine procedures

Energy Technology Data Exchange (ETDEWEB)

Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun [Dept. of Nuclear Medicine, Medical Radiation Safety Research Center, Chonnam National University Hospital, Gwangju (Korea, Republic of)

2017-03-15

Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed.

National conference on radiation safety of nuclear power plants and their environmental impacts

International Nuclear Information System (INIS)

Moravek, J.

1989-01-01

The first national conference on radiation safety of nuclear power plants and their environmental impacts was held in Tale (CS), 12 to 15 October, 1987 with the participation of 201 Czechoslovak specialists representing central authorities, research institutes, institutions of higher education, power plants in operation and under construction, water management and hygiene inspection and some production sectors, specialists from Hungary, Poland and the GDR. The participants heard 110 papers. The conference agenda comprised keynote papers presented in plenary session and five specialist sessions: 1. Radiation control of discharges and their surroundings. 2. Monitoring and evaluation of the radiation situation in nuclear power plants. 3. Equipment for monitoring the nuclear power plant and its environs. 4. Mathematical modelling and assessment of the nuclear power plant radiation environmental impact. 5. Evaluation of sources and of the transport of radioactive materials inside the power plant and the minimization of the nuclear power plant's environmental impact. (Z.M.)

ASN report of the status of nuclear safety and radiation protection in France in 2012

International Nuclear Information System (INIS)

Chevet, Pierre-Franck; Delmestre, Alain; Bardet, Marie-Christine; Covard, Fabienne; Landrin, Sophie

2013-01-01

After a presentation of the French Nuclear Safety Authority (ASN), its missions, some key figures illustrating its activities and its organisation, this report proposes an overview of marking events and of actions undertaken by the ASN after the Fukushima accident. Then, the report proposes a detailed and commented overview of actions undertaken by the ASN in different fields and domains: nuclear activities, principles and actors of nuclear safety and radiation protection control, regulation, control of nuclear activities and of exposures to ionizing radiations, radiological and post-accidental emergency situations, public information and transparency, international relationships, regional overview of nuclear safety and radiation protection. The last part addresses activities controlled by the ASN: medical use of ionizing radiations, industrial, research and veterinary uses and source safety, transport of radioactive materials, electronuclear plants, installations related to nuclear fuel cycle, nuclear research and other nuclear installations, safety of dismantling of base nuclear installations, radioactive wastes and polluted sites

A review of tsp as one of the transportation security aspects of nuclear materials

International Nuclear Information System (INIS)

Wiryono

2013-01-01

A review has done for the Transportation Safety Plan (TSP) as one of the aspects of safety in the transport of nuclear materials. The review is necessary to harmonize national regulations with international practice. International practice of using TSP as one of the security requirements in addition to the Radiation Protection Program as a requirement of safety in the transport of nuclear materials. TSP is intended to ensure sound implementation of the transport of nuclear materials. TSP evaluation process can be done with a prescriptive approach, performance, and combinations. TSP contains information about administrative requirements, delivery security and response planning. TSP can be used to ensure the security of the implementation of the transport of nuclear materials effectively and efficiently. BAPETEN should require the applicant to submit the TSP as one document security requirements prior approval transporting nuclear materials. BAPETEN need to define the approach to the formulation and evaluation of TSP. BAPETEN need to set up an evaluation and inspection procedures for the implementation of TSP. (author)

Proceedings of the 6. Argentine congress on radiation protection and nuclear safety; Actas del 6. congreso argentino de proteccion radiologica y seguridad nuclear

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-12-31

The 6th Argentine Congress on Radiation Protection and Nuclear Safety was organized by the Radioprotection Argentine Society, in Buenos Aires, between the 22 and 24 of september of 1998. In this event, were presented almost 66 papers in the following sessions, about these subjects: 1.- Safety in nuclear installations. 2.- Control of nuclear material and physical protection of nuclear installations. 3.- Programs of quality assurance. 4.- Training, technical information and public information. 5.- Physical dosimetry. 6.- Physical dosimetry and occupational radiation protection. 7.- Exposure of the natural radiation. 8.- Environmental radiological safety. 9.- Biological effects of the ionizing radiations and biological dosimetry. 10.- Radiological protection of the medical practice and the radiological emergencies. 11.- Radioactive wastes management. 12.- Transport of radioactive materials

Nuclear energy - Radioprotection - Procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation

International Nuclear Information System (INIS)

2002-01-01

This International Standard specifies a procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation and describes the procedure in radiation protection monitoring for external exposure to weakly penetrating radiation in nuclear installations. This radiation comprises β - radiation, β + radiation and conversion electron radiation as well as photon radiation with energies below 15 keV. This International Standard describes the procedure in radiation protection planning and monitoring as well as the measurement and analysis to be applied. It applies to regular nuclear power plant operation including maintenance, waste handling and decommissioning. The recommendations of this International Standard may also be transferred to other nuclear fields including reprocessing, if the area-specific issues are considered. This International Standard may also be applied to radiation protection at accelerator facilities and in nuclear medicine, biology and research facilities

Radiation transport in high-level waste form

International Nuclear Information System (INIS)

Arakali, V.S.; Barnes, S.M.

1992-01-01

The waste form selected for vitrifying high-level nuclear waste stored in underground tanks at West Valley, NY is borosilicate glass. The maximum radiation level at the surface of a canister filled with the high-level waste form is prescribed by repository design criteria for handling and disposition of the vitrified waste. This paper presents an evaluation of the radiation transport characteristics for the vitreous waste form expected to be produced at West Valley and the resulting neutron and gamma dose rates. The maximum gamma and neutron dose rates are estimated to be less than 7500 R/h and 10 mRem/h respectively at the surface of a West Valley canister filled with borosilicate waste glass

The computer code system for reactor radiation shielding in design of nuclear power plant

International Nuclear Information System (INIS)

Li Chunhuai; Fu Shouxin; Liu Guilian

1995-01-01

The computer code system used in reactor radiation shielding design of nuclear power plant includes the source term codes, discrete ordinate transport codes, Monte Carlo and Albedo Monte Carlo codes, kernel integration codes, optimization code, temperature field code, skyshine code, coupling calculation codes and some processing codes for data libraries. This computer code system has more satisfactory variety of codes and complete sets of data library. It is widely used in reactor radiation shielding design and safety analysis of nuclear power plant and other nuclear facilities

Guide to the declaration procedure and coding system for criteria concerning significant events related to safety, radiation protection or the environment, applicable to basic nuclear installations and the transport of radioactive materials

International Nuclear Information System (INIS)

Lacoste, Andre-Claude

2005-01-01

This guide notably contains various forms associated with the declaration of significant events, and explanations to fill them in: significant event declaration form for a basic nuclear installation, significant event declaration form for radioactive material transport, significant event report for a basic nuclear installation, significant event report for radioactive material transport, declaration criteria for significant events related to the safety of non-PWR basic nuclear installations, declaration criteria for significant events related to PWR safety, significant events declared further to events resulting in group 1 unavailability and non-compliance with technical operating specifications, declaration criteria for significant events concerning radiation protection for basic nuclear installations, declaration criteria for significant events concerning environmental protection, applicable to basic nuclear installations, and declaration criteria for significant events concerning radioactive material transport

Evaluation of dose equivalent rate distribution in JCO critical accident by radiation transport calculation

CERN Document Server

Sakamoto, Y

2002-01-01

In the prevention of nuclear disaster, there needs the information on the dose equivalent rate distribution inside and outside the site, and energy spectra. The three dimensional radiation transport calculation code is a useful tool for the site specific detailed analysis with the consideration of facility structures. It is important in the prediction of individual doses in the future countermeasure that the reliability of the evaluation methods of dose equivalent rate distribution and energy spectra by using of Monte Carlo radiation transport calculation code, and the factors which influence the dose equivalent rate distribution outside the site are confirmed. The reliability of radiation transport calculation code and the influence factors of dose equivalent rate distribution were examined through the analyses of critical accident at JCO's uranium processing plant occurred on September 30, 1999. The radiation transport calculations including the burn-up calculations were done by using of the structural info...

Sampling and transport of paraffin waste form from CWDS of nuclear power plant

International Nuclear Information System (INIS)

Lee, J. M.; Hwang, J. H.; Kim, C. R.; Park, J. W.

2000-01-01

Sampling and transport of paraffin waste form from concentrated waste drying system (CWDS) of domestic nuclear power plant were performed to collect the leaching characteristic data for the disposal of radioactive waste. Transport was performed according to the national regulations and the internal rules of the nuclear power plant. The sample of paraffin waste form was classified as L type package according to the regulation and radiation exposure of operator was measured in the range of 6 to 12 mrem that was less than the estimated amount

Transport code and nuclear data in intermediate energy region

Energy Technology Data Exchange (ETDEWEB)

Hasegawa, Akira; Odama, Naomitsu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Maekawa, F.; Ueki, K.; Kosaka, K.; Oyama, Y.

1998-11-01

We briefly reviewed the problems of intermediate energy nuclear data file and transport codes in connection with processing of the data. This is a summary of our group in the task force on JENDL High Energy File Integral Evaluation (JHEFIE). In this article we stress the necessity of the production of intermediate evaluated nuclear data file up to 3 GeV for the application of accelerator driven transmutation (ADT) system. And also we state the necessity of having our own transport code system to calculate the radiation fields using these evaluated files from the strategic points of view to keep our development of the ADT technology completely free from other conditions outside of our own such as imported codes and data with poor maintenance or unknown accuracy. (author)

Transport code and nuclear data in intermediate energy region

International Nuclear Information System (INIS)

Hasegawa, Akira; Odama, Naomitsu; Maekawa, F.; Ueki, K.; Kosaka, K.; Oyama, Y.

1998-01-01

We briefly reviewed the problems of intermediate energy nuclear data file and transport codes in connection with processing of the data. This is a summary of our group in the task force on JENDL High Energy File Integral Evaluation (JHEFIE). In this article we stress the necessity of the production of intermediate evaluated nuclear data file up to 3 GeV for the application of accelerator driven transmutation (ADT) system. And also we state the necessity of having our own transport code system to calculate the radiation fields using these evaluated files from the strategic points of view to keep our development of the ADT technology completely free from other conditions outside of our own such as imported codes and data with poor maintenance or unknown accuracy. (author)

Nuclear radiation and the properties of concrete

International Nuclear Information System (INIS)

Kaplan, M.F.

1983-08-01

Concrete is used for structures in which the concrete is exposed to nuclear radiation. Exposure to nuclear radiation may affect the properties of concrete. The report mentions the types of nuclear radiation while radiation damage in concrete is discussed. Attention is also given to the effects of neutron and gamma radiation on compressive and tensile strength of concrete. Finally radiation shielding, the attenuation of nuclear radiation and the value of concrete as a shielding material is discussed

Nuclear and radiation safety policy

International Nuclear Information System (INIS)

Mikus, T; Strycek, E.

1998-01-01

Slovenske elektrarne (SE) is a producer of electricity and heat, including from nuclear fuel source. The board of SE is ultimately responsible for nuclear and radiation safety matters. In this leaflet main principles of maintaining nuclear and radiation safety of the Company SE are explained

ASN report on the status of nuclear safety and radiation protection in France in 2015. Extracts

International Nuclear Information System (INIS)

2016-01-01

After a recall of ASN missions, key figures and organisation, an overview of main events for 2015, and a presentation of the French law related to energy transition for a green growth, a first part of this huge document presents actions undertaken by the ASN in 2015 in different fields: ionizing radiations and risks for health and the environment, principles and actors of control of nuclear safety and radiation protection, regulation, control of nuclear activities and of exposures to ionizing radiations, emergency radiological and post-accidental situations, public information transparency and participation, international relationships, regional overview of nuclear safety and radiation protection. The second part addresses activities controlled by the ASN: medical uses of ionizing radiations, industrial, research and veterinary uses and source safety, transportation of radioactive materials, EDF nuclear power plants, installations related to nuclear fuel cycle, various industrial and research installations, safety of basic nuclear installation dismantling, radioactive wastes and polluted sites and soils

Detection of nuclear radiations

International Nuclear Information System (INIS)

Tanarro Sanz, A.

1967-01-01

A summary of the lectures about the ordinary detectors of nuclear radiations explained by the author in the courses of Nuclear Engineering held at the J.E.N. up to the date of publication is given. Those lectures are considered to be a necessary introduction to Nuclear Instrumentation and Applied Electronics to Nuclear Engineering so it has been intended to underline those characteristics of radiation detectors that must be taken in consideration in choosing or designing the electronic equipment associated to them in order to take advantage of each detector possibilities. (Author)

Detection of nuclear radiations

International Nuclear Information System (INIS)

Tanarro Sanz, A.

1959-01-01

A summary of the lectures about the ordinary detectors of nuclear radiations given by the author in the Courses of Introduction to Nuclear Engineering held at the JEN up to the date of publication is given. Those lectures are considered to be a necessary introduction to Nuclear Instrumentation and Applied electronics to Nuclear Engineering so it has been intent to underline those characteristics of radiation detectors that must be taken in consideration in choosing or designing the electronic equipment associated to them in order to take advantage of each detector possibilities. (Author) 8 refs

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)

Report by the ASN on the situation of nuclear safety and radiation protection in France in 2013

International Nuclear Information System (INIS)

Chevet, Pierre-Franck; Delmestre, Alain; Bardet, Marie-Christine; Covard, Fabienne; Javay, Olivier

2014-01-01

In its first chapters, this huge report presents the various actions undertaken by the ASN. It proposes a detailed overview of the issue of ionizing radiations and risks for health and for the environment in the field of nuclear activities, presents and comments the principles and actors of the control of nuclear safety and of radiation protection, presents the different elements of the legal framework, describes and comments the control of nuclear activities and of exposures to ionizing radiations. The next chapters address the actions controlled by the ASN: radiological and post-accidental radiological situations, present measures related to public information and transparency, overview of international relationships, regional overview of nuclear safety and radiation protection, medical use of ionizing radiations, industrial, research and veterinary uses and the issue of source safety, the issue of radioactive material transportation. Issues of nuclear safety and radiation protection are then discussed for electronuclear plants, for installations dedicated to the nuclear fuel cycle, for various research and industrial nuclear installations, for the dismantling of base nuclear installations, and for radioactive wastes and polluted sites and soils

Post-graduate course on radiation protection and nuclear safety. Vol. 1,2; Curso de post-grado en proteccion radiologica y seguridad nuclear. Tomo 1,2

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

The course handbook on radiation protection and nuclear safety containing two parts some was prepared mainly by scientists of the Nuclear Regulatory Authority (ARN) of the Argentine Republic, under the auspices of the International Atomic Energy Agency. The contents o this handbook have the principals aspects: radiation detection, radio dosimetry, biological effects of the ionizing radiation, occupational exposure, environmental effects, contamination and decontamination, radioactive waste management, transport of radioactive materials, medical and industrial applications and the Argentine regulatory system.

Celecoxib Induced Tumor Cell Radiosensitization by Inhibiting Radiation Induced Nuclear EGFR Transport and DNA-Repair: A COX-2 Independent Mechanism

International Nuclear Information System (INIS)

Dittmann, Klaus H.; Mayer, Claus; Ohneseit, Petra A.; Raju, Uma; Andratschke, Nickolaus H.; Milas, Luka; Rodemann, H. Peter

2008-01-01

Purpose: The purpose of the study was to elucidate the molecular mechanisms mediating radiosensitization of human tumor cells by the selective cyclooxygenase (COX)-2 inhibitor celecoxib. Methods and Materials: Experiments were performed using bronchial carcinoma cells A549, transformed fibroblasts HH4dd, the FaDu head-and-neck tumor cells, the colon carcinoma cells HCT116, and normal fibroblasts HSF7. Effects of celecoxib treatment were assessed by clonogenic cell survival, Western analysis, and quantification of residual DNA damage by γH 2 AX foci assay. Results: Celecoxib treatment resulted in a pronounced radiosensitization of A549, HCT116, and HSF7 cells, whereas FaDu and HH4dd cells were not radiosensitized. The observed radiosensitization could neither be correlated with basal COX-2 expression pattern nor with basal production of prostaglandin E2, but was depended on the ability of celecoxib to inhibit basal and radiation-induced nuclear transport of epidermal growth factor receptor (EGFR). The nuclear EGFR transport was strongly inhibited in A549-, HSF7-, and COX-2-deficient HCT116 cells, which were radiosensitized, but not in FaDu and HH4dd cells, which resisted celecoxib-induced radiosensitization. Celecoxib inhibited radiation-induced DNA-PK activation in A549, HSF7, and HCT116 cells, but not in FaDu and HH4dd cells. Consequentially, celecoxib increased residual γH2AX foci after irradiation, demonstrating that inhibition of DNA repair has occurred in responsive A549, HCT116, and HSF7 cells only. Conclusions: Celecoxib enhanced radiosensitivity by inhibition of EGFR-mediated mechanisms of radioresistance, a signaling that was independent of COX-2 activity. This novel observation may have therapeutic implications such that COX-2 inhibitors may improve therapeutic efficacy of radiation even in patients whose tumor radioresistance is not dependent on COX-2

Radiation protection in nuclear medicine

International Nuclear Information System (INIS)

Corstens, F.

1989-01-01

Aspects of radiation protection in nuclear medicine and the role of the Dutch Society for Nuclear Medicine in these are discussed. With an effective dose-equivalence of averaged 3 mSv per year per nuclear medical examination and about 200.000 examinations per year in the Netherlands, nuclear medicine contributes only to a small degree to the total averaged radiation dose by medical treating. Nevertheless from the beginning, besides to protection of environment and personnel, much attention has been spent by nuclear physicians to dose reduction with patients. Replacing of relatively long living radionuclides like 131 I by short living radionuclides like 99m Tc is an example. In her education and acknowledgement policy the Dutch Society for Nuclear Medicine spends much attention to aspects of radiation reduction. (author). 3 tabs

Radiation transport phenomena and modeling. Part A: Codes; Part B: Applications with examples

International Nuclear Information System (INIS)

Lorence, L.J. Jr.; Beutler, D.E.

1997-09-01

This report contains the notes from the second session of the 1997 IEEE Nuclear and Space Radiation Effects Conference Short Course on Applying Computer Simulation Tools to Radiation Effects Problems. Part A discusses the physical phenomena modeled in radiation transport codes and various types of algorithmic implementations. Part B gives examples of how these codes can be used to design experiments whose results can be easily analyzed and describes how to calculate quantities of interest for electronic devices

Force Triggers YAP Nuclear Entry by Regulating Transport across Nuclear Pores.

Science.gov (United States)

Elosegui-Artola, Alberto; Andreu, Ion; Beedle, Amy E M; Lezamiz, Ainhoa; Uroz, Marina; Kosmalska, Anita J; Oria, Roger; Kechagia, Jenny Z; Rico-Lastres, Palma; Le Roux, Anabel-Lise; Shanahan, Catherine M; Trepat, Xavier; Navajas, Daniel; Garcia-Manyes, Sergi; Roca-Cusachs, Pere

2017-11-30

YAP is a mechanosensitive transcriptional activator with a critical role in cancer, regeneration, and organ size control. Here, we show that force applied to the nucleus directly drives YAP nuclear translocation by decreasing the mechanical restriction of nuclear pores to molecular transport. Exposure to a stiff environment leads cells to establish a mechanical connection between the nucleus and the cytoskeleton, allowing forces exerted through focal adhesions to reach the nucleus. Force transmission then leads to nuclear flattening, which stretches nuclear pores, reduces their mechanical resistance to molecular transport, and increases YAP nuclear import. The restriction to transport is further regulated by the mechanical stability of the transported protein, which determines both active nuclear transport of YAP and passive transport of small proteins. Our results unveil a mechanosensing mechanism mediated directly by nuclear pores, demonstrated for YAP but with potential general applicability in transcriptional regulation. Copyright © 2017 Elsevier Inc. All rights reserved.

Notification determining technical details concerning measures for transportation of nuclear fuel materials

International Nuclear Information System (INIS)

1977-01-01

These provisions are established on the basis of and to enforce ''The regulation for installation and operation of reactor'', ''The regulation concerning the fabricating business of nuclear fuel'' and ''The regulations concerning the reprocessing business of spent fuel''. The terms used hereinafter are according to those used in such regulations. The limit of radioactivity concentration of things contaminated by the nuclear fuel materials which are not required to be enclosed in vessels is defined in the lists attached. In the applications for the approval of the measures concerning the transport of things remarkably difficult to be enclosed in vessels, the name and the address of the applicant, the kind, quantity, form and constitution of the thing contaminated by the nuclear fuel materials to be transported, the date and route of the transport and the measures for the prevention of injuries during the transport must be written. The limit of quantity of nuclear fuel materials classifying the performance of vessels is defined respectively in the lists attached. The radiation dose rates provided for by the Director General of the Science and Technology Agency concerning transported things and transporting apparatuses are 200 millirem per hour on the surfaces of such things and containers. The nuclear fission materials specified, for which the measures for the prevention of criticality are especially required, include uranium 233, uranium 235, plutonium 238, plutonium 239, plutonium 241, and the chemical compounds of such substances, and the nuclear fuel materials containing one or two and more of such substances, excluding the nuclear fuel materials with less than 15 grams of such uranium and plutonium. (Okada, K.)

Coupled electron-photon radiation transport

International Nuclear Information System (INIS)

Lorence, L.; Kensek, R.P.; Valdez, G.D.; Drumm, C.R.; Fan, W.C.; Powell, J.L.

2000-01-01

Massively-parallel computers allow detailed 3D radiation transport simulations to be performed to analyze the response of complex systems to radiation. This has been recently been demonstrated with the coupled electron-photon Monte Carlo code, ITS. To enable such calculations, the combinatorial geometry capability of ITS was improved. For greater geometrical flexibility, a version of ITS is under development that can track particles in CAD geometries. Deterministic radiation transport codes that utilize an unstructured spatial mesh are also being devised. For electron transport, the authors are investigating second-order forms of the transport equations which, when discretized, yield symmetric positive definite matrices. A novel parallelization strategy, simultaneously solving for spatial and angular unknowns, has been applied to the even- and odd-parity forms of the transport equation on a 2D unstructured spatial mesh. Another second-order form, the self-adjoint angular flux transport equation, also shows promise for electron transport

Current status of radiation transport tools for proliferation and terrorism prevention

International Nuclear Information System (INIS)

Sale, K.E.

2004-01-01

We present the current status and future plans for the set of calculational tools and data bases developed and maintained at LLNL. The calculational tools include the Monte Carlo codes TART and COG as well as the deterministic code ARDRA. In addition to these codes presently in use there is a major development effort for a new massively parallel transport code. An important part of the capability we're developing is a sophisticated user interface, based on a commercial 3-D modeling product, to improve the model development process. A major part of this user interface tool is being developed by Strela under the Nuclear Cities Initiative. Strela has developed a hub-and-spoke technology for code input interconversions (between COG, TART and MCNP) and will produce the plug-ins that extend the capabilities of the 3-D modeler for use as a radiation transport input generator. The major advantages of this approach are the built-in user interface for 3-D modeling and the ability to read a large variety of CAD-file formats. In addition to supporting our current radiation transport codes and developing new capabilities we are working on some nuclear data needs for homeland security. These projects are carried out and the Lawrence Berkeley National Laboratory 88' cyclotron and at the Institute for Nuclear Research of the Nation Academy of Science of Ukraine under and STCU contract. (author)

Radiation protection in nuclear facilities

International Nuclear Information System (INIS)

Piechowski, J.; Lochard, J.; Lefaure, Ch.; Schieber, C.; Schneider, Th; Lecomte, J.F.; Delmont, D.; Boitel, S.; Le Fauconnier, J.P.; Sugier, A; Zerbib, J.C.; Barbey, P.

1998-01-01

Close ties exist between nuclear safety and radiation protection. Nuclear safety is made up of all the arrangements taken to prevent accidents occurring in nuclear facilities, these accidents would certainly involved a radiological aspect. Radiation protection is made up of all the arrangements taken to evaluate and reduce the impact of radiation on workers or population in normal situations or in case of accident. In the fifties the management of radiological hazards was based on the quest for minimal or even zero risk. This formulation could lead to call some activities in question whereas the benefits for the whole society were evident. Now a new attitude more aware of the real risks and of no wasting resources prevails. This attitude is based on the ALARA principle whose purpose is to maintain the exposure to radiation as low as reasonably achievable taking into account social and economic concerns. This document regroups articles illustrating different aspects of the radiation protection in nuclear facilities such as a research center, a waste vitrification workshop and a nuclear power plant. The surveillance of radiological impacts of nuclear sites on environment is examined, a point is made about the pending epidemiologic studies concerning La Hague complex. (A.C.)

Nuclear transport - The regulatory dimension

International Nuclear Information System (INIS)

Green, L.

2002-01-01

The benefits that the peaceful applications of nuclear energy have brought to society are due in no small part to industry's capacity to transport radioactive materials safely, efficiently and reliably. The nuclear transport industry has a vital role in realising a fundamental objective of the International Atomic Energy Agency (IAEA) as stated in its statute to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world. The context in which transports currently take place is complex, and rapidly changing. In many respects transport is being viewed as an integral market issue and not a subsidiary concern. The availability of carriers drives routing decisions and changes in material flows necessitate new approaches to packaging and transport scenarios. Pressures on the transport sector are not without serious consequences; they can cause delays and in some cases cancellation of planned movements. Complex routings and the necessary use of chartered carriers can push up costs and work against cost efficiency. Since the events of 11 September 2001 the security of nuclear transports has contributed an added dimension to how transports take place. Transports of radioactive material have an outstanding safety record, indeed the transport of such materials could be regarded as a model for the transport of other classes of dangerous goods. This safety record is achieved by two inter-related factors. It is due primarily to well founded regulations developed by such key intergovernmental organisations as the IAEA, with the essential contributions of the member states who participate in the implementation of regulations and the review process. It is due also to the professionalism of those in the industry. There is a necessary synergy between the two - between the regulators whose task it is to make and to enforce the rules for safe, efficient and reliable transport and those whose job it is to transport within the rules. It

Detection of nuclear radiations; Deteccion de Radiaciones nucleares

Energy Technology Data Exchange (ETDEWEB)

Tanarro Sanz, A

1967-07-01

A summary of the lectures about the ordinary detectors of nuclear radiations explained by the author in the courses of Nuclear Engineering held at the J.E.N. up to the date of publication is given. Those lectures are considered to be a necessary introduction to Nuclear Instrumentation and Applied Electronics to Nuclear Engineering so it has been intended to underline those characteristics of radiation detectors that must be taken in consideration in choosing or designing the electronic equipment associated to them in order to take advantage of each detector possibilities. (Author)

Detection of nuclear radiations; Detectores de radiaciones nucleares

Energy Technology Data Exchange (ETDEWEB)

Tanarro Sanz, A

1959-07-01

A summary of the lectures about the ordinary detectors of nuclear radiations given by the author in the Courses of Introduction to Nuclear Engineering held at the JEN up to the date of publication is given. Those lectures are considered to be a necessary introduction to Nuclear Instrumentation and Applied electronics to Nuclear Engineering so it has been intent to underline those characteristics of radiation detectors that must be taken in consideration in choosing or designing the electronic equipment associated to them in order to take advantage of each detector possibilities. (Author) 8 refs.

Chambers nuclear energy and radiation dictionary

International Nuclear Information System (INIS)

Walker, P.M.B.

1992-01-01

This Dictionary is designed to make it easier for those who are concerned about nuclear power and radiation to learn more about nuclear energy and to come to an informed opinion. The first two of the 11 chapters which precede the dictionary proper describe the properties of the atomic nucleus which make nuclear energy possible and then the problems which have to be overcome in harnessing this energy. The next two chapters discuss the many different kinds of power stations which rely on fission and then the methods of fusion which may produce power in the next century. There are then two chapters on nuclear safety and on the production and enrichment of uranium fuel, together with methods for its eventual disposal. These are followed by a chapter on nuclear bombs of various kinds and one on how nuclear and other forms of radiation can be detected. There is then a chapter which relates the radiation resulting from nuclear fission to other kinds of radiation. The next chapter discusses some basic biology particularly cancer. Finally, the biological effects of radiation are described before comparing the amounts of man-made radiation to that which comes naturally from outer space and from the rocks beneath us. This then leads to the radiation limits which are determined by the various regulartory authorities and the kinds of evidence upon which their decisions are based. (Author)

Nuclear radiation and its role in general nuclear medicine

International Nuclear Information System (INIS)

Kempaiah, A.; Ravi, C.

2012-01-01

Radiation is really nothing more than the emission of energy through space, as well as through physical objects. Nuclear radiations are emitted due to decay of nuclei of radioactive materials and damage cells and the DNA inside them through its ionizing effect. That causes melanoma and other cancers. Nuclear radiation has a number of beneficial uses especially in medical field with low levels of radioactive compounds, better than X-rays. There are some 440 nuclear reactors worldwide, people around will be under the effect of radiation. In nuclear medicine (medical imaging) small amount of radioactive materials were used to diagnose and determine the severity of or treat a variety of disease, including many types of cancers, heart disease, gastrointestinal, endocrine, neurological disorders and other abnormalities within the body it is painless and cost-effective techniques and provides information about both structure and function. Nuclear medicine diagnostic procedures called Gamma camera, single photon emission computed tomography (SPECT) and positron emission tomography (PET) were discussed in this paper. (author)

NASA space radiation transport code development consortium

International Nuclear Information System (INIS)

Townsend, L. W.

2005-01-01

Recently, NASA established a consortium involving the Univ. of Tennessee (lead institution), the Univ. of Houston, Roanoke College and various government and national laboratories, to accelerate the development of a standard set of radiation transport computer codes for NASA human exploration applications. This effort involves further improvements of the Monte Carlo codes HETC and FLUKA and the deterministic code HZETRN, including developing nuclear reaction databases necessary to extend the Monte Carlo codes to carry out heavy ion transport, and extending HZETRN to three dimensions. The improved codes will be validated by comparing predictions with measured laboratory transport data, provided by an experimental measurements consortium, and measurements in the upper atmosphere on the balloon-borne Deep Space Test Bed (DSTB). In this paper, we present an overview of the consortium members and the current status and future plans of consortium efforts to meet the research goals and objectives of this extensive undertaking. (authors)

Nuclear radiation sensors and monitoring following a nuclear or radiological emergencies

International Nuclear Information System (INIS)

Bhatnagar, P.K.

2009-01-01

Management of Nuclear and Radiological Emergencies arising from Radiological Dispersive Device (RDD), Improvised Nuclear Devices (IND), Nuclear Reactors/Power plants and Nuclear War require measurement of ionizing radiations and radioactivity on an enhanced scale relative to the levels encountered in peaceful uses of ionizing radiations and radioactivity. It is heartening that since Hiroshima, Nagasaki nuclear disaster, the world has been quiet but since early 2000 there has been a fear of certain devices to be used by terrorists, which could lead to panic, and disaster due to dispersal of radioactivity by RDD, IND. Nuclear attack would lead to blast, thermal, initial nuclear radiation, nuclear fall out leading to gamma and neutron dose, dose rates in range from few R, R/h to kR, kR/h, and determinations of k Bq or higher order. Such situations have been visualized at national levels and National Disaster Management Authority NDMA has been established and Disaster Management Act 2005 has come into existence. NDMA has prepared guidelines for Nuclear and radiological emergency management highlighting preparedness, mitigation, response, capacity building, etc. Critical point in all these issues is detection of emergency, quick intimation to the concerned for action in shortest possible time. Upper most requirement by those involved in pursuing action, is radiation sensor based radiation monitors for personnel, area, and to assess contamination due to radioactivity.This presentation briefly describes the Indian scenario in the development of the radiation sensors and the sensor-based radiation monitors. (author)

Nuclear radiation sensors and monitoring following a nuclear or radiological emergencies

Energy Technology Data Exchange (ETDEWEB)

Bhatnagar, P K [Defence Laboratory, Jodhpur (India)

2009-01-15

Management of Nuclear and Radiological Emergencies arising from Radiological Dispersive Device (RDD), Improvised Nuclear Devices (IND), Nuclear Reactors/Power plants and Nuclear War require measurement of ionizing radiations and radioactivity on an enhanced scale relative to the levels encountered in peaceful uses of ionizing radiations and radioactivity. It is heartening that since Hiroshima, Nagasaki nuclear disaster, the world has been quiet but since early 2000 there has been a fear of certain devices to be used by terrorists, which could lead to panic, and disaster due to dispersal of radioactivity by RDD, IND. Nuclear attack would lead to blast, thermal, initial nuclear radiation, nuclear fall out leading to gamma and neutron dose, dose rates in range from few R, R/h to kR, kR/h, and determinations of k Bq or higher order. Such situations have been visualized at national levels and National Disaster Management Authority NDMA has been established and Disaster Management Act 2005 has come into existence. NDMA has prepared guidelines for Nuclear and radiological emergency management highlighting preparedness, mitigation, response, capacity building, etc. Critical point in all these issues is detection of emergency, quick intimation to the concerned for action in shortest possible time. Upper most requirement by those involved in pursuing action, is radiation sensor based radiation monitors for personnel, area, and to assess contamination due to radioactivity.This presentation briefly describes the Indian scenario in the development of the radiation sensors and the sensor-based radiation monitors. (author)

Nuclear radiation in water

International Nuclear Information System (INIS)

Abrams, H.L.

1989-01-01

The manifestations of acute radiation sickness in the post-nuclear attack period must be recognized and understood in order to apply therapeutic measure appropriately. The syndromes observed-hematopoietic, gastrointestinal, central nervous system-are dose dependent and vary in the degree of patient impairment and lethality. Estimates of mortality and morbidity following a massive exchange vary profoundly, depending on the targeting scenarios, the modes employed, and the meteorologic conditions anticipated. Even the LD-50 dose remain the subject of controversy. Using a US Government model of such an exchange, an estimated 23 million survivors would have radiation sickness, frequently complicated by trauma and burns. Among these survivors, an overriding consideration will be the presence and extent of infection, associated with alterations in the immune system, malnutrition, dehydration, exposure and hardship. Triage and treatment will be extraordinarily complex, requiring patient relocation, massive fluid replacement, antibiotics, a sterile environment , and many other measures. Massive disparities between supply and demand for physicians, nurses, other health workers, hospital beds, supplies and equipment, antibiotics, and other pharmaceutical agents will render a coherent physician response virtually impossible. Such disparities will be compounded by the destruction of transport systems and intolerably high radiation levels in many areas. If it is true that the meliorative efforts of physicians in post-attack radiation damage will be incapable of addressing this massive health care problem meaningfully, then clearly their most effective role is to prevent the threat from materializing. (authors)

Radiation protection on nuclear medicine services

International Nuclear Information System (INIS)

Anon

2000-01-01

Nuclear medicine is a sector of the medicine that studies and applies radionuclide in diagnosis and therapy. Nuclear medicine is a very specific area of the medicine, making use of non-sealed radioactive sources which are prescribed to the patient orally or are injected. Special procedures in radiation protection are required in nuclear medicine to manipulate these kind of sources and to produce technetium-99m through molybdenum generator. The present paper addresses the them radiation protection in a Nuclear Medicine Department (NMD), showing the main requirements of the CNEN- National Commission of Nuclear Energy and the Public Health. Radiation protection procedures adopted in assembling a NMD, as well the daily techniques for monitoring and for individual dosimetry are discussed. Past and present analyses in a level of radiation protection are presented. (author)

Radiation physics for nuclear medicine

CERN Document Server

Hoeschen, Christoph

2011-01-01

The field of nuclear medicine is expanding rapidly, with the development of exciting new diagnostic methods and treatments. This growth is closely associated with significant advances in radiation physics. In this book, acknowledged experts explain the basic principles of radiation physics in relation to nuclear medicine and examine important novel approaches in the field. The first section is devoted to what might be termed the "building blocks" of nuclear medicine, including the mechanisms of interaction between radiation and matter and Monte Carlo codes. In subsequent sections, radiation sources for medical applications, radiopharmaceutical development and production, and radiation detectors are discussed in detail. New frontiers are then explored, including improved algorithms for image reconstruction, biokinetic models, and voxel phantoms for internal dosimetry. Both trainees and experienced practitioners and researchers will find this book to be an invaluable source of up-to-date information.

Nuclear materials transportation

International Nuclear Information System (INIS)

Ushakov, B.A.

1986-01-01

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

Design of radiation shields in nuclear reactor core

International Nuclear Information System (INIS)

Mousavi Shirazi, A.; Daneshvar, Sh.; Aghanajafi, C.; Jahanfarnia, Gh.; Rahgoshay, M.

2008-01-01

This article consists of designing radiation shields in the core of nuclear reactors to control and restrain the harmful nuclear radiations in the nuclear reactor cores. The radiation shields protect the loss of energy. caused by nuclear radiation in a nuclear reactor core and consequently, they cause to increase the efficiency of the reactor and decrease the risk of being under harmful radiations for the staff. In order to design these shields, by making advantages of the O ppenheim Electrical Network m ethod, the structure of the shields are physically simulated and by obtaining a special algorithm, the amount of optimized energy caused by nuclear radiations, is calculated

Experiences in certification of packages for transportation of fresh nuclear fuel in the context of new safety requirements established by IAEA regulations (IAEA-96 regulations, ST-1) for air transportation of nuclear materials (requirements to C-type packages)

Energy Technology Data Exchange (ETDEWEB)

Dudai, V.I.; Kovtun, A.D.; Matveev, V.Z.; Morenko, A.I.; Nilulin, V.M.; Shapovalov, V.I.; Yakushev, V.A.; Bobrovsky, V.S.; Rozhkov, V.V.; Agapov, A.M.; Kolesnikov, A.S. [Russian Federal Nuclear Centre - All-Russian Research Inst. of Experimental Physics, Sarov (Russian Federation)]|[JSC ' ' MSZ' ' , Electrostal (Russian Federation)]|[JSC ' ' NPCC' ' , Novosibirsk (Russian Federation)]|[Minatom of Russia, Moscow (Russian Federation)]|[Gosatomnadzor of Russia, Moscow (Russian Federation)

2004-07-01

Every year in Russia, a large amount of domestic and international transportation of fresh nuclear fuel (FNF) used in Russian and foreign energy and research atomic reactors and referred to fissile materials based on IAEA Regulations is performed. Here, bulk transportation is performed by air, and it concerns international transportation in particular. According to national ''Main Regulations for Safe Transport and physical Protection of Nuclear Materials (OPBZ- 83)'' and ''Regulations for the Safe Transport of Radioactive Materials'' of the International Atomic Energy Agency (IAEA Regulations), nuclear and radiation security under normal (accident free) and accident conditions of transport must be completely provided by the package design. In this context, high requirements to fissile packages exposed to heat and mechanical loads in transport accidents are imposed. A long-standing experience in accident free transportation of FM has shown that such approach to provide nuclear and radiation security pays for itself completely. Nevertheless, once in 10 years the International Atomic Energy Agency on every revision of the ''Regulations for the Safe Transport of Radioactive Materials'' places more stringent requirements upon the FM and transportation thereof, resulting from the objectively increasing risk associated with constant rise in volume and density of transportation, and also strained social and economical situation in a number of regions in the world. In the new edition of the IAEA Regulations (ST-1), published in 1996 and brought into force in 2001 (IAEA-96 Regulations), the requirements to FM packages conveyed by aircraft were radically changed. These requirements are completely presented in new Russian ''Regulations for the Safe Transport of Radioactive Materials'' (PBTRM- 2004) which will be brought into force in the time ahead.

Radiation hazards in the nuclear medicine

International Nuclear Information System (INIS)

Roo, M.J.K. de

1981-01-01

After a survey of the actual situation of nuclear medicine in Belgium, the evolution of nuclear medicine is studied with regard to quantitative aspects (tracerquantities, number of radioisotopic explorations, number of certified doctors) and qualitative aspects (use of short living isotopes emitting low energy radiation, introduction of in vitro tests). Taking these data into consideration, the exposure of nuclear medicine staff by external or internal radiation is evaluated. From this study it appears that the radiation exposure of the personnel of nuclear medicine departments remains low if proper manipulation methods and simple protective devices are used and if there is an efficient collaboration with an active health physics department or radiation control organism. (author)

Regulatory practices of radiation safety of SNF transportation in Russia

International Nuclear Information System (INIS)

Kuryndina, Lidia; Kuryndin, Anton; Stroganov, Anatoly

2008-01-01

This paper overviews current regulatory practices for the assurance of nuclear and radiation safety during railway transportation of SNF on the territory of Russian Federation from NPPs to longterm-storage of reprocessing sites. The legal and regulatory requirements (mostly compliant with IAEA ST-1), licensing procedure for NM transportation are discussed. The current procedure does not require a regulatory approval for each particular shipment if the SNF fully comply with the Rosatom's branch standard and is transported in approved casks. It has been demonstrated that SNF packages compliant with the branch standard, which is knowingly provide sufficient safety margin, will conform to the federal level regulations. The regulatory approval is required if a particular shipment does not comply with the branch standard. In this case, the shipment can be approved only after regulatory review of Applicant's documents to demonstrate that the shipment still conformant to the higher level (federal) regulations. The regulatory review frequently needs a full calculation test of the radiation safety assurance. This test can take a lot of time. That's why the special calculation tools were created in SEC NRS. These tools aimed for precision calculation of the radiation safety parameters by SNF transportation use preliminary calculated Green's functions. Such approach allows quickly simulate any source distribution and optimize spent fuel assemblies placement in cask due to the transport equation property of linearity relatively the source. The short description of calculation tools are presented. Also, the paper discusses foreseen implications related to transportation of mixed-oxide SNF. (author)

Integrated nuclear and radiation protection systems

International Nuclear Information System (INIS)

Oprea, I.; Oprea, M.; Stoica, V.; Cerga, V.; Pirvu, V.; Badea, E.

1993-01-01

A multifunctional radiation monitoring equipment, flexible and capable to meet virtually environmental radiation monitoring, activity measurement and computational requirements, for nuclear laboratories has been designed. It can be used as a radiation protection system, for radionuclide measurement in isotope laboratories, nuclear technology, health physics and nuclear medicine, nuclear power stations and nuclear industry. The equipment is able to measure, transmit and record gamma dose rate and isotope activities. Other parameters and functions are optionally available, such as: self-contained alarm level, system self-test, dose integrator, syringe volume calculation for a given dose corrected for decay, calibration factor, 99 Mo assays performing and background subtraction

Validation of comprehensive space radiation transport code

International Nuclear Information System (INIS)

Shinn, J.L.; Simonsen, L.C.; Cucinotta, F.A.

1998-01-01

The HZETRN code has been developed over the past decade to evaluate the local radiation fields within sensitive materials on spacecraft in the space environment. Most of the more important nuclear and atomic processes are now modeled and evaluation within a complex spacecraft geometry with differing material components, including transition effects across boundaries of dissimilar materials, are included. The atomic/nuclear database and transport procedures have received limited validation in laboratory testing with high energy ion beams. The codes have been applied in design of the SAGE-III instrument resulting in material changes to control injurious neutron production, in the study of the Space Shuttle single event upsets, and in validation with space measurements (particle telescopes, tissue equivalent proportional counters, CR-39) on Shuttle and Mir. The present paper reviews the code development and presents recent results in laboratory and space flight validation

Deterministic methods in radiation transport

International Nuclear Information System (INIS)

Rice, A.F.; Roussin, R.W.

1992-06-01

The Seminar on Deterministic Methods in Radiation Transport was held February 4--5, 1992, in Oak Ridge, Tennessee. Eleven presentations were made and the full papers are published in this report, along with three that were submitted but not given orally. These papers represent a good overview of the state of the art in the deterministic solution of radiation transport problems for a variety of applications of current interest to the Radiation Shielding Information Center user community

Report on SUJB results achieved in the surveillance of nuclear facilities and radiation protection for 2005. Pt. 1

International Nuclear Information System (INIS)

2006-01-01

This part of the report consists of the following chapters: (1) State Office for Nuclear Safety; (2) Nuclear safety; (3) Spent fuel, rad-waste management, decommissioning; (4) Transport of nuclear materials, physical protection; (5) Radiation protection; (6) Emergency preparedness; (7) Radiation Monitoring Network in the Czech Republic; (8) Non -proliferation, nuclear, biological and chemical weapons; (9) International cooperation; (10) Science and research; (11) Free access to information; (12) Activities of institutes controlled by the State Office for Nuclear Safety. It is concluded that the operation of all Czech nuclear facilities, including the Dukovany and Temelin nuclear power plants, was safe and reliable in 2005. (P.A.)

Inspection of nuclear fuel transport in Spain

International Nuclear Information System (INIS)

Lobo Mendez, J.

1977-01-01

The experience acquired in inspecting nuclear fuel shipments carried out in Spain will serve as a basis for establishing the regulations wich must be adhered to for future transports, as the transport of nuclear fuels in Spain will increase considerably within the next years as a result of the Spanish nuclear program. The experience acquired in nuclear fuel transport inspection is described. (author) [es

Activity transport in nuclear reactors

International Nuclear Information System (INIS)

Narasimhan, S.V.

2000-01-01

The chemistry of the primary coolant is such that the general material loss is immeasurably low. However, the generation of radioactive corrosion products in the coolant, their transportation and distribution to different out of core surfaces occur irrevocably through the life cycle of the reactor. This phenomena leading to the build up of radiation field, which is unique to the nuclear reactor systems, is the only major problem of any significance. Minimization of this phenomenon can be done by many ways. The processes involved in the mechanism of activity transport are quite complex and are not at all thoroughly understood. The codes that have been developed so far use many empirical coefficients for some of the rate processes, which are either partially justified by simulated experimental studies or supported theoretically. In a multi-metal system like that of the reactor, the corrosion rates or release rates need not be similar especially in reactors like PHWRs. The mechanisms involved in the formation of protective oxide coating are quite complex to model in a simplified manner. The paper brings out some these features involved in the activity transport modeling and analyses the need for extensive field related experimental work to substantiate the model. (author)

Role of visualization of nuclear radiation in public education on atomic energy. Visualization of natural nuclear radiation using a cloud chamber

International Nuclear Information System (INIS)

Kaneko, Junichi H.; Fujita, Fumiyuki; Narabayashi, Tadashi

2008-01-01

Nuclear radiation is indispensable tool, i.e., medical diagnostic systems and industrial nondestructive measurement systems, for our life. On the other hand, ordinary people sometimes have bad image for nuclear radiation. To improve this undesirable situation, many individuals and groups keep holding public educational meeting on nuclear radiation. For this purpose, visualization of natural nuclear radiation by a cloud chamber is very effective way; participants feel existence of nuclear radiation directly. In this talk, public educational activity of Hokkaido University and Japan Atomic Energy Society Hokkaido branch will be reported. (author)

Atmospheric Ionizing Radiation and the High Speed Civil Transport. Chapter 1

Science.gov (United States)

Maiden, D. L.; Wilson, J. W.; Jones, I. W.; Goldhagen, P.

2003-01-01

Atmospheric ionizing radiation is produced by extraterrestrial radiations incident on the Earth's atmosphere. These extraterrestrial radiations are of two sources: ever present galactic cosmic rays with origin outside the solar system and transient solar particle events that are at times very intense events associated with solar activity lasting several hours to a few days. Although the galactic radiation penetrating through the atmosphere to the ground is low in intensity, the intensity is more than two orders of magnitude greater at commercial aircraft altitudes. The radiation levels at the higher altitudes of the High Speed Civil Transport (HSCT) are an additional factor of two higher. Ionizing radiation produces chemically active radicals in biological tissues that alter the cell function or result in cell death. Protection standards against low levels of ionizing radiation are based on limitation of excess cancer mortality or limitation of developmental injury resulting in permanent damage to the offspring during pregnancy. The crews of commercial air transport operations are considered as radiation workers by the EPA, the FAA, and the International Commission on Radiological Protection (ICRP). The annual exposures of aircrews depend on the latitudes and altitudes of operation and flight time. Flight hours have significantly increased since deregulation of the airline industry in the 1980's. The FAA estimates annual subsonic aircrew exposures to range from 0.2 to 9.1 mSv compared to 0.5 mSv exposure of the average nuclear power plant worker in the nuclear industry. The commercial aircrews of the HSCT may receive exposures above recently recommended allowable limits for even radiation workers if flying their allowable number of flight hours. An adequate protection philosophy for background exposures in HSCT commercial airtraffic cannot be developed at this time due to current uncertainty in environmental levels. In addition, if a large solar particle event

Computational Modeling of Radiation Phenomenon in SiC for Nuclear Applications

Science.gov (United States)

Ko, Hyunseok

Silicon carbide (SiC) material has been investigated for promising nuclear materials owing to its superior thermo-mechanical properties, and low neutron cross-section. While the interest in SiC has been increasing, the lack of fundamental understanding in many radiation phenomena is an important issue. More specifically, these phenomena in SiC include the fission gas transport, radiation induced defects and its evolution, radiation effects on the mechanical stability, matrix brittleness of SiC composites, and low thermal conductivities of SiC composites. To better design SiC and SiC composite materials for various nuclear applications, understanding each phenomenon and its significance under specific reactor conditions is important. In this thesis, we used various modeling approaches to understand the fundamental radiation phenomena in SiC for nuclear applications in three aspects: (a) fission product diffusion through SiC, (b) optimization of thermodynamic stable self-interstitial atom clusters, (c) interface effect in SiC composite and their change upon radiation. In (a) fission product transport work, we proposed that Ag/Cs diffusion in high energy grain boundaries may be the upper boundary in unirradiated SiC at relevant temperature, and radiation enhanced diffusion is responsible for fast diffusion measured in post-irradiated fuel particles. For (b) the self-interstitial cluster work, thermodynamically stable clusters are identified as a function of cluster size, shape, and compositions using a genetic algorithm. We found that there are compositional and configurational transitions for stable clusters as the cluster size increases. For (c) the interface effect in SiC composite, we investigated recently proposed interface, which is CNT reinforced SiC composite. The analytical model suggests that CNT/SiC composites have attractive mechanical and thermal properties, and these fortify the argument that SiC composites are good candidate materials for the cladding

7th Expert meeting radiation protection. International developments, waste management, challenges for the radiation protection in aging nuclear installations

International Nuclear Information System (INIS)

2010-01-01

The proceedings of the 7th Expert meeting on radiation protection include contributions to the following topics: nuclear power and public opinion, IAEA safety standards, ISOE - information system on occupational exposure, European harmonization of the radiation protection education, WANO - challenges and results, CTBTO's global radiation measurement network, state of final radioactive waste disposal in Germany and worldwide, radioactive waste management and disposal in French NPPs, preparedness for final waste disposal in Schacht Konrad, actualization of the transport study Konrad, transport of NPPs' operational radioactive waste and waste from decommissioned reactor demolition to the final repository Konrad, qualification of radioactive waste casks for the final repository Konrad, radioactive waste disposal management concept in Switzerland, aging management and radiation protection, decontamination as effective measure for dose rate reduction - long-term and sustainable dose rate reduction by primary circuit decontamination, system and component decontamination for individual and collective dose reduction - practical examples, radiation protection map - electronic assistance for work planning, EPR dismantling already today? radiation protection register 2002-2010 - knowledge based on a decade of radiation monitoring, actual information on radiation protection in medicine, mobile telecommunication - actual research results.

Thermal radiation in gas core nuclear reactors for space propulsion

International Nuclear Information System (INIS)

Slutz, S.A.; Gauntt, R.O.; Harms, G.A.; Latham, T.; Roman, W.; Rodgers, R.J.

1994-01-01

A diffusive model of the radial transport of thermal radiation out of a cylindrical core of fissioning plasma is presented. The diffusion approximation is appropriate because the opacity of uranium is very high at the temperatures of interest (greater than 3000 K). We make one additional simplification of assuming constant opacity throughout the fuel. This allows the complete set of solutions to be expressed as a single function. This function is approximated analytically to facilitate parametric studies of the performance of a test module of the nuclear light bulb gas-core nuclear-rocket-engine concept, in the Annular Core Research Reactor at Sandia National Laboratories. Our findings indicate that radiation temperatures in range of 4000-6000 K are attainable, which is sufficient to test the high specific impulse potential (approximately 2000 s) of this concept. 15 refs

The Next Nuclear Gamble. Transportation and storage of nuclear waste

International Nuclear Information System (INIS)

Resnikoff, M.

1985-01-01

The Next Nuclear Gamble examines risks, costs, and alternatives in handling irradiated nuclear fuel. The debate over nuclear power and the disposal of its high-level radioactive waste is now nearly four decades old. Ever larger quantities of commercial radioactive fuel continue to accumulate in reactor storage pools throughout the country and no permanent storage solution has yet been designated. As an interim solution, the government and utilities prefer that radioactive wastes be transported to temporary storage facilities and subsequently to a permanent depository. If this temporary and centralized storage system is implemented, however, the number of nuclear waste shipments on the highway will increase one hundredfold over the next fifteen years. The question directly addressed is whether nuclear transport is safe or represents the American public's domestic nuclear gamble. This Council on Economic Priorities study, directed by Marvin Resnikoff, shows on the basis of hundreds of government and industry reports, interviews and surveys, and original research, that transportation of nuclear materials as currently practiced is unsafe

3D-TRANS-2003, Workshop on Common Tools and Interfaces for Radiation Transport Codes

International Nuclear Information System (INIS)

2004-01-01

Description: Contents proceedings of Workshop on Common Tools and Interfaces for Deterministic Radiation Transport, for Monte Carlo and Hybrid Codes with a proposal to develop the following: GERALD - A General Environment for Radiation Analysis and Design. GERALD intends to create a unifying software environment where the user can define, solve and analyse a nuclear radiation transport problem using available numerical tools seamlessly. This environment will serve many purposes: teaching, research, industrial needs. It will also help to preserve the existing analytical and numerical knowledge base. This could represent a significant step towards solving the legacy problem. This activity should contribute to attracting young engineers to nuclear science and engineering and contribute to competence and knowledge preservation and management. This proposal was made at the on Workshop on C ommon Tools and Interfaces for Deterministic Radiation Transport, for Monte Carlo and Hybrid Codes , held from 25-26 September 2003 in connection with the conference SNA-2003. A first success with the development of such tools was achieved with the BOT3P2.0 and 3.0 codes providing an easy procedure and mechanism for defining and displaying 3D geometries and materials both in the form of refineable meshes for deterministic codes or Monte Carlo geometries consistent with deterministic models. Advanced SUSD: Improved tools for Sensitivity/Uncertainty Analysis. The development of tools for the analysis and estimation of sensitivities and uncertainties in calculations, or their propagation through complex computational schemes, in the field of neutronics, thermal hydraulics and also thermo-mechanics is of increasing importance for research and engineering applications. These tools allow establishing better margins for engineering designs and for the safe operation of nuclear facilities. Such tools are not sufficiently developed, but their need is increasingly evident in many activities

Problems relating to international transport of nuclear fuels

International Nuclear Information System (INIS)

Timm, U.E.

1985-01-01

Owing to the tremendous geographic distances between uranium deposits of interest, to the various degrees of sophistication of nuclear industry in industrialized countries and to the close international cooperation in the field of nuclear energy, safe international transports, physical protection and transport handling play an important role. It is suggested to better coordinate the activities of nuclear power plant operators, the nuclear industry and specialized transport companies with respect to all national and international issues of nuclear fuel transports. (DG) [de

BNFL's experience in preparing and implementing radiation protection programmes for the control of exposure to workers involved with the international transport of nuclear cargoes

International Nuclear Information System (INIS)

Billing, D.

2004-01-01

BNFL International Transport have successfully developed appropriate Radiation Protection Programmes for their business. The business supports BNFL's worldwide Nuclear Fuel Services with key customer bases in Europe, Japan and the UK, utilising marine, rail and road modal transports. Experience in the business spans over 4 decades. The preparation of RPP's for each aspect of its operations has been made relatively straight forward in that the key elements within the internationally recognised model RPP (by WNTI) were already in place in BNFL's procedures to satisfy current National UK and International Regulations. Arrangements are supported by Management systems which comply with International Standards for Quality Assurance. Exposure to key worker groups continues to be within Category 1 (less than 1mSv/y) of the IAEA Transport Regulations TS-R-1 (ST-1 revised)

Determination of technical details concerning measures for transportation of nuclear fuel materials in the works or the enterprise

International Nuclear Information System (INIS)

1979-01-01

The determination is defined under the regulations concerning the fabricating business of nuclear fuel materials, the regulation concerning installation and operation of test reactor, the regulations concerning the reprocessing business of spent fuel and the regulations concerning the uses of nuclear source materials. The notification determining technical details concerning measures for transportation of nuclear fuel materials is abolished. Measures for prevention of hazard designated by the Director General of Science and Technology Agency include such ones not to let radioactive materials easily fly about or leak in regular transport, not to let rain water easily penetrate or make each exterior side of a cubic load more than 10 centi-meters. The application for permission shall be filed for transportation of things highly difficult to be sealed in a vessel, listing name and address of the applicant, kind, quantity, form and nature of the load contaminated by nuclear fuel materials, date and route of transfer and measures taken for prevention of hazard in transport. Radiation doses of load and transporting apparatus are stipulated by the Director for an hour as 200 mili-rem on the surface of load, 10 mili-rem at the distance of 1 meter from the surface of load, and 200 mili-rem on the surface of the vehicle, etc. Dangerous things, signals and radiation dose of particular loads are specified respectively. (Okada, K.)

Transport device for nuclear fuel powder

International Nuclear Information System (INIS)

Adelmann, M.

1987-01-01

The transport device for nuclear fuel powder, which does not disintegrate during transport, has a transport pipe which starts with its entry end from the floor or a closed container and opens with its outlet end at the top into a closed separation container connect via a powder filter to a suction pump. By alternate regular opening and closing of a first control valve for transport gas fitted to a transport pipe to a supply duct and a second control valve for transport gas fitted to the container to an additional supply duct, alternating plugs of nuclear fuel powder and transport gas cushions are formed and are transported to the outlet end of the transport pipe. (orig./HP) [de

Current status of radiation transport tools for proliferation and terrorism prevention

International Nuclear Information System (INIS)

Sale, K.E.

2004-01-01

Full text: We will present the current status and future plans for the set of calculational tools and databases developed and maintained at LLNL. The calculational tools include the Monte Carlo codes TART 1) and COG 2) as well as the deterministic code ARDRA 3) . In addition to these codes we use currently there is a major development effort for a new massively parallel transport code. An important part of the capability we're developing is a sophisticated user interface, based on a commercial 3-D modeling product, to improve the model development process. A major part of this user interface tool is being developed by Strela 4) under the Nuclear Cities Initiative. Strela has developed a hub-and-spoke technology for code input interconversions (between COG, TART and MCNP) and will produce the plug-ins that extend the capabilities of the 3-D modeler for use as a radiation transport input generator. The major advantages of this approach are the built-in user interface for 3-D modeling and the ability to read a large variety of CAD-file formats. In addition to supporting our current radiation transport codes and developing new capabilities we are working on some nuclear data needs for homeland security. These projects are carried out and the Lawrence Berkeley National Laboratory 88' cyclotron and at the Institute for Nuclear Research of the Nation Academy of Science of Ukraine under and STCU contract. Reference: 1. http://www.llnl.gov/cullen1/mc/htm; 2. http://www-phys.llnl.gov/N_Div/COG/ETR/ETR_9306.html; 3. http://www.llnl.gov/CASC/asciturb/talks/PPT-HTML.131596/tsld030.htm; 4. http://strela.snz.ru/

Transport Properties in Nuclear Pasta

Science.gov (United States)

Caplan, Matthew; Horowitz, Charles; Berry, Donald; da Silva Schneider, Andre

2016-09-01

At the base of the inner crust of neutron stars, where matter is near the nuclear saturation density, nuclear matter arranges itself into exotic shapes such as cylinders and slabs, called `nuclear pasta.' Lepton scattering from these structures may govern the transport properties of the inner crust; electron scattering from protons in the pasta determines the thermal and electrical conductivity, as well as the shear viscosity of the inner crust. These properties may vary in pasta structures which form at various densities, temperatures, and proton fractions. In this talk, we report on our calculations of lepton transport in nuclear pasta and the implication for neutron star observables.

Nuclear radiation detectors

International Nuclear Information System (INIS)

Kapoor, S.S.; Ramamurthy, V.S.

1986-01-01

The present monograph is intended to treat the commonly used detectors in the field of nuclear physics covering important developments of the recent years. After a general introduction, a brief account of interaction of radiation with matter relevant to the processes in radiation detection is given in Chapter II. In addition to the ionization chamber, proportional counters and Geiger Mueller counters, several gas-filled detectors of advanced design such as those recently developed for heavy ion physics and other types of studies have been covered in Chapter III. Semiconductor detectors are dealt with in Chapter IV. The scintillation detectors which function by sensing the photons emitted by the luminescence process during the interaction of the impinging radiation with the scintillation detector medium are described in Chapter V. The topic of neutron detectors is covered in Chapter VI, as in this case the emphasis is more on the method of neutron detection rather than on detector type. Electronic instrumentation related to signal pulse processing dealt with in Chapter VII. The track etch detectors based on the visualization of the track of the impinging charge particle have also been briefly covered in the last chapter. The scope of this monograph is confined to detectors commonly used in low and medium energy nuclear physics research and applications of nuclear techniques. The monograph is intended for post-graduate students and those beginning to work with the radiation detectors. (author)

Nuclear energy and radiation

International Nuclear Information System (INIS)

Myers, D.K.; Johnson, J.R.

1980-01-01

Both the light water reactor and the Canadian heavy water reactor systems produce electricity cheaply and efficiently. They produce some fissionable byproducts, which can be recycled to extend energy sources many-fold. Besides the production of electrical power, the nuclear industry produces various radioistopes used for treatment of cancer, in diagnostic procedures in nuclear medicine, in ionization smoke detectors, and as radioactive tracers with various technological applications including the study of the mechanisms of life. The increment in environmental radiation levels resulting from operation of nuclear power reactors represents a very small fraction of the radiation levels to which we are all exposed from natural sources, and of the average radiation exposures resulting from diagnostic procedures in the healing arts. The total health hazard of the complete nuclear power cycle is generally agreed to be smaller than the hazards associated with the generation of an equal amount of electricity from most other currently available sources of energy. The hazards from energy production in terms of shortened life expectancy are much smaller in all cases than the resulting increase in health and life expectancy. (auth)

Next nuclear gamble: transportation and storage of nuclear waste

International Nuclear Information System (INIS)

Resnikoff, M.

1983-01-01

Accidents during transport of nuclear waste are more threatening - though less likely - than a reactor meltdown because transportation accidents could occur in the middle of a populous city, affecting more people and property than a plant accident, according to the Council on Economic Priorities, a non-profit public service research organization. Transportation, as presently practiced, is unsafe. Shipping containers, called casks, are poorly designed and constructed, CEP says. The problem needs attention because the number of casks filled with nuclear waste on the nation's highways could increase a hundred times during the next 15 years under the Nuclear Waste Policy Act of 1982, which calls for storage areas. Recommendations, both technical and regulatory, for reducing the risks are presented

Transport insurance of unirradiated nuclear fuels

International Nuclear Information System (INIS)

Matto, H.

1985-01-01

Special conditions must be taken into account in transport insurance for nuclear materials even if the nuclear risk involved is negligible, as in shipments of unirradiated nuclear fuels. The shipwreck of the 'Mont Louis' has raised a number of open points which must be solved pragmatically within the framework of transport insurance. Some proposals are outlined in the article. (orig.) [de

Nuclear fuel transport and particularly spent fuel transport

International Nuclear Information System (INIS)

Lenail, B.

1986-01-01

Nuclear material transport is an essential activity for COGEMA linking the different steps of the fuel cycle transport systems have to be safe and reliable. Spent fuel transport is more particularly examined in this paper because the development of reprocessing plant. Industrial, techmical and economical aspects are reviewed [fr

Transport of radioactive materials on public roads - with regard to the authorizations granted to the Nuclear Center

International Nuclear Information System (INIS)

Berger, H.U.

1992-10-01

This report shall be a help for scientific and technical personal of the nuclear research center in the choice of the modalities of the transport of radioactive materials on public roads in accordance to regulations and authorizations. Not only the atomic law, the radiation protection ordinance and the ordinance on dangerous goods on roads, which are binding in any case, are regarded in this report but also as the scope and the impositions of the transport authorization of the nuclear research center as the internal instructions of the nuclear research center. With regard to the transport of nuclear fuel material only the cases of transport exempted of authorization and transport of such kinds waste containing nuclear fuel material treated where the waste has a density at most of 15g/cm 3 or where the package contains at most 15g of nuclear fuel material. The reader is guided by dialogue (pretty much as a book for' programmed learning') to the solution of his special problem of transport. In order to narrow down the size of this report, all technical or administrative details are treated in 11 brochures, which are published as technical supplements of this report. These supplements are available on request. (orig.) [de

Radiation protection in nuclear medicine

Energy Technology Data Exchange (ETDEWEB)

Volodin, V; Hanson, G P

1993-12-31

The goal of this Chapter is to give a general outline of the essential principles and procedures for radiation protection in a nuclear medicine department where radionuclides are used for diagnosis and therapy. More detailed recommendations regarding radiation protection in nuclear medicine are given in the publications of the International Commission on Radiation Protection (ICRP, publications 25, 57, 60) and in ILO/IAEA/WHO Manual on Radiation Protection in Hospitals and General Practice (Volume 2: Unsealed Sources, WHO, Geneva, 1975), on which this Chapter is based. This chapter is not intended to replace the above-mentioned international recommendations on radiation protection, as well as existing national regulations on this subject, but intended only to provide guidance for implementing these recommendations in clinical practice

Radiation protection in nuclear medicine

International Nuclear Information System (INIS)

Volodin, V.; Hanson, G.P.

1992-01-01

The goal of this Chapter is to give a general outline of the essential principles and procedures for radiation protection in a nuclear medicine department where radionuclides are used for diagnosis and therapy. More detailed recommendations regarding radiation protection in nuclear medicine are given in the publications of the International Commission on Radiation Protection (ICRP, publications 25, 57, 60) and in ILO/IAEA/WHO Manual on Radiation Protection in Hospitals and General Practice (Volume 2: Unsealed Sources, WHO, Geneva, 1975), on which this Chapter is based. This chapter is not intended to replace the above-mentioned international recommendations on radiation protection, as well as existing national regulations on this subject, but intended only to provide guidance for implementing these recommendations in clinical practice

The nuclear risk

International Nuclear Information System (INIS)

Choudens, Henri de

2013-06-01

After a presentation of some general notions related to radioactivity, to the action and effects of radiation on matter and on living creatures, to natural irradiation and irradiation resulting from human activities, and to standards and regulation in radiation protection, this publication presents issues related to the safety of nuclear installations: presentation of the different types of nuclear installations, safety principles. The next part proposes an overview of different types of criticality accidents by distinguishing those occurring in medical or industrial installations and radioactive sources, those related to military activities, and those occurring in nuclear reactors. Other addressed topics are: radioactive wastes and effluents (definitions, classification, origin and quantity, packaging and storage), transportation of radioactive materials (regulation, parcel types, radiation protection during transportation, transport accidents), regulation of basic nuclear installations and safety organisation (safety control during normal operation, crisis management, post-accidental management, public information), the protection of sensitive nuclear materials (material types and general principles, regulation, arrangement to protect materials in installations, transports, audits, international controls). Nuclear fusion is then presented (principle, confinement types, the ITER project), and an overview of military applications is finally proposed (ship propulsion, nuclear weapons, the non proliferation issue)

Recent developments in the regulation of nuclear transportation

International Nuclear Information System (INIS)

Grella, A.W.

1978-01-01

In the past four years, almost all nations and international or intergovernmental transport organizations have effected transitions from the 1967 to 1973 IAEA standards as their basis for regulatory requirements for the safe transport of radioactive materials. One major exception to this transition is the USA itself, where this transition has not yet taken place. Major amendments to revise 49 CFR Parts 100-199 of the Department of Transportation regulations and 10 CFR Part 71 of the Nuclear Regulatory Commission regulations are required to effect this transition. The notices of proposed rulemaking to effect this transition in the USA are expected to be published by DOT and NRC concurrently sometime in 1978. Final amendments can be expected later, after the public comment period on the notices and considerations of those comments. This paper summarizes the status of current thinking on US adoption of the 1973 IAEA standards, as well as the status of adoption of those standards by international intergovernmental organizations, such as the Intergovernmental Maritime Consultative Organization, International Civil Aviation Organization, etc. A number of the differences between the expected US regulations and other regulations based on the 1973 IAEA standards are explained. This paper also discusses a number of other events or matters which have been taking place in the US in the past four years which have or may have an effect on transport of nuclear materials and its regulation, including air transport of plutonium, rail transport of spent fuel and other regulations by state or political subdivisions. The paper also discusses changes to US regulations accomplished in the past four years, which are not related to 1973 IAEA standards, as well as some other possible areas where regulatory proposals might be anticipated, such as control of radiation exposures to certain transport workers and other matters

Legal aspects of transport of nuclear materials

International Nuclear Information System (INIS)

Jacobsson, Mans.

The Paris Convention and the Brussels Supplementary Convention are briefly discussed and other conventions in the field of civil liability for nuclear damage are mentioned: the Vienna Convention, the Nuclear Ships Convention and the 1971 Convention relating to civil liability in the field of maritime carriage of nuclear material. Legislation on civil liability in the Nordic countries, which is based on the Paris Convention and the Supplementary Convention is discussed, notably the principle of channelling of liability and exceptions from that principle due to rules of liability in older transport conventions and certain problems due to the limited geographical scope of the Paris Convention and the Supplementary Convention. Insurance problems arising in connection with transport of nuclear materials are surveyed and an outline is given of the administrative provisions concerning transport (based on the IAEA transport regulations) which govern transport of radioactive materials by different means: road, rail, sea and air. Finally, the 1968 Treaty on the Non-Proliferation of Nuclear Weapons is discussed. (NEA) [fr

Radiation protection databases of nuclear safety regulatory authority

International Nuclear Information System (INIS)

Janzekovic, H.; Vokal, B.; Krizman, M.

2003-01-01

Radiation protection and nuclear safety of nuclear installations have a common objective, protection against ionising radiation. The operational safety of a nuclear power plant is evaluated using performance indicators as for instance collective radiation exposure, unit capability factor, unplanned capability loss factor, etc. As stated by WANO (World Association of Nuclear Operators) the performance indicators are 'a management tool so each operator can monitor its own performance and progress, set challenging goals for improvement and consistently compare performance with that of other plants or industry'. In order to make the analysis of the performance indicators feasible to an operator as well as to regulatory authorities a suitable database should be created based on the data related to a facility or facilities. Moreover, the international bodies found out that the comparison of radiation protection in nuclear facilities in different countries could be feasible only if the databases with well defined parameters are established. The article will briefly describe the development of international databases regarding radiation protection related to nuclear facilities. The issues related to the possible development of the efficient radiation protection control of a nuclear facility based on experience of the Slovenian Nuclear Safety Administration will be presented. (author)

Management of the process of nuclear transport; Gestion del proceso de transporte nuclear

Energy Technology Data Exchange (ETDEWEB)

Requejo, P.

2015-07-01

Since 1996 ETSA is the only Spanish logistics operator specialized on servicing the nuclear and radioactive industry. Nowadays ETSA has some technological systems specifically designed for the management of nuclear transports. These tools have been the result of the analysis of multiple factors involved in nuclear shipments, of ETSAs wide experience as a logistics operator and the search for continuous improvement. (Author)

Research on crisis communication of nuclear and radiation safety

International Nuclear Information System (INIS)

Cao Yali; Zhang Ying

2013-01-01

Insufficient public cognition of nuclear and radiation safety and absence of effective method to handle crisis lead to common crisis events of nuclear and radiation safety, which brings about unfavorable impact on the sound development of nuclear energy exploring and application of nuclear technology. This paper, based on crisis communication theory, analyzed the effect of current situation on nuclear and radiation safety crisis, discussed how to handle crisis, and tried to explore the effective strategies for nuclear and radiation safety crisis handling. (authors)

Analytical benchmarks for nuclear engineering applications. Case studies in neutron transport theory

International Nuclear Information System (INIS)

2008-01-01

The developers of computer codes involving neutron transport theory for nuclear engineering applications seldom apply analytical benchmarking strategies to ensure the quality of their programs. A major reason for this is the lack of analytical benchmarks and their documentation in the literature. The few such benchmarks that do exist are difficult to locate, as they are scattered throughout the neutron transport and radiative transfer literature. The motivation for this benchmark compendium, therefore, is to gather several analytical benchmarks appropriate for nuclear engineering applications under one cover. We consider the following three subject areas: neutron slowing down and thermalization without spatial dependence, one-dimensional neutron transport in infinite and finite media, and multidimensional neutron transport in a half-space and an infinite medium. Each benchmark is briefly described, followed by a detailed derivation of the analytical solution representation. Finally, a demonstration of the evaluation of the solution representation includes qualified numerical benchmark results. All accompanying computer codes are suitable for the PC computational environment and can serve as educational tools for courses in nuclear engineering. While this benchmark compilation does not contain all possible benchmarks, by any means, it does include some of the most prominent ones and should serve as a valuable reference. (author)

Rules specific to nuclear incidence occurring in installations or during transport of nuclear substances

International Nuclear Information System (INIS)

Rocamora, P.

1976-01-01

International nuclear third party liability conventions deal in depth with the liability system governing the transport of nuclear substances. Without appropriate legislation, international transport would be likely to meet very serious legal difficulties. The rule of nuclear conventions apply the same system to transport as to nuclear installations and mainly enable a determination of the operator liable. They also allow the person responsible for transport to assume liability therefor in place of the operator who whould normally have been liable. These nuclear conventions do not affect application of international transport conventions and this provision has been the cause of serious difficulties regarding maritime transport. This resulted in the adoption in 1971 in Brussels of a convention relating to civil liability in the field of maritime carriage of nuclear material. The purpose of this convention is to establish in the field of maritime transport, the priority of the system of absolute, exclusive and limited liability in the nuclear conventions. (NEA) [fr

Radiation exposure of workers in nuclear medicine

International Nuclear Information System (INIS)

Bujnova, A.

2008-01-01

Nuclear medicine is an interdisciplinary department that deals with diagnosis and therapy using open sources. Therefore workers in nuclear medicine are in daily contact with ionizing radiation and thus it is essential to monitor a radiation load. Each work must therefore carry out monitoring of workers. It monitors compliance with the radiation limits set by law, allows an early detection of deviations from normal operation and to demonstrate whether the radiation protection at the workplace is optimized. This work describes the principles of monitoring of workers in nuclear medicine and monitoring methods for personal dosimetry. In the next section the author specifically deals with personal dosimetry at the Department of Nuclear Medicine St. Elizabeth Cancer Institute, Bratislava (KNM-Ba-OUSA). The main part of the work is to evaluate the results of a one-year monitoring of radiation workers KNM-Ba-OUSA. (author)

Evaluation of the secondary radiation impact on personnel during the dismantling of contaminated nuclear equipment

Directory of Open Access Journals (Sweden)

Stankunas Gediminas

2013-01-01

Full Text Available The article contains a numerical analysis of the secondary radiation contribution to the total radiation affecting the operational personnel during the dismantling activities of the contaminated equipment at a nuclear power plant. This study considers a widely applicable Monte Carlo particle transport code MCNPX and real Ignalina nuclear power plant records. A simplified albedo method is investigated in order to analyze the selected geometrical design cases. Additionally, the impact of the secondary radiation on the personnel dose was analyzed. The numerical MCNPX simulation allowed ascertaining the optimal distance between the source and the wall for the working personnel in closed rooms with contaminated equipment. The developed dose rate maps of the secondary radiation showed cross-sectional distribution of the dose rate inside the enclosed area.

Forms of Approximate Radiation Transport

CERN Document Server

Brunner, G

2002-01-01

Photon radiation transport is described by the Boltzmann equation. Because this equation is difficult to solve, many different approximate forms have been implemented in computer codes. Several of the most common approximations are reviewed, and test problems illustrate the characteristics of each of the approximations. This document is designed as a tutorial so that code users can make an educated choice about which form of approximate radiation transport to use for their particular simulation.

Radiation exposure analysis of female nuclear medicine radiation workers

Energy Technology Data Exchange (ETDEWEB)

Lee, Ju Young [Dept. of Biomedical Engineering Graduate School, Chungbuk National University, Cheongju (Korea, Republic of); Park, Hoon Hee [Dept. of Radiological Technologist, Shingu College, Sungnam (Korea, Republic of)

2016-06-15

In this study, radiation workers who work in nuclear medicine department were analyzed to find the cause of differences of radiation exposure from General Characteristic, Knowledge, Recognition and Conduct, especially females working on nuclear medicine radiation, in order to pave the way for positive defense against radiation exposure. The subjects were 106 radiation workers who were divided into two groups of sixty-four males and forty-two females answered questions about their General Characteristic, Knowledge, Recognition, Conduct, and radiation exposure dose which was measured by TLD (Thermo Luminescence Dosimeter). The results of the analysis revealed that as the higher score of knowledge and conduct was shown, the radiation exposure decreased in female groups, and as the higher score of conduct was shown, the radiation exposure decreased in male groups. In the correlation analysis of female groups, the non-experienced in pregnancy showed decreasing amount of radiation exposure as the score of knowledge and conduct was higher and the experienced in pregnancy showed decreasing amount of radiation exposure as the score of recognition and conduct was higher. In the regression analysis on related factors of radiation exposure dose of nuclear medicine radiation workers, the gender caused the meaningful result and the amount of radiation exposure of female groups compared to male groups. In the regression analysis on related factors of radiation exposure dose of female groups, the factor of conduct showed a meaningful result and the amount of radiation exposure of the experienced in pregnancy was lower compared to the non-experienced. The conclusion of this study revealed that radiation exposure of female groups was lower than that of male groups. Therefore, male groups need to more actively defend themselves against radiation exposure. Among the female groups, the experienced in pregnancy who have an active defense tendency showed a lower radiation exposure. Thus

Radiation exposure analysis of female nuclear medicine radiation workers

International Nuclear Information System (INIS)

Lee, Ju Young; Park, Hoon Hee

2016-01-01

In this study, radiation workers who work in nuclear medicine department were analyzed to find the cause of differences of radiation exposure from General Characteristic, Knowledge, Recognition and Conduct, especially females working on nuclear medicine radiation, in order to pave the way for positive defense against radiation exposure. The subjects were 106 radiation workers who were divided into two groups of sixty-four males and forty-two females answered questions about their General Characteristic, Knowledge, Recognition, Conduct, and radiation exposure dose which was measured by TLD (Thermo Luminescence Dosimeter). The results of the analysis revealed that as the higher score of knowledge and conduct was shown, the radiation exposure decreased in female groups, and as the higher score of conduct was shown, the radiation exposure decreased in male groups. In the correlation analysis of female groups, the non-experienced in pregnancy showed decreasing amount of radiation exposure as the score of knowledge and conduct was higher and the experienced in pregnancy showed decreasing amount of radiation exposure as the score of recognition and conduct was higher. In the regression analysis on related factors of radiation exposure dose of nuclear medicine radiation workers, the gender caused the meaningful result and the amount of radiation exposure of female groups compared to male groups. In the regression analysis on related factors of radiation exposure dose of female groups, the factor of conduct showed a meaningful result and the amount of radiation exposure of the experienced in pregnancy was lower compared to the non-experienced. The conclusion of this study revealed that radiation exposure of female groups was lower than that of male groups. Therefore, male groups need to more actively defend themselves against radiation exposure. Among the female groups, the experienced in pregnancy who have an active defense tendency showed a lower radiation exposure. Thus

Nuclear data needed for applications in radiation oncology

International Nuclear Information System (INIS)

White, R.M.; Chadwick, M.B.; Siantar, C.L.H.; Chandler, W.P.

1994-03-01

Fast neutrons have been used to treat over 15,000 cancer patients in approximately twenty centers worldwide and proton therapy is emerging as a potential treatment of choice for tumors near critical anatomical structures. Neutron therapy requires reaction data to ∼70 MeV while proton therapy requires data to ∼250 MeV. The cross section databases require energy- and angle-dependent cross sections for secondary neutrons, charged-particles and recoil nuclei. We discuss expansion of our nuclear databases and development of a three-dimensional radiation transport package that uses CT images as the input mesh to an all-particle Monte Carlo code. Called PEREGRINE, this code calculates dose distributions in the human body and can be used as a tool to determine the dependence of dose on details of the evaluated nuclear data

Department of Environmental and Radiation Transport Physics - Overview

International Nuclear Information System (INIS)

Woznicka, U.

2001-01-01

Full text: We deal with environmental physics and the radiation transport physics, both theoretically and experimentally. Some results find their way to practical applications. Our environmental physics research encompasses hydrogeological problems as well as measurements of trace elements in the atmosphere and in the water. Theoretical (analytical and numerical) and experimental issues of the radiation transport and radiation fields are our main field of research. The interest in radiation transport phenomena is stimulated by their importance for the environmental physics, industrial and nuclear facilities and methods of geophysical. Environmental isotopes and noble gases are used in the investigation of water-bearing geological formations in order to determine the origin and age of groundwater. The papers listed below and three ''Reports on research'' present recent achievements in this field. The gas chromatography methods are used for monitoring the anthropogenic trace gases (SF 6 and freons), which participate in the Earth green-house effect. A very high detection level of SF 6 in water, 0.0028 fg/cm 3 H 2 0, has been reached as required for hydrogeological purposes. A preliminary verification of the SF 6 tracer method for dating young groundwaters by the tritium method has been carried out. We carried on the work on a method of radon measurement in soil in connection with geological conditions. The national seminar ''Radon in Environment'' organized at the INP aroused an interest of Polish scientific centres in that field. The seminar gathered 60 participants who presented 24 oral reports and 8 posters. Within the scope of the radiation transport physics we studied thermal neutron transport in finite hydrogenous media. Advantages and limitations of a Monte Carlo code (MCNP) in thermal neutron transport simulations have been examined by both the analytical solution and the experiment on the INP pulsed neutron generator. An interesting contribution to the

Physics of nuclear radiations concepts, techniques and applications

CERN Document Server

Rangacharyulu, Chary

2013-01-01

Physics of Nuclear Radiations: Concepts, Techniques and Applications makes the physics of nuclear radiations accessible to students with a basic background in physics and mathematics. Rather than convince students one way or the other about the hazards of nuclear radiations, the text empowers them with tools to calculate and assess nuclear radiations and their impact. It discusses the meaning behind mathematical formulae as well as the areas in which the equations can be applied. After reviewing the physics preliminaries, the author addresses the growth and decay of nuclear radiations, the stability of nuclei or particles against radioactive transformations, and the behavior of heavy charged particles, electrons, photons, and neutrons. He then presents the nomenclature and physics reasoning of dosimetry, covers typical nuclear facilities (such as medical x-ray machines and particle accelerators), and describes the physics principles of diverse detectors. The book also discusses methods for measuring energy a...

The Australian radiation protection and Nuclear Safety Agency

International Nuclear Information System (INIS)

Macnab, D.; Burn, P.; Rubendra, R.

1998-01-01

The author talks about the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA), the new regulatory authority which will combine the existing resources of the Australian Radiation Laboratory and the Nuclear Safety Bureau. Most uses of radiation in Australia are regulated by State or Territory authorities, but there is presently no regulatory authority for Commonwealth uses of radiation. To provide for regulation of the radiation practices of the Commonwealth, the Australian Government has decided to establish the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) and a Bill has passed through the House of Representatives and will go to the Spring sitting of the Senate. The new agency will subsume the resources and functions of the Nuclear Safety Bureau and the Australian Radiation Laboratory, with additional functions including the regulation of radiation protection and nuclear safety of Commonwealth practices. Another function of ARPANSA will be the promotion of uniform regulatory requirements for radiation protection across Australia. This will be done by developing, in consultation with the States and Territories, radiation health policies and practices for adoption by the Commonwealth, States and Territories. ARPANSA will also provide research and services for radiation health, and in support of the regulatory and uniformity functions. The establishment of ARPANSA will ensure that the proposed replacement research reactor, the future low level radioactive waste repository and other Commonwealth nuclear facilities and radiation practices are subject to a regulatory regime which reflects the accumulated experience of the States and Territories and best international practice, and meets public expectations

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - New Zealand

International Nuclear Information System (INIS)

2008-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive Substances and Equipment; 4. Nuclear installations; 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Nuclear security; 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities - National Radiation Laboratory - NRL; 2. Advisory bodies - Radiation Protection Advisory Council; 3. Public and semi-public agencies - Research institutes

Radiation transport in numerical astrophysics

International Nuclear Information System (INIS)

Lund, C.M.

1983-02-01

In this article, we discuss some of the numerical techniques developed by Jim Wilson and co-workers for the calculation of time-dependent radiation flow. Difference equations for multifrequency transport are given for both a discrete-angle representation of radiation transport and a Fick's law-like representation. These methods have the important property that they correctly describe both the streaming and diffusion limits of transport theory in problems where the mean free path divided by characteristic distances varies from much less than one to much greater than one. They are also stable for timesteps comparable to the changes in physical variables, rather than being limited by stability requirements

Evaluation of radiation protection in nuclear medicine diagnostic procedures

International Nuclear Information System (INIS)

Mohammed, Ezzeldien Mohammed Nour

2013-05-01

This study conducted to evaluate the radiation protection in nuclear medicine diagnostic procedures in four nuclear medicine departments in Sudan. The evaluated procedures followed in these departments were in accordance with the standards, International Recommendations and code of practice for radiation protection in nuclear medicine. The evolution included the optimum design for diagnostic nuclear medicine departments, dealing with radioactive sources, quality assurance and quality control, training and responsibilities for radiation worker taking into account economic factors in Sudan. Evaluation of radiation protection procedures in diagnostic investigations was carried out by taken direct measurements of dose rate and the contamination level in some areas where radiation sources, radiation workers and public are involved. Designated questionnaires covered thirteen areas of radiation protection based on inspection check list for nuclear medicine prepared by the International Atomic Energy Agency (IAEA) and American Association of Physicist in Medicine (AAPM) were used in the evaluation. This questionnaire has been Filled by Radiation Protection Officer (RPO), nuclear medicine technologist, nuclear medicine specialist in the nuclear medicine departments. Four hospitals, two governmental hospital and two private hospitals, have been assisted, the assessment shows that although the diagnostic nuclear medicine department in Sudan are not applying a fully safety and radiation protection procedures, but the level of radiation dose and the contamination level were found within acceptable limits. The private hospital D scored the higher level of protection (85.25%) while the governmental hospital C scored the lower level of protection (59.02%). Finally, this study stated some recommendations that if implemented could improve the level of radiation protection in nuclear medicine department. One of the most important recommendations is that a proper radiation protection

General aspects of nuclear power, radiation and environmental effects. Chapter 3

International Nuclear Information System (INIS)

1978-01-01

A general introduction to the principles of the functioning of a nuclear reactor and of power plants based on the reactor types at present in use, and likely to be used in the near future (PWR,BWR,FBR,HTGR and CANDU) is given. The general principles of a thermonuclear power plant are also briefly presented, and general safety aspects discussed. The physics of ionising radiations is briefly presented and natural and artificial sources of radiation are discussed. The fuel cycle, from mining to reprocessing and waste disposal and transport, is presented. The behaviour and effects of radioactive substances in the biosphere, radiation doses, and biological effects of ionising radiation are discussed. In conclusion there is an appendix in which the main characteristics of a number of elements which have important radioactive isotopes are presented. (JIW)

A nuclear radiation actuated valve for a nuclear reactor

International Nuclear Information System (INIS)

Christiansen, D.W.; Schively, D.P.

1983-01-01

The valve has a first part (such as a valve rod with piston) and a second part (such as a valve tube surrounding the valve rod, with the valve tube having side slots surrounding the piston). Both valve parts have known nuclear radiation swelling characteristics which are different. The valve parts are positioned so that the valve's first and second parts create a valve orifice which changes in size due to the different nuclear radiation caused swelling of the valve's first part compared to the valve's second part. The valve may be used in a nuclear reactor's core coolant system. (author)

Pulse generator circuit triggerable by nuclear radiation

International Nuclear Information System (INIS)

Fredrickson, P.B.

1980-01-01

A pulse generator circuit triggerable by a pulse of nuclear radiation is described. The pulse generator circuit includes a pair of transistors arranged, together with other electrical components, in the topology of a standard monostable multivibrator circuit. The circuit differs most significantly from a standard monostable multivibrator circuit in that the circuit is adapted to be triggered by a pulse of nuclear radiation rather than electrically and the transistors have substantially different sensitivities to radiation, due to different physical and electrical characteristics and parameters. One of the transistors is employed principally as a radiation detector and is in a normally non-conducting state and the other transistor is normally in a conducting state. When the circuit is exposed to a pulse of nuclear radiation, currents are induced in the collector-base junctions of both transistors but, due to the different radiation sensitivities of the transistors, the current induced in the collector-base junction of the radiation-detecting transistor is substantially greater than that induced in the collector-base junction of the other transistor. The pulse of radiation causes the radiation-detecting transistor to operate in its conducting state, causing the other transistor to operate in its non-conducting state. As the radiation-detecting transistor operates in its conducting state, an output signal is produced at an output terminal connected to the radiation-detecting transistor indicating the presence of a predetermined intensity of nuclear radiation

Radiation Effects in Nuclear Ceramics

Directory of Open Access Journals (Sweden)

L. Thomé

2012-01-01

Full Text Available Due to outstanding physicochemical properties, ceramics are key engineering materials in many industrial domains. The evaluation of the damage created in ceramics employed in radiative media is a challenging problem for electronic, space, and nuclear industries. In this latter field, ceramics can be used as immobilization forms for radioactive wastes, inert fuel matrices for actinide transmutation, cladding materials for gas-cooled fission reactors, and structural components for fusion reactors. Information on the radiation stability of nuclear materials may be obtained by simulating the different types of interactions involved during the slowing down of energetic particles with ion beams delivered by various types of accelerators. This paper presents a review of the radiation effects occurring in nuclear ceramics, with an emphasis on recent results concerning the damage accumulation processes. Energetic ions in the KeV-GeV range are used to explore the nuclear collision (at low energy and electronic excitation (at high energy regimes. The recovery by electronic excitation of the damage created by ballistic collisions (SHIBIEC process is also addressed.

Order of 20 September 1993 amending the Order of 26 March 1982 on protection and control of nuclear materials during transport

International Nuclear Information System (INIS)

1993-01-01

This Order amends and supplements the system for the transport of nuclear materials laid down by the 1982 Order. Two new provisions have been inserted. The first specifies that in the event of an accident or an incident occurring during the transport of nuclear materials which implies a radiological risk, the Central Service for Proteciton against Ionizing Radiation (SCPRI) must be notified immediately. The other provision specifies that the transport vehicle must be equipped with a means of communication so as to inform the Institute for Protection and Nuclear Safety (IPSN) about the main stages of the operation. (NEA)

Radiation protection programme for nuclear gauges

International Nuclear Information System (INIS)

Muzongomerwa, A.

2014-04-01

Ionizing radiation including the use of nuclear gauges can be very hazardous to humans and steps must be taken to minimize the risks so as to prevent deterministic effects and limiting chances for stochastic effects. The availability of a Radiation Protection Programme and its effective implementation ensures appropriate safety and security provisions for sealed radiation sources and promotes a safety culture within a facility that utilizes these sources. This study aims at establishing a guide on the radiation protection programme in nuclear gauges that comply with national requirements derived from current international recommendations. Elements that form part of a radiation protection programme are covered in detail as well as recommendations. The overall objective is to protect people (operators and the public) and the environment from the harmful effects of these sources if they are not properly controlled. Nuclear gauges for well logging and X-ray based gauges are outside the scope of this study. (au)

Nuclear and radiation safety in Mongolia

International Nuclear Information System (INIS)

Batjargala, Erdev

2010-01-01

The main purpose of the paper is to assess legal environment of Mongolia for development of nuclear and radiation safety and security. The Nuclear Energy Agency, regulatory agency of the Government of Mongolia, was founded in the beginning of 2009. Since then, it has formulated the State Policy for Utilization of Radioactive Minerals and Nuclear Energy and the Nuclear Energy Law, regulatory law of the field. The State Great Khural of Mongolia has enacted these acts. By adopting the State Policy and Nuclear Energy Law, which together imported the international standards for nuclear and radiation safety and security, it is possible to conclude that legal environment has formed in Mongolia to explore and process radioactive minerals and utilize nuclear energy and introduce technologies friendly to human health and environment. (author)

The eyes, ears and collective voice for nuclear transport

International Nuclear Information System (INIS)

Green, L.

2000-01-01

Transport is a vital part of the nuclear industry and the safety record of radioactive materials transport across the world is excellent. This record is due primarily to well-founded regulations developed by such intergovernmental organisations as the International Atomic Energy Agency and the International Maritime Organisation. It is due, also, to the professionalism of those in the industry. Attitudes to nuclear transport are important. They have the potential, if not heeded, and not responded to sensitively and convincingly to make life very much more difficult for those committed to the safe, reliable and efficient transport of nuclear materials. What is required is a balanced situation, which takes account both of the public's attitudes and industry's need for an efficient operation. The voices of the nuclear transport industry and those who value the industry need to be heard. The World Nuclear Transport Institute was established to provide the nuclear transport industry with the collective eyes, ears and voice in the key intergovernmental organisations which are so important to it. The nuclear transport industry has a safety record which could be regarded as a model for the transport of dangerous goods of all kinds. The industry is situated within a comprehensive and strict regime of national and international standards and regulations. That is the message to be disseminated, and that is the commitment of the World Nuclear Transport Institute as it works to protect and to promote the safe, efficient and reliable transport of radioactive materials. (author)

Radiation protection aspects of design for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the Contracting Parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

Public and media acceptance of nuclear materials transport

International Nuclear Information System (INIS)

Lindeman, E.

1999-01-01

Transport is absolutely essential to the continued existence of a nuclear industry that includes large-scale power generation, sophisticated research, and medicine. Indeed, transport of nuclear materials is hardly a new business. What is new is the public's awareness and distrust of this transport - a distrust fuelled by the well-funded and skilled manipulation of the nuclear industry's detractors. The nuclear industry itself has only recently begun to acknowledge the importance and the implications of transport. This paper looks at the public and media response to the European-Japanese and the US Department of Energy's transport campaigns and quotes from several telling newspaper articles. It emphasizes the need for the nuclear industry to continue to be vigilant in its efforts to reach the public, media and governments with good science, openness and well-communicated facts. (author)

Strengthening global norms for protecting nuclear materials - feedback on little countries radiation safety

International Nuclear Information System (INIS)

Chelidze, L.; Kakushadze, S.

2002-01-01

Full text: Georgia is the part of New Great Silk Road, connecting Europe and Asia. Along this rout will be laid oil and gas pipelines, transport and telecommunication lines. Unfortunately, besides economical communication, the rout can be used for illegal transit of nuclear materials. There is special concern regarding uncontrolled territories of conflict zones. Taking into consideration recent terrible terrorist acts we feel great responsibility for ensuring safety of this rout, which is a precondition of economical development and political stability of the whole Caucasian region A potentially hazardous radiological situation developed in Georgia with orphan radiation sources in the late 1990s and 2001: discovery of high-activity strong Radiation sources of (Strontium-90 from thermo-generators) in Tsalenjikha district. Eight such generators were brought to Georgia in 1984, and four of them have been found in Svanety mountainous region in addition to the two found in the Tsalenjikha, but remaining two are not yet found. During the last years several incidents of illicit trafficking were reported. The radiation problems greatly relate to the withdrawal of the Russian military bases. The radiological accident took place in Lilo, Georgia, when sealed radiation sources had been abandoned by a previous owner at a site. Taking into account the geopolitical location of Georgia it is quite important to strengthen the physical protection infrastructure in country with has serious territorial problems. The first step was to provide an appropriate legal framework for the safety management in the country and clearly identify regulatory body. The ministry implements state control in the nuclear and radiation safety field for protection of environment and natural resources of Georgia (hereinafter referred to as the Ministry). The Ministry is obliged to supervise the physical protection systems. The Ministry shall co-ordinate the state system of physical protection of the use

Transport of nuclear substances in Canada

Energy Technology Data Exchange (ETDEWEB)

Faille, S. [Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

2015-07-01

CNSC Regulates all Nuclear-related facilities and activities including Uranium mines and mill;, uranium fuel fabrication and processing; nuclear power plants; nuclear substance processing; industrial and medical applications; nuclear research and education; transport; export/import control; security and safeguards and waste management facilities. Our mandate is to protect the health, safety and security of Canadians and the environment, and implement Canada's International commitments on the peaceful use of nuclear energy and disseminate objective scientific, technical and regulatory information to the public. Based on the International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive Material, 1996 Edition, Revised and currently being revised to reflect the 2012 edition of the IAEA Regulations.

Transport of nuclear substances in Canada

International Nuclear Information System (INIS)

Faille, S.

2015-01-01

CNSC Regulates all Nuclear-related facilities and activities including Uranium mines and mill;, uranium fuel fabrication and processing; nuclear power plants; nuclear substance processing; industrial and medical applications; nuclear research and education; transport; export/import control; security and safeguards and waste management facilities. Our mandate is to protect the health, safety and security of Canadians and the environment, and implement Canada's International commitments on the peaceful use of nuclear energy and disseminate objective scientific, technical and regulatory information to the public. Based on the International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive Material, 1996 Edition, Revised and currently being revised to reflect the 2012 edition of the IAEA Regulations.

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Iceland

International Nuclear Information System (INIS)

2008-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General Regulatory Regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances and equipment; 4. Nuclear installations; 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Nuclear security; 9. Transport; 10. Nuclear Third Party Liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (Minister of Health and Social Security; Icelandic Radiation Protection Institute)

Nuclear analysis methods. Rudiments of radiation protection

International Nuclear Information System (INIS)

Roth, E.

1998-01-01

The nuclear analysis methods are generally used to analyse radioactive elements but they can be used also for chemical analysis, with fields such analysis and characterization of traces. The principles of radiation protection are explained (ALARA), the biological effects of ionizing radiations are given, elements and units used in radiation protection are reminded in tables. A part of this article is devoted to how to use radiation protection in a nuclear analysis laboratory. (N.C.)

Dictionary of radiation protection, radiobiology and nuclear medicine

Energy Technology Data Exchange (ETDEWEB)

Sube, R [comp.

1986-01-01

Radiation protection, including aspects of radiobiology, nuclear medicine, and nuclear legislation, has an important role within nuclear research and the use of radioactive materials. Radiation protection comprises all measures and efforts to prevent the unwanted distribution and negative influence of ionizing radiation, especially where the human organism and the living environment are involved. The increasing role of radiation protection is reflected by the foundation of institutes in all industrial countries to control such radiant energy and prevent radiation damage. Nowadays ionizing radiation is employed on a large scale for basic investigations in biochemistry, molecular biology and genetics, in soil tests, fertilization problems and pest control in agriculture, as well as for medicinal diagnoses and therapy. This dictionary is a thematic enlargement of the four-language 'Dictionary of Nuclear Engineering', compiled by the same author. It comprises about 12,000 terms in each language.

Ordinance concerning the filing of transport of nuclear fuel materials

International Nuclear Information System (INIS)

1987-01-01

This Order provides provisions concerning nuclear fuel substances requiring notification (nuclear fuel substance, material contaminated with nuclear fuel substances, fissionable substances, etc.), procedure for notification (to prefectural public safety commission), certificate of transpot (issued via public safety commission), instructions (speed of vehicle for transporting nuclear fuel substances, parking of vehicle, place for loading and unloading of nuclear fuel substances, method for loading and unloading, report to police, measures for disaster prevention during transport, etc.), communication among members of public safety commission (for smooth transport), notification of alteration of data in transport certificate (application to be submitted to public safety commission), application of reissue of transport certificate, return of transport certificate, inspection concerning transport (to be performed by police), submission of report (to be submitted by refining facilities manager, processing facilities manager, nuclear reactor manager, master of foreign nuclear powered ship, reprocessing facilities manager, waste disposal facilities manager; concerning stolen or missing nuclear fuel substances, traffic accident, unusual leakage of nuclear fuel substances, etc.). (Nogami, K.)

Nuclear and radiation safety in Kazakhstan

International Nuclear Information System (INIS)

Kim, A.A.

2001-01-01

Major factors by which the radiation situation in Kazakhstan is formed are: enterprises of nuclear fuel cycle, including uranium mining and milling activity and geological exploration of uranium; nuclear power plant and research reactors; residues of atmospheric and underground nuclear explosions, which were conducted for military and peaceful purposes at different test sites; mining and milling of commercial minerals accompanied by radioactive substances; use of radioactive sources in industry, medicine, agriculture and scientific research. Since 1991, after getting sovereignty, creation was started of an own legislative basis of the country for the field of atomic energy use. It includes laws, regulations and standards for nuclear and radiation safety of nuclear installations, personnel, involved in the activity with using of atomic energy, population and environment. An applicable system of state regulation in this area (including a central regulatory body in the field of atomic energy use) and various ministries, agencies and committees, was created. As a result of these reforms, regulatory activities were improved in the country. This paper presents the current matters of nuclear and radiation safety in Kazakhstan and some difficulties which Kazakhstan encountered during the transition to an independent state. (author)

Parallel processing Monte Carlo radiation transport codes

International Nuclear Information System (INIS)

McKinney, G.W.

1994-01-01

Issues related to distributed-memory multiprocessing as applied to Monte Carlo radiation transport are discussed. Measurements of communication overhead are presented for the radiation transport code MCNP which employs the communication software package PVM, and average efficiency curves are provided for a homogeneous virtual machine

Dictionary of radiation protection, radiobiology and nuclear medicine

International Nuclear Information System (INIS)

Sube, R.

1986-01-01

Radiation protection, including aspects of radiobiology, nuclear medicine, and nuclear legislation, has an important role within nuclear research and the use of radioactive materials. Radiation protection comprises all measures and efforts to prevent the unwanted distribution and negative influence of ionizing radiation, especially where the human organism and the living environment are involved. The increasing role of radiation protection is reflected by the foundation of institutes in all industrial countries to control such radiant energy and prevent radiation damage. Nowadays ionizing radiation is employed on a large scale for basic investigations in biochemistry, molecular biology and genetics, in soil tests, fertilization problems and pest control in agriculture, as well as for medicinal diagnoses and therapy. This dictionary is a thematic enlargement of the four-language 'Dictionary of Nuclear Engineering', compiled by the same author. It comprises about 12,000 terms in each language. (orig.)

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Mexico

International Nuclear Information System (INIS)

2009-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment; 4. Nuclear installations (Licensing and inspection, including nuclear safety; Protection of the environment against radiation effects; Emergency response); 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Non-proliferation and physical protection; 9. Transport; 10. Nuclear third party liability; 11. Nuclear terrorism; II. Institutional Framework - The federal government: 1. Regulatory and supervisory authorities (Ministry of Energy; Ministry of Health; Ministry of Labour and Social Security; Ministry of the Environment and Natural Resources; Ministry of Communications and Transport); 2. Public and semi-public agencies: (National Nuclear Safety and Safeguards Commission; National Nuclear Research Institute)

Radiation damage studies of nuclear structural materials

International Nuclear Information System (INIS)

Barat, P.

2012-01-01

Maximum utilization of fuel in nuclear reactors is one of the important aspects for operating them economically. The main hindrance to achieve this higher burnups of nuclear fuel for the nuclear reactors is the possibility of the failure of the metallic core components during their operation. Thus, the study of the cause of the possibility of failure of these metallic structural materials of nuclear reactors during full power operation due to radiation damage, suffered inside the reactor core, is an important field of studies bearing the basic to industrial scientific views.The variation of the microstructure of the metallic core components of the nuclear reactors due to radiation damage causes enormous variation in the structure and mechanical properties. A firm understanding of this variation of the mechanical properties with the variation of microstructure will serve as a guide for creating new, more radiation-tolerant materials. In our centre we have irradiated structural materials of Indian nuclear reactors by charged particles from accelerator to generate radiation damage and studied the some aspects of the variation of microstructure by X-ray diffraction studies. Results achieved in this regards, will be presented. (author)

IAEA safety glossary. Terminology used in nuclear, radiation, radioactive waste and transport safety. Version 1.0. Working material

International Nuclear Information System (INIS)

2000-04-01

The IAEA safety standards for nuclear installations, radiation protection, radioactive waste management and the transport of radioactive materials have been historically developed in four separate programmes, each of them developing its own terminology. The purpose was to explain the meaning of technical terms that might be unfamiliar to a reader; to explain any special meanings assigned to common words or terms and to define precisely how terms are used in particular publications to avoid ambiguity concerning some important aspects of their meaning. It is intended primarily to provide guidance to the drafters and reviewers of Agency safety related publications, including IAEA Technical officers, consultants and members of Technical Committees, Advisory Groups and safety standards advisory bodies. It is also likely to be a useful source of information for other Agency staff, notably editors and translators, and for external users of IAEA safety related publications

Transportation of irradiated fuel elements

International Nuclear Information System (INIS)

1980-01-01

A critique is presented of current methods of transporting spent nuclear fuel and the inadequacies of the associated contingency plans, with particular reference to the transportation of irradiated fuel through London. Anti-nuclear and pro-nuclear arguments are presented on a number of factors, including tests on flasks, levels of radiation exposure, routine transport arrangements and contingency arrangements. (U.K.)

Radiation, ionization, and detection in nuclear medicine

International Nuclear Information System (INIS)

Gupta, Tapan K.

2013-01-01

Up-to-date information on a wide range of topics relating to radiation, ionization, and detection in nuclear medicine. In-depth coverage of basic radiophysics relating to diagnosis and therapy. Extensive discussion of instrumentation and radiation detectors. Detailed information on mathematical modelling of radiation detectors. Although our understanding of cancer has improved, the disease continues to be a leading cause of death across the world. The good news is that the recent technological developments in radiotherapy, radionuclide diagnostics and therapy, digital imaging systems, and detection technology have raised hope that cancer will in the future be combatted more efficiently and effectively. For this goal to be achieved, however, safe use of radionuclides and detailed knowledge of radiation sources are essential. Radiation, Ionization, and Detection in Nuclear Medicine addresses these subjects and related issues very clearly and elaborately and will serve as the definitive source of detailed information in the field. Individual chapters cover fundamental aspects of nuclear radiation, including dose and energy, sources, and shielding; the detection and measurement of radiation exposure, with detailed information on mathematical modelling; medical imaging; the different types of radiation detector and their working principles; basic principles of and experimental techniques for deposition of scintillating materials; device fabrication; the optical and electrical behaviors of radiation detectors; and the instrumentation used in nuclear medicine and its application. The book will be an invaluable source of information for academia, industry, practitioners, and researchers.

Radiation, ionization, and detection in nuclear medicine

Energy Technology Data Exchange (ETDEWEB)

Gupta, Tapan K. [Radiation Monitoring Devices Research, Nuclear Medicine, Watertown, MA (United States)

2013-08-01

Up-to-date information on a wide range of topics relating to radiation, ionization, and detection in nuclear medicine. In-depth coverage of basic radiophysics relating to diagnosis and therapy. Extensive discussion of instrumentation and radiation detectors. Detailed information on mathematical modelling of radiation detectors. Although our understanding of cancer has improved, the disease continues to be a leading cause of death across the world. The good news is that the recent technological developments in radiotherapy, radionuclide diagnostics and therapy, digital imaging systems, and detection technology have raised hope that cancer will in the future be combatted more efficiently and effectively. For this goal to be achieved, however, safe use of radionuclides and detailed knowledge of radiation sources are essential. Radiation, Ionization, and Detection in Nuclear Medicine addresses these subjects and related issues very clearly and elaborately and will serve as the definitive source of detailed information in the field. Individual chapters cover fundamental aspects of nuclear radiation, including dose and energy, sources, and shielding; the detection and measurement of radiation exposure, with detailed information on mathematical modelling; medical imaging; the different types of radiation detector and their working principles; basic principles of and experimental techniques for deposition of scintillating materials; device fabrication; the optical and electrical behaviors of radiation detectors; and the instrumentation used in nuclear medicine and its application. The book will be an invaluable source of information for academia, industry, practitioners, and researchers.

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Japan

International Nuclear Information System (INIS)

2011-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General Regulatory Regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment; 4. Nuclear installations (Licensing and inspection, including nuclear safety; Emergency response); 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Nuclear security; 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (Cabinet Office; Minister of Economy, Trade and Industry - METI; Minister of Land, Infrastructure and Transport - MLIT; Minister of Education, Culture, Sports, Science and Technology - MEXT); 2. Advisory bodies (Atomic Energy Commission - AEC; Nuclear Safety Commission - NSC; Radiation Council; Special Committee on Energy Policy; Other advisory bodies); 3. Public and Semi-Public Agencies (Japan Atomic Energy Agency - JAEA)

The sea transport of irradiated nuclear fuel

International Nuclear Information System (INIS)

Miller, M.L.

1995-01-01

The paper describes the development of a transport system dedicated to the sea transport of irradiated nuclear fuel. It reviews the background to why shipments were required and the establishment of a specialist shipping company, Pacific Nuclear Transport Limited. A description of the ships, flasks and other equipment utilized is provided, together with details of key procedures implemented to ensure safety and customer satisfaction

Nonrelativistic grey Sn-transport radiative-shock solutions

International Nuclear Information System (INIS)

Ferguson, J. M.; Morel, J. E.; Lowrie, R. B.

2017-01-01

We present semi-analytic radiative-shock solutions in which grey Sn-transport is used to model the radiation, and we include both constant cross sections and cross sections that depend on temperature and density. These new solutions solve for a variable Eddington factor (VEF) across the shock domain, which allows for interesting physics not seen before in radiative-shock solutions. Comparisons are made with the grey nonequilibrium-diffusion radiative-shock solutions of Lowrie and Edwards [1], which assumed that the Eddington factor is constant across the shock domain. It is our experience that the local Mach number is monotonic when producing nonequilibrium-diffusion solutions, but that this monotonicity may disappear while integrating the precursor region to produce Sn-transport solutions. For temperature- and density-dependent cross sections we show evidence of a spike in the VEF in the far upstream portion of the radiative-shock precursor. We show evidence of an adaptation zone in the precursor region, adjacent to the embedded hydrodynamic shock, as conjectured by Drake [2, 3], and also confirm his expectation that the precursor temperatures adjacent to the Zel’dovich spike take values that are greater than the downstream post-shock equilibrium temperature. We also show evidence that the radiation energy density can be nonmonotonic under the Zel’dovich spike, which is indicative of anti-diffusive radiation flow as predicted by McClarren and Drake [4]. We compare the angle dependence of the radiation flow for the Sn-transport and nonequilibriumdiffusion radiation solutions, and show that there are considerable differences in the radiation flow between these models across the shock structure. Lastly, we analyze the radiation flow to understand the cause of the adaptation zone, as well as the structure of the Sn-transport radiation-intensity solutions across the shock structure.

Nuclear radiation application to nanotechnology

International Nuclear Information System (INIS)

Chakarvarti, S.K.

2012-01-01

Out of the numerous uses and applications of nuclear radiation, in particular heavy ions, the interaction of radiation with materials have culminated into a gamut of fine tools and technologies for taming the synergetic potential of the interaction. One such field of the immense importance is nanotechnology through nuclear radiation via use of ion-crafted polymeric membranes- so called 'Template Synthesis'. This talk will be addressed to the users of membranes - organic (polymeric) in general, formed through irradiation of polymeric foils with heavy and energetic ions followed by chemical processing leading finally to what is known as 'Track Etch Membranes (TEMs)', and present the review of the innovative uses of these membranes from filtration to electro-kinetic based applications and nano-/micro fabrication of devices- the potent aspect of emerging technologies. The emphasis would be on the dependence of useful and novel usages including applications in nano devices' fabrication. A membrane, with its most comprehensive and clear definition, is an intervening phase separating two phases and/or acting as an active or passive barrier to the transport of matter between phases. The very existence of a membrane relies upon the functionality domain of the pores contained therein. The geometrical traits and morphology of the pore ensembles dictate the applications, which any membrane can serve to. There are variety of membranes being developed and used in myriad of applications in diverse fields of science and technology. The range of commercially available membrane materials is quiet diverse and varies widely in terms of composition, and physical structure. The creation of pores, whether through natural self-assembling phenomenon or man-made processes, might itself be an issue of interest but these are the pore-traits which are fundamentally more important, whether the membrane is being used for sieving-one of the ever most important applications the mankind has been

Radiation safety in nuclear industry in retrospect and perspective

International Nuclear Information System (INIS)

Pan Ziqiang

1993-01-01

More than 30 years have passed since the starting up of nuclear industry in China from the early 1950's. Over the past 30-odd years, nuclear industry has always kept a good record in China thanks to the policy of 'quality first, safety first' clearly put forward for nuclear industry from the outset and a lot of suitable effective measures taken over that period. Internationally, there is rapid progress in radiation protection and nuclear safety (hereafter refereed to as radiation safety) and a number of new concepts in the field of radiation protection have been advanced. Nuclear industry is developing based on the international standardization. To ensure the further development of nuclear utility, radiation safety needs to be further strengthened

Survey of radiation protection programmes for transport

International Nuclear Information System (INIS)

Lizot, M.T.; Perrin, M.L.; Sert, G.; Lange, F.; Schwarz, G.; Feet, H.J.; Christ, R.; Shaw, K.B.; Hughes, J.S.; Gelder, R.

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.)

Radiation Effects in Nuclear Waste Materials

International Nuclear Information System (INIS)

Weber, William J.; Wang, Lumin; Hess, Nancy J.; Icenhower, Jonathan P.; Thevuthasan, Suntharampillai

2003-01-01

The objective of this project is to develop a fundamental understanding of radiation effects in glasses and ceramics, as well as the influence of solid-state radiation effects on aqueous dissolution kinetics, which may impact the performance of nuclear waste forms and stabilized nuclear materials. This work provides the underpinning science to develop improved glass and ceramic waste forms for the immobilization and disposition of high-level tank waste, excess plutonium, plutonium residues and scrap, other actinides, and other nuclear waste streams. Furthermore, this work is developing develop predictive models for the performance of nuclear waste forms and stabilized nuclear materials. Thus, the research performed under this project has significant implications for the immobilization of High-Level Waste (HLW) and Nuclear Materials, two mission areas within the Office of Environmental Management (EM). With regard to the HLW mission, this research will lead to improved understanding of radiation-induced degradation mechanisms and their effects on dissolution kinetics, as well as development of predictive models for waste form performance. In the Nuclear Materials mission, this research will lead to improvements in the understanding of radiation effects on the chemical and structural properties of materials for the stabilization and long-term storage of plutonium, highly-enriched uranium, and other actinides. The research uses plutonium incorporation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of alpha decay and beta decay on relevant glasses and ceramics. The research under this project has the potential to result in improved glass and ceramic materials for the stabilization and immobilization of high-level tank waste, plutonium residues and scraps, surplus weapons plutonium, highly-enriched uranium, other actinides, and other radioactive materials

Radiation Effects in Nuclear Waste Materials

International Nuclear Information System (INIS)

Weber, William J.

2005-01-01

The objective of this project is to develop a fundamental understanding of radiation effects in glasses and ceramics, as well as the influence of solid-state radiation effects on aqueous dissolution kinetics, which may impact the performance of nuclear waste forms and stabilized nuclear materials. This work provides the underpinning science to develop improved glass and ceramic waste forms for the immobilization and disposition of high-level tank waste, excess plutonium, plutonium residues and scrap, other actinides, and other nuclear waste streams. Furthermore, this work is developing develop predictive models for the performance of nuclear waste forms and stabilized nuclear materials. Thus, the research performed under this project has significant implications for the immobilization of High-Level Waste (HLW) and Nuclear Materials, two mission areas within the Office of Environmental Management (EM). With regard to the HLW mission, this research will lead to improved understanding of radiation-induced degradation mechanisms and their effects on dissolution kinetics, as well as development of predictive models for waste form performance. In the Nuclear Materials mission, this research will lead to improvements in the understanding of radiation effects on the chemical and structural properties of materials for the stabilization and long-term storage of plutonium, highly-enriched uranium, and other actinides. The research uses plutonium incorporation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of alpha decay and beta decay on relevant glasses and ceramics. The research under this project has the potential to result in improved glass and ceramic materials for the stabilization and immobilization of high-level tank waste, plutonium residues and scraps, surplus weapons plutonium, highly-enriched uranium, other actinides, and other radioactive materials

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Slovenia

International Nuclear Information System (INIS)

2013-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General Regulatory Regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment; 4. Nuclear installations (Licensing and inspection, including nuclear safety; Emergency response); 5. Trade in nuclear materials and equipment; 6. Safeguards for nuclear material; 7. Radiation protection; 8. Radioactive waste management; 9. Nuclear security; 10. Transport; 11. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (Slovenian Nuclear Safety Administration - SNSA; Slovenian Radiation Protection Administration - SRPA); 2. Advisory bodies; 3. Public and semi-public agencies; 4. Technical support organisations - approved experts

Safety and radiation protection in Indian nuclear power plants

International Nuclear Information System (INIS)

Ghadge, S.G.

2008-01-01

Full text: Nuclear energy, an important option for electricity generation is environment friendly, technologically proven, economically competitive and associated with the advantages of energy security and diversity. At present, India has an installed nuclear power generation capacity of 4120 M We with 6 more reactors are under construction/ commissioning at 4 sites. Nuclear power program, in India, as of now is primarily based on pressurized heavy water technology and these reactors are designed with safety features, such as, independent and diverse shut down systems, emergency core cooling system, double containment; pressure suppression pool etc. The principles of redundancy, diversity, fail-safe and passive systems are used in the design. The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. In this regard the prime responsibility for safety rests with the organization responsible for facilities and activities that give rise to radiation risks and is achieved by establishing and maintaining the necessary competence, providing adequate training and information, establishing procedures and arrangements to maintain safety under all conditions; verifying appropriate design and the adequate quality of facilities and activities and of their associated equipment; ensuring the safe control of all radioactive material that is used, produced, stored or transported, ensuring the safe control of all radioactive waste that is generated. 'Radiation Protection for Nuclear Facilities', issued by Atomic Energy Regulatory Board (the regulatory authority for NPPs in India) is the basic document for following radiation protection procedures in NPPs. Approved work procedures for all radiation jobs exist. Pre job briefing and post job analysis are carried out. Radiation protection is integrated with plant operation. Radiation levels indicate the performance of several systems. Several measures are adopted in design and

Practical methods for radiation survey in nuclear installations

International Nuclear Information System (INIS)

Shweikani, R.

2001-12-01

This study is placed to those who are responsible to perform radiation survey in the nuclear installations, especially the beginners. Therefore, it gives a comprehensive view to all-important aspects related to their work starting from the structure of atoms to the practical steps for radiation survey works. So, it clarify how to perform personal monitoring, methods for monitoring surface contamination, methods for measuring radioactivity of gases and radioactive aerosols in air, monitoring radiation doses, measuring radiation influences in workplaces and finally measuring internal exposure of radiation workers in nuclear installations. Finally, The study shows some cases of breaches of radiation protection rules in some American nuclear installations and describes the final results of these breaches. The aim of this is to assure that any breach or ignore to radiation protection principles may produce bad results, and there is no leniency in implementing environmental radiation protection principles. (author)

Radiation protection aspects in the design of nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2008-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the Contracting Parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

New aspects regarding to radiation protection in nuclear medicine

International Nuclear Information System (INIS)

Shabestani Monfared, A.; Amiri, M.

2002-01-01

Introduction and objectives: The society has been concerned about nuclear energy usage and nuclear environment pollution for ages. The necessity of using radiation and its applications in modern life especially in medicine is undeniable. Some interesting properties such as the potential for non-destructive tests, detection simplicity, and penetrability into substances and having reactions with them cause radiation to be known as a useful tool for peace purposes. Nuclear weapons' experiments (1945-1973) and nuclear accidents in Three-Mile Island in USA, Goiania in Brazil and Chernobyl in Ukraine Republic have enhanced man's worries towards nuclear radiation and radioactivity in environment, and founding associations and groups which are against nuclear energy, such as green peace society, can be related with above mentioned concerns. Today, nuclear medicine has rapidly been developed so that in some cases plays a unique role in diagnosis but unfortunately in spite of diagnostic and therapeutic advantages, the term N UCLEAR c an induce worries in patients and society. In this article, base on new documents we intend to show that this worries has no scientific basis. Material and Methods: To produce a realistic view, regarding to radiation protection we used several ways such as natural origin of radiation, high natural background radiation areas' data non-linear dose-effect model, risk versus benefit, use of arbitrary unit for measurement of radiation, radio adaptive response and radiation hormesis. Discussion and conclusion: Harmful effects of radiation on biologic systems has obviously been shown, but most of related documents are based on receiving high doses in nuclear and atomic accidents and explosions and radiation protection regulations are based on this observations. So, it sometimes causes patients are afraid of low doses of radiation in medical diagnostic procedures so that some of them even resist against performing this procedures. Thus, being aware of

ASN report abstracts on the state of Nuclear Safety and Radiation Protection in France in 2008. ASN annual report 2008

International Nuclear Information System (INIS)

2009-01-01

ASN is an independent administrative authority tasked, on behalf of the state, with regulating nuclear safety and radiation protection in order to protect workers, patients and the environment from the hazards involved in nuclear activities. It also contributes to informing the public. ASN, run by a five-member commission, regulates the whole of the sector, acting in a completely impartial manner. The ASN Commission presents its report on the state of nuclear safety and radiation protection in France in 2008. Contents: A - Introduction: The year 2008. B - Key topics: 1. ASN actions to promote greater transparency; 2. EDF nuclear power plant ageing and operating life: the conditions for continued operation; 3. The prevention of malicious acts; 4. ASN regulation of the radiotherapy sector; 5. Regulating and monitoring the construction of the Flamanville 3 EPR reactor; 6. ASN's international nuclear safety responsibilities; 7. The new nuclear countries; 8. Decommissioning of basic nuclear installations and the low-level, long-lived waste disposal project. C - Overview: 1 - Nuclear activities: ionising radiations and health risks; 2 - Principles and stakeholders in the regulation of nuclear safety and radiation protection; 3 - Regulation; 4 - Regulation of nuclear activities and exposure to ionising radiations; 5 - Environmental protection; 6 - Public information and transparency; 7 - International relations; 8 - Radiological emergencies; 9 - Medical uses of ionising radiations; 10 - Industrial and research activities; 11 - Transport of radioactive materials; 12 - EDF nuclear power plants; 13 - Nuclear fuel cycle installations; 14 - Nuclear research facilities and various nuclear installations; 15 - Safe decommissioning of basic nuclear installations; 16 - Radioactive waste and polluted sites. D - Appendices: List of basic nuclear installations; ASN decisions and opinions published in 2008 in its Official Bulletin; Acronyms, abbreviations and names

Nuclear transport

International Nuclear Information System (INIS)

Anon.

2002-01-01

During September and October 2001, 1 event has been reported and classified at the first level of the INES scale. This incident concerns the violation of the European regulation that imposes to any driver of radioactive matter of being the holder of a certificate asserting that he attended a special training. During this period, 13 in-site inspections have been made in places related to nuclear transport. (A.C.)

Radiation chemistry in the nuclear power reactor environment: from laboratory study to practical application

International Nuclear Information System (INIS)

Stuart, C.R.

1999-01-01

This paper discusses the work carried out at the Chalk River Nuclear Laboratories in underlying and applied radiation chemical research performed to optimise the processes occurring in the four aqueous systems in and around the core. The aqueous systems subject to radiolysis in CANDU reactors are Heat Transport System, Moderator, Liquid Zone Controls and End Shields.

Liability and insurance aspects of international transport of nuclear materials

International Nuclear Information System (INIS)

van Gijn, S.H.

1985-01-01

The Paris and Vienna Conventions do not affect the application of any international transport agreement already in force. However, in certain circumstances both the nuclear operator and the carrier may be held liable for nuclear damage which arises during international transports of nuclear materials. The ensuing cumulation of liabilities under the Nuclear and Transport Conventions may cause serious problems in obtaining adequate insurance cover for such transports. The 1971 Brussels Convention seeks to solve this problem by exonerating any person who might be held liable for nuclear damage under an international maritime convention or national law. Similar difficulties are encountered in the case of transports of nuclear materials between states which have and states which have not ratified the Paris and Vienna Conventions. (NEA) [fr

Ecological radiation protection criteria for nuclear power

International Nuclear Information System (INIS)

Kryshev, I.I.

1993-01-01

By now a large quantity of radioactive hazards of all sizes and shapes has accumulated in Russia. They include RBMK, VVER, and BN (fast-neutron) nuclear power plants, nuclear fuel processing plants, radioactive waste dumps, ships with nuclear power units, etc. In order to evaluate the radioecological situation correctly, the characteristics of the radioactive contamination must be compiled in these areas with some system of criteria which will provide an acceptable level of ecological safety. Currently health criteria for radiation protection are, which are oriented to man's radiation protection, predominate. Here the concept of a thresholdless linear dose-response dependence, which has been confirmed experimentally only at rather high doses (above 1 Gy), is taken as the theoretical basis for evaluating and normalizing radiation effects. According to one opinion, protecting people against radiation is sufficient to protect other types of organisms, although they are not necessarily of the same species. However, from the viewpoint of ecology, this approach is incorrect, because it does not consider radiation dose differences between man and other living organisms. The article discusses dose-response dependences for various organisms, biological effects of ionizing radiation, and appropriate radiation protection criteria

Transportation of nuclear materials: the nuclear focus of the 80's

International Nuclear Information System (INIS)

Meyers, S.; Hardin, E.C. Jr.; Jefferson, R.M.

1980-01-01

The transport of radioactive material has been carried out since the inception of the nuclear age (over 30 years) with an unparralled safety record. Despite these achievements, there is a need to strive for improvements, to develop safer and more efficient transportation systems, moreover to perform these tasks in a highly visible manner so that public concern can be allayed. But, in the same vein that the past record is not of itself sufficient, neither is public participation the solution to all the issues surrounding the transportation of radioactive materials. The solutions to the problems facing the nuclear transport industry involve many disciplines, much of which rest on a foundation of sound technology. This conference is built around a core of papers on the developing technology of nuclear transportation: on systems, their design and development, their manufacturing processes, their operation and the methodologies of quality assurance in each of these activities. The role of IAEA in the collecting of data to compile information on the flow of radioactive materials, the mode of transport and the corresponding accident/incident experience, as well as its role in initiating a program to develop a worldwide uniform methodology to address the risks of transporting radioactive materials are covered in this symposium

The IRSN's scientific strategy for the progress of nuclear safety, nuclear security and radiation protection

International Nuclear Information System (INIS)

2015-12-01

This publication defines the new strategy of the IRSN to fulfil its role in nuclear safety, in the protection of mankind and of the environment against ionizing radiations, and in the protection of nuclear materials, installations and transports against malevolent acts. The IRSN is also involved in public information, and as an actor and a partner in the definition of other major public policies such as research and innovation, work health or environmental health. In a first part, the report highlights these missions, the current evolution of the international scientific, technological and economic context, and briefly evokes the major scientific challenges for the next decade. The second part highlights the abilities and capacities of the IRSN to support scientific approaches and works. The main orientations are then formulated and commented: to justify scientific orientation backgrounds and means to assign, to associate final recipients to research works, to implement initiatives to develop national, European and international cooperation in the field of nuclear and radiological risks, to develop academic partnerships and to participate to national research alliances, to develop collaboration with industries, nuclear operators and actors of the medical sector, to possess tools to perform numeric simulation, to guarantee the access for the Institute to research and experimentation infrastructures and data bases, to develop methodologies and tools for aid to decision, to perpetuate knowledge and know-how for a better renewal of risk assessment. The report then presents the main questions of interest regarding radiation protection and nuclear safety

Estimated effects on radiation doses from alternatives in a spent fuel transportation system

International Nuclear Information System (INIS)

Schneider, K.J.; Ross, W.A.; Smith, R.I.

1988-07-01

This paper contains the results of a study of estimated radiation doses to the public and workers from the transport of spent fuel from commercial nuclear power reactors to a geologic repository. A postulated reference rail/legal-weight truck transportation system is defined that would use current transportation technology, and provide a breakdown of activities and time/distance/dose-rate estimates for each activity within the system. Collective doses are estimated for each of the major activities at the reactor site, in transit, and at the repository receiving facility. Annual individual doses to the maximally exposed individuals or groups of individuals are also estimated. The dose-reduction potentials and costs are estimated for a total of 17 conceptual alternatives and subalternatives to the postulated reference system. Most of the alternatives evaluated are estimated to provide both cost and dose reductions. The major conclusion is that the potential exists for significant future reductions in radiation doses to the public and workers and for reductions in costs compared to those based on a continuation of past practices in the US

Estimated effects on radiation doses from alternatives in a spent fuel transportation system

International Nuclear Information System (INIS)

Schneider, K.J.; Ross, W.A.; Smith, R.I.

1988-01-01

This paper contains the results of a study of estimated radiation doses to the public and workers from the transport of spent fuel from commercial nuclear power reactors to a geologic repository. A postulated reference rail/legal-weight truck transportation system is defined that would use current transportation technology, and provide a breakdown of activities and time/distance/dose-rate estimates for each activity within the system. Collective doses are estimated for each of the major activities at the reactor site, in transit, and at the repository receiving facility. Annual individual doses to the maximally exposed individuals or groups of individuals also estimated. The dose-reduction potentials and costs are estimated for a total of 17 conceptual alternatives and subalternatives to the postulated reference system. Most of the alternatives evaluated are estimated to provide both cost and dose reductions. The major conclusion is that the potential exists for significant future reductions in radiation doses to the public and workers and for reductions in costs compared to those based on a continuation of past practices in the U.S

The Role of Nuclear Fragmentation in Particle Therapy and Space Radiation Protection.

Science.gov (United States)

Zeitlin, Cary; La Tessa, Chiara

2016-01-01

The transport of the so-called HZE particles (those having high charge, Z, and energy, E) through matter is crucially important both in space radiation protection and in the clinical setting where heavy ions are used for cancer treatment. HZE particles are usually considered those having Z > 1, though sometimes Z > 2 is meant. Transport physics is governed by two types of interactions, electromagnetic (ionization energy loss) and nuclear. Models of transport, such as those used in treatment planning and space mission planning must account for both effects in detail. The theory of electromagnetic interactions is well developed, but nucleus-nucleus collisions are so complex that no fundamental physical theory currently describes them. Instead, interaction models are generally anchored to experimental data, which in some areas are far from complete. The lack of fundamental physics knowledge introduces uncertainties in the calculations of exposures and their associated risks. These uncertainties are greatly compounded by the much larger uncertainties in biological response to HZE particles. In this article, we discuss the role of nucleus-nucleus interactions in heavy charged particle therapy and in deep space, where astronauts will receive a chronic low dose from galactic cosmic rays (GCRs) and potentially higher short-term doses from sporadic, unpredictable solar energetic particles (SEPs). GCRs include HZE particles; SEPs typically do not and we, therefore, exclude them from consideration in this article. Nucleus-nucleus collisions can result in the breakup of heavy ions into lighter ions. In space, this is generally beneficial because dose and dose equivalent are, on the whole, reduced in the process. The GCRs can be considered a radiation field with a significant high-LET component; when they pass through matter, the high-LET component is attenuated, at the cost of a slight increase in the low-LET component. Not only are the standard measures of risk

GLONASS satellite monitoring of nuclear transports

International Nuclear Information System (INIS)

Davydov, Yu.L.

2012-01-01

In 2011 Rosatom has made the decision to create the industry-wide automated system for monitoring of transports of radioactive substances (RS) and wastes (RAW), as well as hazardous loads by rail and automobile, based upon the same hardware as used by the GLONASS satellite navigation system - the so-called ASBT-GLONASS system. The new system will use the same technical infrastructure as the existing operational Automated System for Safe Transport of Nuclear Materials of Categories I and II (ASBT). The ASBT structure includes a network of control centres fitted with automation and communication hardware. In addition, ASBT includes technical complexes installed upon transport vehicles intended for nuclear material transport. In order to identify transport vehicle location, the GLONASS/GPS (GALS-P-ASBT) satellite navigational receiver device is used, it is developed especially for ASBT systems taking in account information security requirements. By now the basic software and hardware complex ASBT-GLONASS has been created (equipment to be carried on-board the transport vehicle loaded with RS and RAW, as well as the transport control stations) that supports transport monitoring and transmission of an emergency signal to control stations of companies which deal with RS and RAW transportation [ru

Nuclear safety and radiation protection report of the nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Concrete alkali-silica reaction and nuclear radiation damage

International Nuclear Information System (INIS)

Ichikawa, Tsuneki

2008-01-01

The deterioration of concrete by alkali-silica reaction of aggregates (ASR) and the effect of nuclear radiations on the ASR have been reviewed based on our studies on the mechanism of ASR and the effect of nuclear radiations on the resistivity of minerals to alkaline solution. It has been found that the ASR is initiated by the attack of alkaline solution in concrete to silicious aggregates to convert them into hydrated alkali silicate. The consumption of alkali hydroxide by the aggregates induces the dissolution of Ca 2+ ions into the solution. The alkali silicate surrounding the aggregates then reacts with Ca 2+ ions to convert to insoluble tight and rigid reaction rims. The reaction rim allows the penetration of alkaline solution but prevents the leakage of viscous alkali silicate, so that alkali silicate generated afterward is accumulated in the aggregate to give an expansive pressure enough for cracking the aggregate and the surrounding concrete. The effect of nuclear radiation on the reactivity of quartz and plagioclase, a part of major minerals composing volcanic rocks as popular aggregates, to alkaline solution has been examined for clarifying whether nuclear radiations accelerates the ASR. It has been found that the irradiation of these minerals converts them into alkali-reactive amorphous ones. The radiation dose for plagioclase is as low as 10 8 Gy, which suggests that the ASR of concrete surrounding nuclear reactors is possible to be accelerated by nuclear radiation. (author)

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Portugal

International Nuclear Information System (INIS)

2011-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment; 4. Nuclear installations (Licensing and inspection, including nuclear safety; Protection of the environment against radiation effects; Emergency response); 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Non-proliferation and physical protection; 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (Ministry of Health; Minister of Science, Technology and Higher Education; Ministry of Economy and Innovation; Ministry of Environment and Territorial Planning; Other authorities); 2. Advisory bodies (Independent Commission for Radiological Protection and Nuclear Safety - CIPRSN; National Radiation Protection Commission - CNPCR; National Commission for Radiological Emergencies - CNER; Other advisory bodies); 3. Public and semi-public agencies

Intercomparison of Environmental Nuclear Radiation Measuring

Institute of Scientific and Technical Information of China (English)

GAO; Fei; NI; Ning; HOU; Jin-bing; SONG; Ming-zhe

2015-01-01

In 2015,Radiation Metrology Division of China Institute of Atomic Energy organized an environmental monitoring of nuclear radiation measuring intercomparison,and 9laboratories attended.The intercomparison included environmental level dosemeters and protection level

Conception and activity directions of journal ''Nuclear and radiation safety''

International Nuclear Information System (INIS)

Olena, M.; Volodymyr, S.

2000-01-01

In connection with the State Scientific and Technical Centre onr Nuclear and Radiation Safety (SSTC NRA) and Odessa State Polytechnic University the journal 'Nuclear and Radiation Safety' was established in 1998. In Ukraine many people are interested in nuclear energy problems. The accident in Chernobyl NPP unit 4 touches all Ukrainians and brings about strong and regular attention to nuclear and radiation safety of nuclear installations and nuclear technology, on the other side more than 50 per cent of electric power is produced in 5 NPPs and as following national power supply depends on stability of NPPs work. Main goals of the journal are: Support to Nuclear Regulatory Administration (NRA) of MEPNS of Ukraine, creation of information space for effective exchange of results of scientific, scientific and technical, scientific and analytical work in the field of Nuclear and Radiation Safety, assistance in integrated development of research for Nuclear and Radiation Safety by publication in a single issue of scientific articles, involvement of state scientific potential in resolving actual problems, participation in international collaboration in the framework of agreements, programs and plans. (orig.)

Distributing radiation management system of nuclear power plants

International Nuclear Information System (INIS)

Mihoya, Eiichi; Akashi, Michio

1999-01-01

The importance of radiation management for nuclear facilities including nuclear power plants has increased as the general public understanding has progressed, and necessary information for management must be processed exactly and quickly. In nuclear power plants, radiation management is performed by each individual operation, and collected information is managed by the system of each operation. The distributing radiation management system has been developed aiming to use a general-purpose LAN and make quick and efficient use of information managed by individual operations. This paper describes the system configuration and functions. (author)

Optical Fibers in Nuclear Reactor Radiation Environments.

Science.gov (United States)

Holcomb, David Eugene

1992-01-01

A performance evaluation of fiber optics under radiation conditions similar to those encountered in nuclear power plants is reported. The evaluation was accomplished by the creation of an analytical model for atomic scale radiation damage in silica glass and by the execution of an extensive fiber performance measurement program. The analytic model calculates displacement and electronic damage rates for silica glass subjected to a specified nuclear reactor radiation environment. It accomplishes this by first generating the primary charged particle spectrum produced in silica irradiated in a nuclear reactor. The resultant spectra are then applied to the integral equations describing radiation damage in polyatomic solids. The experimental measurements were selected to span the range of fiber types, radiation environments, temperatures, and light powers expected to be used in nuclear power plants. The basic experimental protocol was to expose the optical fibers to either a nuclear reactor or a ^{60}Co radiation environment while simultaneously monitoring fiber light transmission. Experimental temperatures were either ~23 ^circC or ~100 ^circC and light powers were either -30 dBm or -60 dBm. Measurements were made at each of the three standard communications wavelengths (850 nm, 1300 nm, and 1550 nm). Several conclusions are made based on these performance measurements. First, even near the core of a nuclear reactor the vast majority of the dose to silica glass is due to gamma rays. Even with the much lower doses (factor of roughly 40) neutrons cause much more displacement damage than gamma rays (35 times the oxygen displacement rate and 500 times the silicon displacement rate). Even with neutrons having many times the displacement rate as compared with gamma rays, little if any difference is observed in the transmission losses for gamma only as compared to mixed neutron/gamma transmission losses. Therefore, atomic displacement is not a significant damage mechanism for

Radiation transport: Progress report, July 1, 1987-September 30, 1987

International Nuclear Information System (INIS)

O'Dell, R.D.; Nagy, A.

1988-05-01

Research and development progress in radiation transport for the Los Alamos National Laboratory's Group S-6 for the fourth quarter of FY 87 is reported. Included are unclassified tasks in the areas of Deterministic Radiation Transport, Monte Carlo Radiation Transport, and Cross Sections and Physics. 23 refs., 9 figs

Radiation dose assessment in nuclear medicine

International Nuclear Information System (INIS)

Stabin, M.G.

2002-01-01

In any application involving the use of ionizing radiation in humans, risks and benefits must be properly evaluated and balanced. Radionuclides are used in nuclear medicine in a variety of diagnostic and therapeutic procedures. Recently, interest has grown in therapeutic agents for a number of applications in nuclear medicine, particularly in the treatment of hematologic and non-hematologic malignancies. This has heightened interest in the need for radiation dose calculations and challenged the scientific community to develop more patient-specific and relevant dose models. Consideration of radiation dose in such studies is central to efforts to maximize dose to tumor while sparing normal tissues. In many applications, a significant absorbed dose may be received by some radiosensitive organs, particularly the active marrow. This talk will review the methods and models used in internal dosimetry in nuclear medicine, and discuss some current trends and challenges in this field

Integrated nuclear radiation detector and monitor

International Nuclear Information System (INIS)

Biehl, B.L.; Lieberman, S.I.

1982-01-01

A battery powered device which can continuously monitor and detect nuclear radiation utilizing fully integrated circuitry and which is provided with an alarm which alerts persons when the radiation level exceeds a predetermined threshold

Radiation damage in nuclear waste materials

International Nuclear Information System (INIS)

Jencic, I.

2000-01-01

Final disposal of high-level radioactive nuclear waste is usually envisioned in some sort of ceramic material. The physical and chemical properties of host materials for nuclear waste can be altered by internal radiation and consequently their structural integrity can be jeopardized. Assessment of long-term performance of these ceramic materials is therefore vital for a safe and successful disposal. This paper presents an overview of studies on several possible candidate materials for immobilization of fission products and actinides, such as spinel (MgAl 2 O 4 ), perovskite (CaTiO 3 ), zircon (ZrSiO 4 ), and pyrochlore (Gd 2 Ti 2 O 7 and Gd 2 Zr 2 O 7 ). The basic microscopic picture of radiation damage in ceramics consists of atomic displacements and ionization. In many cases these processes result in amorphization (metaminctization) of irradiated material. The evolution of microscopic structure during irradiation leads to various macroscopic radiation effects. The connection between microscopic and macroscopic picture is in most cases at least qualitatively known and studies of radiation induced microscopic changes are therefore an essential step in the design of a reliable nuclear waste host material. The relevance of these technologically important results on our general understanding of radiation damage processes and on current research efforts in Slovenia is also addressed. (author)

Radiative transport-based frequency-domain fluorescence tomography

International Nuclear Information System (INIS)

Joshi, Amit; Rasmussen, John C; Sevick-Muraca, Eva M; Wareing, Todd A; McGhee, John

2008-01-01

We report the development of radiative transport model-based fluorescence optical tomography from frequency-domain boundary measurements. The coupled radiative transport model for describing NIR fluorescence propagation in tissue is solved by a novel software based on the established Attila(TM) particle transport simulation platform. The proposed scheme enables the prediction of fluorescence measurements with non-contact sources and detectors at a minimal computational cost. An adjoint transport solution-based fluorescence tomography algorithm is implemented on dual grids to efficiently assemble the measurement sensitivity Jacobian matrix. Finally, we demonstrate fluorescence tomography on a realistic computational mouse model to locate nM to μM fluorophore concentration distributions in simulated mouse organs

Electromagnetic and nuclear radiation detector using micromechanical sensors

Science.gov (United States)

Thundat, Thomas G.; Warmack, Robert J.; Wachter, Eric A.

2000-01-01

Electromagnetic and nuclear radiation is detected by micromechanical sensors that can be coated with various interactive materials. As the micromechanical sensors absorb radiation, the sensors bend and/or undergo a shift in resonance characteristics. The bending and resonance changes are detected with high sensitivity by any of several detection methods including optical, capacitive, and piezoresistive methods. Wide bands of the electromagnetic spectrum can be imaged with picoJoule sensitivity, and specific absorptive coatings can be used for selective sensitivity in specific wavelength bands. Microcantilevers coated with optical cross-linking polymers are useful as integrating optical radiation dosimeters. Nuclear radiation dosimetry is possible by fabricating cantilevers from materials that are sensitive to various nuclear particles or radiation. Upon exposure to radiation, the cantilever bends due to stress and its resonance frequency shifts due to changes in elastic properties, based on cantilever shape and properties of the coating.

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Switzerland

International Nuclear Information System (INIS)

2010-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment (Nuclear fuels; Radioactive substances and equipment generating ionising radiation); 4. Nuclear installations (Licensing and inspection, including nuclear safety; Protection of the environment against radiation effects; Emergency response); 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Non-proliferation and physical protection; 9. Transport; 10. Nuclear third party liability; 11. Environmental protection; II. Institutional Framework: 1. Regulatory and supervisory authorities (Federal Council; Federal Assembly; Federal Department of the Environment, Transport, Energy and Communications - DETEC; Federal Office of Energy - SFOE; Swiss Federal Nuclear Safety Inspectorate - IFSN; Federal Department of Home Affairs - FDHA; Federal Office of Public Health - FOPH; State Secretariat for Education and Research - SER; Other authorities); 2. Advisory bodies (Swiss Federal Nuclear Safety Commission - KNS; Federal Commission for Radiological Protection and Monitoring of the Radioactivity in the Environment; Federal Emergency Organisation on Radioactivity); 3. Public and semi-public agencies (Paul-Scherrer Institute - PSI; Fund for the decommissioning of nuclear installations and for the waste disposal; National Co-operative for the

Review of radiation effects in solid-nuclear-waste forms

International Nuclear Information System (INIS)

Weber, W.J.

1981-09-01

Radiation effects on the stability of high-level nuclear waste (HLW) forms are an important consideration in the development of technology to immobilize high-level radioactive waste because such effects may significantly affect the containment of the radioactive waste. Since the required containment times are long (10 3 to 10 6 years), an understanding of the long-term cumulative effects of radiation damage on the waste forms is essential. Radiation damage of nuclear waste forms can result in changes in volume, leach rate, stored energy, structure/microstructure, and mechanical properties. Any one or combination of these changes might significantly affect the long-term stability of the nuclear waste forms. This report defines the general radiation damage problem in nuclear waste forms, describes the simulation techniques currently available for accelerated testing of nuclear waste forms, and reviews the available data on radiation effects in both glass and ceramic (primarily crystalline) waste forms. 76 references

Regulatory inspections in nuclear plants in the field of radiation protection

International Nuclear Information System (INIS)

Hort, M.; Fuchsova, D.

2014-01-01

State Office for Nuclear Safety executes state administration and performs inspections at peaceful use of nuclear energy and ionizing radiation in the field of radiation protection and nuclear safety. Inspections on radiation protection at nuclear power plants are secured by inspectors of the Department of Radiation Protection in Fuel Cycle, who work at the Regional centre Brno and Ceske Budejovice. (authors)

Renormalization-group approach to nonlinear radiation-transport problems

International Nuclear Information System (INIS)

Chapline, G.F.

1980-01-01

A Monte Carlo method is derived for solving nonlinear radiation-transport problems that allows one to average over the effects of many photon absorptions and emissions at frequencies where the opacity is large. This method should allow one to treat radiation-transport problems with large optical depths, e.g., line-transport problems, with little increase in computational effort over that which is required for optically thin problems

The new deterministic 3-D radiation transport code Multitrans: C5G7 MOX fuel assembly benchmark

International Nuclear Information System (INIS)

Kotiluoto, P.

2003-01-01

The novel deterministic three-dimensional radiation transport code MultiTrans is based on combination of the advanced tree multigrid technique and the simplified P3 (SP3) radiation transport approximation. In the tree multigrid technique, an automatic mesh refinement is performed on material surfaces. The tree multigrid is generated directly from stereo-lithography (STL) files exported by computer-aided design (CAD) systems, thus allowing an easy interface for construction and upgrading of the geometry. The deterministic MultiTrans code allows fast solution of complicated three-dimensional transport problems in detail, offering a new tool for nuclear applications in reactor physics. In order to determine the feasibility of a new code, computational benchmarks need to be carried out. In this work, MultiTrans code is tested for a seven-group three-dimensional MOX fuel assembly transport benchmark without spatial homogenization (NEA C5G7 MOX). (author)

Radiation exposure of nuclear medicine procedures in Germany

International Nuclear Information System (INIS)

Hacker, M.

2005-01-01

Nuclear Medicine procedures offer the possibility to detect abnormalities on the basis of physiological and metabolic changes and to treat a growing number of diseases in human beings. However, the use of radiopharmaceuticals for nuclear medicine examinations causes a significant component of the total radiation exposure of populations. In Germany it is an essential task of the Federal Office for Radiation Protection to determinate and assess radiation exposure of the population due to nuclear medicine diagnostics and therapy. An important input for this task is the frequency of nuclear-medical examinations with application of ionising radiation and the radiation exposure of patients related to the various procedures. Additional implementation of age- and gender-specific data today allows more exact risk stratification in focusing on different subgroups of patients. Moreover, the collective effective dose as well as the per caput effective dose of the German population may be estimated and compared with earlier collected data or foreign countries. These data reveal where the indication should be questioned particularly critically and if the dose for the various examinations can be reduced and, thus, contribute to the definition of diagnostic reference levels for nuclear medicine procedures in Germany with the aim of both a sufficient image quality and a minimum of radiation exposure. Exceeding the high- as well as the low-values requires documentation and explanation. (orig.)

Multi-MGy Radiation Hardened Camera for Nuclear Facilities

International Nuclear Information System (INIS)

Girard, Sylvain; Boukenter, Aziz; Ouerdane, Youcef; Goiffon, Vincent; Corbiere, Franck; Rolando, Sebastien; Molina, Romain; Estribeau, Magali; Avon, Barbara; Magnan, Pierre; Paillet, Philippe; Duhamel, Olivier; Gaillardin, Marc; Raine, Melanie

2015-01-01

There is an increasing interest in developing cameras for surveillance systems to monitor nuclear facilities or nuclear waste storages. Particularly, for today's and the next generation of nuclear facilities increasing safety requirements consecutive to Fukushima Daiichi's disaster have to be considered. For some applications, radiation tolerance needs to overcome doses in the MGy(SiO 2 ) range whereas the most tolerant commercial or prototypes products based on solid state image sensors withstand doses up to few kGy. The objective of this work is to present the radiation hardening strategy developed by our research groups to enhance the tolerance to ionizing radiations of the various subparts of these imaging systems by working simultaneously at the component and system design levels. Developing radiation-hardened camera implies to combine several radiation-hardening strategies. In our case, we decided not to use the simplest one, the shielding approach. This approach is efficient but limits the camera miniaturization and is not compatible with its future integration in remote-handling or robotic systems. Then, the hardening-by-component strategy appears mandatory to avoid the failure of one of the camera subparts at doses lower than the MGy. Concerning the image sensor itself, the used technology is a CMOS Image Sensor (CIS) designed by ISAE team with custom pixel designs used to mitigate the total ionizing dose (TID) effects that occur well below the MGy range in classical image sensors (e.g. Charge Coupled Devices (CCD), Charge Injection Devices (CID) and classical Active Pixel Sensors (APS)), such as the complete loss of functionality, the dark current increase and the gain drop. We'll present at the conference a comparative study between these radiation-hardened pixel radiation responses with respect to conventional ones, demonstrating the efficiency of the choices made. The targeted strategy to develop the complete radiation hard camera

Multi-MGy Radiation Hardened Camera for Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Girard, Sylvain; Boukenter, Aziz; Ouerdane, Youcef [Universite de Saint-Etienne, Lab. Hubert Curien, UMR-CNRS 5516, F-42000 Saint-Etienne (France); Goiffon, Vincent; Corbiere, Franck; Rolando, Sebastien; Molina, Romain; Estribeau, Magali; Avon, Barbara; Magnan, Pierre [ISAE, Universite de Toulouse, F-31055 Toulouse (France); Paillet, Philippe; Duhamel, Olivier; Gaillardin, Marc; Raine, Melanie [CEA, DAM, DIF, F-91297 Arpajon (France)

2015-07-01

There is an increasing interest in developing cameras for surveillance systems to monitor nuclear facilities or nuclear waste storages. Particularly, for today's and the next generation of nuclear facilities increasing safety requirements consecutive to Fukushima Daiichi's disaster have to be considered. For some applications, radiation tolerance needs to overcome doses in the MGy(SiO{sub 2}) range whereas the most tolerant commercial or prototypes products based on solid state image sensors withstand doses up to few kGy. The objective of this work is to present the radiation hardening strategy developed by our research groups to enhance the tolerance to ionizing radiations of the various subparts of these imaging systems by working simultaneously at the component and system design levels. Developing radiation-hardened camera implies to combine several radiation-hardening strategies. In our case, we decided not to use the simplest one, the shielding approach. This approach is efficient but limits the camera miniaturization and is not compatible with its future integration in remote-handling or robotic systems. Then, the hardening-by-component strategy appears mandatory to avoid the failure of one of the camera subparts at doses lower than the MGy. Concerning the image sensor itself, the used technology is a CMOS Image Sensor (CIS) designed by ISAE team with custom pixel designs used to mitigate the total ionizing dose (TID) effects that occur well below the MGy range in classical image sensors (e.g. Charge Coupled Devices (CCD), Charge Injection Devices (CID) and classical Active Pixel Sensors (APS)), such as the complete loss of functionality, the dark current increase and the gain drop. We'll present at the conference a comparative study between these radiation-hardened pixel radiation responses with respect to conventional ones, demonstrating the efficiency of the choices made. The targeted strategy to develop the complete radiation hard camera

NMTC/JAM, Simulates High Energy Nuclear Reactions and Nuclear-Meson Transport Processes

International Nuclear Information System (INIS)

Furihata, Shiori

2002-01-01

1 - Description of program or function: NMTC/JAM is an upgraded version of the code system NMTC/JAERI97. NMTC/JAERI97 simulates high energy nuclear reactions and nucleon-meson transport processes. It implements an intra-nuclear cascade model taking account of the in-medium nuclear effects and the pre-equilibrium calculation model based on the exciton one. For treating the nucleon transport process, the nucleon-nucleus cross sections are revised to those derived by the systematics of Pearlstein. Moreover, the level density parameter derived by Ignatyuk is included as a new option for particle evaporation calculation. A geometry package based on the Combinatorial Geometry with multi-array system and the importance sampling technique is implemented in the code. Tally function is also employed for obtaining such physical quantities as neutron energy spectra, heat deposition and nuclide yield without editing a history file. The code can simulate both the primary spallation reaction and the secondary particle transport in the intermediate energy region from 20 MeV to 3.5 GeV by the use of the Monte Carlo technique. The code has been employed in combination with the neutron-photon transport codes available to the energy region below 20 MeV for neutronics calculation of accelerator-based subcritical reactors, analyses of thick target spallation experimented and so on. 2 - Methods: High energy nuclear reactions induced by incident high energy protons, neutrons and pions are simulated with the Monte Carlo Method by the intra-nuclear nucleon-nucleon reaction probabilities based on an intra-nuclear nucleon cascade model followed by the particle evaporation including high energy fission process. Jet-Aa Microscopic transport model (JAM) is employed to simulate high energy nuclear reactions in the energy range of GeV. All reaction channels are taken into account in the JAM calculation. An intra-nuclear cascade model (ISOBAR code) taking account of the in-medium nuclear effects

Survey of cognition on nuclear and radiation in Beijing high school students

International Nuclear Information System (INIS)

Wang Chao; He Jianrong; Zhu Xiayang; Yang Guoliang; Cong Huiling; Hu Qinfang

2014-01-01

Objective: To explore cognition level on nuclear and radiation in Beijing high school students, which may provide evidence for promoting science popularization on nuclear and radiation. Methods: Questionnaire-based survey was conducted in Beijing high school students, randomized cluster sampling was used to recruit study participants. Demographic information was collected, and cognition level on nuclear and radiation was evaluated by questionnaire. Results: A total of 1029 pieces of eligible questionnaires were collected. The correct rate for answering common sense about nuclear and radiation was 58%, with score of boys significantly higher than that of girls (t = 4.131, P < 0.05). About subjective cognition of nuclear and radiation knowledge, 87 (8.5%) indicated 'quite clear', 779 (75.7%) indicated 'know a little', 163 (15.8%) indicated 'know nothing'. There was significant difference in score of common sense about nuclear and radiation among people with various subjective cognition level of nuclear and radiation (J-T = 8.279, P < 0.05). There was a linear correlation between support degree for nuclear power and subjective cognition level of nuclear and radiation (r = 0.161, P < 0.05). There was significant difference in score of common sense about nuclear and radiation among people with various support degree for nuclear power (J-T = 7.508, P < 0.05), whereas those who had got high scores tended to support nuclear power to a higher degree. Conclutions: Students knew little about knowledge on nuclear and radiation. It is necessary to strengthen propaganda and education on nuclear and radiation, which may help enhance the students' comprehensive quality, and sustainable expansion of nuclear power more support in the long run. (authors)

History of radiation and nuclear disasters in the former USSR

International Nuclear Information System (INIS)

Malko, M.V.

2013-01-01

The report describes the history of radiation and nuclear accidents in the former USSR. These accidents accompanied development of military and civilian use of nuclear energy. Some of them as testing of the first Soviet nuclear, Kyshtym radiation accident, radiation contamination of the Karachai lake and the Techa river, nuclear accidents at the Soviet submarine on August 10, 1985 in the Chazhma Bay (near Vladivostok) as well as nuclear accidents on April 26, 1986 at the Chernobyl NPP were of large scale causing significant radiological problems for many hundreds thousands of people. There were a number of important reasons of these and other accidents. The most important among them were time pressure by development of nuclear weapon, an absence of required financial and material means for adequate management of problems of nuclear and radiation safety, and inadequate understanding of harmful interaction of ionizing radiation on organism as well as a hypersecrecy by realization of projects of military and civilian use of nuclear energy in the former USSR. (author)

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Sweden

International Nuclear Information System (INIS)

2008-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment; 4. Nuclear installations (Licensing and inspection, including nuclear safety; Protection of the environment against radiation effects (The Environmental Code, Environmental impact statement, Permit under the Environmental Code)); 5. Trade in nuclear materials and equipment; 6. Radiological protection; 7. Radioactive waste management; 8. Non-proliferation and physical protection; 9. Transport; 10. Nuclear third party liability (The Nuclear Liability Act; Chernobyl legislation); II. Institutional Framework: 1. Ministries with responsibilities concerning nuclear activities (Ministry of the Environment; Ministry of Enterprise, Energy and Communications; Ministry of Justice; Ministry of Foreign Affairs); 2. Swedish Radiation Safety Authority

Energetics of Transport through the Nuclear Pore Complex

NARCIS (Netherlands)

Ghavami, Ali; van der Giessen, Erik; Onck, Patrick R

2016-01-01

Molecular transport across the nuclear envelope in eukaryotic cells is solely controlled by the nuclear pore complex (NPC). The NPC provides two types of nucleocytoplasmic transport: passive diffusion of small molecules and active chaperon-mediated translocation of large molecules. It has been shown

3.International conference 'Nuclear and Radiation Physics'

International Nuclear Information System (INIS)

2001-01-01

The 3-rd International Conference 'Nuclear and Radiation Physics' was held in Almaty (Kazakhstan) 4-7 June 2001. The primary purpose of the conference is consolidation of the scientists efforts in the area of fundamental and applied investigations on nuclear physics, radiation physics of solids and radioecology. In the conference more than 350 papers were presented by participants from 17 countries

Statistics of Monte Carlo methods used in radiation transport calculation

International Nuclear Information System (INIS)

Datta, D.

2009-01-01

Radiation transport calculation can be carried out by using either deterministic or statistical methods. Radiation transport calculation based on statistical methods is basic theme of the Monte Carlo methods. The aim of this lecture is to describe the fundamental statistics required to build the foundations of Monte Carlo technique for radiation transport calculation. Lecture note is organized in the following way. Section (1) will describe the introduction of Basic Monte Carlo and its classification towards the respective field. Section (2) will describe the random sampling methods, a key component of Monte Carlo radiation transport calculation, Section (3) will provide the statistical uncertainty of Monte Carlo estimates, Section (4) will describe in brief the importance of variance reduction techniques while sampling particles such as photon, or neutron in the process of radiation transport

Development of Nuclear Energy and Radiation Textbooks for Elementary School Students

International Nuclear Information System (INIS)

Han, E.; Choi, Y.; Yang, J.; Lee, S.

2015-01-01

The textbooks for elementary school students were developed to help future generations make value judgments based on appropriate information about nuclear energy and radiation. The themes and educational contents of the 13 lessons, to be delivered in one semester at elementary school level, were selected by the educational requirements of students, science teachers, and experts. The “Radiation and Life” textbook for elementary school students consists of the following chapters: – Chapter 1. What is nuclear energy and radiation?, – Chapter 2. Who discovered the nuclear energy and radiation?, – Chapter 3. Why is nuclear energy and radiation important?, – Chapter 4. Is nuclear energy and radiation dangerous?, – Chapter 5. Let’s learn about what to do when an accident occurs, – Chapter 6. How are nuclear energy and radiation used?, – Chapter 7. What is nuclear power generation?, – Chapter 8. Why is radiation used for food?, – Chapter 9. What is medical radiation?, – Chapter 10. What kind of irradiated products are in our daily lives?, – Chapter 11. What jobs are related to nuclear energy and radiation?, – Chapter 12. What are energies of future?, – Chapter 13. Concept of Talk-talk (a study review game). The general trend in recent educational curriculum development suppresses national education course organizations and authorities and expands the autonomy and authority of regions and schools. The derived textbook contents are expected to be helpful as first textbooks for the autonomous selection of education about nuclear energy and radiation for use in creative experiences developed at the school level. (author)

Radiation transport. Progress report, April 1-December 31, 1983

International Nuclear Information System (INIS)

O'Dell, R.D.

1984-10-01

Research and development progress in radiation transport by the Los Alamos National Laboratory's Group X-6 for the last nine months of CY 83 is reported. Included are unclassified tasks in the areas of Fission Reactor Neutronics, Deterministic Transport Methods, Monte Carlo Radiation Transport, and Cross Sections and Physics

Nuclear materials transport in France

International Nuclear Information System (INIS)

Korycanek, J.

1990-01-01

About 1.5 million tons of uranium ore, 8000 tons of uranium concentrate, 1000 tons of UF 6 , 340 spent fuel containers, and 30 000 m 3 of nuclear wastes are transported annually by trucks, trains and ships in France. Annual costs of this transportation amount to 500-600 million FRF, and about 200 employees are engaged in this activity. Transportation of spent fuel to the La Hague and Marcoule fuel reprocessing plants, and the transport of plutonium are dealt with in detail. (Z.M.). 5 figs., 1 ref

Radiation exposure due to nuclear power

International Nuclear Information System (INIS)

This information brochure contains 12 earlier papers of leading experts on the radiation hazard the population incurs during normal operation of nuclear facilities and the radiation-biological fundamentals of the effects of ionizing radio humans. (HP) [de

Organization of nuclear safety and radiation protection in Switzerland

International Nuclear Information System (INIS)

Pretre, S.

1995-01-01

In Switzerland an important distinction is made between radiation protection (in charge of the use of ionizing radiations for medical uses or non nuclear industry), and nuclear safety (in charge of nuclear industry, including prevention or limitation of any risk of nuclear accident). In the eighties, it has been decided to make two laws for these two topics. The law for radioprotection, voted in 1991 is enforced since 1994 by OFSP (Office Federal de la Sante Publique). It performs any radiation monitoring outside nuclear industry plants. The law for nuclear safety, that should be enforced by OFEN (Office Federal de l'ENergie), is still not voted. The only existing legislation is the 1959 atomic law. (D.L.). 1 fig., 1 map

Nuclear radiation gauge standard

International Nuclear Information System (INIS)

Berry, R.L.

1977-01-01

A hydrophobic standard for calibrating nuclear radiation moisture gauges is described, comprising a body of superposed interleaved thin layers of a moderating material containing hydrogen in the molecular structure thereof and of a substantially non-moderating material

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Canada

International Nuclear Information System (INIS)

2009-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction (Licensing system; Offences, compliance and enforcement; Regulatory documents; Other relevant legislation); 2. Mining regime; 3. Nuclear substances and radiation devices; 4. Nuclear facilities; 5. Trade in nuclear materials and equipment (Exports, Other imports); 6. Radiation protection; 7. Radioactive waste management; 8. Non-proliferation and nuclear security; 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (Governor in council; Minister of natural resources; Other Ministerial authorities; Canadian Nuclear Safety Commission - CNSC); 2. Public and semi-public agencies (National Research Council - NRC; Natural Sciences and Engineering Research Council; Atomic Energy of Canada Ltd. - AECL)

Ascertaining directionality information from incident nuclear radiation

Energy Technology Data Exchange (ETDEWEB)

Archambault, Brian C. [Purdue University (United States); Lapinskas, Joseph R. [QSA Global, Inc. (United States); Wang Jing; Webster, Jeffrey A. [Purdue University (United States); McDeavitt, Sean [Texas A and M University (United States); Taleyarkhan, Rusi P., E-mail: rusi@purdue.edu [Purdue University (United States)

2011-10-15

Highlights: > Use of tensioned metastable fluids for detection of fast neutron radiation. > Monitored neutrons with 100% gamma photon blindness capability. > Monitored direction of incoming neutron radiation from special nuclear material emissions. > Ascertained directionality of neutron source to within 30 deg. and with 80% confidence with 2000 detection events at rate of 30-40 per second. > Conducted successful blind test for determining source of neutrons from a hidden neutron emitting source. > Compared results with MCNP5-COMSOL based multi-physics model. - Abstract: Unprecedented capabilities for the detection of nuclear particles via tailored resonant acoustic systems such as the acoustic tensioned metastable fluid detection (ATMFD) systems were assessed for determining directionality of incoming fast neutrons. This paper presents advancements that expand on these accomplishments, thereby increasing the accuracy and precision of ascertaining directionality information utilizing enhanced signal processing-cum-signal analysis, refined computational algorithms, and on demand enlargement of the detector sensitive volume. Advances in the development of ATMFD systems were accomplished utilizing a combination of experimentation and theoretical modeling. Modeling methodologies include Monte-Carlo based nuclear particle transport using MCNP5 and multi-physics based assessments accounting for acoustic, structural, and electromagnetic coupling of the ATMFD system via COMSOL's multi-physics simulation platform. Benchmarking and qualification studies have been conducted with a 1 Ci Pu-Be neutron-gamma source. These results show that the specific ATMFD system used for this study can enable detection of directionality of incoming fast neutrons from the neutron source to within 30{sup o} with 80% confidence; this required {approx}2000 detection events which could be collected within {approx}50 s at a detection rate of {approx}30-40 per second. Blind testing was

Ascertaining directionality information from incident nuclear radiation

International Nuclear Information System (INIS)

Archambault, Brian C.; Lapinskas, Joseph R.; Wang Jing; Webster, Jeffrey A.; McDeavitt, Sean; Taleyarkhan, Rusi P.

2011-01-01

Highlights: → Use of tensioned metastable fluids for detection of fast neutron radiation. → Monitored neutrons with 100% gamma photon blindness capability. → Monitored direction of incoming neutron radiation from special nuclear material emissions. → Ascertained directionality of neutron source to within 30 deg. and with 80% confidence with 2000 detection events at rate of 30-40 per second. → Conducted successful blind test for determining source of neutrons from a hidden neutron emitting source. → Compared results with MCNP5-COMSOL based multi-physics model. - Abstract: Unprecedented capabilities for the detection of nuclear particles via tailored resonant acoustic systems such as the acoustic tensioned metastable fluid detection (ATMFD) systems were assessed for determining directionality of incoming fast neutrons. This paper presents advancements that expand on these accomplishments, thereby increasing the accuracy and precision of ascertaining directionality information utilizing enhanced signal processing-cum-signal analysis, refined computational algorithms, and on demand enlargement of the detector sensitive volume. Advances in the development of ATMFD systems were accomplished utilizing a combination of experimentation and theoretical modeling. Modeling methodologies include Monte-Carlo based nuclear particle transport using MCNP5 and multi-physics based assessments accounting for acoustic, structural, and electromagnetic coupling of the ATMFD system via COMSOL's multi-physics simulation platform. Benchmarking and qualification studies have been conducted with a 1 Ci Pu-Be neutron-gamma source. These results show that the specific ATMFD system used for this study can enable detection of directionality of incoming fast neutrons from the neutron source to within 30 o with 80% confidence; this required ∼2000 detection events which could be collected within ∼50 s at a detection rate of ∼30-40 per second. Blind testing was successfully

The so-called 'Castor-Crisis': Transport of spent nuclear fuel elements and German 'Angst'. How to prevent the public relations catastrophe

International Nuclear Information System (INIS)

Suess, Werner

1999-01-01

Full text: 1. 'Castor-Crisis' - The Real Facts. - the background: radioactive contamination on the surface of transport containers for spent nuclear fuel elements; - legal aspects: transport limit values and notification obligations; - health aspects: radioactive contamination and ionising radiation; - the news media: divergence between technical facts and public perception. 2. 'Castor-Crisis' - The Reactions. 2.1 Technical measures: - 'action plan' of the Federal Ministry for Environment Protection and Reactor Safety; - IT-based European Information and Report System for the transport of nuclear combustibles => 'Transparent Transport Procedures'; - optimisation of decontamination procedures and transport organisation; - simplification of logistics, clearer responsibilities. 2.2 Communications measures: - defense strategy: 'we made a mistake...'; - information campaign: 'we owe you some answers...'; - regaining credibility: public testimonials of employees in newspaper ads, brochures etc.; - regaining credibility: neutral investigation of all relevant circumstances by KPMG. 3. 'Castor-Crisis' - The Lessons: - internal crisis management: improved co-ordination at company and branch level; - pro-active strategy: 'The benefits of nuclear energy' (avoidance Of CO 2 -emissions); - limits of communications; - communications efforts for nuclear energy - the European context. (author)

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Czech Republic

International Nuclear Information System (INIS)

2008-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear items and spent fuel (Ionising radiation sources; Nuclear items; Spent fuel); 4. Nuclear installations (Licensing and inspection, including nuclear safety; Emergency response; Decommissioning); 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Non-proliferation and physical protection; 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (State Office for Nuclear Safety - SUJB; Ministry of Industry and Trade; Ministry of the Interior; Ministry of the Environment); 2. Public and semi-public agencies (CEZ, a.s.; National Radiation Protection Institute - NRPI; Radioactive Waste Repository Authority - RAWRA; Diamo; Nuclear Physics Institute - NPI; National Institute for Nuclear, Chemical and Biological Protection; Nuclear Research Institute Rez, a.s. - NRI)

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - France

International Nuclear Information System (INIS)

2011-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General Regulatory Framework: 1. General (The French nuclear power programme and its main players; French nuclear law); 2. Mining Regime; 3. Radioactive Substances and Nuclear Equipment (Regulatory diversity; Radioactive sources; Medical activities); 4. Trade in Nuclear Materials and Equipment (Basic nuclear installations - INB; Tax on basic nuclear installations, Additional taxes, Funding nuclear costs; Installations classified for environmental protection purposes (ICPE) using radioactive substances; Nuclear pressure equipment - ESPN; Defence-related nuclear installations and activities - IANID; Emergency plans); 5. Trade in Nuclear Materials and Equipment (General provisions; Patents); 6. Radiation protection (Protection of the public; Protection of workers; Radiation protection inspectors; Labour inspectors; Protection of individuals in a radiological emergency); 7. Radioactive Waste Management (General regulations; Radioactive waste regulations; Discharge of effluents); 8. Non-proliferation and physical protection (Materials not used for the nuclear deterrent; Materials used for the nuclear deterrent); 9. Transport (Licensing and notification regime: Transport of radioactive materials, Transport of nuclear materials, Transport of radioactive substances between member states of the European Union; Methods of transport: Land transport, Sea transport, Air transport, Transport by post); 10

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Norway

International Nuclear Information System (INIS)

2001-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General Regulatory Regime: 1. Introduction; 2. Mining Regime; 3. Radioactive Substances, Nuclear Fuel and Equipment; 4. Nuclear Installations (Licensing and inspection, including nuclear safety; Emergency response); 5. Trade in Nuclear Materials and Equipment (Trade governed by nuclear energy legislation; Trade governed by radiation protection legislation; Trade governed by export/import control legislation); 6. Radiation Protection; 7. Radioactive Waste Management; 8. Non-Proliferation and Physical Protection; 9. Transport; 10. Nuclear Third Party Liability; II. Institutional Framework: 1. Regulatory and Supervisory Authorities: A. Ministerial Level (Ministry of Health and Social Affairs; Ministry of Trade and Industry; Ministry of Foreign Affairs; Other Ministries); B. Subsidiary Level: (The Norwegian Radiation Protection Authority - NRPA; The Norwegian Nuclear Emergency Organisation); 2. Public and Semi-Public Agencies - Institute for Energy Technology - IFE

A multigroup treatment of radiation transport

International Nuclear Information System (INIS)

Tahir, N.A.; Laing, E.W.; Nicholas, D.J.

1980-12-01

A multi-group radiation package is outlined which will accurately handle radiation transfer problems in laser-produced plasmas. Bremsstrahlung, recombination and line radiation are included as well as fast electron Bremsstrahlung radiation. The entire radiation field is divided into a large number of groups (typically 20), which diffuse radiation energy in real space as well as in energy space, the latter occurring via electron-radiation interaction. Using this model a radiation transport code will be developed to be incorporated into MEDUSA. This modified version of MEDUSA will be used to study radiative preheat effects in laser-compression experiments at the Central Laser Facility, Rutherford Laboratory. The model is also relevant to heavy ion fusion studies. (author)

Nuclear Power and Radiation in Public Acceptance

International Nuclear Information System (INIS)

Vastchenko, S. V.

2002-01-01

The special knowledge deficiency does not give the possibility to the majority of people to pattern their behaviour in a correct way on radiation problems and to estimate faithfully the possible damage rate to the health of a human being from the different radiation sources effects. Studying of the public opinion in Belarus has shown that one of the results of the Chernobyl NPP accident consequences is inseparability of nuclear and radiation danger in public consciousness. The anonymous questionnaire of the inhabitants living in various Belarus regions has been carried out aiming at definition of a general radiation erudition, as well as revealing the knowledge of the population about the effect of power stations (nuclear and thermal) on the environment and the human being health. Answers on questions connected with power have shown a very poor erudition of population about ecological advantages and drawbacks inherent in thermal and nuclear power plants. The majority of the respondents (about 80%) does not know about the absence of CO 2 discharge and oxygen preservation in the air. The questionnaire analysis shows that people are exclusively frightened with radiation from NPPs, but the rest sources of radiation effect do not cause so anxiety and apprehension. People in Belarus have learnt well that the reason of the majority of the diseases is radiation, so it can be frequently heard not only from mass media, but also at scientific conferences and seminars. Most of medical workers are sure that all diseases are caused by radiation. The deficiency of special knowledge on nuclear technologies in the people majority and availability of a great amount of contradictory and untrue information supplied by mass media result in overestimation of danger from energy objects and underestimation of the increased radiation dose from other sources consequences, for example, under roentgen medical examination and treatment. The investigations carried out will help to arrange

Radiation transport calculation methods in BNCT

International Nuclear Information System (INIS)

Koivunoro, H.; Seppaelae, T.; Savolainen, S.

2000-01-01

Boron neutron capture therapy (BNCT) is used as a radiotherapy for malignant brain tumours. Radiation dose distribution is necessary to determine individually for each patient. Radiation transport and dose distribution calculations in BNCT are more complicated than in conventional radiotherapy. Total dose in BNCT consists of several different dose components. The most important dose component for tumour control is therapeutic boron dose D B . The other dose components are gamma dose D g , incident fast neutron dose D f ast n and nitrogen dose D N . Total dose is a weighted sum of the dose components. Calculation of neutron and photon flux is a complex problem and requires numerical methods, i.e. deterministic or stochastic simulation methods. Deterministic methods are based on the numerical solution of Boltzmann transport equation. Such are discrete ordinates (SN) and spherical harmonics (PN) methods. The stochastic simulation method for calculation of radiation transport is known as Monte Carlo method. In the deterministic methods the spatial geometry is partitioned into mesh elements. In SN method angular integrals of the transport equation are replaced with weighted sums over a set of discrete angular directions. Flux is calculated iteratively for all these mesh elements and for each discrete direction. Discrete ordinates transport codes used in the dosimetric calculations are ANISN, DORT and TORT. In PN method a Legendre expansion for angular flux is used instead of discrete direction fluxes, land the angular dependency comes a property of vector function space itself. Thus, only spatial iterations are required for resulting equations. A novel radiation transport code based on PN method and tree-multigrid technique (TMG) has been developed at VTT (Technical Research Centre of Finland). Monte Carlo method solves the radiation transport by randomly selecting neutrons and photons from a prespecified boundary source and following the histories of selected particles

Transport and attenuation of radiations

CERN Document Server

Nimal, J C

2003-01-01

This article treats of the calculation methods used for the dimensioning of the protections against radiations. The method consists in determining for a given point the flux of particles coming from a source at a given time. A strong attenuation (of about some few mu Sv.h sup - sup 1) is in general expected between the source and the areas accessible to the personnel or the public. The calculation has to take into account a huge number of radiation-matter interactions and to solve the integral-differential transport equation which links the particles flux to the source. Several methods exist from the simplified physical model with numerical developments to the more or less precise resolution of the transport equation. These methods allows also the calculation of the uncertainties of equivalent dose rates, heat sources, structure damages using the data covariances (efficient cross-sections, modeling, etc..): 1 - transport equation; 2 - Monte-Carlo method; 3 - semi-numerical methods S sub N; 4 - methods based o...

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Australia

International Nuclear Information System (INIS)

2008-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I) - General Regulatory Regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances and equipment; 4. Nuclear installations (Licensing and inspection, including nuclear safety; Protection of the environment against radiation effects); 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Non-proliferation and physical protection (Bilateral safeguards agreements; International Atomic Energy Agency Safeguards Agreement; The South Pacific Nuclear Free Zone Treaty Act; The Comprehensive Nuclear Test-Ban Treaty Act; The Nuclear Non-Proliferation (Safeguards) Act); 9. Transport; 10. Nuclear third party liability; II) - Institutional Framework: 1. Regulatory and supervisory authorities (Minister for Health and Ageing; Minister for Foreign Affairs; Minister for the Environment, Heritage and the Arts; Minister for, Resources, Energy and Tourism); 2. Advisory bodies (Radiation Health and Safety Advisory Council; Advisory Committees); 3. Public and semi-public agencies (Australian Radiation Protection and Nuclear Safety Agency (ARPANSA); Australian Safeguards and Non-Proliferation Office; Australian Nuclear Science and Technology Organisation (ANSTO); Supervising Scientist)

RADIATION EFFECTS IN NUCLEAR WASTE MATERIALS

International Nuclear Information System (INIS)

Weber, William J.

2000-01-01

The objective of this research was to develop fundamental understanding and predictive models of radiation effects in glasses and ceramics at the atomic, microscopic, and macroscopic levels, as well as an understanding of the effects of these radiation-induced solid-state changes on dissolution kinetics (i.e., radionuclide release). The research performed during the duration of this project has addressed many of the scientific issues identified in the reports of two DOE panels [1,2], particularly those related to radiation effects on the structure of glasses and ceramics. The research approach taken by this project integrated experimental studies and computer simulations to develop comprehensive fundamental understanding and capabilities for predictive modeling of radiation effects and dissolution kinetics in both glasses and ceramics designed for the stabilization and immobilization of high-level tank waste (HLW), plutonium residues and scraps, surplus weapons plutonium, other actinides, and other highly radioactive waste streams. Such fundamental understanding is necessary in the development of predictive models because all experimental irradiation studies on nuclear waste materials are ''accelerated tests'' that add a great deal of uncertainty to predicted behavior because the damage rates are orders of magnitude higher than the actual damage rates expected in nuclear waste materials. Degradation and dissolution processes will change with damage rate and temperature. Only a fundamental understanding of the kinetics of all the physical and chemical processes induced or affected by radiation will lead to truly predictive models of long-term behavior and performance for nuclear waste materials. Predictive models of performance of nuclear waste materials must be scientifically based and address both radiation effects on structure (i.e., solid-state effects) and the effects of these solid-state structural changes on dissolution kinetics. The ultimate goal of this

Radiation Monitoring - A Key Element in a Nuclear Power Program

International Nuclear Information System (INIS)

Hussein, A.S.; El-dally, T.A.

2008-01-01

For a nuclear power plant, radiation is especially of great concern to the public and the environment. Therefore, a radiation monitoring program is becoming a critical importance. This program covers all phases of the nuclear plant including preoperational, normal operation, accident and decommissioning. The fundamental objective of radiation monitoring program is to ensure that the health and safety of public inside and around the plant and to confirm the radiation doses are below the dose limits for workers and the public. This paper summarizes the environmental radiation monitoring program for a nuclear power plant

Australian Radiation Protection and Nuclear Safety Act 1998. Act No 133

International Nuclear Information System (INIS)

1999-01-01

A set of legislation consisting of three Acts in the field of radiation protection and nuclear safety was passed by both Houses of Parliament on 10 December 1998 and was proclaimed on 5 February 1999. Act No. 133 - Australian Radiation Protection and Nuclear Safety Act, which is a framework Law, established the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) as the regulatory body for radiation protection and nuclear safety, in place of the Nuclear Safety Bureau. The Chief Executive Officer of ARPANSA, who is appointed by the Governor-General for a term of up to 5 years, is obliged to submit annual and quarterly reports to the Minister on the operations of the Chief Executive Officer, ARPANSA, the Council, the Radiation Health Committee and the Nuclear Safety Committee. The Council is a consultative body which examines issues relating to radiation protection and nuclear safety and advises the Chief Executive Officer on these issues as well as on the adoption of recommendations, policies and codes. The Radiation Health Committee and the Nuclear Safety Committee are to be established as advisory committees to the Chief Executive Officer or the Council. Both committees should draft national policies, codes and standards in their respective fields and review their effectiveness periodically. The second in this series of legislation, Act No. 134, Australian Radiation Protection and Nuclear Safety (License Charges) Act requires holders of both facility and source licenses to pay an annual charge, to be prescribed by the regulations. The third, Act No. 135 , Australian Radiation Protection and Nuclear Safety (Consequential Amendments) Act repeals those provisions of the 1987 Australian Nuclear Science and Technology Organisation Act which concern the Nuclear Safety Bureau, and the 1978 Environment Protection Act as a whole

Australian Radiation Protection and Nuclear Safety Act 1998. Act No 133

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-11-01

A set of legislation consisting of three Acts in the field of radiation protection and nuclear safety was passed by both Houses of Parliament on 10 December 1998 and was proclaimed on 5 February 1999. Act No. 133 - Australian Radiation Protection and Nuclear Safety Act, which is a framework Law, established the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) as the regulatory body for radiation protection and nuclear safety, in place of the Nuclear Safety Bureau. The Chief Executive Officer of ARPANSA, who is appointed by the Governor-General for a term of up to 5 years, is obliged to submit annual and quarterly reports to the Minister on the operations of the Chief Executive Officer, ARPANSA, the Council, the Radiation Health Committee and the Nuclear Safety Committee. The Council is a consultative body which examines issues relating to radiation protection and nuclear safety and advises the Chief Executive Officer on these issues as well as on the adoption of recommendations, policies and codes. The Radiation Health Committee and the Nuclear Safety Committee are to be established as advisory committees to the Chief Executive Officer or the Council. Both committees should draft national policies, codes and standards in their respective fields and review their effectiveness periodically. The second in this series of legislation, Act No. 134, Australian Radiation Protection and Nuclear Safety (License Charges) Act requires holders of both facility and source licenses to pay an annual charge, to be prescribed by the regulations. The third, Act No. 135 , Australian Radiation Protection and Nuclear Safety (Consequential Amendments) Act repeals those provisions of the 1987 Australian Nuclear Science and Technology Organisation Act which concern the Nuclear Safety Bureau, and the 1978 Environment Protection Act as a whole

Radiation Protection Programme in Nuclear Medicine Practice

International Nuclear Information System (INIS)

Alarfaj, Abd-I.M.

2003-01-01

This paper specifies the main elements of the radiation protection programma (RPP) that should be estabished for each practice, which involves radiation exposure. Practices of nuclear medicine have been considered as an example, since among the 245 installations which are conducting different practices with radiation sources in the Kingdom of Saudi Arabia, there are 78 installations dealing with nuclear medicine practices. Reviewing the RPP in these nuclear medicine installations, it may be easily concluded that the RPPs for the majority of these installations do not respond to the requirements of the regulatory body of the Kingdom, which is King Abdulaziz City for Science and Technology (KACST). This may be attributed to a set of different reasons, such as shortage in understanding the main elements of the RPP as well as in applying methodologies

INSAG's ongoing work on nuclear, radiation and waste safety

International Nuclear Information System (INIS)

Baer, A.J.

1999-01-01

The International Nuclear Safety Advisory Group (INSAG) is an advisory group to the Director General of the IAEA. It identifies current nuclear safety issues, draws conclusions from its analyses and gives advice on those issues. INSAG is currently working on four documents: a complete revision of INSAG-3, the classical paper on safety principles for nuclear plants, published in 1988; 'Safety Management', the effective system for the management of operational strategy; 'Safe Management of the Life Cycle of Nuclear Power Plants'; and the fourth document in preparation entitled 'The Safe Management of Sources of Radiation: Principles and Strategies'. The fourth document is aimed primarily at political decision makers who have no knowledge of radiation safety or of nuclear matters generally but are called upon to make important decisions in this field. INSAG has attempted to present them with a 'unified doctrine' of the management of all radiation sources, even though, for historical reasons radiation protection and nuclear safety have evolved largely independently of each other. The major conclusion to be drawn from the paper is that a systematic application of protection and safety principles, and of appropriate strategies, goes a long way towards ensuring the safe management of technologies involving radiation. Furthermore, the management of sources of radiation could benefit from the experience accumulated in other industries facing comparable challenges

Nuclear law. January 2011 - July 2012

International Nuclear Information System (INIS)

Bringuier, Pierre; Di Costanzo, Laura

2012-01-01

This paper gives a synthesis of legal aspects concerning nuclear power in France. The following main points are reviewed: institutional aspects (notably the independence of the Nuclear Safety Authority - ASN); transparency and public information; nuclear safety and radiation protection; nuclear materials, their control and security aspects; transports; trade and non-proliferation agreements; radioactive wastes; radiation accidents; liabilities and insurance; nuclear arms

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Germany

International Nuclear Information System (INIS)

2011-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment (Definitions; Licensing requirements); 4. Nuclear installations (Licensing regime; Protection of the environment against radiation effects; Emergency response; Surveillance of installations and activities); 5. Trade in nuclear materials and equipment; 6. Radiation protection (General; Principal elements of the Radiation Protection Ordinance; Additional radiation protection norms); 7. Radioactive waste management (Atomic Energy Act 2002; Radiation Protection Ordinance; International obligations); 8. Non-proliferation and physical protection (Non-proliferation regime; Physical protection regime); 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities: Federal authorities (Federal Minister for the Environment, Nature Conservation and Nuclear Safety, Federal Minister for Education and Research, Federal Minister of Finance, Federal Minister of Transport, Building and Urban Affairs, Federal Minister for Economy and Technology, Federal Minister of Defence, Federal Office for Radiation Protection - BfS, Federal Office of Economics and Export Control); Authorities of the Laender; 2. Advisory bodies (Reactor Safety Commission - RSK; Radiation Protection Commission - SSK; Disposal Commission - ESK; Nuclear Technology

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Finland

International Nuclear Information System (INIS)

2008-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment; 4. Nuclear installations; (Licensing and inspection, including nuclear safety; Emergency response); 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Nuclear security; 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (Ministry of Trade and Industry - KTM; Ministry of Social Affairs and Health; Ministry of the Interior; Ministry of the Environment; Ministry of Foreign Affairs); 2. Advisory bodies (Advisory Committee on Nuclear Energy; Advisory Committee on Nuclear Safety); 3. Public and semi-public agencies (Finnish Radiation and Nuclear Safety Authority - STUK; State Nuclear Waste Management Fund)

Building competence in radiation and nuclear safety through education and training - the approach of a national regulatory authority

International Nuclear Information System (INIS)

Karfopoulos, K.L.; Carinou, E.; Kamenopoulou, V.; Dimitriou, P.; Housiadas, Ch.

2015-01-01

The Greek Atomic Energy Commission (EEAE) is the national competent authority for radiation and nuclear safety and security as well as for the radiation protection of ionizing and artificially produced non-ionizing radiation. The legal framework determines, inter alia, the responsibilities in education and training issues. The EEAE has a range of activities, in providing postgraduate and continuous education and training on radiation protection, and nuclear safety and security, at the national and international levels. At the national level, and particularly in the medical field, the EEAE is a participant in and a major contributor to the Inter-University Postgraduate Program on Medical Radiation Physics. Since 2003, the EEAE has been the Regional Training Center (RTC) for radiation, transport and waste safety of the International Atomic Energy Agency (IAEA) for the European Region in the English language. Moreover, the EEAE has also been recognized as the IAEA's Regional Training Center (RTC) in nuclear security in the English language since 2013. The EEAE recently proceeded to two significant initiatives: the design of a national program for education and training, and the certification of the Department of Education according to ISO 29990:2010. In this paper, the initiatives taken to enhance the radiation protection system in the country through education and training are presented. (authors)

TIERCE: A code system for particles and radiation transport in thick targets

Energy Technology Data Exchange (ETDEWEB)

Bersillon, O.; Bauge, E.; Borne, F.; Clergeau, J.F.; Collin, M.; Cotten, D.; Delaroche, J.P.; Duarte, H.; Flament, J.L.; Girod, M.; Gosselin, G.; Granier, T.; Hilaire, S.; Morel, P.; Perrier, R.; Romain, P.; Roux, L. [CEA, Bruyeres-le-Chatel (France). Service de Physique Nucleaire

1997-09-01

Over the last few years, a great effort at Bruyeres-le-Chatel has been the development of the TIERCE code system for the transport of particles and radiations in complex geometry. The comparison of calculated results with experimental data, either microscopic (double differential spectra, residual nuclide yield...) or macroscopic (energy deposition, neutron leakage...), shows the need to improve the nuclear reaction models used. We present some new developments concerning data required for the evaporation model in the framework of a microscopic approach. 22 refs., 6 figs.

Experience with the loading and transport of fuel assembly transport casks, including CASTOR casks, and the radiation exposure of personnel

International Nuclear Information System (INIS)

Bentele, W.; Kinzelmann, T.

1999-01-01

In 1997 and 1998, six spent fuel assembly transports started from the nuclear power plant Gemeinschaftskernkraftwerk Neckar (GKN), using CASTOR-V19 casks. Professor Kuni of Marburg University challenged the statement made by the German Federal Office for Radiation Protection (Bundesamt fuer Strahlenschutz (BfS)) based on accepted scientific knowledge, according to which so-called CASTOR transports present no risk, either to the population or to the escorting police units. This paper shows that the collective dose during the loading of the CASTOR casks amounted to 4.5 mSv (gamma and neutrons) per cask at the most, and that the maximum individual dose amounted to 0.26 mSv. In addition to these doses, the collective dose during handling and transport must be considered: this amounted to 0.35 mSv (gamma and neutrons). The dose to the police escort was -2 (limit for surface contamination), presented degrees of contamination >4 Bq cm -2 upon reaching the Valognes/Cogema terminal. However, transport casks coming from French plants also revealed degrees of contamination >4 Bq cm -2 , as well as 'hot spots'. No such contamination was found on NTL 11 casks transported from the GKN to Sellafield. Neither was any increased contamination found upon the arrival of CASTOR-V19 casks transported from GKN to Gorleben or Ahaus. The partially sensationalist media reports were inversely proportional to the actual radiological relevance of the matter. The German Commission on Radiation Protection (SSK) confirmed that the radiological effect of such contaminated spent fuel transports is negligible. (author)

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.

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Ireland

International Nuclear Information System (INIS)

2009-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment; 4. Nuclear installations; 5. Trade in nuclear materials and equipment; 6. Radiation protection (Radiation protection standards; Emergency response); 7. Radioactive waste management; 8. Non-proliferation and physical protection; 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (Minister for the Environment, Heritage and Local Government; Minister for Agriculture and Food; Minister for Communications, Marine and Natural Resources; Minister for Finance; Minister for Health and Children; Minister for Defence); 2. Public and semi-public agencies (Radiological Protection Institute of Ireland; Food Safety Authority of Ireland)

Radiation effects, nuclear energy and comparative risks

International Nuclear Information System (INIS)

Gopinath, D.V.

2007-01-01

Nuclear energy had a promising start as an unlimited, inexpensive and environmentally benign source of energy for electricity generation. However, over the decades its growth was severely retarded due to concerns about its possible detrimental effects on the well-being of mankind and the environment. Since such concerns are essentially due to the gigantic magnitude of radioactivity and ionizing radiations associated with nuclear energy, this article starts with a comprehensive account of effects of the ionizing radiation on living systems. Quantitative description of types of radiation exposure and their varied effects is given. The origin, type and magnitude of mutagenic effects of radiation are described. The concept of radiation risk factors, basis for their evaluation and their currently accepted values are presented. With this background, origin and magnitude of radioactivity and associated ionizing radiations in nuclear reactors are presented and the elaborate measures to contain them are described. It is recognized that notwithstanding all the measures taken in the nuclear industry, certain amount of radiation exposure, however small, is inevitable and the values, based on the experience world over, are presented. Estimated health risk due to such exposures is evaluated. For a comparative analysis, risks in other options of electricity generation such as hydel and fossil-fuelled plants are described. It is seen that on an overall basis, the nuclear option is no more risky than the other commonly employed options, and is in fact, significantly less. Lastly, since every option of electricity generation entails some risk, the case of 'no addition of electricity, and its impact on the society are considered. Based on the analysis of extensive data provided by UNDP on the human development parameters for different countries in the world, it is shown that at least for developing countries, any option of addition of electricity would be far more desirable than the

Ukraine International cooperation in nuclear and radiation safety: public-administrative aspect

Directory of Open Access Journals (Sweden)

I. P. Krynychnay

2017-03-01

Full Text Available The article examines international cooperation of Ukraine with other States in the sphere of ensuring nuclear and radiation safety and highlights the main directions of development and improvement of nuclear and radiation safety in Ukraine based on international experience, with the aim of preventing the risks of accidents and contamination areas radiological substances. Illuminated that for more than half a century of experience in the use of nuclear energy by the international community under the auspices of the UN, IAEA and other international organizations initiated and monitored the implementation of key national and international programs on nuclear and radiation safety. Of the Convention in the field of nuclear safety and the related independent peer review, effective national regulatory infrastructures, current nuclear safety standards and policy documents, as well as mechanisms of evaluation in the framework of the IAEA constitute important prerequisites for the creation of a world community, the global regime of nuclear and radiation safety. For analysis of the state of international cooperation of Ukraine with other States in the sphere of nuclear and radiation safety, highlighted the legal substance of nuclear and radiation safety of Ukraine, which is enshrined in the domestic Law of Ukraine «On nuclear energy use and radiation safety». Considered the most relevant legal relations. It is established that, despite the current complex international instruments, existing domestic legislation on nuclear and radiation safety, partly there is a threat of emergency nuclear radiation nature, in connection with the failure of fixed rules and programs, lack of funding from the state is not always on time and in full allows you to perform fixed strategy for overcoming the consequences of radiation accidents, the prevention of the threat of environmental pollution. Found that to improve and further ensuring nuclear and radiation safety of

Code of practice for radiation protection in nuclear medicine

International Nuclear Information System (INIS)

Hamed, M. I.

2010-05-01

In aim of this study was to develop a draft for a new code practice for radiation protection in nuclear medicine that meets the current relevant international recommendation. The draft includes the following main fields: methods of radiation protection for workers, patients and public. Also, the principles of safe design of nuclear medicine departments, quality assurance program, proper manipulation of radiation sources including radioactive waste and emergency preparedness and response. The practical part of this study includes inspections of three nuclear medicine departments available in Sudan so as to assess the degree of compliance of those departments with what is stated in this code. The inspection missions have been conducted using a checklist that addresses all items that may affect radiation raincoat issues in addition to per formin area radiation monitoring around the installation of the radioactive sources. The results of this revealed that most of the departments do not have effective radiation protection program which in turn could lead to unnecessary exposure to patients, public and workers. Finally, some recommendations are given that - if implemented - could improve the status of radiation protection in nuclear medicine department. (Author)

Transportation risks in the US nuclear fuel cycle

International Nuclear Information System (INIS)

Rhoads, R.E.; Andrews, W.B.

1980-01-01

Estimated risks associated with accidental releases of materials transported for each step of the nuclear fuel cycle are presented. The risk estimates include both immediate and latent fatilities caused by releases of these materials in transportation accidents. Studies of the risk of transporting yellowcake, fresh nuclear and low level wastes from the front end of the fuel cycle have not been completed. Existing information does permit estimates of the risks to be made. The estimates presented result from the very low hazards associated with release of these materials. These estimates are consistent with the results of other studies. The results show that risks from all the fuel cycle transportation steps are low. The results also indicate that the total transportation risks associated with the nuclear fuel cycle are distributed about evenly between the fuel supply end and waste management end of the cycle. Risks in the front end of the cycle result primarily from the chemical toxicity of the materials transported. The results of the risk analysis studies for transportation of nuclear fuel cycle materials are compared with the results for the three studies that have been completed for non-nuclear systems. The risk analysis methodology used in these studies identifies the complete spectrum of potential accident consequences and estimates the probability of events producing that level of consequence. The maximum number of fatalities predicted for each material is presented. A variety of risk measures have been used because of the inherent difficulties in making risk comparisons. Examination of a number of risk measures can provide additional insights and help guard against conclusions that are dependent on the way the risk information has been developed and displayed. The results indicate that the risks from transporting these materials are all relatively low in comparison to other risks in society

Origin, characteristics and detection of nuclear radiation

International Nuclear Information System (INIS)

Goettel, K.

1975-06-01

The report is an introduction into the physical principles of radiation protection. After a brief summary of the most significant experimental results and data on the atomic structure of the matter and after explaining the principles of atomic and nuclear structure, radioactive decay and its laws are dealt with. This is followed by a representation of the characteristics of nuclear radiation, its interaction with the matter as well as the biological effects. After a description of the measurement units for radioactivity and doses the most inportant methods for radiation detection and the principles of how detectors function are explained. (ORU/LN) [de

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

International Nuclear Information System (INIS)

Kawasaki, Masashi; Kageyama, Tomio; Suzuki, Toru

2004-01-01

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

Overview and applications of the Monte Carlo radiation transport kit at LLNL

International Nuclear Information System (INIS)

Sale, K. E.

1999-01-01

Modern Monte Carlo radiation transport codes can be applied to model most applications of radiation, from optical to TeV photons, from thermal neutrons to heavy ions. Simulations can include any desired level of detail in three-dimensional geometries using the right level of detail in the reaction physics. The technology areas to which we have applied these codes include medical applications, defense, safety and security programs, nuclear safeguards and industrial and research system design and control. The main reason such applications are interesting is that by using these tools substantial savings of time and effort (i.e. money) can be realized. In addition it is possible to separate out and investigate computationally effects which can not be isolated and studied in experiments. In model calculations, just as in real life, one must take care in order to get the correct answer to the right question. Advancing computing technology allows extensions of Monte Carlo applications in two directions. First, as computers become more powerful more problems can be accurately modeled. Second, as computing power becomes cheaper Monte Carlo methods become accessible more widely. An overview of the set of Monte Carlo radiation transport tools in use a LLNL will be presented along with a few examples of applications and future directions

Response of high Tc superconducting Josephson junction to nuclear radiation

International Nuclear Information System (INIS)

Ding Honglin; Zhang Wanchang; Zhang Xiufeng

1992-10-01

The development of nuclear radiation detectors and research on high T c superconducting nuclear radiation detectors are introduced. The emphases are the principle of using thin-film and thick-film Josephson junctions (bridge junction) based on high T c YBCO superconductors to detect nuclear radiation, the fabrication of thin film and thick-film Josephson junction, and response of junction to low energy gamma-rays of 59.5 keV emitted from 241 Am and beta-rays of 546 keV. The results show that a detector for measuring nuclear radiation spectrum made of high T c superconducting thin-film or thick-film, especially, thick-film Josephson junction, certainly can be developed

Nuclear science in the 20th century. Radiation chemistry and radiation processing

International Nuclear Information System (INIS)

Fu Tao; Xu Furong; Zheng Chunkai

2003-01-01

The application of nuclear science and technology to chemistry has led to two important subjects, radiation chemistry and radiation processing, which are playing important roles in many aspects of science and society. We review the development and major applications of radiation chemistry and radiation processing, including the basic physical and chemical mechanisms involved

Code of practice of radiation protection in fixed nuclear gauges

International Nuclear Information System (INIS)

Eltayeb, M. A. M.

2012-09-01

The present work aims at developing and updating a code of practice of radiation protection in fixed nuclear gauges that comply with current international recommendations. The work also intended to evaluate the current radiation protection situation in two selected companies using nuclear gauges in Sudan. A draft of the code is proposed which includes the basic principle of protection such as source construction and gauges radiation monitoring, storage maintenance and leak testing as well as specific issues related to nuclear gauges. The practical part of this study included investigation of radiation protection in the comparisons using nuclear gauges for level detection, to evaluate the level of radiation protection and the compliance to the regulatory authority regulations. The result revealed that the two companies do not have an effective radiation protection program and that can lead to exposure of workers to unnecessary doses. Some recommendations were stated, if implemented they could improve the status of radiation protection in those companies. (Author)

Nuclear facts

International Nuclear Information System (INIS)

1982-01-01

The subject is discussed as follows: the case for using nuclear energy (Britain's energy needs; energy policy); safety; transport of spent fuel; radiation (natural radioactivity); environment (land use of nuclear power plants; storage and disposal of radioactive wastes). (U.K.)

Essay about nuclear right

International Nuclear Information System (INIS)

Puig, D.

1994-01-01

The present essay treat about all Uruguaian Nuclear Energy legislation. Nuclear energy history, international treaties, agreements, national programs, nuclear government politics, radiation protection regulations, wastes, radioactive materials transport, environment and safeguards has been given in this compilation

The new law on radiation and nuclear power

International Nuclear Information System (INIS)

Niittylae, A.

1990-01-01

The Law on Nuclear Energy, which entered into force in 1988, controls the use of nuclear power. The new Law on Radiation is under consideration in the Parliament. The internationally approved main principles on radiation protection are the basis of the law. In the article, these principles and the contents of the law are described

On the derivation of vector radiative transfer equation for polarized radiative transport in graded index media

International Nuclear Information System (INIS)

Zhao, J.M.; Tan, J.Y.; Liu, L.H.

2012-01-01

Light transport in graded index media follows a curved trajectory determined by Fermat's principle. Besides the effect of variation of the refractive index on the transport of radiative intensity, the curved ray trajectory will induce geometrical effects on the transport of polarization ellipse. This paper presents a complete derivation of vector radiative transfer equation for polarized radiation transport in absorption, emission and scattering graded index media. The derivation is based on the analysis of the conserved quantities for polarized light transport along curved trajectory and a novel approach. The obtained transfer equation can be considered as a generalization of the classic vector radiative transfer equation that is only valid for uniform refractive index media. Several variant forms of the transport equation are also presented, which include the form for Stokes parameters defined with a fixed reference and the Eulerian forms in the ray coordinate and in several common orthogonal coordinate systems.

Environmental radiation monitoring around the nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Lee, Chang Woo; Choi, Geun Sik and others

2001-02-01

Environmental Radiation Monitoring was carried out with measurement of environment. Radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry.

Environmental radiation monitoring around the nuclear facilities

International Nuclear Information System (INIS)

Lee, Chang Woo; Choi, Young Ho

2000-02-01

Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows: The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost some level compared with the past years. Gross α, β radioactivity in environmental samples showed a environmental level. γ-radionuclides in water sample were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by γ-spectrometry. (author)

Environmental radiation monitoring around the nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Lee, Chang Woo; Choi, Young Ho

2000-02-01

Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows: The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost some level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water sample were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author)

Environmental radiation monitoring around the nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Lee, Chang Woo; Choi, Young Ho; Lee, M.H. [and others

1999-02-01

Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul research reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul research reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul research reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author). 3 refs., 50 tabs., 12 figs.

Environmental radiation monitoring around the nuclear facilities

International Nuclear Information System (INIS)

Lee, Chang Woo; Choi, Geun Sik and others

2001-02-01

Environmental Radiation Monitoring was carried out with measurement of environment. Radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross α, β radioactivity in environmental samples showed a environmental level. γ-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by γ-spectrometry

Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety, Regional Meeting on International Radiation Protection Association (IRPA)and 3. Peruvian Meeting on Radiological Protection

International Nuclear Information System (INIS)

1995-10-01

There we show works of the Third Regional Meeting on Radiological and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin americans specialists talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation. More than 225 works were presented on the meeting

Revised estimates of the radiological impact of the transport of irradiated nuclear fuels within the UK

International Nuclear Information System (INIS)

Macdonald, H.F.

1987-10-01

This report presents revised estimates of individual and collective doses associated with irradiated fuel movements from CEGB and SSEB nuclear power stations within the UK. In particular, earlier estimates of transport doses have been updated to take account of recent changes in the patterns of rail traffic. This results in a reduction in the estimated maximum individual doses to members of the public living near marshalling yards where flasks stop en route and also to rail workers incidentally exposed at these locations. The maximum levels of individual dose associated with irradiated fuel transport within the UK are in general low compared with those due to natural background radiation. Further, the associated collective doses are small compared with other sources of dose arising in the nuclear fuel cycle and represent -4 % of the natural background radiation dose to the UK population. In absolute terms the maximum contributions to the annual transport collective doses from Magnox, AGR and projected PWR fuel movements are estimated to be 18, 9 and 0.7 man mSv · a -1 respectively. These results neglect any reduction in doses due to the effects of shielding by buildings or natural obstacles such as railway cuttings or tunnels. Inclusion of these effects has been estimated to reduce the annual transport collective doses to 13, 6 and 0.45 man mSv · a -1 for Magnox, AGR and PWR fuels respectively. (U.K.)

Basis for radiation protection of the nuclear worker

International Nuclear Information System (INIS)

Guevara, F.A.

1982-01-01

A description is given of the standards for protection of persons who work in areas that have a potential for radiation exposure. A review is given of the units of radiation exposure and dose equivalent and of the value of the maximum permissible dose limits for occupational exposure. Federal Regulations and Regulatory Guides for radiation protection are discussed. Average occupational equivalent doses experienced in several operations typical of the United States Nuclear Industry are presented and shown to be significantly lower than the maximum permissible. The concept of maintaining radiation doses to As-Low-As-Reasonably-Achievable is discussed and the practice of imposing engineering and administrative controls to provide effective radiation protection for the nuclear worker is described

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

District file of major risks for the Moselle district: B6 - The nuclear risk; B7 - The risk related to radioactive material transport

International Nuclear Information System (INIS)

2013-10-01

A first document addresses the nuclear risk with some generalities (definition, occurrence, consequences for people and for the environment with an indication of exposure thresholds, presentation of individual safety directives), a discussion of the nuclear risk level in the district (history, contamination threats, preventive actions for the Cattenom nuclear plant, existence of a triple barrier for radioactive product containment, other factors aimed at nuclear safety, urban development control, control of nuclear activities, information, rescue organisation, map of concerned communes). The second document addresses the risk related to radioactive material transport with some generalities (definition, occurrence, consequences for persons and goods, individual safety directive in case of road or railway accident), a more detailed analysis of the risk in the district (situation of the radioactive material transport in the district, risk history, human and environmental stakes, preventive actions, radiation protection safety challenges, safety factors, control of transports, rescue organisation)

ipole: Semianalytic scheme for relativistic polarized radiative transport

Science.gov (United States)

Moscibrodzka, Monika; Gammie, Charles F.

2018-04-01

ipole is a ray-tracing code for covariant, polarized radiative transport particularly useful for modeling Event Horizon Telescope sources, though may also be used for other relativistic transport problems. The code extends the ibothros scheme for covariant, unpolarized transport using two representations of the polarized radiation field: in the coordinate frame, it parallel transports the coherency tensor, and in the frame of the plasma, it evolves the Stokes parameters under emission, absorption, and Faraday conversion. The transport step is as spacetime- and coordinate- independent as possible; the emission, absorption, and Faraday conversion step is implemented using an analytic solution to the polarized transport equation with constant coefficients. As a result, ipole is stable, efficient, and produces a physically reasonable solution even for a step with high optical depth and Faraday depth.

Radiation levels in nuclear diagnostic examinations

International Nuclear Information System (INIS)

Vermeulen, A.M.T.I.

1987-01-01

To estimate the risks for a pregnant radiological worker, radiation level measurements are executed for common nuclear diagnostic techniques. These measurements are combined with the time which the radiologic worker is present during the performance of the diagnostic techniques. It is concluded that a radiologic worker is receiving less than 5 mSv during pregnancy. This is the case with in vivo determination in a department of nuclear medicine with common diagnostic techniques. Reduction of radiation doses during pregnancy is possible by reduction of heart function examinations, skeletal examinations and brain scans. 1 figure; 13 tabs

Transportation of nuclear fuel

International Nuclear Information System (INIS)

Prowse, D.R.

1979-01-01

Shipment of used fuel from nuclear reactors to a central fuel management facility is discussed with particular emphasis on the assessment of the risk to the public due to these shipments. The methods of transporting used fuel in large shipping containers is reviewed. In terms of an accident scenario, it is demonstrated that the primary risk of transport of used fuel is due to injury and death in common road accidents. The radiological nature of the used fuel cargo is, for all practical purposes, an insignificant factor in the total risk to the public. (author)

Transport of nuclear materials

International Nuclear Information System (INIS)

Anon.

2002-01-01

During november and december 2001, 2 events concerning nuclear transport were reported and classified on the first grade (grade 1) of the INES scale. The first event concerns a hole in a transport cask of contaminated tools. The hole seems to have been made by the fork of a handling equipment. The second event concerns the loss of a parcel containing a technetium generator, this generator represented an activity of about 141 G Becquerel of 99 Mo the day it left the premises of CIS-bio in Saclay. (A.C.)

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Denmark

International Nuclear Information System (INIS)

2015-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General Regulatory Regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment; 4. Nuclear installations (Licensing and inspection, including nuclear safety; Emergency response); 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Nuclear security; 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (Minister of Health; Minister for the Environment/Minister of Transport and Energy; Minister of Justice; Minister of Defence; National Board of Health; Emergency Management Agency); 2. Advisory bodies (The Danish Ministry of Energy, Supply and Climate and the Danish Energy Agency); 3. Public and semi-public agencies (Risoe National Laboratory)

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Italy

International Nuclear Information System (INIS)

2010-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment; 4. Nuclear installations (Licensing and inspection, including nuclear safety; Protection of the environment against radiation effects; Emergency response); 5. Trade in nuclear materials and equipment (General provisions; Patents); 6. Radiation Protection (Protection of workers; Protection of the public; Protection of the environment); 7. Radioactive Waste Management; 8. Non-proliferation and physical protection; 9. Transport; 10. Nuclear Third Party Liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (Interdepartmental Committee for Economic Planning; Nuclear Safety Agency; Prime Minister; Minister for Economic Development; Minister for Labour and Social Security; Minister for Health; Minister for the Environment; Minister for the Interior; Minister for Transport and Navigation; Minister for Foreign Trade (now incorporated in Ministry for Economic Development); Minister for Education; Treasury Minister; Minister for Universities and for Scientific and Technical Research; Minister for Foreign Affairs; State Advocate General); 2. Advisory bodies (Inter-ministerial Council for Consultation and Co-ordination; Coordinating Committee for Radiation Protection of Workers and the Public; Regional and Provincial Commissions for Public Health Protection

The maritime transport of nuclear substances

International Nuclear Information System (INIS)

Los Santos, A. de; Corretjer, L.

1976-01-01

In view of the fact that the regulation of maritime transport of nuclear materials comes under both maritime and nuclear law has raised problems which it was attempted to solve by specific standards. As regards the prevention of nuclear hazards, these standards are based on the recommendations of competent international organizations, while concerning compensation of nuclear damage, a Convention which has just come into force lays down that nuclear law has priority over maritime law. Despite the progress made, a study of the situation in this field shows that it can be further improved. (N.E.A.) [fr

Experience of air transport of nuclear fuel material in Japan

International Nuclear Information System (INIS)

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

2004-01-01

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

Interface between radiation protection and nuclear safety

International Nuclear Information System (INIS)

Bengtsson, G.; Hoegberg, L.

1991-01-01

Interface issues concern the character and management of overlaps between radiation protection and nuclear safety in nuclear power plants. Typical examples include the selection of inspection and maintenance volumes in order to balance occupational radiation doses versus the safety status of the plant, and the intentional release to the environment in the course of an accident in order to secure better plant control. The paper discusses whether it is desirable and possible to employ a consistent management of interface issues with trade-offs between nuclear safety and radiation protection. Illustrative examples are quoted from a major Nordic research programme on risk analysis and safety rationale. These concern for instance in-service inspections, modifications of plant systems and constructions after the plant has been taken into operation, and studies on the limitations of probabilistic safety assessment. They indicate that in general there are no simple rules for such trade-offs

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

Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Fessenheim nuclear power plant (INB 75, Haut-Rhin, 68 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Nuclear safety and radiation protection report of the Penly nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Penly nuclear power plant (INB 136 and 140, Seine-Maritime, 76 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Fessenheim nuclear power plant (INB 75, Haut-Rhin, 68 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Blayais nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Blayais nuclear power plant (INB 86 and 110, Gironde (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Nuclear safety and radiation protection report of the Penly nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Penly nuclear power plant (INB 136 and 140, Seine-Maritime, 76 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Civaux nuclear power plant (INB 158 and 159, Vienne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Blayais nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Blayais nuclear power plant (INB 86 and 110, Gironde (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Civaux nuclear power plant (INB 158 and 159, Vienne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Environmental radiation monitoring around the nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Lee, Chang Woo

2012-03-15

Environmental Radiation Monitoring was carried out with measurement of environment. radiation and environmental radioactivity analysis on the sites of KAERI nuclear facilities and Seoul Research Reactors and their environments. The average level of environmental radiation dose measured by an ERM and the accumulated radiation dose by a TLD were almost same level compared with the previous years. The activity of gross {alpha} and gross {beta}, Tritium, Uranium and Strontium in environmental samples showed a environmental level. The {gamma}-radionuclides such as natural radionuclides 40K or 7Be were detected in pine needle and food. The nuclear radionuclides 134Cs, 137Cs or 131I were temporarily detected in the samples of air particulate and rain in April and of fall out in 2nd quarter from the effect of Fukusima accident.

Radiation protection problems by diagnostic procedures of pediatric nuclear medicine

International Nuclear Information System (INIS)

Kletter, K.

1994-01-01

Special dosimetry considerations are necessary in the application of radiopharmaceuticals in pediatric nuclear medicine. The influence of differences in irradiation geometry and biokinetic parameters on the radiation dose in children and adults is discussed. Assuming an equal activity concentration, both factors lead rather to a reduced radiation dose than an increased radiation burden in children compared to adults. However, the same radiation dose in children and adults may lead to a different detriment. This is explained by differences in life expectancy and radiation sensitivity for both groups. From special formulas an age dependent reduction factor can be calculated for the application of radiopharmaceuticals in pediatric nuclear medicine. Radiation exposure to hospital staff and parents from children, undergoing nuclear medicine diagnostic or therapeutic procedures, is low. (author)

Method of processing dismantled products of radiation-contaminated equipments and transportation container therefor

International Nuclear Information System (INIS)

Komura, Shiro; Heki, Hideaki.

1991-01-01

In a method of decontaminating dismantled products of radiation-contaminated equipments removed at nuclear power facilities and classifying the dismantled products depending on their remaining radioactivity levels measured at a processing facility, the dismantled products are contained in a transportation container, to which decontamination liquids are injected and they are transferred to the processing facility. The decontaminated liquid wastes are drained from the transportation container, the dismantled products are washed while being contained in the transportation container as they are. Then, they are transferred to a step for measuring their remaining radioactivity level. This can shorten the time from the containment of the dismantled products to the transportation container to the completion of the decontamination, to improve the efficiency for the decontamination processing. Further, by separately containing the dismantled products on every kind of materials to respective containers, the processing time can be appropriately controlled respectively even if the dissolving efficiency to the decontamination liquids is different depending on the materials. (T.M.)

Occupational radiation exposure in nuclear fuel cycle facilities

International Nuclear Information System (INIS)

1979-01-01

Full text: This symposium forms an essential part of the continuing tradition of subjecting nuclear energy to periodic review to assess the adequacy of radiation protection practices and experiences and to identify those areas needing further study and development. Specifically, the symposium focused on a review of statistical data on radiation exposure experience to workers in the nuclear fuel cycle through 1978. The technical sessions were concerned with occupational exposures: experienced in Member States; in research and development facilities; in nuclear power plants; in nuclear Fuel reprocessing facilities; in waste management facilities; and techniques to minimize doses. A critical review was made of internal and external exposures to the following occupational groups: uranium miners; mill workers; fuel fabricators; research personnel, reactor workers; maintenance staff; hot cell workers; reprocessing plant personnel; waste management personnel. In particular, attention was devoted to the work activities causing the highest radiation exposures and successful techniques which have been used to minimize individual and collective doses. Also there was an exchange of information on the trends of occupational exposure over the lifespan of individual nuclear power plants and other facilities in the nuclear fuel cycle. During the last session there was a detailed panel discussion on the conclusions and future needs highlighted during the symposium. While past symposia on nuclear power and its fuel cycle have presented data on occupational dose statistics, this symposium was the first to focus attention on the experience and trends of occupational exposure in recent years. The papers presented an authoritative account of the status of the levels and trends of the average annual individual dose as well as the annual collective dose for occupational workers in most of the world up to 1979. From the data presented it became evident that considerable progress has been

Radiation-related impacts for nuclear plant physical modifications

International Nuclear Information System (INIS)

Sciacca, F.; Knudson, R.; Simion, G.; Baca, G.; Behling, H.; Behling, K.; Britz, W.; Cohen, S.

1989-10-01

The radiation fields in nuclear power plants present significant obstacles to accomplishing repairs and modifications to many systems and components in these plants. The NRC's generic cost estimating methodology attempts to account for radiation-related impacts by assigning values to the radiation labor productivity factor. This radiation labor productivity factor is then used as a multiplier on the greenfield or new nuclear plant construction labor to adjust for the actual operating plant conditions. The value assigned to the productivity factor is based on the work-site radiation levels. The relationship among ALARA practices, work-place radiation levels, and radiation-related cost impacts previously had not been adequately characterized or verified. The assumptions made concerning the use and application of radiation-reduction measures such as system decontamination and/or the use of temporary shielding can significantly impact estimates of both labor requirements and radiation exposure associated with a particular activity. Overall guidance was needed for analysts as to typical ALARA practices at nuclear power plants and the effects of these practices in reducing work-site dose rates and overall labor requirements. This effort was undertaken to better characterize the physical modification cost and radiological exposure impacts related to the radiation environment of the work place. More specifically, this work sought to define and clarify the quantitative relationships between or among: radiation levels and ALARA practices, such as the use of temporary shielding, decontamination efforts, or the use of robots and remote tools; radiation levels and labor productivity factors; radiation levels, in-field labor hours, and worker radiation exposure; radiation levels and health physics services costs; and radiation levels, labor hours, and anti-contamination clothing and equipment. 48 refs., 4 figs., 4 tabs

Fundamental Technology Development for Radiation Damage in Nuclear Materials

International Nuclear Information System (INIS)

Kwon, Sang Chul; Kwon, J. H.; Kim, E. S. and others

2005-04-01

This project was performed to achieve technologies for the evaluation of radiation effects at materials irradiated at HANARO and nuclear power plants, to establish measurement equipment and software for the analysis of radiation defects and to set up facilities for the measurements of radiation damage with non-destructive methods. Major targets were 1) establishment of hot laboratories and remote handling facilities/ technologies for the radioactive material tests, 2) irradiation test for the simulation of nuclear power plant environment and measurement/calculation of physical radiation damage, 3) evaluation and analysis of nano-scale radiation damage, 4) evaluation of radiation embrittlement with ultrasonic resonance spectrum measurement and electromagnetic measurement and 5) basic research of radiation embrittlement and radiation damage mechanism. Through the performance of 3 years, preliminary basics were established for the application research to evaluation of irradiated materials of present nuclear power plants and GEN-IV systems. Particularly the results of SANS, PAS and TEM analyses were the first output in Korea. And computer simulations of radiation damage were tried for the first time in Korea. The technologies will be developed for the design of GEN-IV material

Principles of nuclear radiation detection

International Nuclear Information System (INIS)

Eichholz, G.G.; Poston, J.W.

1985-01-01

This book covers the transistorization of equipment and provides an introduction into practice of semiconductor and thermoluminescent detectors. It discusses the principles of radiation detectors most widely used in nuclear technology, medical practice and radiation protection. It stresses the alternative detectors available and discusses practical considerations in choosing and setting up detector systems for actual use. Traditional materials, including semiconductors, TLD's and modern data handling facilities are covered

Radiation protection philosophy and control of radiation doses from nuclear waste disposal

International Nuclear Information System (INIS)

Bryant, P.M.

1981-01-01

The author has reviewed the concurrent developments in each of the three decades from 1950 to the present day in radiation protection philosophy and in the control of radioactive waste disposals, with particular reference to the control of radiation doses to the public from disposals from nuclear installations. In addition, the author has summarised the OECD Nuclear Energy Agency's optimisation study which is a generic analysis of the quantitative factors pertinent to the management of tritium, carbon-14, krypton-85 and iodine-129, identified as being the radionuclides in fuel cycle effluents likely to be significant in the radiation exposure of large populations. (author)

Discussions about nuclear and radiation risk information communication

International Nuclear Information System (INIS)

Yang Bo; Wang Erqi; Peng Xianxun

2013-01-01

This paper described the definition and the objective of risk communication and the development of the risk communication research. It stated that how to establish a trustworthy relationship with public and the 8 aspects that should be done for keeping the relationship. With the analysis of the cognition and the influencing of the nuclear and radiation risk, this article figured out the factors which could influence the cognition of public on nuclear and radiation risk. Moreover, it explained the principles for enhancing the efficiency of the risk communication and the specific works in each phase of the risk communication. Finally, the suggestions for the development of the risk communication of the nuclear and radiation in China had been provided. (authors)

DIAPHANE: A portable radiation transport library for astrophysical applications

Science.gov (United States)

Reed, Darren S.; Dykes, Tim; Cabezón, Rubén; Gheller, Claudio; Mayer, Lucio

2018-05-01

One of the most computationally demanding aspects of the hydrodynamical modelingof Astrophysical phenomena is the transport of energy by radiation or relativistic particles. Physical processes involving energy transport are ubiquitous and of capital importance in many scenarios ranging from planet formation to cosmic structure evolution, including explosive events like core collapse supernova or gamma-ray bursts. Moreover, the ability to model and hence understand these processes has often been limited by the approximations and incompleteness in the treatment of radiation and relativistic particles. The DIAPHANE project has focused on developing a portable and scalable library that handles the transport of radiation and particles (in particular neutrinos) independently of the underlying hydrodynamic code. In this work, we present the computational framework and the functionalities of the first version of the DIAPHANE library, which has been successfully ported to three different smoothed-particle hydrodynamic codes, GADGET2, GASOLINE and SPHYNX. We also present validation of different modules solving the equations of radiation and neutrino transport using different numerical schemes.

Los Alamos radiation transport code system on desktop computing platforms

International Nuclear Information System (INIS)

Briesmeister, J.F.; Brinkley, F.W.; Clark, B.A.; West, J.T.

1990-01-01

The Los Alamos Radiation Transport Code System (LARTCS) consists of state-of-the-art Monte Carlo and discrete ordinates transport codes and data libraries. These codes were originally developed many years ago and have undergone continual improvement. With a large initial effort and continued vigilance, the codes are easily portable from one type of hardware to another. The performance of scientific work-stations (SWS) has evolved to the point that such platforms can be used routinely to perform sophisticated radiation transport calculations. As the personal computer (PC) performance approaches that of the SWS, the hardware options for desk-top radiation transport calculations expands considerably. The current status of the radiation transport codes within the LARTCS is described: MCNP, SABRINA, LAHET, ONEDANT, TWODANT, TWOHEX, and ONELD. Specifically, the authors discuss hardware systems on which the codes run and present code performance comparisons for various machines

Nuclear radiation moisture gauge calibration standard

International Nuclear Information System (INIS)

1977-01-01

A hydrophobic standard for calibrating nuclear radiation moisture gauges is described. Each standard has physical characteristics and dimensions effective for representing to a nuclear gauge undergoing calibration, an infinite mass of homogeneous hydrogen content. Calibration standards are discussed which are suitable for use with surface gauges and with depth gauges. (C.F.)

Radiation dosimetry in nuclear medicine

International Nuclear Information System (INIS)

Stabin, M.G.; Tagesson, M.; Ljungberg, M.; Strand, S.E.; Thomas, S.R.

1999-01-01

Radionuclides are used in nuclear medicine in a variety of diagnostic and therapeutic procedures. A knowledge of the radiation dose received by different organs in the body is essential to an evaluation of the risks and benefits of any procedure. In this paper, current methods for internal dosimetry are reviewed, as they are applied in nuclear medicine. Particularly, the Medical Internal Radiation Dose (MIRD) system for dosimetry is explained, and many of its published resources discussed. Available models representing individuals of different age and gender, including those representing the pregnant woman are described; current trends in establishing models for individual patients are also evaluated. The proper design of kinetic studies for establishing radiation doses for radiopharmaceuticals is discussed. An overview of how to use information obtained in a dosimetry study, including that of the effective dose equivalent (ICRP 30) and effective dose (ICRP 60), is given. Current trends and issues in internal dosimetry, including the calculation of patient-specific doses and in the use of small scale and microdosimetry techniques, are also reviewed

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Austria

International Nuclear Information System (INIS)

2003-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I) - General Regulatory Regime - General Outline: 1. Introduction; 2. Mining Regime; 3. Radioactive Substances, Nuclear Fuel and Equipment; 4. Nuclear Installations (Licensing and inspection, including nuclear safety; Emergency response); 5. Trade in Nuclear Materials and Equipment; 6. Radiation Protection; 7. Radioactive Waste Management; 8. Non-Proliferation and Physical Protection; 9. Transport; 10. Nuclear Third Party Liability; II) - Institutional Framework: 1. Regulatory and Supervisory Authorities: A. Federal Authorities - Bund (The Federal Chancellery; The Federal Minister for Women's Affairs and Consumer Protection; The Federal Minister of the Interior; The Federal Minister for Economic Affairs; The Federal Minister of Finance; The Federal Minister of Labour, Health and Social Affairs; The Federal Minister of Science and Transport; The Federal Minister of Justice; The Federal Minister for the Environment; The Federal Minister for Foreign Affairs) B. Regional Authorities - Laender; C. District Authorities - Bezirksverwaltungsbehorden; 2. Advisory Bodies (Forum for Nuclear Questions, Radiation Protection Commission - SSK); 3. Public and Semi-Public Agencies (The Seibersdorf Austrian Research Centre; The Graz Nuclear Institute; The Nuclear Institute of the Austrian Universities; The Institute of Risk Research, University of Vienna)

Nuclear radiation monitoring instruments for personnel in nuclear disaster for defence needs

International Nuclear Information System (INIS)

Bhatnagar, P.K.; Vaijapurkar, S.G.; Yadav, Ashok

2005-01-01

Ever since the tragedy of nuclear device exploding over Japan by USA in 1945 awareness exists amongst the armed forces personnel all over the world that a requirement of implementing radiological protection is imminent. Towards this adoption of radiological safety programme is a criterion. In a nuclear war disaster scenario, one encounters initial nuclear radiation (gamma and neutron radiations), gamma radiations from fallout, heat and blast. At certain distances Tanks/ armoured vehicles will survive and 4 R/s radiation level sensing to actuate relays for closing the ports of vehicles is essential, leading to reduction in inhalation, ingestion of fallout radioactivity and reduction in radiation dose received by occupants of the vehicle. Towards this sturdy radiation monitors to indicate gamma dose rate of the order of 1000 R/h, gamma and neutron dosimeters of the order of 1000 cGy with reading instruments are to be developed. These must work in harsh environment and sustain JSS 55555 conditions of army. Defence Laboratory, Jodhpur over past one decade has been involved in developing personnel, area and field monitoring instruments like dosimeters, survey meters, which are useful, acceptable to army personnel, armoured and personnel carrier vehicles, field structures/shelters. Technology transfer after satisfaction of armed forces, product ionisation and supply, maintenance, training has been the endeavor of the DRDO. Herein it is proposed to highlight the techno electronics nuclear radiation monitoring sensors and associated electronics systems developed first time in the country and productionised in bulk for Services for implementing personnel protection. The sensors developed and described are - Radiophotoluminescent Glass (RPLG) for gamma radiation dosimetry , neutron sensitive PIN diode for fast neutron dosimetry, gamma radiation sensitive PIN diode, superheated liquid neutron and gamma sensors. The dosimeter, dose rate meter and field/area instruments are

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Luxembourg

International Nuclear Information System (INIS)

2008-01-01

This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General Regulatory Framework: 1. General; 2. Mining; 3. Radioactive substances, nuclear fuel and equipment; 4. Nuclear installations (Licensing and inspection, including nuclear safety; Emergency measures); 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Non-proliferation and physical protection; 9. Transport; 10. Nuclear third party liability; II. General Institutional Framework: 1. Regulatory and supervisory authorities (Minister of Health; Minister of Labour; Other Ministers competent); 2. Advisory bodies (Higher Health Council)

Nuclear power and low level radiation hazards

International Nuclear Information System (INIS)

Myers, D.K.; Newcombe, H.B.

1979-03-01

Even in the future, nuclear power is expected to contribute less than 1/10th of the present total population exposure to man-made radiation. By the best estimates available, the current health risks of nuclear power generation appear to be much less than those associated with the major alternative sources of energy, with the exception of natural gas which is about equally safe. Uncertainties concerning the radiation risks from nuclear power, from medical x-rays and from the effects of reduced ventillation to conserve heat appear to be less than those associated with estimates of risks from the use of coal and various other sources of energy. This is in part because of the large amount of effort devoted to studies of radiation effects. The benefits in terms of current life expectancy associated with any of the conventional or unconventional methods of power production appear to greatly outweigh the associated current health hazards. (author)

Present status of Radiation and Nuclear Education at High School in Japan

International Nuclear Information System (INIS)

Kudo, Kazuhiko

1999-01-01

A special committee for 'Radiation and Nuclear Education' made an investigation into textbooks for social and science courses at high school in 1996. The committee concluded that descriptions of subjects related to energy, radiation and nuclear power in textbooks should be more substantial . In textbooks for social course, nuclear power was described from the point of view of resource, energy and environment. Some of the textbooks described that Chernobyl power plant's accident and nuclear weapons testing contaminated and destructed the earth environment. Descriptions about nuclear power were perceptional and one-sided . In textbooks for science course, subjects related to radiation, nucleus, nuclear reactor and nuclear power plant were described in detail to a certain extent . Descriptions about radiation hazard and radiation utilization were objective and balanced. In order that high school students can understand objectively nuclear power as a energy resource and conservation of the earth environment, the committee recommended the government course guidelines to be revised. (M. Suetake)

Parallel thermal radiation transport in two dimensions

International Nuclear Information System (INIS)

Smedley-Stevenson, R.P.; Ball, S.R.

2003-01-01

This paper describes the distributed memory parallel implementation of a deterministic thermal radiation transport algorithm in a 2-dimensional ALE hydrodynamics code. The parallel algorithm consists of a variety of components which are combined in order to produce a state of the art computational capability, capable of solving large thermal radiation transport problems using Blue-Oak, the 3 Tera-Flop MPP (massive parallel processors) computing facility at AWE (United Kingdom). Particular aspects of the parallel algorithm are described together with examples of the performance on some challenging applications. (author)

Parallel thermal radiation transport in two dimensions

Energy Technology Data Exchange (ETDEWEB)

Smedley-Stevenson, R.P.; Ball, S.R. [AWE Aldermaston (United Kingdom)

2003-07-01

This paper describes the distributed memory parallel implementation of a deterministic thermal radiation transport algorithm in a 2-dimensional ALE hydrodynamics code. The parallel algorithm consists of a variety of components which are combined in order to produce a state of the art computational capability, capable of solving large thermal radiation transport problems using Blue-Oak, the 3 Tera-Flop MPP (massive parallel processors) computing facility at AWE (United Kingdom). Particular aspects of the parallel algorithm are described together with examples of the performance on some challenging applications. (author)

Australian Radiation Protection and Nuclear Safety Act 1998. Guide to the Australian radiation protection and nuclear safety licensing framework. 1. ed.

International Nuclear Information System (INIS)

1999-03-01

The purpose of this guide is to provide information to Commonwealth entities who may require a license under the Australian Radiation Protection and Nuclear Safety (ARPANS) Act 1998 to enable them to posses, have control of, use, operate or dispose of radiation sources. The guide describes to which agencies and what activities require licensing. It also addresses general administrative and legal matters such as appeal procedures, ongoing licensing requirements, monitoring and compliance. Applicants are advised to consult the Australian Radiation Protection and Nuclear Safety Act 1998 and accompanying Regulations when submitting applications

Australian Radiation Protection and Nuclear Safety Act 1998. Guide to the Australian radiation protection and nuclear safety licensing framework; 1. ed

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

The purpose of this guide is to provide information to Commonwealth entities who may require a license under the Australian Radiation Protection and Nuclear Safety (ARPANS) Act 1998 to enable them to posses, have control of, use, operate or dispose of radiation sources. The guide describes to which agencies and what activities require licensing. It also addresses general administrative and legal matters such as appeal procedures, ongoing licensing requirements, monitoring and compliance. Applicants are advised to consult the Australian Radiation Protection and Nuclear Safety Act 1998 and accompanying Regulations when submitting applications

Radiation chemistry in nuclear technology

International Nuclear Information System (INIS)

Katsumura, Yosuke

2006-01-01

The importance of radiation chemistry in the field of nuclear technology including reactor chemistry, spent fuel reprocessing and radioactive high level waste repository, is summarized and, in parallel, our research activity will be briefly presented. (author)

Regulatory aspects for nuclear and radiation applications

International Nuclear Information System (INIS)

Duraisamy, S.

2014-01-01

The Atomic Energy Regulatory Board (AERB) is the national authority for ensuring that the use of ionizing radiation and nuclear energy does not cause any undue risk to the health of workers, members of the public and to the environment. AERB was constituted on November 15, 1983 and derives its regulatory power from the rules and notifications promulgated under the Atomic Energy Act, 1962 and the Environment (Protection) Act, 1986. AERB is provided with the necessary powers and mandate to frame safety policies, lay down safety standards and requirements for monitoring and enforcing the safety provisions. AERB follows multi-tier system for its review and assessment, safety monitoring, surveillance and enforcement. While regulating various nuclear and radiation facilities, AERB adopts a graded approach taking into account the hazard potential associated with the facilities being regulated. The regulatory process has been continuous evolving to cater to the new developments in reactor and radiation technologies. The regulatory effectiveness and efficiency of AERB have grown over the last three decades to make it into a robust organization. The radiation protection infrastructure in the country is on a sound footing and is constantly being strengthened based on experience and continued research and development. As one of its mandates AERB prescribes radiation dose limits for the occupational workers and the public, in line with the IAEA Safety Standard and ICRP recommendations. The current dose limits and the radiation safety requirements are more stringent than past. To meet the current safety standards, it is important for the facilities to have state of art radiation monitoring system and programme in place. While recognizing the current system in place, this presentation also highlights certain key radiation protection challenges associated with the implementation of radiation protection standards in the nuclear and radiation facilities especially in the areas of

Radiation exposure of employees in nuclear fuel facilities in fiscal 1982

International Nuclear Information System (INIS)

1984-01-01

The enterprises of nuclear fuel refining, fabrication, reprocessing and usage are obligated by law to keep the radiation exposure dose of the employees below the permissible level. The radiation exposure dose in the respective enterprises in the fiscal year 1982 is summarized in a table as follows: radiation exposure dose distribution, the number of employees, total exposure dose, and average dose. The radiation exposure dose was all well below the permissible level. The enterprises covered were one refining (Power Reactor and Nuclear Fuel Development Corporation), five fabrication (Mitsubishi Nuclear Fuel Co., Ltd., etc.), one reprocessing (Power Reactor and Nuclear Fuel Development Corporation), and ten usage (Power Reactor and Nuclear Fuel Development Corporation, Japan Atomic Energy Research Institute, etc.). (Mori, K.)

A National Institute of Radiation Protection and Nuclear Safety?

International Nuclear Information System (INIS)

Hartley, B.M.

1993-01-01

The practice of radiation protection within Australia is fragmented on a number of different levels. Each state has its own radiation protection organisation. Within the Commonwealth there is also a large number of bodies which deal with different aspects of radiation protection or nuclear safety. There is also an interest in occupational radiation protection by Departments responsible for Occupational Health and Safety. It is estimated that this fragmentation affects the practice of radiation protection at a State level and also the role which Australia can play internationally. The establishment of a National Institute of Radiation Protection and Nuclear Safety is therefore proposed. Possible structures and organizational arrangements for such an institute are discussed. 4 refs., 4 tabs., 3 figs

Nuclear Safety and Radiation Protection in Europe - a common approach

International Nuclear Information System (INIS)

McGarry, Ann

2010-01-01

In Europe, the European Union has adopted directives and implemented other measures which form the basis of a common approach to nuclear safety and radiation protection across all Member States. In particular, there are EU directives setting out radiation protection standards and establishing a Community framework for the nuclear safety of nuclear installations. There are also arrangements in place to provide for an effective response to nuclear emergencies and to facilitate high quality research into nuclear and radiation protection related topics. Inevitably the stage of development in each area is somewhat different, but generally progress is ongoing in each area. From the point of view of a small country like Ireland, the development of common standards and arrangements across Europe is beneficial as they are based on the best available knowledge and expertise; they provide for greater transparency; they facilitate public confidence and make best use of the available resources. However, there are some areas in which common approaches could be further advanced. For example, the medical exposure of patients is increasingly of concern across Europe and the further development of common approaches in this area would be helpful. It would also be useful to develop a more integrated approach to nuclear safety and radiation protection regulation and to better integrate nuclear and radiation issues with other public health and environment concerns. (author)

Radiation doses and radiation risk in foreign nuclear objects

International Nuclear Information System (INIS)

Tvehlov, Yu.

2001-01-01

Data on levels of irradiation on NPP operating in different regions of the world obtained from the data of the International Information System ISOE created by IAEA in association with the Nuclear Energetic Agency OECD are performed. Effect of commissioning new NPP, sacrifice of radiation situation at the Ignalina NPP in 1996, importance of the development and introduction of programs on perfecting of radiation protection and culture of safety are noted [ru

Nuclear radiation in warfare. A SIPRI publication. Strahlungswirkungen beim Einsatz von Kernwaffen. Eine SIPRI-Publikation

Energy Technology Data Exchange (ETDEWEB)

Rotblat, J.

1986-01-01

The subject is covered in chapters, entitled: introduction; digest of nuclear weaponry (characteristics of nuclear weapons; effects of nuclear weapons other than ionizing radiation (fire-ball, fall-out, thermal radiation, blast wave, electromagnetic pulse); the nuclear arms race; war scenarios; biological effects of radiations on man (radiation doses; natural sources of radiation; acute effects of radiation; long-term somatic effects; genetic effects; factors affecting the biological response to radiation; internal exposure; synergistic effects; protection against radiation effects); radiations from nuclear explosions (initial radiation; fall-out; effects of fall-out on animal and plant life; contamination of water and food supplies by fall-out); radiation casualties in a nuclear war; effectiveness of civil defence; other warlike uses of radiation (attacks on civilian nuclear power installations; radiological warfare; terrorist activities); conclusion.

Radiation inactivation studies of renal brush border water and urea transport

International Nuclear Information System (INIS)

Verkman, A.S.; Dix, J.A.; Seifter, J.L.; Skorecki, K.L.; Jung, C.Y.; Ausiello, D.A.

1985-01-01

Radiation inactivation was used to determine the nature and molecular weight of water and urea transport pathways in brush border membrane vesicles (BBMV) isolated from rabbit renal cortex. BBMV were frozen to -50 degrees C, irradiated with 1.5 MeV electrons, thawed, and assayed for transport or enzyme activity. The freezing process had no effect on enzyme or transport kinetics. BBMV alkaline phosphatase activity gave linear ln(activity) vs. radiation dose plots with a target size of 68 +/- 3 kDa, similar to previously reported values. Water and solute transport were measured using the stopped-flow light-scattering technique. The rates of acetamide and osmotic water transport did not depend on radiation dose (0-7 Mrad), suggesting that transport of these substances does not require a protein carrier. In contrast, urea and thiourea transport gave linear ln(activity) vs. dose curves with a target size of 125-150 kDa; 400 mM urea inhibited thiourea flux by -50% at 0 and 4.7 Mrad, showing that radiation does not affect inhibitor binding to surviving transporters. These studies suggest that BBMV urea transport requires a membrane protein, whereas osmotic water transport does not

Management of the process of nuclear transport

International Nuclear Information System (INIS)

Requejo, P.

2015-01-01

Since 1996 ETSA is the only Spanish logistics operator specialized on servicing the nuclear and radioactive industry. Nowadays ETSA has some technological systems specifically designed for the management of nuclear transports. These tools have been the result of the analysis of multiple factors involved in nuclear shipments, of ETSAs wide experience as a logistics operator and the search for continuous improvement. (Author)

Memorandum of understanding between the Federal Minister for the Environment, nature conservation and nuclear safety of the Federal Republic of Germany and the atomic energy control board of Canada on cooperation and exchange of information respecting nuclear safety and radiation

International Nuclear Information System (INIS)

1991-01-01

This Memorandum of Understanding on co-operation and exchange of information respecting nuclear safety and radiation protection covers the period 23 May 1991 to 1 June 1996. The Parties may exchange information on any matter concerning the civil uses of nuclear energy within the other Party's jurisdiction and, in particular information on: nuclear installations, their siting, construction, operation and decommissioning; uranium mining and milling; nuclear fuel production; radioactive waste treatment, storage and disposal; transport of nuclear fuel and radioactive waste; radiation protection; legislation, regulations, standards. All information received and the results of activities carried out under this Memorandum of Understanding will be used exclusively for peaceful purposes [fr

Overview of radiation protection programme in nuclear medicine facility for diagnostic procedures

International Nuclear Information System (INIS)

Ahmed, Ezzeldein Mohammed Nour Mohammed