WorldWideScience

Sample records for nuclear radiation center

  1. Graphical user interfaces for McClellan Nuclear Radiation Center

    International Nuclear Information System (INIS)

    Brown-VanHoozer, S.A.; Power, M.; Forsmann, H.

    1998-01-01

    The control console of the TRIGA reactor at McClellan's Nuclear Radiation Center (MNRC) is in the process of being replaced because of spurious scrams, outdated software, and obsolete parts. The intent of the new control console is to eliminate the existing problems by installing a UNIX-based computer system with industry-standard interface software and by incorporating human factors during all stages of the graphical user interface (GUI) development and control console design. This paper gives a brief description of some of the guidelines used in developing the MNRC's GUIs as continuous, real-time displays

  2. External radiation levels in installations of nuclear technology center

    International Nuclear Information System (INIS)

    Maletta, Paulo Guilherme M.; Filipetto, Joao; Wakabayashi, Tetsuaki; Silva, Teogenes A. da

    2005-01-01

    The radiological protection is a basic activity of nuclear technology center so that can carry through its activities with security, having to be planned and executed with total effectiveness. One of the basic tools of the radiological protection is the adoption of monitoring programs, that have as objective generality to evaluate the radiological conditions of the workstation and to assure that these conditions are acceptable safe for the displayed individuals, either workers or members of the public, as established in the basic norms of radiological protection. The Centro de Desenvolvimento da Tecnologia Nuclear - CDTN, first institution in Brazil, created in 1952 to entirely dedicate the related works to the nuclear area, to own 39 building, of which they are kept the Triga Reactor, Irradiation Gamma Laboratory, Reject Laboratory, Calibration Dosemeters Laboratory and others. In such installations, radioactive materials are produced, handled, processed and stored, being necessary the levels of external radiation ambient monitoring. As part of the radioprotection plan, monitoring 63 points on strategically located in the external areas to the building of CDTN, using characterized and calibrated thermoluminescence dosemeters. This work describes the dose distribution of the points, the doses evaluation procedure and the 4 results carried through between 2001 and 2004. The data demonstrate the attendance to the level of security established in the basic norm, what it contributed for the operation licensing of to the IBAMA. (author)

  3. 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.

  4. Selection and construction of nuclear and radiation emergency medical center in a region

    International Nuclear Information System (INIS)

    Wang Guojun; He Xu; Liao Li; Gao Dong

    2014-01-01

    Three level of first-class comprehensive hospital is an important force of nuclear and radiation accident rescue, has a very rich experience in response to nuclear and radiation accidents and deal with large quantities of the sick and wounded. With the foundation and the ability of the construction and operation of medical emergency rescue center. This paper according to the median model location theory of emergency center, combined with the specific situation of the nuclear and radiation accident in Hunan Province, reference location, rescue experience, emergency allocation of resources, teaching and research capacity, establish regional medical emergency center of nuclear and radiation accidents based on three level of first-class comprehensive hospital, break the traditional concept that the center must be provincial capital,form a multi-level, three-dimensional, network of emergency hospital rescue system. The main duties of the center are accident emergency response, on-site treatment and technical guidance of accident, psychological grooming. The author propose building measures according to the duties of the center: increase national and provincial financial investment, carry out training, drills and first aid knowledge missionaries regularly, innovative materials management, speed up the construction of information platform, establish and improve the hospital rescue system, improve organization institution and system of plans, reengineering rescue process. (authors)

  5. 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.

  6. Graphical user interfaces for McCellan Nuclear Radiation Center (MNRC)

    International Nuclear Information System (INIS)

    Brown-VanHoozer, S. A.

    1998-01-01

    McClellan's Nuclear Radiation Center (MNRC) control console is in the process of being replaced due to spurious scrams, outdated software, and obsolete parts. The intent of the new control console is to eliminate the existing problems by installing a UNIX-based computer system with industry-standard interface software and incorporating human factors during all stages of the graphical user interface (GUI) development and control console design

  7. Radiation effect calculation means of the Crisis Technical Center of the Nuclear Safety and Protection Institut

    International Nuclear Information System (INIS)

    Crabol, B.; Manesse, D.; Robeau, D.

    1989-07-01

    The available calculation tools of the Crisis Technical Center (CTC), for the analysis and evaluation of radiation effects from a nuclear accident, are presented. The CTC calculation unit depends on local means, and on the National Meteorology system, in order to collect the data needed for the atmospheric waste diffusion evaluation. For the radiation dose calculations, plotters and software allowing the analysis of all waste Kinetics and all the meteorological conditions are available. The work developed by CTC calculation unit enables an easy application of the calculation tools as well as the results obtention. Images from data bases are provided to complete the obtained results [fr

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

    International Nuclear Information System (INIS)

    Ahmed, Amel Bushra Abaker

    2001-01-01

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

  9. Nuclear Reaction Data Centers

    International Nuclear Information System (INIS)

    McLane, V.; Nordborg, C.; Lemmel, H.D.; Manokhin, V.N.

    1988-01-01

    The cooperating Nuclear Reaction Data Centers are involved in the compilation and exchange of nuclear reaction data for incident neutrons, charged particles and photons. Individual centers may also have services in other areas, e.g., evaluated data, nuclear structure and decay data, reactor physics, nuclear safety; some of this information may also be exchanged between interested centers. 20 refs., 1 tab

  10. Radiation exposure to the staff of the Karlsruhe Nuclear Research Center, 1969-1981

    International Nuclear Information System (INIS)

    Koelzer, W.

    1983-07-01

    Evaluation of the data from the personnel dosimetry of the staff monitored from 1969 until 1981 at the Karlsruhe Nuclear Research Center (Kernforschungszentrum Karlsruhe GmbH) gives a total external dose of 6,335 rem including natural radiaiton background. The occupational exposure of the radiation workers within this period comes to 3,076 rem, which gives an average annual external occupational exposure of 0.14 rem. In 1,832 cases an annual dose between 0.5 and 1.5 rem per year and in 353 cases a dose of more than 1.5 rem per year have been measured. The highest value, measured in 1972, amounted to 6.8 rem. During the period from 1969 until 1981 more than 34,000 incorporation measurements were performed with the whole body counter and the lung counter, 1,963 cases with positive findings. In 96% of the cases the values of incorporated activity were inferior to 1% - in 70% even inferior to 0.1% - of the maximum permissible body burden values of ICRP 2. Only 5 cases exceeded these values. (orig.) [de

  11. Architectural Design of a Nuclear Research Center with Radiation Safety Considerations, in North Western Coast of Egypt (Using Auto CAD and 3ds Max Programs)

    International Nuclear Information System (INIS)

    Farahat, M.A.Z.

    2016-01-01

    This research discusses the design of nuclear research centers to help architects and engineers who will design these centers. Also, the research covers the site characteristics which are used in site selection of nuclear research centers. It covers the principles and standards used in design and planning of nuclear research centers. The master plan of a nuclear research center should be designed based on the system of segregation according to the level of radioactivity. Radiation safety is an important aspect in the design of nuclear research centers. The Egyptian Atomic Energy Authority consists of three nuclear research centers, namely, the Nuclear Research Center in Inshas (Grid Planning Concept), the Hot Laboratories and Waste Management Center in Inshas (Grid Planning Concept) and The National Center for Radiation Research and Technology in Nasr City (Linear Planning Concept). The Radial Planning Concept is the best among all the Planning Concepts as regard radiation safety considerations. Therefore, an architectural design of a new nuclear research center was proposed in a suitable site in North Western Coast of Egypt (Radial Planning Concept) using Auto CAD and 3ds Max programs. This site is suitable and satisfies many of the site requirements. It is recommended that the architectural design of nuclear research centers should be supervised by an architectural engineer experienced in architectural design of nuclear facilities

  12. Ambient radiation monitoring at a PET/CT imaging center within a nuclear medicine department

    International Nuclear Information System (INIS)

    Lai, Y.C.; Chen, Y.W.; Chuang, Y.W.

    2006-01-01

    Full text of publication follows: Potential environmental dose rates in a patient waiting room at the PET/CT Imaging Center within our Nuclear Medicine Department (N.M.D.) are evaluated by both of the computer modeling method and real-time monitoring in practical settings. The maximum dose rate is directly read from a peak dose-rate frozen-up, digital gamma G-M survey meter. The design basis of our PET/CT Imaging Center facility has assumed a maximum total of five 18 FDG-patients presented at any given time either in an Am or a Pm session according to two separated drug batch delivering runs. Due to the relatively high gamma energy of 511 keV emitted by the F- 18 labeled compound, we have remodeled our facility with a 0.5-cm thick Pb wall and larger space separations between rooms that include a PET/CT scan room, two separated 18 FDG i.v. injection rooms, and a delayed-phase patient waiting room. Patient could normally complete two separate PET/CT scan runs, if a delayed-phase scan is needed, within three hours time frame from an initial dose of 370 MBq (10 mCi) that has a physical half-live of 110 minutes for an F-18 labeled compound. When all the needed scans are finished, the patient is released from our PET/CT Imaging Center that has to follow the radiation safety guideline of less than 50 mSv/hr (5 m R/hr) at one meter distance. During typical operation, each drug i.v. injection room or the scan room is restricted to one patient access only. As a worst case scenario, the maximum ambient dose rate may only occur when two or more delayed phase patients would stay in the PET/CT waiting room that is excluded for other non-PET patient use. Theoretically using a computer discrete-ordinate integrating methods, dose rates at one meter distance from a mid-point geometry, based on a simulated 10 mCi F-18 point, line or volumetric source (assuming 170 cm in height and 20 cm in radius of homogeneous water media), can also be calculated to give values of 5.71, 4.73 and 3

  13. Contributions to nuclear safety and radiation technologies in Ukraine by the Science and Technology Center in Ukraine (STCU)

    International Nuclear Information System (INIS)

    Taranenko, L.; Janouch, F.; Owsiacki, L.

    2001-01-01

    This paper presents Science and Technology Center in Ukraine (STCU) activities devoted to furthering nuclear and radiation safety, which is a prioritized STCU area. The STCU, an intergovernmental organization with the principle objective of non-proliferation, administers financial support from the USA, Canada, and the EU to Ukrainian projects in various scientific and technological areas; coordinates projects; and promotes the integration of Ukrainian scientists into the international scientific community, including involving western collaborators. The paper focuses on STCU's largest project to date 'Program Supporting Y2K Readiness at Ukrainian NPPs' initiated in April 1999 and designed to address possible Y2K readiness problems at 14 Ukrainian nuclear reactors. Other presented projects demonstrate a wide diversity of supported directions in the fields of nuclear and radiation safety, including reactor material improvement ('Improved Zirconium-Based Elements for Nuclear Reactors'), information technologies for nuclear industries ('Ukrainian Nuclear Data Bank in Slavutich'), and radiation health science ('Diagnostics and Treatment of Radiation-Induced Injuries of Human Biopolymers').

  14. Contributions to nuclear safety and radiation technologies in Ukraine by the Science and Technology Center in Ukraine (STCU)

    Energy Technology Data Exchange (ETDEWEB)

    Taranenko, L. E-mail: lyubov@stcu.kiev.ua; Janouch, F.; Owsiacki, L

    2001-06-01

    This paper presents Science and Technology Center in Ukraine (STCU) activities devoted to furthering nuclear and radiation safety, which is a prioritized STCU area. The STCU, an intergovernmental organization with the principle objective of non-proliferation, administers financial support from the USA, Canada, and the EU to Ukrainian projects in various scientific and technological areas; coordinates projects; and promotes the integration of Ukrainian scientists into the international scientific community, including involving western collaborators. The paper focuses on STCU's largest project to date 'Program Supporting Y2K Readiness at Ukrainian NPPs' initiated in April 1999 and designed to address possible Y2K readiness problems at 14 Ukrainian nuclear reactors. Other presented projects demonstrate a wide diversity of supported directions in the fields of nuclear and radiation safety, including reactor material improvement ('Improved Zirconium-Based Elements for Nuclear Reactors'), information technologies for nuclear industries ('Ukrainian Nuclear Data Bank in Slavutich'), and radiation health science ('Diagnostics and Treatment of Radiation-Induced Injuries of Human Biopolymers')

  15. Tehran Nuclear Research Center

    International Nuclear Information System (INIS)

    Taherzadeh, M.

    1977-01-01

    The Tehran Nuclear Research Center was formerly managed by the University of Tehran. This Center, after its transformation to the AEOI, has now become a focal point for basic research in the area of Nuclear Energy in Iran

  16. Radiation monitoring program at nuclear scientific experimental and educational center - IRT-Sofia

    International Nuclear Information System (INIS)

    Mladenov, A.; Stankov, D.; Marinov, K.; Nonova, T.; Krezhov, K.

    2012-01-01

    Ensuring minimal risk of personnel exposure without exceeding the dose limits is the main task of the General Program for Radiation Monitoring of Nuclear Scientific Experimental and Education Centre (NSEEC) with research reactor IRT. Since 2006 the IRT-Sofia is equipped with a new and modern Radiation Monitoring System (RMS). All RMS detectors are connected to the server RAMSYS. They have online (real-time) visualization in two workstations with RAMVISION software. The RMS allows the implementation of technological and environmental monitoring at the nuclear facility site. Environmental monitoring with the RMS external system includes monitoring of dose rate; alpha and beta activity; radon activity; Po-218, Po-214, Po-212 activity; gamma control of vehicles. Technological control of reactor gases includes: Alpha beta particulate monitor; Iodine monitor; Noble gases monitor; Stack flow monitor. The General Program based on the radiation monitoring system allows real-time monitoring and control of radiation parameters in the controlled area and provides for a high level of radiation protection of IRT staff and users of its facilities. This paper presents the technical and functional parameters of the radiation monitoring system and radiation protection activities within the restricted zone in IRT facilities. (authors)

  17. Aube storage center. Information report on nuclear safety and radiation protection 2015

    International Nuclear Information System (INIS)

    2016-01-01

    The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2015 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, security, events or incidents, environmental monitoring and effluents, wastes management, public information, recommendations of the Health and safety Committee (CHSCT)

  18. Aube storage center. Information report on nuclear safety and radiation protection 2016

    International Nuclear Information System (INIS)

    2017-01-01

    The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2016 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, security, events or incidents, environmental monitoring and effluents, wastes management, public information, recommendations of the Health and safety Committee (CHSCT)

  19. 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

  20. 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.)

  1. McClellan Nuclear Radiation Center (MNRC) TRIGA reactor: The national organization of test research and training reactors

    International Nuclear Information System (INIS)

    Kiger, Kevin M.

    1994-01-01

    This year's TRTR conference is being hosted by the McClellan Nuclear Radiation Center. The conference will be held at the Red Lion Hotel in Sacramento, CA. The conference dates are scheduled for October 11-14, 1994. Deadlines for sponsorship commitment and papers have not been set, but are forthcoming. The newly remodeled Red Lion Hotel provides up-to-date conference facilities and one of the most desirable locations for dining, shopping and entertainment in the Sacramento area. While attendees are busy with the conference activities, a spouses program will be available. Although the agenda has not been set, the Sacramento area offers outings to San Francisco, Pier 39, Ghirardelli Square (famous for their chocolate), and a chance to discover 'El Dorado' in the gold country. Not to forget our own bit of history with visits to 'Old Sacramento and Old Folsom', where antiquities abound, to the world renown train museum and incredible eating establishments. (author)

  2. Goals, tasks and aspects of activity of Ukrainian State Scientific and Technical Center on Nuclear and Radiation Safety

    International Nuclear Information System (INIS)

    Kovbasenko, Yu.

    2001-01-01

    The goal of SSTC NRS activities is scientific, technical, analytical and expert support to the Nuclear Regulatory Department as a State Nuclear and Radiation Safety Regulatory Authority.The main tasks are: 1. Development and improvement of normative and legal framework in the field of nuclear power use in Ukraine; 2. Expert support in making regulatory decisions; 3. Research and development work on improvement engineering and operational safety of nuclear power facilities in Ukraine. The organizational structure of SSTC NRS is also given

  3. Reactor control system upgrade for the McClellan Nuclear Radiation Center Sacramento, CA

    International Nuclear Information System (INIS)

    Power, M. A.

    1999-01-01

    Argonne National Laboratory is currently developing a new reactor control system for the McClellan Nuclear Radiation Facility. This new control system not only provides the same functionality as the existing control system in terms of graphic displays of reactor process variables, data archival capability, and manual, automatic, pulse and square-wave modes of operation, but adds to the functionality of the previous control system by incorporating signal processing algorithms for the validation of sensors and automatic calibration and verification of control rod worth curves. With the inclusion of these automated features, the intent of this control system is not to replace the operator but to make the process of controlling the reactor easier and safer for the operator. For instance, an automatic control rod calibration method reduces the amount of time to calibrate control rods from days to minutes, increasing overall reactor utilization. The control rod calibration curve, determined using the automatic calibration system, can be validated anytime after the calibration, as long as the reactor power is between 50W and 500W. This is done by banking all of the rods simultaneously and comparing the tabulated rod worth curves with a reactivity computer estimate. As long as the deviation between the tabulated values and the reactivity estimate is within a prescribed error band, then the system is in calibration. In order to minimize the amount of information displayed, only the essential flux-related data are displayed in graphical format on the control screen. Information from the sensor validation methods is communicated to the operators via messages, which appear in a message window. The messages inform the operators that the actual process variables do not correlate within the allowed uncertainty in the reactor system. These warnings, however, cannot cause the reactor to shutdown automatically. The reactor operator has the ultimate responsibility of using this

  4. Evaluation of gamma radiation cumulative exposure monitoring system in the Nuclear Technology Development Center (CDTN) with thermoluminescent dosimeters

    Energy Technology Data Exchange (ETDEWEB)

    Domingues, Danieli S.; Barreto, Alberto A.; Siqueira, Gessilane M.; Oliveira, Eugênio M.; Silva, Robson L.; Belo, Luiz Cláudio M., E-mail: danielisilva@ymail.com, E-mail: aab@cdtn.br, E-mail: gessilane.siqueira@cdtn.br, E-mail: emo@cdtn.br, E-mail: rls@cdtn.br, E-mail: lcmb@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    Cumulative exposure to gamma radiation is monitored at the Nuclear Technology Development Center - CDTN, located on the campus of the Federal University of Minas Gerais in Belo Horizonte - MG, since 1986. This monitoring is part of the Institution's Environmental Monitoring Program. The measurement is carried out through the use of thermoluminescent dosimeters (TLD's), which are placed in the perimeter of the CDTN property, distanced approximately 50 m each other, and at the air sampling stations, totaling 36 sampling points. The TLDs are positioned one meter from the ground, inside a PVC pipe where they remain exposed for a period of approximately three months. The objective of this work is to present and evaluate the results of this monitoring by investigating the dose values of gamma radiation (Dose Equivalent to Photons) obtained. Another important issue presented is about some failures identified in certain periods. There were problems with the sampling methodology and changes were proposed in the shelters to avoid contact of TLDs with excess moisture, which can compromise the results and the equipment of measurement of the thermoluminescence of crystals. The change was made at a sampling point and the results were compared with the historical data in the last 30 years. (author)

  5. Evaluation of gamma radiation cumulative exposure monitoring system in the Nuclear Technology Development Center (CDTN) with thermoluminescent dosimeters

    International Nuclear Information System (INIS)

    Domingues, Danieli S.; Barreto, Alberto A.; Siqueira, Gessilane M.; Oliveira, Eugênio M.; Silva, Robson L.; Belo, Luiz Cláudio M.

    2017-01-01

    Cumulative exposure to gamma radiation is monitored at the Nuclear Technology Development Center - CDTN, located on the campus of the Federal University of Minas Gerais in Belo Horizonte - MG, since 1986. This monitoring is part of the Institution's Environmental Monitoring Program. The measurement is carried out through the use of thermoluminescent dosimeters (TLD's), which are placed in the perimeter of the CDTN property, distanced approximately 50 m each other, and at the air sampling stations, totaling 36 sampling points. The TLDs are positioned one meter from the ground, inside a PVC pipe where they remain exposed for a period of approximately three months. The objective of this work is to present and evaluate the results of this monitoring by investigating the dose values of gamma radiation (Dose Equivalent to Photons) obtained. Another important issue presented is about some failures identified in certain periods. There were problems with the sampling methodology and changes were proposed in the shelters to avoid contact of TLDs with excess moisture, which can compromise the results and the equipment of measurement of the thermoluminescence of crystals. The change was made at a sampling point and the results were compared with the historical data in the last 30 years. (author)

  6. McClellan Nuclear Radiation Center (MNRC) TRIGA reactor: Four years of operations

    International Nuclear Information System (INIS)

    Heidel, C.C.; Richards, W.J.

    1994-01-01

    McClellan Air Force Base, at Sacramento, California, is headquarters for the Sacramento Air Force Logistics Center (SM-ALC). McClellan Air Force Base provides extensive inspection and maintenance capabilities for the F-111, F-1 5, and other military aircraft. Criticality of the MNRC TRIGA reactor was obtained on January 20, 1990 with 63 standard TRIGA fuel elements, three fuel-followed control rods and one air-followed control rod. Presently there are 93 fuel elements in the reactor core. The reactor can be operated at 1 MW steady state power, producing pulses up to three dollars worth of reactivity addition, and can be square waved up to 1 MW. The reactor core contains a circular grid plate and a graphite reflector assembly surrounding the core. Four tangential beam ports installed in the reflector assembly provide a thermal neutron flux to four radiography bays. The reactor tank is twenty-four (24) feet deep, seven and one-half (7.5) feet in diameter, and has a protrusion in the upper portion of the reactor tank. This protrusion is scheduled for use as a neutron thermal collimator in the future. Besides the neutron radiography capabilities, the reactor contains a pneumatic rabbit system, a central thimble, an in-core irradiation facility, and three additional cutouts that provide locations for additional irradiation facilities. The central thimble can be removed along with the B-ring locations of the upper portion of the grid plate to provide an additional and larger in-core irradiation facility. A new upper grid plate has been manufactured to expand one triangular cutout so that larger experiments can be inserted directly into the reactor core. Some operational problems experienced during the first four years of operations are the timeout of the CSC and DAC watchdogs, deterioration of the heat exchanger gaskets, and loss of thermocouples in the instrumented fuel elements. (author)

  7. 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.)

  8. 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

  9. 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)

  10. 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

  11. A multipurpose radiation service center

    International Nuclear Information System (INIS)

    Hofmann, E.-G.

    1977-01-01

    In Germany, AEG-Telefunken has been working as a supplier of irradiation equipment for more than ten years. There is a close cooperation with Radiation Dynamics Inc., Westbury, N.Y. Radiation sources are available for most industrial applications. As a special service AEG is establishing a multipurpose radiation service center in Hamburg-Wedel, Germany. This center will be used by a host of companies to investigate the effects of radiation on a broad range of materials, to develop special processing equipment, to process customer supplied products and to perform R and D work and contracts. Initially this service center will be equipped with one research type High-Power X-ray Unit (200 kV/32 mA) and one industrial type Dynamitron accelerator (1500 kV/37.5 kW). (author)

  12. Nuclear medicine radiation dosimetry

    CERN Document Server

    McParland, Brian J

    2010-01-01

    Complexities of the requirements for accurate radiation dosimetry evaluation in both diagnostic and therapeutic nuclear medicine (including PET) have grown over the past decade. This is due primarily to four factors: growing consideration of accurate patient-specific treatment planning for radionuclide therapy as a means of improving the therapeutic benefit, development of more realistic anthropomorphic phantoms and their use in estimating radiation transport and dosimetry in patients, design and use of advanced Monte Carlo algorithms in calculating the above-mentioned radiation transport and

  13. National Nuclear Data Center

    Science.gov (United States)

    data The EXFOR project EXFOR Basics Short guide Codes Checking & utility codes Reaction codes -development ENDF-6 Format Manual (not yet available) Introduction to ENDF Formats ADVANCE ENDF continuous Educational Links ABC of Nuclear Science Brief Introduction History of Chemical Elements IUPAC Periodic Table

  14. 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)

  15. 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)

  16. Nuclear data services of the Nuclear Data Centers Network available at the National Nuclear Data Center

    International Nuclear Information System (INIS)

    McLane, V.

    1997-01-01

    The Nuclear Data Centers Network provides low and medium energy nuclear reaction data to users around the world. Online retrievals are available through the U.S. National Nuclear Data Center, the Nuclear Energy Agency Data Bank, and the IAEA Nuclear Data Section from these extensive bibliographic, experimental data, and evaluated data files. In addition to nuclear reaction data, the various databases also provide nuclear structure and decay data, and other information of interest to users. The WorldWideWeb sites at the National Nuclear Data Center and the NEA Data Bank provide access to some of the Centers' files. (orig.)

  17. Contributions to nuclear safety and radiation technologies in Ukraine by the Science and Technology Center in Ukraine (STCU)

    Czech Academy of Sciences Publication Activity Database

    Taraněnko, L.; Janouch, František; Owsiacki, L.

    2001-01-01

    Roč. 61, 3/6 (2001), s. 795-796 ISSN 0969-806X R&D Projects: GA AV ČR KSK2067107 Keywords : Ukrainian nuclear facilities * nuclear data bank Subject RIV: JF - Nuclear Energetics Impact factor: 0.819, year: 2001

  18. Management of nuclear training center

    International Nuclear Information System (INIS)

    Seo, In Suk; Lee, Han Young; Cho, Boung Jae; Lee, Seung Hee; Lee, Eoi Jin; You, Byung Hoon; Lee, Won Ku; Jeon, Hyung Ryeon; Seo, Kyung Won; Kim, Young Joong; Kim, Ik Hyun; Hyun, Ha Il; Choi, Il Ki; Hong, Choon Sun; Won, Jong Yeul; Joo, Yong Chang; Nam, Jae Yeul; Sin, Eun Jeong

    1996-02-01

    This report describes the annual results of training courses. The scope and contents are as follows : 1. Regional and interregional training courses, 2. Training courses assisted by foreign experts, 3. Training courses for nuclear industry personnel, 4. Training courses for internal staff-members, 5. Training courses under the law. The nuclear training center executed the open-door training courses for 2,699 engineers/scientists from the regulatory body, nuclear industries, research institutes and other related organizations by means of offering 69 training courses during the fiscal year 1995. (Author) .new

  19. 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

  20. 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)

  1. 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)

  2. 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

  3. Laboratory for Calibration of Gamma Radiation Measurement Instruments (LabCal) of Institute of Chemical, Biological, Radiological and Nuclear Defense (IDQBRN) from Brazilian Army Technology Center (CTEx)

    International Nuclear Information System (INIS)

    Amorim, Aneuri de; Balthar, Mario Cesar V.; Santos, Avelino; Vilela, Paulo Ricardo T. de; Oliveira, Luciano Santa Rita; Penha, Paulo Eduardo C. de Oliveira; Gonzaga, Roberto Neves; Andrade, Edson Ramos de; Oliveira, Celio Jorge Vasques de; Fagundes, Luiz Cesar S.

    2016-01-01

    This paper describes the calibration laboratory deployment steps (LABCAL) gamma ionizing radiation measuring instruments in the Army Technology Center, CTEx. Initially the calibration of radiation monitors will be held in the dosimetric quantity air kerma and operational quantity ambient dose equivalent H*(d). The LABCAL / CTEx has not yet authorized by CASEC / CNEN. This laboratory aims to calibrate the ionizing radiation instruments used by the Brazilian Army. (author)

  4. Nuclear information services at the National Nuclear Data Center

    International Nuclear Information System (INIS)

    Burrows, T.W.; Tuli, J.K.

    1996-01-01

    The numeric and bibliographic nuclear data bases maintained by the National Nuclear Data Center and access to these data bases will be described. The U.S. Nuclear Data and Reaction Data Networks will also be briefly described

  5. Russian Federal nuclear center facilities for nuclear spectroscopy investigations

    International Nuclear Information System (INIS)

    Ilkaev, R.I.; Punin, V.T.; Abramovich, S.N.

    2001-01-01

    Russian Federal Nuclear Center facilities for Spectroscopy investigation in the field of nuclear spectroscopy are described. Here are discussed basic properties of used radiation sources, facilities and technologies for target material production and manufacture of targets from rare, high-toxic or radioactive materials. Here are also reported basic features of complex detector systems and technologies for manufacture of scintillation detectors with special properties VNIIEF was founded as a weapons laboratory. The development of nuclear and thermonuclear bombs was followed by a wide complex of nuclear-physics investigations. Naturally, data on nuclear-physics properties of active and structure materials being part of nuclear weapons were of greatest interest.At the initial stage of work on the development of nuclear weapons the information on nuclear constants of materials including the most important neutron ones was rather scant. Data published in scientific literature had low exactness and were insecure. Results of measurements sometimes differed greatly by various groups of investigators. At the same time it was clear that, for example, a 1,5-times mistake in the fission cross-section could cause a several times mistake in the choice of uranium or plutonium mass, which is necessary for the bomb development. These circumstances determined importance of the nuclear-physics investigations. Demands on knowledge of process details occurring inside the nuclei conditioned by a problem of developing and improving of nuclear weapons and atomic power are rather limited. However, the further development of nuclear industry has proved a well-known point that this knowledge being accumulated forms a critical mass that leads to an explosive situation in the elaboration both of ideological and technological aspects of these problems. It is the tendency of inside development of nuclear science that has conditioned preparedness of knowledge about intranuclear processes for

  6. 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

  7. Bolivia. The new nuclear research center in El Alto

    International Nuclear Information System (INIS)

    Nogarin, Mauro

    2016-01-01

    Research reactors in Latin America have become a priority in public policy in the last decade. Bolivia wants to become the 8th country to implement peaceful nuclear technology in this area with the new Center for Research and Development in the Nuclear Technology. The Center will be the most advanced in Latin America. It will provide for a wide use of radiation technologies in agriculture, medicine, and industry. After several negotiations Bolivia and the Russian Federation signed the Intergovernmental Agreement on cooperation in the peaceful use of atomic energy and the construction of the Nuclear Research and Technology Center.

  8. Bolivia. The new nuclear research center in El Alto

    Energy Technology Data Exchange (ETDEWEB)

    Nogarin, Mauro

    2016-05-15

    Research reactors in Latin America have become a priority in public policy in the last decade. Bolivia wants to become the 8th country to implement peaceful nuclear technology in this area with the new Center for Research and Development in the Nuclear Technology. The Center will be the most advanced in Latin America. It will provide for a wide use of radiation technologies in agriculture, medicine, and industry. After several negotiations Bolivia and the Russian Federation signed the Intergovernmental Agreement on cooperation in the peaceful use of atomic energy and the construction of the Nuclear Research and Technology Center.

  9. Emergency control centers for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    Guidance is provided for the development and implementation of emergency control centers for nuclear power plants, including nuclear plant control room, nuclear plant company headquarters, emergency control center, and nuclear plant alternate emergency control center. Requirements and recommendations are presented for the mission, communications, instrumentation and equipment associated with each type of control center. Decisional aids, manning requirements and resources are also given; the decision aids cover both the accident assessment and protective action areas. Both normal and alternate means of communications are considered. Off-site emergency control centers, although not covered in the strict sense by this standard, are considered in an appendix

  10. 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)

  11. 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.

  12. 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

  13. Hanford Nuclear Energy Center study

    International Nuclear Information System (INIS)

    Harty, H.

    1976-01-01

    Studies of a Nuclear Energy Center (NEC) at Hanford have not revealed any insurmountable technical problems, but problems have been identified that appear to be more difficult to resolve than for dispersed siting. Major technical developments in meteorology, and probably in seismology, are needed before an environmental report or safety analysis report could be prepared for an NEC. It would be helpful in further NEC studies if licensing requirements (and related criteria) were defined for them. An NEC will likely cause a step change in the amount of planning and involvement of regional groups in the energy picture compared to dispersed siting. The tools that must be developed for analysis of NECs will probably be used for evaluating dispersed siting in greater detail. NECs will probably bring about the use of dry or wet/dry cooling before it is required in equivalent amount for dispersed plants

  14. Hanford Nuclear Energy Center study

    Energy Technology Data Exchange (ETDEWEB)

    Harty, H.

    1976-03-16

    Studies of a Nuclear Energy Center (NEC) at Hanford have not revealed any insurmountable technical problems, but problems have been identified that appear to be more difficult to resolve than for dispersed siting. Major technical developments in meteorology, and probably in seismology, are needed before an environmental report or safety analysis report could be prepared for an NEC. It would be helpful in further NEC studies if licensing requirements (and related criteria) were defined for them. An NEC will likely cause a step change in the amount of planning and involvement of regional groups in the energy picture compared to dispersed siting. The tools that must be developed for analysis of NECs will probably be used for evaluating dispersed siting in greater detail. NECs will probably bring about the use of dry or wet/dry cooling before it is required in equivalent amount for dispersed plants.

  15. Radiation-induced centers in inorganic glasses

    International Nuclear Information System (INIS)

    Brekhovskikh, S.M.; Tyul'nin, V.A.

    1988-01-01

    The nature, structure and formation mechanisms of radiation-induced colour centers, EPR, luminescence, generated ionizing radiation in nonorganic oxide glasses are considered. Experimental material covering both fundamental aspects of radiation physics and glass chemistry, and aspects intimately connected with the creation of new materials with the given radiation-spectral characteristics, with possibilities to prepare radiation-stable and radiation-sensitive glasses is systematized and generalized. Considerable attention is paid to the detection of radiation-induced center binding with composition, glass structures redox conditions for their synthesis. Some new possibilities of practical application of glasses with radiation-induced centers, in particular, to record optical information are reflected in the paper

  16. Current status of Hiroshima Synchrotron Radiation Center

    International Nuclear Information System (INIS)

    Taniguchi, Masaki

    2000-01-01

    The Hiroshima Synchrotron Radiation Center is a common facility for both research and education in the field of synchrotron radiation science. The role of the center is to promote original research, training of young scientists, international exchange and cooperative research with neighbouring universities, public organizations and industries. (author)

  17. 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

  18. 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

  19. Weight Estimate and Centers of Gravity for JT-11 Nuclear Conversion Study

    International Nuclear Information System (INIS)

    Manning, R. W.

    1958-01-01

    Weight estimates and centers of gravity for the JT-11 nuclear conversion study are tabulated. Included in the radiator section are: diffuser, shrouds, supports, radiator, liquid metal, shafting and casing.

  20. Radiation protection in nuclear medicine

    International Nuclear Information System (INIS)

    Seeburrun, V.

    2013-04-01

    Radiation protection in nuclear medicine in this project is concerned with the reduction of doses to workers, patients and members of the public. Protection of workers is achieved by adopting good personal habits, good housekeeping, proper use of personal protective devices and equipment, attend training and have continuous education. Exposure to radiation of workers and the members of the public are minimised by proper management of radioactive waste and safe transport of radioactive material. The design and shielding of a nuclear medicine department shall further provide for the protection of the worker, the patient and the general public. Protection of patient is achieved by justifying the procedure, delivering the minimum radiation dose possible to the patient while obtaining the best image quality and applying guidance levels. Special considerations shall be given to pregnant and breast-feeding patients. Quality assurance programme through image quality, radiopharmaceutical quality and patient records on nuclear medicine procedures shall provide assurance to the patient. (au)

  1. Karlsruhe nuclear research center. Main activities

    International Nuclear Information System (INIS)

    The article reports on problems of securing the fuel supply for nuclear power generation, on reprocessing and ultimate storage of radioactive material, on the safety of nuclear facilities, on new technologies and basic research, and on the infrastructure of the Karlsruhe nuclear research center, as well as finance and administration. (HK) [de

  2. Activities planning of Nuclear Data Center - 1980

    International Nuclear Information System (INIS)

    Nair, R.P.K.

    1980-01-01

    The main process systems of nuclear data files and the actual nuclear data processing implantation in the Instituto de Estudos Avancados, are presented. The research activities of Nuclear Data Center during 1980 in relation to the implantation of file process systems for multigroup cross sections, and the calculations of integral reactor parameters, are described. (M.C.K.) [pt

  3. 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

  4. 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)

  5. Argentina, regional training center on radiation protection for Latin America

    International Nuclear Information System (INIS)

    Terrado, Carlos A.; Menossi, Carlos A.

    2008-01-01

    Argentina has an extensive background in education and training on Radiation Protection. Since the beginning of the nuclear activity in the country, prominence was given to the aspects related to radiation protection and training of the personnel involved in the use of ionizing radiation. These educative activities have been delivered for more than 50 years, having accumulated an important experience in the field. The Nuclear Regulatory Authority has the statutory obligation to address, among other matters, the control of the aspects of nuclear safety and radiation protection on the whole country, to protect the people of the harmful effects of ionizing radiation resulting from the nuclear activities. This includes the responsibility to develop and enforce the regulations, standards and other requirements, particularly, establishing the requests and promoting activities regarding education and training on radiation protection. Argentina, currently through the Nuclear Regulatory Authority, has performed postgraduate courses on radiation protection and nuclear safety at inter regional and regional level for 28 years without interruption. This important experience has been valued and exploited to form a Regional Center on Education and Training for Latin America and the Caribbean, sponsored by the International Atomic Energy Agency. The Regional Center that in fact has been running in Argentina, trained 404 foreign participants and 327 local participants since 1980, totalizing 731 graduates from our annual post graduate courses. Our commitment is that all the effort made in education and training on radiation protection and nuclear safety contributes to a better use of the benefits of nuclear development. Since 2001 the International Atomic Energy Agency raised the need to develop plans and establish agreements to ensure a long-term sustainability of the education and training programs, allowing a better use of the resources in this area. In order to achieve this goal

  6. ELBE Center for High-Power Radiation Sources

    Directory of Open Access Journals (Sweden)

    Peter Dr. Michel

    2016-01-01

    Full Text Available In the ELBE Center for High-Power Radiation Sources, the superconducting linear electron accelerator ELBE, serving  two free electron lasers, sources for intense coherent THz radiation, mono-energetic positrons, electrons, γ-rays, a neutron time-of-flight system as well as two synchronized ultra-short pulsed Petawatt laser systems are collocated. The characteristics of these beams make the ELBE center a unique research instrument for a variety of external users in fields ranging from material science over nuclear physics to cancer research, as well as scientists of the Helmholtz-Zentrum Dresden-Rossendorf (HZDR.

  7. Nuclear information services at the National Nuclear Data Center

    International Nuclear Information System (INIS)

    Burrows, T.W.; Tuli, J.K.

    1997-01-01

    The National Nuclear Data Center (NNDC) at the Brookhaven National Laboratory has maintained and disseminated data from several numeric and bibliographic data bases for many years. These data bases now cover most of low- and medium-energy nuclear physics and are produced by the NNDC and other groups belonging to various international and national networks. The numeric and bibliographic nuclear data bases maintained by the National Nuclear Data Center and access to these data bases is described. The U.S. Nuclear Data and Reaction Data Networks is also briefly described. (author)

  8. Activities of the Nuclear Data Center

    International Nuclear Information System (INIS)

    Fuketa, Toyojiro

    1978-01-01

    The present status of international cooperation system for the nuclear data activities is introductorily explained in outline. The Nuclear Data Center of Japan Atomic Energy Research Institute is presently the only public data center in the field of nuclear data in Japan, and it has the following scope of the works: evaluation of the nuclear data, compilation of the Japanese Evaluated Nuclear Data Library (JENDL), application of the data including benchmark tests, development of the data storage, retrieval and processing systems, data service to the users, secretariat of the Japanese Nuclear Data Committee, and international cooperation. An introduction to the use of nuclear data is given with a brief information on the availability of the data and with some matters that demand special attention. (auth.)

  9. Rhabdomyosarcoma: The Experience of the Pediatric Unit of Kasr El-Aini Center of Radiation Oncology and Nuclear Medicine (NEMROCK) (from January 1992 to January 2001)

    International Nuclear Information System (INIS)

    Abdel Aal, H.H.; Habib, E.E.; Mishrif, M.M.

    2006-01-01

    Our present study is a retrospective analysis of the treatment results of new rhabdomyosarcoma pediatric patients who had attended the pediatric unit clinic of Kasr El-Aini Center of Radiation Oncology and Nuclear Medicine (NEMROCK) from January 1992 to January 200 I). Patients and Methods: Fifty-five new cases of pediatric rhabdomyosarcoma attended the pediatric unit outpatient clinic of (NEMROCK) from the period of January 1992 until January 200 I. Patients were divided into 4 stages and classified into low-risk patients and high-risk patients according to the extent of resection. Stage I, II orbital and stage I para-testicular embryonal rhabdomyosarcomas received 32 weeks of vincristine and actinomycin-D (vincristine 1.5 mg/m 2 weekly, actinomycin-D 0.015 mg/ Kg/day day 1 to day 5). Other pathologies, sites and stages received 52 weeks of chemotherapy. Chemotherapy regimens included VAC (vincristine 1.5 mg/m 2 weekly, actinomycin-D 0.015 mg/Kg/day day 1 to day 5 and endoxan 2.2 gm/m 2 LV with mesna every 21 days), VAl (vincristine, actinomycin-D and ifosfamide 1.8 gm/m2 l.V day 1 to day 5 with mesna) or VIE (vincristine, ifosfamide and vepesid 100 mg/m 2 1. V day 1 to day 5) [11,12]. Stages I and II received conventional fractionation radiotherapy 4140 c Gy on week 13, stages Ill and IV received conventional fractionation radiation therapy 5040 c Gy also, on week 13. The radiation volume included the tumor bed with a 2 cm safety margin at least. Relapsing cases received palliative radiation therapy and chemotherapy (cisplatinum LV 100 mg/m 2 divided over 2 days and vepesid 100 mg/m2 l.V day 1 to day 3 to be recycled every 21 days). Patients were followed-up for 5 years, with a median follow-up of 36 months. Overall survival, disease free survival, treatment response, and complications of treatment were assessed and statistically analyzed. Results: Fifty-five new cases of pediatric rhabdomy-osarcoma attended the pediatric unit outpatient clinic of (NEMROCK) and

  10. Radiation Detection Center on the Front Lines

    International Nuclear Information System (INIS)

    Hazi, A

    2005-01-01

    Many of today's radiation detection tools were developed in the 1960s. For years, the Laboratory's expertise in radiation detection resided mostly within its nuclear test program. When nuclear testing was halted in the 1990s, many of Livermore's radiation detection experts were dispersed to other parts of the Laboratory, including the directorates of Chemistry and Materials Science (CMS); Physics and Advanced Technologies (PAT); Defense and Nuclear Technologies (DNT); and Nonproliferation, Arms Control, and International Security (NAI). The RDC-- was formed to maximize the benefit of radiation detection technologies being developed in 15 to 20 research and development (R and D) programs. These efforts involve more than 200 Laboratory employees across eight directorates, in areas that range from electronics to computer simulations. The RDC's primary focus is the detection, identification, and analysis of nuclear materials and weapons. A newly formed outreach program within the RDC-- is responsible for conducting radiation detection workshops and seminars across the country and for coordinating university student internships. Simon Labov, director of the RDC, says, ''Virtually all of the Laboratory's programs use radiation detection devices in some way. For example, DNT uses radiation detection to create radiographs for their work in stockpile stewardship and in diagnosing explosives; CMS uses it to develop technology for advancing the detection, diagnosis, and treatment of cancer; and the Energy and Environment Directorate uses radiation detection in the Marshall Islands to monitor the aftermath of nuclear testing in the Pacific. In the future, the National Ignition Facility will use radiation detection to probe laser targets and study shock dynamics.''

  11. International nuclear service centers: a bibliography

    International Nuclear Information System (INIS)

    Petty, G.M.; Yokota, M.

    1978-03-01

    The literature relating specifically to international nuclear fuel service centers would appear to be relatively scarce, based on the results of searches of the Energy Data Base, the libraries of the University of California at Los Angeles, and The Rand Corporation, and other sources. Works specifically relating to international service centers are annotated in this bibliography. Also listed, without annotation, are studies of various kinds of multinational public enterprises. In addition, there are references to many of the studies of the one-nation nuclear energy center concept. Most of these resulted from the survey of possible sites for these centers mandated by the US Energy Reorganization Act of 1974

  12. 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.

  13. 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

  14. Information on the Karlsruhe Nuclear Research Center

    International Nuclear Information System (INIS)

    Reuter, H.H.

    1980-01-01

    A short overview is given about the origins of Karlsruhe Nuclear Research Center. The historical development of the different companies operating the Center is shown. Because the original task assigned to the Center was the construction and testing of the first German reactor exclusively built by German companies, a detailed description of this reactor and the changes made afterwards is presented. Next, today's organizational structure of the Center is outlined and the development of the Center's financing since its foundation is shown. A short overview about the structure of employees from the Center's beginning up to now is also included as well as a short description of today's main activities. (orig.)

  15. Nuclear research center transformation experience

    International Nuclear Information System (INIS)

    Diaz, J. L.; Jimenez, J. M.

    2001-01-01

    As consequence of the changes in the energy polities of each countries in the 80th. many of the Nuclear Research Centres suffered a transformation (more of less deep) in other Research and Development Centres with a wider spectrum that the exclusively nuclear one. This year is the 50 anniversary of the Spanish Centre of Nuclear Research-Junta de Energia Nuclear.The JEN the same as other suffered a deep renovation to become the CIEMAT Centro de Investigaciones Energeticas Medioambientales y Tecnologicas (Research Centre for Energy, Environment and Technology). This paper is focussed on the evolution of JEN to CIEMAT besides analysing the reach of this re-foundation considering the political reasons and technical aspect that justified it and the laws in those it is based on. (Author)

  16. Nuclear Research Center Karlsruhe, Central Safety Department. Annual report 1992

    International Nuclear Information System (INIS)

    Koelzer, W.

    1993-05-01

    The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, biophysics of multicellular systems, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1992 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

  17. Karlsruhe Nuclear Research Center, Central Safety Department. Annual report 1993

    International Nuclear Information System (INIS)

    Koelzer, W.

    1994-04-01

    The Central Safety Department is responsible for handling all tasks of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: behavior of trace elements in the environment and decontamination of soil, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurements and personnel dosimetry. This report gives details of the different duties, indicates the results of 1993 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

  18. 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.

  19. Radiation shield for nuclear reactors

    International Nuclear Information System (INIS)

    Weissenfluh, J.A.

    1978-01-01

    A shield for use with nuclear reactor systems to attenuate radiation resulting from reactor operation is described. The shield comprises a container preferably of a thin, flexible or elastic material, which may be in the form of a bag, a mattress, a toroidal segment or toroid or the like filled with radiation attenuating liuid. Means are provided in the container for filling and draining the container in place. Due to its flexibility, the shield readily conforms to irregularities in surfaces with which it may be in contact in a shielding position

  20. China Nuclear Data Center (CNDC) status report

    International Nuclear Information System (INIS)

    Zhuang Youxiang

    2002-01-01

    This paper is the status report of the China Nuclear Data Center, Beijing. It describes the nuclear data evaluation, the validation of CENDL-3.0, the CINDA and EXFOR compilation and gives a list of meetings in this subject area. (a.n.)

  1. National Nuclear Data Center status report

    International Nuclear Information System (INIS)

    2002-01-01

    This paper is the status report of the US National Nuclear Data Center, Brookhaven. It describes the new NDS approach to customer services, which is based on users initiating wish lists on topics of interest with the possibility to receive reports in hardcopy or electronically forms. After completion within the next two years of the multi platform software for management and data retrievals from shared databases, users will have the opportunity to install directly their own local nuclear data center for desktop applications. The paper describes the computer facilities, the nuclear reaction data structure, the database migration and the customer services. (a.n.)

  2. Radiation color and electron-hole centers of serpentines

    International Nuclear Information System (INIS)

    Lyutoev, V.P.; Yukhtanov, P.P.

    1999-01-01

    Radiation-induced coloring of serpentine (Mg 3 [Si 2 O 5 ](OH) 4 ), gamma radiation dose being 30 Mrad, is studied by the ESR and absorption spectroscopy methods. It is ascertained that ionizing radiation gives rise to formation of radiation centers on the mineral basic structural elements. paramagnetic centers and coloring centers, relating to radiation centers, stem from the same type of defects - O - oxygen centers, formed as a result of radiation-induced break of OH-bonds [ru

  3. Status Report of JAEA Nuclear Data Center

    International Nuclear Information System (INIS)

    Fukahori, T.

    2011-01-01

    Nuclear Data Center of Japan Atomic Energy Agency (JAEA) is working on the nuclear data evaluation for Japanese Evaluated Nuclear Data Library JENDL. The evaluation and related works are performed in the cooperation with Universities, Research Organizations and Companies in Japan through Japanese Nuclear Data Committee. The number of Nuclear Data Center staff members is 7 including one technical assistant as of April 1, 2011. The manpower is not enough for the evaluation and related work. The budget is obtained from MEXT (Ministry of Education, Culture, Sports, Science and Technology), but is annually decreasing after establishment of JAEA. Especially the budget must be much shorter than usual in 2011FY, since many of it will be spent for recovering after the earthquake. We are seeking another fund to compensate the decreasing budget.

  4. Status Report of JAEA Nuclear Data Center

    International Nuclear Information System (INIS)

    Fukahori, T.

    2012-01-01

    Nuclear Data Center of Japan Atomic Energy Agency (JAEA) is working on the nuclear data evaluation for Japanese Evaluated Nuclear Data Library JENDL. The evaluation and related works are performed in the cooperation with Universities, Research Organizations and Companies in Japan through Japanese Nuclear Data Committee. The number of Nuclear Data Center staff members is 7 including one technical assistant as of April 1, 2012. The manpower is not enough for the evaluation and related work. The budget is obtained from Ministry of Education, Culture, Sports, Science and Technology (MEXT), but is annually decreasing after establishment of JAEA. Especially the budget must be much shorter than usual in 2012FY, since many of it will be spent for recovering after the earthquake and Fukushima accident. We are seeking another fund to compensate the decreasing budget.

  5. Nuclear medicine: the Philippine Heart Center experience

    International Nuclear Information System (INIS)

    Cancino, E.L.

    1994-01-01

    The following is a report of a three (3) months on-the-job training in Nuclear Medicine at the Nuclear Medicine Department of the Philippine Heart Center. The hospital has current generation nuclear medicine instruments with data processor and is capable of a full range of in vivo and in vitro procedures. Gamma camera is the principal instrument for imaging in nuclear medicine used in the Philippine Heart Center. Thyroid scanning procedure is being performed with these instruments. Also the cardiovascular procedures, the pulmonary, skeletal, renal and hepatobiliary procedures were being performed with the use of gamma camera. Special emphasis is on nuclear cardiology since the PHC attends primarily to cardiovascular patients. (auth.)

  6. Centro Regional de Ciencias Nucleares (a Brazilian regional center for nuclear sciences) - activities report - 1999

    International Nuclear Information System (INIS)

    1999-12-01

    The annual activities report of 1999 of nuclear sciences regional center - Brazilian organization - introduces the next main topics: institutional relations; sectorial actions - logistic support and training, laboratory of radiation protection and dosimetry, laboratory of metrology, laboratory of chemical characterization; technical and scientific events; and financial resources and perspectives for 2000

  7. Radiation protection at the Cadarache research center

    International Nuclear Information System (INIS)

    Anon.

    2015-01-01

    This article recalls the French law about radiation protection and its evolution due to the implementation of the 2013/59-EURATOM directive that separates the missions of counsel from the more operative missions of the person appointed as 'competent in radiation protection'. The organisation of the radiation protection of the Cadarache research center is presented. The issue of sub-contracting and the respect of an adequate standard of radioprotection is detailed since 2 facilities operated by AREVA are being dismantled on the site. (A.C.)

  8. International nuclear data centers and the nuclear data center of Instituto de Estudos Avancados

    International Nuclear Information System (INIS)

    Corcuera, R.P.; Nair, R.P.K.; Santos, R. dos

    1985-01-01

    The nuclear data centers existent in the world and their areas, of responsability are presented. The efforts made by the Instituto de Estudos Avancados of Centro Tecnico Aeroespacial, in Brazil to create a local nuclear data center are presented. (M.C.K.) [pt

  9. 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

  10. 2010/11 Status Report of China Nuclear Data Center

    International Nuclear Information System (INIS)

    Ge, Zhigang

    2011-01-01

    China Nuclear Data Center (CNDC) was established in 1975 and joined the nuclear data activities of IAEA as the national nuclear data center of China since 1984. The main task of CNDC: The nuclear data evaluations, libraries and relevant technique researches. The exchange of nuclear data activities with IAEA, foreign nuclear data centers and agencies. The management of domestic nuclear data activities. The services for domestic and foreign nuclear data users.

  11. Business of Nuclear Safety Analysis Office, Nuclear Technology Test Center

    International Nuclear Information System (INIS)

    Hayakawa, Masahiko

    1981-01-01

    The Nuclear Technology Test Center established the Nuclear Safety Analysis Office to execute newly the works concerning nuclear safety analysis in addition to the works related to the proving tests of nuclear machinery and equipments. The regulations for the Nuclear Safety Analysis Office concerning its organization, business and others were specially decided, and it started the business formally in August, 1980. It is a most important subject to secure the safety of nuclear facilities in nuclear fuel cycle as the premise of developing atomic energy. In Japan, the strict regulation of safety is executed by the government at each stage of the installation, construction, operation and maintenance of nuclear facilities, based on the responsibility for the security of installers themselves. The Nuclear Safety Analysis Office was established as the special organ to help the safety examination related to the installation of nuclear power stations and others by the government. It improves and puts in order the safety analysis codes required for the cross checking in the safety examination, and carries out safety analysis calculation. It is operated by the cooperation of the Science and Technology Agency and the Agency of Natural Resources and Energy. The purpose of establishment, the operation and the business of the Nuclear Safety Analysis Office, the plan of improving and putting in order of analysis codes, and the state of the similar organs in foreign countries are described. (Kako, I.)

  12. Idaho national laboratory - a nuclear research center

    International Nuclear Information System (INIS)

    Zaidi Mohammed, K.

    2006-01-01

    Full text: The Idaho National Laboratory (INL) is committed to providing international nuclear leadership for the 21st Century, developing and demonstrating compelling national security technologies, and delivering excellence in science and technology as one of the United States Department of Energy's (DOE) multi program national laboratories. INL runs three major programs - Nuclear, Security and Science. Nuclear programs covers the Advanced test reactor, Six Generation IV technology concepts selected for Rand D, targeting tumors - Boron Neutron Capture therapy. Homeland Security establishes the Control System Security and Test Center, Critical Infrastructure Test Range evaluates technologies on a scalable basis, INL conducts high performance computing and visualization research and science. To provide leadership in the education and training, INL has established an Institute of Nuclear Science and Engineering (INSE) under the Center for Advanced Energy Studies (CAES) and the Idaho State University (ISU). INSE will offer a four year degree based on a newly developed curriculum - two year of basic science course work and two years of participation in project planning and development. The students enrolled in this program can continue to get a masters or a doctoral degree. This summer INSE is the host for the training of the first international group selected by the World Nuclear University (WNU) - 75 fellowship holders and their 30 instructors from 40 countries. INL has been assigned to provide future global leadership in the field of nuclear science and technology. Here, at INL, we keep safety first above all things and our logo is 'Nuclear leadership synonymous with safety leadership'. (author)

  13. 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

  14. 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

  15. 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

  16. 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.)

  17. 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

  18. 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

  19. Sociopolitical ramifications of nuclear energy centers

    International Nuclear Information System (INIS)

    Meier, P.M.

    1977-01-01

    The sociopolitical ramifications of nuclear energy centers, as emerging from a case study in Ocean County, New Jersey, are examined from the standpoint of identifying key issues of public controversy, and with emphasis on implications for national energy planning and the course of nuclear debate. Various dimensions of institutional tension are analyzed, including interstate issues and federal preemption, and the ability of the institutional and political framework to address the many equity issues that are exacerbated by clustered siting. The evolution of public attitudes, and the subsequent mobilization of effective political channels in opposition to proposed NEC's are discussed in light of New Jersey experience. The degree to which energy centers affect public attitudes to nuclear power is identified as the key issue requiring further analysis before widespread implementation of the concept can be advocated

  20. Nuclear power for an urban center

    International Nuclear Information System (INIS)

    de Pass, V.E.

    1976-01-01

    In recent years public concern over the effects of nuclear power plants on the environment has led to organized opposition to proposed plants, to changes in the radiation standards and licensing procedures of the Nuclear Regulatory Commission (NRC), formerly the Atomic Energy Commission (AEC), and to federal and state legislation, referenda, and numerous lawsuits. Unfortunately, movement has been slow toward an overall federal program for licensing nuclear power plants and the NRC does not have the sole responsibility for environmental regulations. It is therefore imperative that an interagency impasse not be permitted to develop in which the Nuclear Regulatory Commission is allowed to proceed with its NEPA reviews but the Environmental Protection Agency is not obligated in any way to abide by the Commission's findings

  1. Proceedings of the First Seminar on Radiation Safety Technology and Nuclear Biomedicine

    International Nuclear Information System (INIS)

    Suprihadi, Topo

    2003-01-01

    The First Seminar on Radiation Safety Technology and Nuclear Biomedicine was held on 10-11 April 2001 at the Center for Research and Development of Radiation Safety and Nuclear Biomedicine have presented 19 papers about upgrading manpower resources, researcher, investigator, manager, and user of nuclear facilities, to go out against free market era

  2. Nuclear energy center site survey reactor plant considerations

    International Nuclear Information System (INIS)

    1976-05-01

    The Energy Reorganization Act of 1974 required the Nuclear Regulatory Commission (NRC) to make a nuclear energy center site survey (NECSS). Background information for the NECSS report was developed in a series of tasks which include: socioeconomic inpacts; environmental impact (reactor facilities); emergency response capability (reactor facilities); aging of nuclear energy centers; and dry cooled nuclear energy centers

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  4. 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

  5. Scientific activities 1980 Nuclear Research Center ''Democritos''

    International Nuclear Information System (INIS)

    1982-01-01

    The scientific activities and achievements of the Nuclear Research Center Democritos for the year 1980 are presented in the form of a list of 76 projects giving title, objectives, responsible of each project, developed activities and the pertaining lists of publications. The 16 chapters of this work cover the activities of the main Divisions of the Democritos NRC: Electronics, Biology, Physics, Chemistry, Health Physics, Reactor, Scientific Directorate, Radioisotopes, Environmental Radioactivity, Soil Science, Computer Center, Uranium Exploration, Medical Service, Technological Applications, Radioimmunoassay and Training. (N.C.)

  6. Radiation protection courses in the Milan Copic Nuclear Training Centre

    International Nuclear Information System (INIS)

    Kozelj, M.; Stritar, A.

    1998-01-01

    We have briefly described the legal framework for the radiation protection training in Slovenia. The history of that activity at the Milan Copic Nuclear Training Center in Ljubljana is than described with the detailed description and summary of all performed courses.(author)

  7. Design of instrument for monitoring nuclear radiation and baneful gas

    International Nuclear Information System (INIS)

    Xiong Jianping; Chen Jun; Zhu Wenkai

    2006-01-01

    Counters and ionization chambers are applied to sensors, and microprocessor based on ARM IP is applied to center controller in the instrument. It is achieved to monitor nuclear radiation and baneful gas in an instrument. The instrument is capable of LCD displaying, menu operating and speech alarming. (authors)

  8. Meteorological evaluation of multiple reactor contamination probabilities for a Hanford Nuclear Energy Center

    International Nuclear Information System (INIS)

    Ramsdell, J.V.; Diebel, D.I.

    1978-03-01

    The conceptual Hanford energy center is composed of nuclear power plants, hence the name Hanford Nuclear Energy Center (HNEC). Previous topical reports have covered a variety of subjects related to the HNEC including: electric power transmission, fuel cycle, and heat disposal. This report discusses the probability that a radiation release from a single reactor in the HNEC would contaminate other facilities in the center. The risks, in terms of reliability of generation, of this potential contamination are examined by Clark and Dowis

  9. Nuclear Research Center IRT reactor dynamics calculation

    International Nuclear Information System (INIS)

    Aleman Fernandez, J.R.

    1990-01-01

    The main features of the code DIRT, for dynamical calculations are described in the paper. With the results obtained by the program, an analysis of the dynamic behaviour of the Research Reactor IRT of the Nuclear Research Center (CIN) is performed. Different transitories were considered such as variation of the system reactivity, coolant inlet temperature variation and also variations of the coolant velocity through the reactor core. 3 refs

  10. 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

  11. 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

  12. 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

  13. 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)

  14. 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)

  15. 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)

  16. Idaho National Laboratory - Nuclear Research Center

    International Nuclear Information System (INIS)

    Zaidi, M.K.

    2005-01-01

    Full text: The Idaho National Laboratory is committed to the providing international nuclear leadership for the 21st Century, developing and demonstrating compiling national security technologies, and delivering excellence in science and technology as one of the United States Department of Energy's (DOE) multiprogram national laboratories. INL runs three major programs - Nuclear, Security and Science. nuclear programs covers the Advanced test reactor, Six Generation technology concepts selected for R and D, Targeting tumors - Boron Neutron capture therapy. Homeland security - Homeland Security establishes the Control System Security and Test Center, Critical Infrastructure Test Range evaluates technologies on a scalable basis, INL conducts high performance computing and visualization research and science - INL facility established for Geocentrifuge Research, Idaho Laboratory, a Utah company achieved major milestone in hydrogen research and INL uses extremophile bacteria to ease bleaching's environmental cost. To provide leadership in the education and training, INL has established an Institute of Nuclear Science and Engineering (Inset). The institute will offer a four year degree based on a newly developed curriculum - two year of basic science course work and two years of participation in project planning and development. The students enrolled in this program can continue to get a masters or a doctoral degree. This summer Inset is the host for the training of the first international group selected by the World Nuclear University (WNU) - 75 fellowship holders and their 30 instructors from 40 countries. INL has been assigned to provide future global leadership in the field of nuclear science and technology. Here, at INL, we keep safety first above all things and our logo is 'Nuclear leadership synonymous with safety leadership'

  17. 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)

  18. 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.

  19. Computerized based training in nuclear safety in the nuclear research center Negev

    International Nuclear Information System (INIS)

    Ben-Shachar, B.; Krubain, H.; Sberlo, E.

    2002-01-01

    The Department of Human Resources and Training in the Nuclear Research Center, Negev, in collaboration with the Department of Radiation Protection and Safety used to organize different kinds of training and refresher courses for different aspects of safety in nuclear centers (radiation safety, biological effects of ionizing radiation, industrial safety, fire fighting, emergency procedures, etc.). All radiation workers received a training program of several days in all these subjects, each year. The administrative employees received a shorter training, each second year. The training included only frontal lectures and no quiz or exams were done. No feedback of the employees was received after the training, as well. Recently, a new training program was developed by the NRC-Negev and the CET (Center for Educational Technology), in order to perform the refresher courses. The training includes CBT-s (Computer Based Training), e.g. tutorials and quiz. The tutorial is an interactive course in one subject, including animations, video films and photo stills. The employee gets a simple and clear explanation (including pictures). After each tutorial there is a quiz which includes 7 American style questions. In the following lecture different parts from two of the tutorials used for the refresher courses, will be presented

  20. Radiation protection in nuclear reactors

    International Nuclear Information System (INIS)

    El-Ashkar, Mohamed

    2008-01-01

    Full text: People are exposed to ionizing radiation in many different forms: cosmic rays that penetrate earth atmosphere or radiation from soil and mineral resources are natural forms of ionizing radiation. Other forms are produced artificially using radioactive materials for various beneficial applications in medicine, industry and other fields. The greatest concerns about ionizing radiation are tied to its potential health effects and a system of radiation protection has been developed to protect people from harmful radiation. The promotion of radiation protection is one of the International Atomic Energy Agency main activities. Radiation protection concerns the protection of workers, members of public, and patients undergoing diagnosis and therapy against the harmful effects of ionizing radiation. The report covers the responsibility of radiation protection officer in Egypt Second Research Reactor (ETRR-2) in Inshas - Egypt, also presents the protection against ionizing radiation from external sources, including types of radiation, sources of radiation (natural - artificial), and measuring units of dose equivalent rate. Also covers the biological effects of ionizing radiation, personal monitoring and radiation survey instruments and safe transport of radioactive materials. The report describes the Egypt Second Research Reactor (ETRR-2), the survey instruments used, also presents the results obtained and gave a relations between different categories of data. (author)

  1. 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)

  2. International Nuclear Safety Center (INSC) database

    International Nuclear Information System (INIS)

    Sofu, T.; Ley, H.; Turski, R.B.

    1997-01-01

    As an integral part of DOE's International Nuclear Safety Center (INSC) at Argonne National Laboratory, the INSC Database has been established to provide an interactively accessible information resource for the world's nuclear facilities and to promote free and open exchange of nuclear safety information among nations. The INSC Database is a comprehensive resource database aimed at a scope and level of detail suitable for safety analysis and risk evaluation for the world's nuclear power plants and facilities. It also provides an electronic forum for international collaborative safety research for the Department of Energy and its international partners. The database is intended to provide plant design information, material properties, computational tools, and results of safety analysis. Initial emphasis in data gathering is given to Soviet-designed reactors in Russia, the former Soviet Union, and Eastern Europe. The implementation is performed under the Oracle database management system, and the World Wide Web is used to serve as the access path for remote users. An interface between the Oracle database and the Web server is established through a custom designed Web-Oracle gateway which is used mainly to perform queries on the stored data in the database tables

  3. 7. Annual seminar of the scientific initiation of the Center for Development of Nuclear Technology. Abstracts

    International Nuclear Information System (INIS)

    2012-01-01

    This seminar presents the Scientific Initiation Program developed at the CDTN - Brazilian Center for the Development of Nuclear Technology and focuses on activities of the sectors of: radiopharmaceutical production; radiation applied to health; waste management; structural integrity; environment; nanotechnology and nuclear materials; reactor technology; mineral technology; reactor and analytical techniques

  4. Capabilities for Clinical Management of Radiation Injuries of the Nikiforov Russian Center of Emergency and Radiation Medicine (EMERCOM of Russia)

    International Nuclear Information System (INIS)

    Aleksanin, S.

    2016-01-01

    This article presents an overview of the capabilities for clinical management of radiation injuries available at the Nikiforov Russian Center of Emergency and Radiation Medicine (NRCERM) of the Ministry of the Russian Federation for Civil Defense, Emergencies and Elimination of Consequences of Natural Disasters (EMERCOM). NRCERM is a federal state budgetary institution and the Russian Federation's head organization for providing medical assistance for persons overexposed to ionizing radiation, responders to radiation emergencies and people evacuated from radiation contaminated areas. As the WHO Collaborating Center for Treatment and Rehabilitation of Accident Recovery Workers of Nuclear and Other Disasters and a member of the WHO Radiation Emergency Medical Preparedness and Assistance Network (REMPAN), NRCERM is prepared to provide assistance and technical support in case of a radiation accident. For this purpose, NRCERM hospitals are equipped with technologically advanced facilities and possess well-trained specialist staff. (authors)

  5. 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)

  6. 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.

  7. 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.

  8. 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)

  9. 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)

  10. The first symposium of Research Center for Radiation Safety, NIRS. Perspective of future studies of radiation safety

    International Nuclear Information System (INIS)

    Shimo, Michikuni

    2002-03-01

    This paper summarizes presentations given in the title symposium, held at the Conference Room of National Institute of Radiological Sciences (NIRS) on November 29 and 30, 2001. Contained are Introductory remarks: Basic presentations concerning exposure dose in man; Environmental levels of radiation and radioactivity, environmental radon level and exposure dose, and radiation levels in the specific environment (like in the aircraft): Special lecture (biological effects given by space environment) concerning various needs for studies of radiation safety; Requirement for open investigations, from the view of utilization, research and development of atomic energy, from the clinical aspect, and from the epidemiological aspect: Special lecture (safety in utilization of atomic energy and radiation-Activities of Nuclear Safety Commission of Japan) concerning present state and perspective of studies of radiation safety; Safety of radiation and studies of biological effects of radiation-perspective, and radiation protection and radiation safety studies: Studies in the Research Center for Radiation Safety; Summary of studies in the center, studies of the biological effects of neutron beam, carcinogenesis by radiation and living environmental factors-complicated effects, and studies of hereditary effects: Panel discussion (future direction of studies of radiation safety for the purpose of the center's direction): and concluding remarks. (N.I.)

  11. 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.)

  12. 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.

  13. 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)

  14. 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)

  15. 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.

  16. 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

  17. 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)

  18. Nuclear radiation detection by a variband semiconductor

    International Nuclear Information System (INIS)

    Volkov, A.S.

    1981-01-01

    Possibilities of using a variband semiconductor for detecting nuclear radiations are considered. It is shown that the variaband quasielectric field effectively collects charges induced by a nuclear particle only at a small mean free path in the semiconductor (up to 100 μm), the luminescence spectrum of the variband semiconductor when a nuclear particle gets into it, in principle, permits to determine both the energy and mean free path in the semiconductor (even at large mean free paths) [ru

  19. Radiation protection in nuclear energy. V.1

    International Nuclear Information System (INIS)

    1988-01-01

    The conference was convened to provide a forum for the exchange of international views on the principles of radiation protection for regulators and practitioners, to highlight issues of current importance, to examine the problems encountered in applying the principles of radiation protection, and, where possible, to identify generic solutions. A special session entitled ''The dose-response relationship: implications for nuclear energy'', and a panel on ''Radiation protection education and training'' were included in the conference programme. Refs, figs and tabs

  20. 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

  1. 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)

  2. Nuclear data for radiation shielding

    International Nuclear Information System (INIS)

    Miyasaka, Shunichi; Takahashi, Hiroshi.

    1976-01-01

    The third shielding expert conference was convened in Paris in Oct. 1975 for exchanging informations about the sensitivity evaluation of nuclear data in shielding calculation and integral bench mark experiment. The requirements about nuclear data presented at present from the field of nuclear design do not reflect sufficiently the requirements of shielding design, therefore it was the object to gather the requirements about nuclear data from the field of shielding. The nuclides used for shielding are numerous, and the nuclear data on these isotopes are required. Some of them cannot be ignored as the source of secondary γ-ray or in view of the radioactivation of materials. The requirements for the nuclear data of neutrons in the field of shielding are those concerning the reaction cross sections producing secondary γ-ray, the reaction cross sections including the production of secondary neutrons, elastic scattering cross sections, and total cross sections. The topics in the Paris conference about neutron shielding data are described, such as the methodology of sensitivity evaluation, the standardization of group constant libraries, the bench mark experiment on iron and sodium, and the cross section of γ-ray production. In the shielding of nuclear fission reactors, the γ-ray production owing to nuclear fission reaction is also important. In (d, t) fusion reactors, high energy neutrons are generated, and high energy γ-ray is emitted through giant E1 resonance. (Kako, I.)

  3. Russian Federal Nuclear Center VNIIEF - possibilities of international cooperation

    International Nuclear Information System (INIS)

    Shaburov, V.M.; Mozharov, R.V.

    2000-01-01

    The Russian Federation Nuclear Center - the All-Russian Experimental Physics Research Institute (RFNC-AREPRI; VNIIEF) is a major scientific-technical center of Russia capable of solving the most difficult problems in the interests of defense, science and the national economy. There was a time when the RFNC-AREPRI played a decisive role in liquidating the U.S. monopoly on nuclear weapons and ensuring half a century of world civilization without global political and military conflicts. Today, RFNC-AREPRI specialists are entrusted with the mission of maintaining and perfecting Russia's nuclear shield that ensures its security and independence. As well as defense-oriented projects, the Institute is busy developing and implementing a number of projects in the most diverse fields of science and technology. At present, the Institute possesses an experimental and testing base that includes: a gas dynamic complex for testing manufactured products and explosives, irradiation facilities, nuclear reactors, laser systems, complexes for mechanical, temperature and climatic testing of specific manufactured products and instruments, and an aero-ballistic testing complex. The Institute's material base, with its mathematical support, is one of the most powerful in Russia. The RFNC-AREPRI employs about 20,000 workers, including 9,500 scientists and engineers. Today, the RFNC-AREPRI is engaged in activities in the following principal directions: - properties of material under extreme pressure and temperature; - gas dynamics; - nuclear physics; - radiation physics; - laser physics and equipment; - super-powerful magnetic fields; - high-temperature plasma physics; - development of physical models of complex physical processes and the creation of mathematical methodologies and software based on these models; - energy; - medicine; - ecology; - progressive technologies for various sectors of the economy. International cooperation of the RFNC-AREPRI is reviewed. (authors)

  4. Hanford Nuclear Energy Center: a conceptual study

    Energy Technology Data Exchange (ETDEWEB)

    Harty, H. (comp.)

    1978-09-30

    The objective of the study is to develop an improved understanding of the nuclear energy center (NEC) concept and to identify research and development needed to evaluate the concept fully. A specific context was selected for the study--the Hanford site. Thus, the study primarily addresses the HNEC concept, but the findings are extrapolated to generic NECs where possible. The major emphasis in the HNEC study was to explore potential technical and environmental problems in a specific context and in sufficient detail to evaluate potential problems and propose practical solutions. The areas of concern are typical of those considered in preparing environmental and safety analysis reports, including: topics dealing with engineering choices (e.g., site selection, heat sink management, electrical transmission, and reliability of generation); environmental matters (e.g., terrestrial and radiological effects); socioeconomic factors (e.g., community impacts); and licensing considerations.

  5. Radiation hazards of nuclear engineering

    International Nuclear Information System (INIS)

    Oster, H.

    1981-01-01

    The basic mechanisms and principles of nuclear power plants are discussed, since their knowledge is mandatory for the understanding of the true risk associated with nuclear technology. Differences between predictable and catastrophic accidents are compared, terms which have been frequently confused to the extent that the public has become unjustifiably and irresponsibly alarmed. A description of the jobs and their responsibilities is also given. Known accidents are reported and the role of the physician in the care of accidents and the scheduling of emergency situations is described. Finally, the usefullness, necessity and risk associated with nuclear power are discussed. (orig.) [de

  6. 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)

  7. Nuclear Radiation and the Thyroid

    Science.gov (United States)

    ... told to evacuate? Nuclear releases are unpredictable and traffic jams are likely to delay speedy evacuation. People ... patient information section on the American Thyroid Association ® website at www.thyroid.org .

  8. Nuclear Criticality Experimental Research Center (NCERC) Overview

    Energy Technology Data Exchange (ETDEWEB)

    Goda, Joetta Marie [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Grove, Travis Justin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hayes, David Kirk [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Myers, William L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sanchez, Rene Gerardo [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-03-03

    The mission of the National Criticality Experiments Research Center (NCERC) at the Device Assembly Facility (DAF) is to conduct experiments and training with critical assemblies and fissionable material at or near criticality in order to explore reactivity phenomena, and to operate the assemblies in the regions from subcritical through delayed critical. One critical assembly, Godiva-IV, is designed to operate above prompt critical. The Nuclear Criticality Experimental Research Center (NCERC) is our nation’s only general-purpose critical experiments facility and is only one of a few that remain operational throughout the world. This presentation discusses the history of NCERC, the general activities that makeup work at NCERC, and the various government programs and missions that NCERC supports. Recent activities at NCERC will be reviewed, with a focus on demonstrating how NCERC meets national security mission goals using engineering fundamentals. In particular, there will be a focus on engineering theory and design and applications of engineering fundamentals at NCERC. NCERC activities that relate to engineering education will also be examined.

  9. Memphis State University Center for Nuclear Studies progress report

    International Nuclear Information System (INIS)

    1976-01-01

    This quarterly report outlines the progress made by the Center for Nuclear Studies at Memphis State University in the development of specialized educational programs for the nuclear industry through the month of February, 1976

  10. 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

  11. Integrated Support Center for Nuclear Nonproliferation and Security

    International Nuclear Information System (INIS)

    Kimura, Naohito; Naoi, Yosuke

    2010-01-01

    In April 2010, at the Nuclear Security Summit, Japan demonstrated its commitment to the strengthening of nuclear non-proliferation and nuclear security and announced the establishment of the Integrated Comprehensive Support Center for Nuclear Non-proliferation and Nuclear Security in the Japan Atomic Energy Agency (JAEA), under the guidance and authority of the Ministry of Education, Culture, Sports and Science and Technology (MEXT), and in cooperation with other ministries. The goal of the Center is to strengthen nuclear non-proliferation and security in emerging nuclear power countries by sharing Japan's accumulated experiences in its peaceful use of nuclear energy. To achieve its goal, the Center serves three functions: (1) human resource and capacity building, (2) infrastructure development and technical assistance and (3) international coordination and cooperation. The Center will offer three types of training courses to strengthen human resources and capacity building in emerging nuclear power countries. In the Training Course on Nuclear Security, the participants will learn the design and evaluation process for physical protection and detection of and response to illegal or unauthorized acts related to nuclear materials. They will learn these issues not only through lectures and training but also using mockup facilities and virtual reality systems. Second, in the Training Course on Safeguards and State System of Accounting for and Control of Nuclear Material (SSAC), the Center will teach the experience of advanced safeguards activities in Japan for its full-scale nuclear fuel cycle facilities as a non-nuclear weapon state. The participants will learn the IAEA and national safeguards systems, the material accounting system and inspector activities. Third, in the Training on the International Nuclear Nonproliferation Framework, the participants will learn the international framework of nuclear non-proliferation including the IAEA safeguards system and

  12. Regional nuclear fuel cycle centers study project

    International Nuclear Information System (INIS)

    Bennett, L.; Catlin, R.G.; Meckoni, V.

    1977-01-01

    The concept of regional fuel cycle centers (RFCC) has attracted wide interest. The concept was endorsed by many countries in discussions at the General Conference of the International Atomic Energy Agency and at the General Assembly of the United Nations. Accordingly, in 1975, the IAEA initiated a detailed study of the RFCC concept. The Agency study has concentrated on what is referred to as the ''back-end'' of the fuel cycle because that is the portion which is currently problematic. The study covers transport, storage, processing and recycle activities starting from the time the spent fuel leaves the reactor storage pools and through all steps until the recycled fuel is in finished fuel elements and shipped to the reactor. A detailed evaluation of the specific features of large regional fuel cycle centers established on a multinational basis vis-a-vis smaller dispersed fuel cycle facilities set up on a national basis has been carried out. The methodology for assessment of alternative strategies for fuel storage, reprocessing, and recycling of plutonium has been developed, characteristic data on material flows and cost factors have been generated, and an analytic system has been developed to carry out such evaluations including appropriate sensitivity analysis. Studies in related areas on institutional and legal, organizational, environmental, materials control and other essential aspects have also been made. The material developed during the course of this Study would enable any group of interested Member States to examine and work out alternative strategies pertinent to their present and projected nuclear fuel cycle needs, as well as evolve institutional, legal and other appropriate frameworks or agreements for the establishment of fuel cycle centers on a multinational cooperative basis

  13. 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

  14. 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

  15. Activities of the USSR Nuclear Data Center

    International Nuclear Information System (INIS)

    Usachev, L.M.; Popov, V.J.

    1972-01-01

    In any activity, one must start with the determination of its usefulness: in the field of nuclear data, this consists in the compilation of request lists, analogous to the RENDA list, issued in cooperation by the CCDN and the Nuclear Data Center of the N. D. S. At Obninsk, we have a somewhat different approach for our RENDA entries. We do not ask our reactor physicists to formulate their requests for concrete microscopic measurements or to share the requested accuracies between the different needed cross sections, because they are not really specialists in this field. We ask them to formulate their requirements, based on technical and economical considerations, for the tolerable uncertainties on the reactor parameters which are, of course, linked to the uncertainties on nuclear data. In addition, we ask them to give us the sensitivity coefficients for the values of reactor parameters as a function of modifications of the nuclear data. These sensitivity coefficients include all the needed information concerning the reactor in view of the determination of the requirements on nuclear data. The problem of the determination of the set of measurements necessary to obtain the reactor parameters with the required accuracies must, from our point of view be treated mathematically by specialists of the planification theory, working in close connection with specialists of microscopic data measurements and of integral experiments. In order to work out an optimal planing, it is necessary to evaluate the relative costs of the experiments; it is also essential to evaluate correctly the correlations between the uncertainties of the measurements and the estimation of their costs. Moreover, we may know all the information concerning the present accuracy on the measurements of a given type, first of all for a comparative evaluation of the costs of the experiments and, secondly, for drawing conclusions on the possible necessity for more accurate values by comparing the accuracies which

  16. Russian center of nuclear science and education is the way of nuclear engineering skilled personnel training

    International Nuclear Information System (INIS)

    Murogov, V.M.; Sal'nikov, N.L.

    2006-01-01

    Nuclear power engineering as the key of nuclear technologies is not only the element of the power market but also the basis of the country's social-economic progress. Obninsk as the first science town in Russia is the ideal place for the creation of integrated Science-Research Center of Nuclear Science and Technologies - The Russian Center of Nuclear Science and Education (Center for conservation and development of nuclear knowledge) [ru

  17. International nuclear safety center database on material properties

    International Nuclear Information System (INIS)

    Fink, J.K.

    1996-01-01

    International nuclear safety center database on the following material properties is described: fuel, cladding,absorbers, moderators, structural materials, coolants, concretes, liquid mixtures, uranium dioxide

  18. 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

  19. 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

  20. 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)

  1. 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

  2. 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)

  3. 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

  4. 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.

  5. Radiation shield for nuclear reactors

    International Nuclear Information System (INIS)

    Weissenfluh, J.A.

    1980-01-01

    A reusable radiation shield for use in a reactor installation comprises a thin-walled, flexible and resilient container, made of plastic or elastomeric material, containing a hydrogenous fluid with boron compounds in solution. The container can be filled and drained in position and the fluid can be recirculated if required. When not in use the container can be folded and stored in a small space. The invention relates to a shield to span the top of the annular space between a reactor vessel and the primary shield. For this purpose a continuous toroidal container or a series of discrete segments is used. Other forms can be employed for different purposes, e.g. mattress- or blanket-like forms can be draped over potential sources of radiation or suspended from a mobile carrier and placed between a worker and a radiation source. (author)

  6. 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

  7. Personal radiation protection in nuclear industry

    International Nuclear Information System (INIS)

    Gol'dshtejn, D.S.; Koshcheev, V.S.

    1983-01-01

    Specific peculiarities of organization of personal radiation protection at various nuclear industry enterprises when dealing with radioactive and other toxic substances are illuminated. Effect of heatin.g and cooling microclimate is discussed. Medical and technical requirements for personal protection means and tasks of personal protection in the field of nuclear industry are considered in short along with some peculiarities of application of different kinds of personal protection means and psychological aspects of personnel protection

  8. Natural radiation, nuclear wastes and chemical pollutants

    International Nuclear Information System (INIS)

    Christensen, T.; Ehdwall, H.; Stranden, E.

    1990-01-01

    Doses from natural radiation to the population in the Nordic Countries are summarized and man made modifications of the natural radiation environment are discussed. An account is given of the radiological consequences of energy conservation by reduced ventilation. Risks from possible future releases of radioactivity from final repositories of spent nuclear fuel are compared to the risks from present natural radioactivity in the environment. The possibilities for comparison between chemical and radiological risks are discussed. (author) 13 refs

  9. 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)

  10. Radiation detector for use in nuclear reactors

    International Nuclear Information System (INIS)

    Cisco, T.C.; Grimaila, A.G.

    1981-01-01

    A multi-sensor radiation detection system for removable insertion into a nuclear reactor is described in which one conductor of all the sensors is a single, common element. This single common element is contained within a tubular metallic sheath and in crosssection comprises a multiple radial armed metallic conductor having a star shaped cross-section dimensioned to form wedgeshaped compartments throughout the active radiation detecting length of the metallic sheath

  11. Annual report of nuclear technology and education center. April 1, 2002 - March 31, 2003

    International Nuclear Information System (INIS)

    2003-10-01

    This report summarizes the activities of Nuclear Technology and Education Center (NuTEC) in Japan Atomic Energy Research Institute in FY 2002. It includes the domestic educational activities in Tokyo Education Center in Komagome Tokyo for RI and radiation engineers and Tokai Education Center in Tokai for nuclear engineers, and the international training activities for Asia-Pacific region which were planned and administrated by International Technology Transfer Division. The new course so called 'Introductory Course for the Use and the Experiment of Neutron' was started with good appreciation by the participants. All scheduled course plan in Tokyo Education Center and Tokai Education Center was accomplished and the total number of the trainee of both Center was 1,297. The courses for RI and radiation engineers implemented in Tokyo Education Center were closed in this FY and transferred to Tokai Establishment in next FY where the course will be integrated with the ones at Tokai Education Center. The land of Tokyo Education Center will be returned to land-owner by the end of FY 2003 after dismantlement of the facilities. The equipments and instruments used in Tokyo Education Center were transferred to Tokai Education Center after finishing all courses in Tokyo in this FY. The improvement and re-arrangement of the facilities in Tokyo Education Center were proceeded to prepare the courses from Tokyo Education Center. (author)

  12. 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)

  13. 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

  14. Electronic detection of nuclear radiations

    International Nuclear Information System (INIS)

    Campos, J.

    1972-01-01

    This report is the first draft of one of the chapters of a book being prepared under the title: Topics on Practical Nuclear Physics. It is published as a report because of i ts immediate educational value and in order to include in its final draft the suggestions of the readers. (Author)

  15. Offshore heat dissipation for nuclear energy centers

    International Nuclear Information System (INIS)

    Bauman, H.F.

    1978-09-01

    The technical, environmental, and economic aspects of utilizing the ocean or other large water bodies for the dissipation of reject heat from Nuclear Energy Centers (NECs) were investigated. An NEC in concept is an aggregate of nuclear power plants of 10 GW(e) capacity or greater on a common site. The use of once-through cooling for large power installations offers advantages including higher thermal efficiencies, especially under summer peak-load conditions, compared to closed-cycle cooling systems. A disadvantage of once-through cooling is the potential for greater adverse impacts on the aquatic environment. A concept is presented for minimizing the impacts of such systems by placing water intake and discharge locations relatively distant from shore in deeper water than has heretofore been the practice. This technique would avoid impacts on relatively biologically productive and ecologically sensitive shallow inshore areas. The NEC itself would be set back from the shoreline so that recreational use of the shore area would not be impaired. The characteristics of a heat-dissipation system of the size required for a NEC were predicted from the known characteristics of a smaller system by applying hydraulic scaling laws. The results showed that adequate heat dissipation can be obtained from NEC-sized systems located in water of appropriate depth. Offshore intake and discharge structures would be connected to the NEC pump house on shore via tunnels or buried pipelines. Tunnels have the advantage that shoreline and beach areas would not be disturbed. The cost of an offshore heat-dissipation system depends on the characteristics of the site, particularly the distance to suitably deep water and the type of soil or rock in which water conduits would be constructed. For a favorable site, the cost of an offshore system is estimated to be less than the cost of a closed-cycle system

  16. Biological effects of nuclear radiation

    International Nuclear Information System (INIS)

    Hotz, G.

    1975-01-01

    After a brief survey about the main radiobiological effects caused by ionizing radiation, human symptoms after irradiation and incorporation are shown. The special radiotoxic effect of radionuclides which are chemically associated with metabolism-specific elements such as calcium and potassium is shown and methods of treatment are indicated. (ORU) [de

  17. 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)

  18. 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

  19. 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

  20. National Nuclear Center of the Republic of Kazakhstan

    International Nuclear Information System (INIS)

    Tukhvatulin, Sh.T.

    2001-01-01

    The fact that the 20th century became a thing of the past was important for Kazakhstan from the view of territory and state establishment. This year the Republic of Kazakhstan celebrates 10 years of independence. After the USSR breakup in 1991, Kazakh SSR became a sovereign state that inherited the unique test complex Semipalatinsk Nuclear Test Site, the pride of the entire Soviet people in the past. For the first time in the history of nuclear weapon (one of mass destruction types) creation, development and partial elimination the test site created for testing such weapons was eliminated. The Republic of Kazakhstan declared itself a non-nuclear state and started solving such complicated problems as the possibility to use the territory of the former nuclear test site in the national economy. For this it was necessary to start work on nuclear test infrastructure elimination and this work commenced. Great assistance in conduction of such work has been and is rendered by the specialists from the USA, different international organizations, for example, IAEA, NATO etc. In order to determine whether it's possible to transfer the test site territory to national economy it is necessary not only to eliminate tests infrastructure but also to obtain reliable data on the dimensions and degree of radioactive contamination of the territory within and outside the test site borders. National Nuclear Center specialists working in close cooperation with many Kazakhstan and International Organizations contributed much to studies on radioecological situation at the former STS territory and regions adjoining it, as well as to radiation parameter data obtaining process. The problems of Semipalatinsk test site are in focus of the State. At the Second UN General Assembly, the President of Kazakhstan pointed out this problem and appealed to the International Community to solve it in cooperation. In order to implement Resolution 52/169M of UN General Assembly 'on international cooperation

  1. Nuclear energy center finance and ownership considerations

    International Nuclear Information System (INIS)

    Morris, J.A.; Wilder, R.P.

    1980-09-01

    Finance and ownership alternatives for a nuclear energy center (NEC) in South Carolina are analyzed in the context of the capital market and tax differences among alternatives. The ownership alternatives considered are (1) the private or private/public joint venture, (2) full public ownership and (3) a hybrid ownership form featuring federal involvement in the initial site development and permit phase, followed by a transition to private ownership. Public ownership is associated with considerably lower out-of-pocket costs than private ownership; the difference between the two, however, is related to subsidies from other parts of society to electricity customers of a publicly owned NEC. The attitudes of participating utilities on ownership forms are examined, with the finding of general strong opposition to increased federal involvement in the electric utility industry through NEC ownership. The conclusion is that the private-private/public joint venture is the preferable ownership form and that public ownership should be employed only if the private sector fails to respond to future energy demand

  2. Power components behavior under nuclear radiations

    International Nuclear Information System (INIS)

    Jaureguy, J.C.; Azais, B.

    1989-01-01

    Many apparatus, either fixed or on-board of vehicles, use power converters. The most common scheme includes chopper with bipolar transistors. In case of nuclear radiations, these equipments may be severely damaged. Depending on the disturbance level, the need for changes in power transistor technology has to be considered or not [fr

  3. Radiation Protection, Nuclear Safety and Security

    International Nuclear Information System (INIS)

    Faye, Ndeye Arame Boye; Ndao, Ababacar Sadikhe; Tall, Moustapha Sadibou

    2014-01-01

    Senegal has put in place a regulatory framework which allows to frame legally the use of radioactive sources. A regulatory authority has been established to ensure its application. It is in the process of carrying out its regulatory functions. It cooperates with appropriate national or international institutions operating in fields related to radiation protection, safety and nuclear safety.

  4. Nuclear Bragg diffraction using synchrotron radiation

    International Nuclear Information System (INIS)

    Rueffer, R.; Gerdau, E.; Grote, M.; Hollatz, R.; Roehlsberger, R.; Rueter, H.D.; Sturhahn, W.

    1990-01-01

    Nuclear Bragg diffraction with synchrotron radiation as source will become a powerful new X-ray source in the A-region. This source exceeds by now the brilliance of conventional Moessbauer sources giving hyperfine spectroscopy further momentum. As examples applications to yttrium iron garnet (YIG) and iron borate will be discussed. (author)

  5. Nuclear Forensics and Radiochemistry: Radiation Detection

    Energy Technology Data Exchange (ETDEWEB)

    Rundberg, Robert S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-11-08

    Radiation detection is necessary for isotope identification and assay in nuclear forensic applications. The principles of operation of gas proportional counters, scintillation counters, germanium and silicon semiconductor counters will be presented. Methods for calibration and potential pitfalls in isotope quantification will be described.

  6. Nuclear Forensics and Radiochemistry: Radiation Detection

    International Nuclear Information System (INIS)

    Rundberg, Robert S.

    2017-01-01

    Radiation detection is necessary for isotope identification and assay in nuclear forensic applications. The principles of operation of gas proportional counters, scintillation counters, germanium and silicon semiconductor counters will be presented. Methods for calibration and potential pitfalls in isotope quantification will be described.

  7. Nuclear radiation moisture gauge calibration standard

    International Nuclear Information System (INIS)

    Berry, R.L.

    1981-01-01

    A hydrophobic standard for calibrating radiation moisture gauges is described. This standard has little or no affinity for water and accordingly will not take up or give off water under ambient conditions of fluctuating humidity in such a manner as to change the hydrogen content presented to a nuclear gauge undergoing calibration. (O.T.)

  8. 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

  9. 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)

  10. Imaging plates for nuclear radiations

    International Nuclear Information System (INIS)

    Abe, Ken; Takebe, Masahiro

    1997-01-01

    Full text. The imaging plate (IP, hereafter) is a new opto-electronic X-ray film developed by Fuji Photo Film Co. Ltd., formed with a large area of thin flexible plastic plate coated with photo-estimulable storage phosphor (e.g. Ba F Br: Eu 2+ ). Recently, it has been found highly sensitive to soft X-ray (SR), soft electrons, and also usual alpha, beta, gamma rays and others, e.g. cosmic rays, energy heavy ions, and moreover neutrons through suitable converters inside or outside of the IP. Many types of IP are now used in various fields, such as medical examinations, auto-radiography in vivo/ in situ/ in vitro, X-ray/neutron diffraction/ radiography, electron microscopy. RI contamination, assay of ore. The IP has other striking performances, e.e. extremely low intrinsic noises, a high position resolution, high detection efficiency (100-1000 times) as high as an X-ray film), extremely wide dynamic range of dose (more than 10 5 ). Besides the thermal fading yet left unresolved materially, the only feature lacking and that one has ben longing for is the radiation identification by itself. We found out that the IP has a full potential ability of radiation identification in itself. One evidence found is that the ratio of the twin peaks of the PSL (photo-stimulated luminescence) excitation spectra indicates simply the particle energies, studied and now established. Another is that the photo-beaching provides the fluorescent responses different enough to discriminate the radiations, yet in progress with cyclotron experiments, into the usage of double labeled bio tracers

  11. 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

  12. Nuclear energy center site survey: fuel cycle studies

    International Nuclear Information System (INIS)

    1976-05-01

    Background information for the Nuclear Regulatory Commission Nuclear Energy Center Site Survey is presented in the following task areas: economics of integrated vs. dispersed nuclear fuel cycle facilities, plutonium fungibility, fuel cycle industry model, production controls and failure contingencies, environmental impact, waste management, emergency response capability, and feasibility evaluations

  13. Nuclear safety and radiation protection in France in 2011

    International Nuclear Information System (INIS)

    2012-01-01

    The first part of this voluminous report describe the different ASN (Nuclear Safety Authority) actions: nuclear activities (ionising radiation and health and environmental risks), principles and stakeholders in nuclear safety regulation, radiation protection and protection of the environment, regulation, regulation of nuclear activities and exposure to ionizing radiation, radiological emergencies, public information and transparency, international relations. It also gives an overview of nuclear safety and radiation protection activities in the different French regions. The second part addresses activities regulated by the ASN: medical uses of ionizing radiation, non-medical uses of ionizing radiation, transport of radioactive materials, nuclear power plants, nuclear fuel cycle installations, nuclear research facilities and various nuclear installations, safe decommissioning of basic nuclear installations, radioactive waste and contaminated sites and soils

  14. Dynamical nuclear polarization using multi-colour control of color centers in diamond

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Pengcheng [Huazhong University of Science and Technology, School of Physics, Wuhan (China); Huazhong University of Science and Technology, Center for Quantum Optical Science, Wuhan (China); Plenio, Martin B. [Universitaet Ulm, Institut fuer Theoretische Physik, Ulm (Germany); Universitaet Ulm, Center for Integrated Quantum Science and Technology, Ulm (Germany); Cai, Jianming [Huazhong University of Science and Technology, School of Physics, Wuhan (China); Huazhong University of Science and Technology, Center for Quantum Optical Science, Wuhan (China); Universitaet Ulm, Institut fuer Theoretische Physik, Ulm (Germany); Universitaet Ulm, Center for Integrated Quantum Science and Technology, Ulm (Germany)

    2016-12-15

    Dynamical nuclear polarization (DNP) transfers the polarization of electron spins at cryogenic temperatures to achieve strong nuclear polarization for applications in nuclear magnetic resonance. Recently introduced approaches employ optical pumping of nitrogen-vacancy (NV) centers in diamond to achieve DNP even at ambient temperatures. In such schemes microwave radiation is used to establish a Hartmann-Hahn condition between the NV electron spin and proximal nuclear spins to facilitate polarization transfer. For a single monochromatic microwave driving field, the Hartmann-Hahn condition cannot be satisfied for an ensemble of NV centers due to inhomogeneous broadening and reduces significantly the overall efficiency of dynamical nuclear polarization using an ensemble of NV centers. Here, we adopt generalized Hartmann-Hahn type dynamical nuclear polarization schemes by applying microwave driving fields with (multiple) time-modulated frequencies. We show that it is possible to enhance the effective coupling between an ensemble of NV center spins with inhomogeneous broadening and nuclear spins, thereby improving significantly the overall efficiency of dynamical nuclear polarization. This approach can also be used to achieve dynamical nuclear polarization of an ensemble of nuclei with a distribution of Larmor frequencies, which would be helpful in magnetic resonance spectroscopy using a single NV spin sensor. (orig.)

  15. Radiation Emergency Preparedness Tools: Virtual Community Reception Center

    Centers for Disease Control (CDC) Podcasts

    2011-02-28

    This podcast is an overview of resources from the Clinician Outreach and Communication Activity (COCA) Call: Practical Tools for Radiation Emergency Preparedness. A specialist working with CDC's Radiation Studies Branch describes a web-based training tool known as a Virtual Community Reception Center (vCRC).  Created: 2/28/2011 by National Center for Environmental Health (NCEH) Radiation Studies Branch and Emergency Risk Communication Branch (ERCB)/Joint Information Center (JIC); Office of Public Health Preparedness and Response (OPHPR).   Date Released: 2/28/2011.

  16. Environmental Radiation Monitoring Around the Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Geun Sik; Lee, Chang Woo

    2008-05-15

    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, Uraniu and Strontium in environmental samples showed a environmental level. The radioactivities of most {gamma}-radionuclides in air particulate, surface water and ground water were less than MDA except {sup 40}K or {sup 7}Be which are natural radionuclides. However, not only {sup 40}K or {sup 7}Be but also {sup 137}Cs were detected at the background level in surface soil, discharge sediment and fallout or pine needle.

  17. Citation buidelines for nuclear data retrieved from databases resident at the Nuclear Data Centers Network

    International Nuclear Information System (INIS)

    McLane, V.

    1996-07-01

    The Nuclear Data Centers Network is a world-wide cooperation of nuclear data centers under the auspices of the International Atomic Energy Agency. The Network organizes the task of collecting, compiling, standardizing, storing, assessing, and distributing the nuclear data on an international scale. Information available at the Centers includes bibliographic, experimental, and evaluated databases for nuclear reaction data and for nuclear structure and radioactive decay data. The objective of the Network is to provide the information to users in a convenient, readily-available form. To this end, online data services have been established at three of the centers: the National Nuclear Data Center (NNDC), the Nuclear Data Section of the International Atomic Energy Agency (NDS), and the OECD Nuclear Energy Agency Data Bank (NEADB). Some information is also available at the NNDC and NEADB World Wide Web sites

  18. Centro Regional de Ciencias Nucleares (a Brazilian regional center for nuclear sciences) - activities report - 1999; Centro Regional de Ciencias Nucleares - relatorio de atividades - 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-01

    The annual activities report of 1999 of nuclear sciences regional center - Brazilian organization - introduces the next main topics: institutional relations; sectorial actions - logistic support and training, laboratory of radiation protection and dosimetry, laboratory of metrology, laboratory of chemical characterization; technical and scientific events; and financial resources and perspectives for 2000.

  19. Nuclear energy, radiation and environment

    International Nuclear Information System (INIS)

    Rajan, M.P.

    2013-01-01

    Over the past few decades, energy has been the subject of much debate. Energy is the backbone of technology and economic development. Today, most machines run on electricity and they are needed to make anything and everything. Hence, our energy requirements have spiraled in the years following the industrial revolution. This rapid increase in use of energy has created problems of demand and supply in addition to the environmental consciousness which picked momentum in last decades of 20 th century. The impending crisis the world over due to overuse of nonrenewable energy sources to reduce this gap shall soon lead to a situation for all concerned to take a prudent decision to tap other sources of energy, including relatively new renewable sources. Future economic growth crucially depends on the long-term availability of energy from sources that are affordable, accessible and environmentally friendly. The drive for more energy has had the happy consequences of spawning new technologies and improving earlier ones. Emphasis on renewable sources has resulted in viable harnessing of solar, wind and tidal energies. Even though these sources offer relatively clean energy, their potential to supply reliable energy in large scale in an economically viable way is limited. Nuclear energy offers a major source of commercial energy, which is economic, reliable and environmentally benign

  20. Radiation protection in nuclear energy. V.2

    International Nuclear Information System (INIS)

    1988-01-01

    The conference was convened to provide a forum for the exchange of international views on the principles of radiation protection for regulators and practitioners, to highlight issues of current importance, to examine the problems encountered in applying the principles of radiation protection, and, where possible, to identify generic solutions. The highlights of the conference were the sessions on the interface between nuclear safety and radiation protection, the evolution of radiation protection principles, exemption rules and accident experiences. The special session on the practical implications of the linear dose-response relationships also provoked particular interest. Although the session on optimization and decision aiding did not reveal any new developments, it did indicate an increasing emphasis on the optimization of radiation protection. A clear trend towards attaining lower collective doses per unit practice over a given time period, despite the increase in nuclear power plant capacity, is also apparent, although very few data on job-related worker doses have been published to date in the open literature. From the regulators' viewpoint, a very strong desire was expressed for a move towards regulatory strategies that exempt practices and sources causing insignificant individual and collective doses. Refs, figs and tabs

  1. Nuclear Data Center International Standard Towards TSO Initiative

    International Nuclear Information System (INIS)

    Raja Murzaferi Raja Moktar; Mohd Fauzi Haris; Siti Nurbahyah Hamdan

    2011-01-01

    Nuclear Data Center is the main facility for Nuclear Malaysia Agency IT infrastructure comprising of main critical servers, research and operational data storage, HPC-clusters system and vital network core equipment. In recent years, international body such as TIA-Telecommunication Industry Association and Up time Institute have came out with proper international data center standards in order to ensure data center operation on achieving maximum operational up time and minimal downtime. The standard are currently being rated as tier level ranging from Data Center tier I up to tier IV, differentiate by facility standard and up time/ downtime percentage ratio. This paper will discuss Nuclear Data Center adopting international standards in supporting Nuclear Malaysia TSO initiative thus ensuring the critical core component of agency IT services availability and further more International standard recognitions. (author)

  2. Epidemiological studies on radiation carcinogenesis in human populations following acute exposure: nuclear explosions and medical radiation

    International Nuclear Information System (INIS)

    Fabrikant, J.I.

    1981-01-01

    The present review provides an understanding of our current knowledge of the carcinogenic effect of low-dose radiation in man, and surveys the epidemiological studies of human populations exposed to nuclear explosions and medical radiation. Discussion centers on the contributions of quantitative epidemiology to present knowledge, the reliability of the dose-incidence data, and those relevant epidemiological studies that provide the most useful information for risk estimation of cancer induction in man. Reference is made to dose-incidence relationships from laboratory animal experiments where they may obtain, for problems and difficulties in extrapolation from data obtained at high doses to low doses, and from animal data to the human situation. The paper describes the methods of application of such epidemiological data for estimation of excess risk of radiation-induced cancer in exposed human populations and discusses the strengths and limitations of epidemiology in guiding radiation protection philosophy and public health policy

  3. Radiation exposure in German nuclear power plants

    International Nuclear Information System (INIS)

    Mueller, W.

    1981-01-01

    The individual and collective doses in German nuclear power stations have decreased remarkably since the beginning of the commercial nuclear power production. The paper discusses the influencing factors, that have caused this development and points out areas where improvements are possible in the future. Moreover the interaction between radiation protection practice and the relevant legal regulations is considered. Usually the recording of job related doses is regarded as the most direct access to possible improvements. Concluding, it is therefore demonstrated by some examples how the evaluation of such information has taken effect in practice. (orig.) [de

  4. Some radiation chemical aspects of nuclear engineering

    International Nuclear Information System (INIS)

    Pikaev, A.K.; Kabakchi, S.A.; Egorov, G.F.

    1988-01-01

    Some radiation chemical aspects of nuclear engineering are discussed (predominantly on the base of the works performed in the Soviet Union). The data on the influence of temperature within the range of 0-300 0 C on the yields of water radiolysis products are considered. The results obtained from the study of reactivity of actinide ions towards inorganic free radicals in acid aqueous solutions are summarized. The information on composition and properties of the products of radiolytic transformations of different extragents and diluents and on their influence on the behaviour of extraction systems during processing of irradiated nuclear fuel is presented. (author)

  5. Radiation damage in nuclear waste ceramics

    International Nuclear Information System (INIS)

    Turcotte, R.P.; Roberts, F.P.; Rusin, J.M.; Wald, J.W.

    1982-01-01

    The text contains a number of specific observations about the radiation-induced changes in glass, glass-ceramic, and supercalcine nuclear waste forms. Other, more general conclusions can be summarized: Radiation-induced property changes follow an exponential ingrowth curve to saturation. Actinide host phases in both crystalline waste forms become X-ray amorphous. The magnitudes of the waste-form density changes observed could not be directly related to observed changes in the primary actinide phases. Although large crystal-structure changes occur in the materials studied, obvious physical degradation was not observed

  6. Ionizing radiation, nuclear energy and radiation protection for school

    International Nuclear Information System (INIS)

    Lucena, E.A.; Reis, R.G.; Pinho, A.S.; Alves, A.S.; Rio, M.A.P.; Reis, A.A.; Silva, J.W.S.; Paula, G.A. de; Goncalves Junior, M.A.

    2017-01-01

    Since the discovery of X-rays in 1895, ionizing radiation has been applied in many sectors of society, such as medicine, industry, safety, construction, engineering and research. However, population is unaware of both the applications of ionizing radiation and their risks and benefits. It can be seen that most people associate the terms 'radiation' and 'nuclear energy' with the atomic bomb or cancer, most likely because of warlike applications and the stealthy way radioactivity had been treated in the past. Thus, it is necessary to clarify the population about the main aspects related to the applications, risks and associated benefits. These knowledge can be disseminated in schools. Brazilian legislation for basic education provides for topics such as nuclear energy and radioactivity to high school students. However, some factors hamper such an educational practice, namely, few hours of class, textbooks do not address the subject, previous concepts obtained in the media, difficulty in dealing with the subject in the classroom, phobia, etc. One solution would be the approximation between schools and institutions that employ technologies involving radioactivity, which would allow students to know the practices, associated radiological protection, as well as the risks and benefits to society. Currently, with the increasing application of ionizing radiation, especially in medicine, it is necessary to demystify the use of radioactivity. (author)

  7. Survey of radiation protection, radiation transport, and shielding information needs of the nuclear power industry. Final report

    International Nuclear Information System (INIS)

    Maskewitz, B.F.; Trubey, D.K.; Roussin, R.W.; McGill, B.L.

    1976-04-01

    The Radiation Shielding Information Center (RSIC) is engaged in a program to seek out, organize, and disseminate information in the area of radiation transport, shielding, and radiation protection. This information consists of published literature, nuclear data, and computer codes and advanced analytical techniques required by ERDA, its contractors, and the nuclear power industry to improve radiation analysis and computing capability. Information generated in this effort becomes a part of the RSIC collection and/or data base. The purpose of this report on project 219-1 is to document the results of the survey of information and computer code needs of the nuclear power industry in the area of radiation analysis and protection

  8. Survey of radiation protection, radiation transport, and shielding information needs of the nuclear power industry. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Maskewitz, B.F.; Trubey, D.K.; Roussin, R.W.; McGill, B.L.

    1976-04-01

    The Radiation Shielding Information Center (RSIC) is engaged in a program to seek out, organize, and disseminate information in the area of radiation transport, shielding, and radiation protection. This information consists of published literature, nuclear data, and computer codes and advanced analytical techniques required by ERDA, its contractors, and the nuclear power industry to improve radiation analysis and computing capability. Information generated in this effort becomes a part of the RSIC collection and/or data base. The purpose of this report on project 219-1 is to document the results of the survey of information and computer code needs of the nuclear power industry in the area of radiation analysis and protection.

  9. Radiation monitor system for nuclear power plants

    International Nuclear Information System (INIS)

    Wu Bingzhe; Guo Shusheng

    1990-12-01

    The system has 8 kinds of radiation monitors and 2 stage microcomputers designed for processing the data from each monitor, storaging the information, printing out and displaying on the colour CRT. The function of the system includes high-value alarm, warm alarm and failure alarm, so called t hree-level alarms . Two functions of the alarms are the threshold alarm and the tendency alarm, so that this system is an intelligency system. This system has high reliability and very wide range when LOCA accident takes place. It is aseismic and immune to industrial interference. The system can meet IEC-761-1 standard and is of nuclear safety 3rd class. Also the following monitors were designed: 133 Xe monitor, 131 I monitor, low-level liquid monitor and high radiation γ area monitor. The system can meet the requirements of nuclear power plants

  10. Radiation protection at nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Endo, K.; Momose, T.; Furuta, S.

    2011-01-01

    Radiation protection methodologies concerning individual monitoring, workplace monitoring and environmental monitoring in nuclear fuel facilities have been developed and applied to facilities in the Nuclear Fuel Cycle Engineering Laboratories (NCL) of Japan Atomic Energy Agency (JAEA) for over 40 y. External exposure to photon, beta ray and neutron and internal exposure to alpha emitter are important issues for radiation protection at these facilities. Monitoring of airborne and surface contamination by alpha and beta/photon emitters at workplace is also essential to avoid internal exposure. A critical accident alarm system developed by JAEA has been proved through application at the facilities for a long time. A centralised area monitoring system is effective for emergency situations. Air and liquid effluents from facilities are monitored by continuous monitors or sampling methods to comply with regulations. Effluent monitoring has been carried out for 40 y to assess the radiological impacts on the public and the environment due to plant operation. (authors)

  11. Radiation control system of nuclear power plants

    International Nuclear Information System (INIS)

    Kapisovsky, V.; Kosa, M.; Melichar, Z.; Moravek, J.; Jancik, O.

    1977-01-01

    The SYRAK system is being developed for in-service radiation control of the V-1 nuclear power plant. Its basic components are an EC 1010 computer, a CAMAC system and communication means. The in-service release of radionuclides is measured by fuel can failure detection, by monitoring rare gases in the coolant, by gamma spectrometric coolant monitoring and by iodine isotopes monitoring in stack disposal. (O.K.)

  12. Radiation Emergency Preparedness Tools: Virtual Community Reception Center

    Centers for Disease Control (CDC) Podcasts

    This podcast is an overview of resources from the Clinician Outreach and Communication Activity (COCA) Call: Practical Tools for Radiation Emergency Preparedness. A specialist working with CDC's Radiation Studies Branch describes a web-based training tool known as a Virtual Community Reception Center (vCRC).

  13. Nuclear energy research in Germany 2008. Research centers and universities

    International Nuclear Information System (INIS)

    Tromm, Walter

    2009-01-01

    This summary report presents nuclear energy research at research centers and universities in Germany in 2008. Activities are explained on the basis of examples of research projects and a description of the situation of research and teaching in general. Participants are the - Karlsruhe Research Center, - Juelich Research Center (FZJ), - Dresden-Rossendorf Research Center (FZD), - Verein fuer Kernverfahrenstechnik und Analytik Rossendorf e.V. (VKTA), - Technical University of Dresden, - University of Applied Sciences, Zittau/Goerlitz, - Institute for Nuclear Energy and Energy Systems (IKE) at the University of Stuttgart, - Reactor Simulation and Reactor Safety Working Group at the Bochum Ruhr University. (orig.)

  14. Radiation safely culture in nuclear facilities

    International Nuclear Information System (INIS)

    Coates, R.

    2018-01-01

    The importance of developing a sound radiation safety culture is a relatively new development in the practical application of radiation protection in operational facilities. It is instructive to trace the evolution of the fundamental approaches to controlling operational exposures, staring with the engineering-based 'Distance, Shielding and Time' mantra, through the growing emphasis on ALARA and systematic management-based approaches, towards a recognition of the importance of developing a more 'hearts and minds' approach based within the wider safety culture of the organization. The underlying requirements for developing a strong radiation safety culture are not novel, and are largely identical to those necessary for nuclear safety culture, which is why an integrated approach to culture within the organization is essential

  15. Activities report 1991-1992: Nuclear Research Center of Strasbourg

    International Nuclear Information System (INIS)

    1993-01-01

    This activities report of the Nuclear Research Centre of Strasbourg for the years 1991 and 1992, presents nine research axis: theoretical physics, mechanisms of reactions and nuclear structure, extreme forms of nuclei, exotic nuclei, hot and dense nuclear matter, ultra-relativistic heavy ions, physics of LEP (European Large Electron-Positron storage ring) at 'DELPHI', chemistry and physics of radiations, physics and applications of semi-conductors

  16. Lightweight Radiator for in Space Nuclear Electric Propulsion

    Science.gov (United States)

    Craven, Paul; Tomboulian, Briana; SanSoucie, Michael

    2014-01-01

    Nuclear electric propulsion (NEP) is a promising option for high-speed in-space travel due to the high energy density of nuclear fission power sources and efficient electric thrusters. Advanced power conversion technologies may require high operating temperatures and would benefit from lightweight radiator materials. Radiator performance dictates power output for nuclear electric propulsion systems. Game-changing propulsion systems are often enabled by novel designs using advanced materials. Pitch-based carbon fiber materials have the potential to offer significant improvements in operating temperature, thermal conductivity, and mass. These properties combine to allow advances in operational efficiency and high temperature feasibility. An effort at the NASA Marshall Space Flight Center to show that woven high thermal conductivity carbon fiber mats can be used to replace standard metal and composite radiator fins to dissipate waste heat from NEP systems is ongoing. The goals of this effort are to demonstrate a proof of concept, to show that a significant improvement of specific power (power/mass) can be achieved, and to develop a thermal model with predictive capabilities making use of constrained input parameter space. A description of this effort is presented.

  17. Radiation emergency preparedness in nuclear power plants

    International Nuclear Information System (INIS)

    Geetha, P.V.; Ramamirtham, B.; Khot, P.

    2008-01-01

    The purpose of planning for radiation emergency response is to ensure adequate preparedness for protection of the plant personnel and members of the public from significant radiation exposures in the unlikely event of an accident. With a number of safety features in the reactor design and sound operating procedures, the probability of a major accident resulting in the releases of large quantities of radioactivity is extremely small. However, as an abundant cautious approach a comprehensive radiation emergency response preparedness is in place in all the nuclear power plants (NPPs). Radiation Emergency in NPPs is broadly categorized into three types; plant emergency, site emergency and off-site emergency. During off site emergency conditions, based on levels of radiation in the environment, Civil Authorities may impose several counter measures such as sheltering, administering prophylaxis (stable iodine for thyroid blocking) and evacuation of people from the affected area. Environmental Survey Laboratory (ESL) carries out environmental survey extensively in the affected sector identified by the meteorological survey laboratory. To handle emergency situations, Emergency Control Centre with all communication facility and Emergency Equipment Centre having radiation measuring instruments and protective equipment are functional at all NPPs. AERB stipulates certain periodicity for conducting the exercises on plant, site and off site emergency. These exercises are conducted and deficiencies corrected for strengthening the emergency preparedness system. In the case of off site emergency exercise, observers are invited from AERB and Crisis Management Group of Department of Atomic Energy (DAE). The emergency exercises conducted by Nuclear Power Plant Sites have been very satisfactory. (author)

  18. Secondary standard dosimetry laboratory Saraykoy Nuclear Research and Training Center Ankara, Turkey

    International Nuclear Information System (INIS)

    Okruhlica, P.

    2014-01-01

    Turkish Saraykoy Nuclear Research and Training Center (SANA) was founded in 2005. In 2014 the company PTW Freiburg in cooperation with VF Cerna Hora started the construction of a comprehensive national metrology laboratories of ionizing radiation 'Secondary Standard Dosimetry Laboratory' (SSDL). The laboratory will be located in the area of 'Saraykoy Nuclear Research and Training Center' in Ankara in Turkey. SSDL will be equipped with metrology departments for calibration and measurement of standard required quantities of metrology of ionizing radiation: - Neutron workplace; Gamma workplace (low-energy X-ray, gamma Standard Cs-137 and high dose rate, Co-60); - Beta workplace; - Control system of metrology laboratories and irradiation VF DARS; - Radiation monitoring system VF RMS; - Camera and security system; - Measuring instruments (ionization chambers, electrometers, monitors for environmental measurements ...) with the appropriate phantoms and other systems.

  19. Nuclear energy centers: Economic and environmental problems

    International Nuclear Information System (INIS)

    Dollezhal', N.A.; Bobolovich, V.N.; Emel'yanov, I.Ya.; Kochenov, A.S.; Koryakin, Yu.I.; Stolyarevskij, A.Ya.; Chernyaev, V.A.; Ponomarev-Stepnoj, N.N.; Protsenko, A.M.

    1977-01-01

    The report deals with qualitative and quantitative analysis of factors and problems, which may arise in the nearest future with the dispersion of sites of nuclear and fuel cycle plants. These problems arise with a large increase in the transportation of radioactive nuclear fuel, the necessity in valuable land and water resources, delay in construction and scheduled commercial operation of nuclear power plant, increase in the cost of labour and other economic and environmental factors and limitations. The report has an analysis of one of the ways of decreasing these difficulties, connected with the construction of large nuclear energy centres, consisting of a cluster of reactors on a single reactor site with the combined capacity of 40,000-50,000 MWe. The centres may consist, for example, of a cluster of conventional nuclear power plants that mainly consist of fast breeders and fuel cycle plants. They should be located in regions with a low density population and low value and deficiency of land and water resources. Electricity will be transmitted to consumers. The social-economic functions of such centres as factors that give birth to industrial regions are considered. Also given is the comparative estimate of benefits and problems of these two ways of further development of nuclear power system [ru

  20. Method of fabricating self-powered nuclear radiation detector assemblies

    International Nuclear Information System (INIS)

    Playfoot, K.; Bauer, R.F.; Sekella, Y.M.

    1982-01-01

    In a method of fabricating a self-powered nuclear radiation detector assembly an emitter electrode wire and signal cable center wire are connected and disposed within the collector electrode tubular sheath with compressible insulating means disposed between the wires and the tubular sheath. The above assembly is reduced in diameter while elongating the tubular sheath and the emitter wire and signal cable wire. The emitter wire is reduced to a predetermined desired diameter, and is trimmed to a predetermined length. An end cap is hermetically sealed to the tubular sheath at the extending end of the emitter with insulating means between the emitter end and the end cap. (author)

  1. Radiation damage of light guide fibers in gamma radiation field - on-line monitoring of absorption centers formation

    International Nuclear Information System (INIS)

    Blaha, J.; Simane, C.; Finger, M.; Slunecka, M.; Finger, M. Jr.; Sluneckova, V.; Janata, A.; Vognar, M.; Sulc, M.

    2004-01-01

    The kinetics of radiation-induced changes of absorption coefficient was studied by online transmission spectra measurement for two different Kuraray light guide fibers. The samples were irradiated by bremsstrahlung gamma radiation, dose rates were from 2 Gy/s to 25 Gy/s. The kinetic coefficients both for absorption centers formation and for recovery processes were calculated. Good agreement of experimental data and simple one-short-lived absorption center model were received for radiation-hard light guide Kuraray (KFC). The more complicated process was observed on Kuraray (PSM) clear fiber. It was caused by the reaction of the oxygen dissolved in fiber and created radicals. The results are very useful for prediction of an optical fibers response in conditions of new nuclear and particle physics experiments. (author)

  2. 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

  3. Kazakhstan center of nuclear technology safety. Approach of work, possibilities and plans

    International Nuclear Information System (INIS)

    Tazhibaeva, I.L; Romanenko, O.G.; Cherepnin, Yu. S.; Planchon, H.P; Imel, G; Newton, D.

    2000-01-01

    NTSC was created in November, 1997 as an association of experts in all the areas of nuclear and radiation safety and radioactive materials handling The main goal of creation is investigation of safety aspects of nuclear power in the Republic of Kazakhstan, taking into account the interests of environment and human health protection in the regions of nuclear industry units allocation. The Center was created with support and special cooperation with the US, has grown and developed cooperative ties with several other countries.In the report are enumerate the main directions of NTSC activity, general directions of cooperation, current and completed activity, planing activity

  4. Nuclear dynamical diffraction using synchrotron radiation

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Dennis Eugene [Stanford Univ., CA (United States)

    1993-05-01

    The scattering of synchrotron radiation by nuclei is extensively explored in this thesis. From the multipole electric field expansion resulting from time-dependent nonrelativistic perturbation theory, a dynamical scattering theory is constructed. This theory is shown, in the many particle limit, to be equivalent to the semi-classical approach where a quantum mechanical scattering amplitude is used in the Maxwell inhomogeneous wave equation. The Moessbauer specimen whose low-lying energy levels were probed is a ferromagnetic lattice of 57Fe embedded in a yttrium iron garnet (YIG) crystal matrix. The hyperfine fields in YIG thin films were studied at low and room temperature using time-resolved quantum beat spectroscopy. Nuclear hyperfine structure quantum beats were measured using a fast plastic scintillator coincidence photodetector and associated electronics having a time resolution of 2.5 nsec. The variation of the quantum beat patterns near the Bragg [0 0 2] diffraction peak gave a Lamb-Moessbauer factor of 8.2±0.4. Exploring characteristic dynamical features in the higher order YIG [0 0 10] reflection revealed that one of the YIG crystals had bifurcated into two different layers. The dynamics of nuclear superradiance was explored. This phenomenon includes the radiative speedup exhibited by a collective state of particles, and, in striking concurrence, resonance frequency shifts. A speedup of a factor of 4 in the total decay rate and a beat frequency shift of 11/2 natural resonance linewidths were observed. Nuclear resonance scattering was also found to be a useful way of performing angular interferometry experiments, and it was used to observe the phase shift of a rotated quantum state. On the whole, nuclear dynamical diffraction theory has superbly explained many of the fascinating features of resonant magnetic dipole radiation scattered by a lattice of nuclei.

  5. Nuclear dynamical diffraction using synchrotron radiation

    International Nuclear Information System (INIS)

    Brown, D.E.

    1993-05-01

    The scattering of synchrotron radiation by nuclei is extensively explored in this thesis. From the multipole electric field expansion resulting from time-dependent nonrelativistic perturbation theory, a dynamical scattering theory is constructed. This theory is shown, in the many particle limit, to be equivalent to the semi-classical approach where a quantum mechanical scattering amplitude is used in the Maxwell inhomogeneous wave equation. The Moessbauer specimen whose low-lying energy levels were probed is a ferromagnetic lattice of 57 Fe embedded in a yttrium iron garnet (YIG) crystal matrix. The hyperfine fields in YIG thin films were studied at low and room temperature using time-resolved quantum beat spectroscopy. Nuclear hyperfine structure quantum beats were measured using a fast plastic scintillator coincidence photodetector and associated electronics having a time resolution of 2.5 nsec. The variation of the quantum beat patterns near the Bragg [0 0 2] diffraction peak gave a Lamb-Moessbauer factor of 8.2±0.4. Exploring characteristic dynamical features in the higher order YIG [0 0 10] reflection revealed that one of the YIG crystals had bifurcated into two different layers. The dynamics of nuclear superradiance was explored. This phenomenon includes the radiative speedup exhibited by a collective state of particles, and, in striking concurrence, resonance frequency shifts. A speedup of a factor of 4 in the total decay rate and a beat frequency shift of 1 1/2 natural resonance linewidths were observed. Nuclear resonance scattering was also found to be a useful way of performing angular interferometry experiments, and it was used to observe the phase shift of a rotated quantum state. On the whole, nuclear dynamical diffraction theory has superbly explained many of the fascinating features of resonant magnetic dipole radiation scattered by a lattice of nuclei

  6. Nuclear Energy Center Site Survey, 1975. Part II. The U.S. electric power system and the potential role of nuclear energy centers

    International Nuclear Information System (INIS)

    1976-01-01

    Information related to Nuclear Energy Centers (NEC) in the U.S. is presented concerning the U.S. electric power system today; electricity demand history and forecasts; history and forecasts of the electric utility industry; regional notes; the status, history, and forecasts of the nuclear role; power plant siting problems and practices; nuclear facilities siting problems and practices; origin and evolution of the nuclear energy center concept; conceptualized description of nuclear energy centers; potential role of nuclear energy centers; assumptions, criteria, and bases; typical evolution of a nuclear energy center; and the nuclear fuel cycle

  7. Occupational radiation exposure in nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    1979-01-01

    ) determination of the trends in plant radiation fields, (2) control of the sources of radiation, e.g. through quality control of materials used in construction, (3) testing coolant purification techniques, (4) investigating the influence of coolant chemistry control, and (5) developing techniques for decontamination. The previously mentioned Canadian and Swedish experiences together with some significant Japanese results are being incorporated in these US research efforts. Radiation exposure experiences were described for fuel reprocessing plants in Belgium, Federal Republic of Germany, France and the United States using both direct and indirect maintenance. Exposures were similar to those received by nuclear power plant operators, maintenance and health physics personnel, all were well within international guidelines. The major part of the discussion centered around the following topics: the difficulties of applying cost/benefit analysis; the need for uniform reporting of exposure data; the necessity of preparing and designing for high-exposure maintenance activities; the desire for epidemiological studies on radiation workers which will include exposure; to other carcinogenic agents, smoking habits and medical and natural exposures; the reasons behind reported dose reductions. A great deal of practical experience is now available on minimizing industrial and collective doses to radiation workers, as well as on advanced techniques to control occupational exposure at nuclear fuel cycle facilities. (author)

  8. Nuclear Reaction and Structure Databases of the National Nuclear Data Center

    International Nuclear Information System (INIS)

    Pritychenko, B.; Arcilla, R.; Herman, M. W.; Oblozinsky, P.; Rochman, D.; Sonzogni, A. A.; Tuli, J. K.; Winchell, D. F.

    2006-01-01

    The National Nuclear Data Center (NNDC) collects, evaluates, and disseminates nuclear physics data for basic research and applied nuclear technologies. In 2004, the NNDC migrated all databases into modern relational database software, installed new generation of Linux servers and developed new Java-based Web service. This nuclear database development means much faster, more flexible and more convenient service to all users in the United States. These nuclear reaction and structure database developments as well as related Web services are briefly described

  9. Program strategy document for the Nuclear Materials Transportation Technology Center

    International Nuclear Information System (INIS)

    Jefferson, R.M.

    1979-07-01

    A multiyear program plan is presented which describes the program of the Nuclear Materials Transportation Technology Center (TIC) at Sandia Laboratories. The work element plans, along with their corresponding work breakdown structures, are presented for TTC activities in the areas of Technology and Information Center, Systems Development, Technology, and Institutional Issues for the years from 1979 to 1985

  10. Specific schedule conditions for the formation of personnel of A or B category working in nuclear facilities. Option research center

    CERN Document Server

    Int. At. Energy Agency, Wien

    2002-01-01

    This document describes the specific dispositions relative to the Research Center, for the formation to the conventional and radiation risks prevention of personnel of A or B category working in nuclear facilities. The application domain, the applicable documents, the liability, the specificity of the Research Center and of the retraining, the Passerelle formation, are presented. (A.L.B.)

  11. Radiation Induced Color Centers in a La Doped PWO Crystal

    CERN Document Server

    Deng, Qun

    1998-01-01

    This report presents result of a study on radiation induced color center densities in a La doped lead tungstate ( PWO) crystal. The creation and annihilation constants of radiation induced color centers were determined by using transmittance data measured for a PWO sample before and during Co-60 gamma ray irradiation at a dose rate of 15 rad/hr. Following a model of color center kinetics, these constants were used to calculate color center densities under irradiations at 100 rad/hr. The result was found to be in a good agreement with experimental data, indicating that this model of color center kinetics can be used to predict behavior of PWO crystals under irradiation.

  12. The Role of the Radiation Safety Information Computational Center (RSICC) in Knowledge Management

    International Nuclear Information System (INIS)

    Valentine, T.

    2016-01-01

    Full text: The Radiation Safety Information Computational Center (RSICC) is an information analysis center that collects, archives, evaluates, synthesizes and distributes information, data and codes that are used in various nuclear technology applications. RSICC retains more than 2,000 packages that have been provided by contributors from various agencies. RSICC’s customers obtain access to such computing codes (source and/or executable versions) and processed nuclear data files to promote on-going research, to help ensure nuclear and radiological safety, and to advance nuclear technology. The role of such information analysis centers is critical for supporting and sustaining nuclear education and training programmes both domestically and internationally, as the majority of RSICC’s customers are students attending U.S. universities. RSICC also supports and promotes workshops and seminars in nuclear science and technology to further the use and/or development of computational tools and data. Additionally, RSICC operates a secure CLOUD computing system to provide access to sensitive export-controlled modeling and simulation (M&S) tools that support both domestic and international activities. This presentation will provide a general review of RSICC’s activities, services, and systems that support knowledge management and education and training in the nuclear field. (author

  13. 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

  14. National Nuclear Data Center status report

    International Nuclear Information System (INIS)

    2001-01-01

    In September the NNDC hosted a workshop for international collaborators to discuss issues related to database migration and use of the relational database concept. It is expected that full migration will take four to five years. The preliminary design of the Nuclear Reaction Database has been completed by the Reaction Database Design Team. The nuclear structure team at NNDC has begun investigating options for the nuclear structure databases. A preliminary ENSDF database using Access is being tested. The NNDC continues to compile neutron and charged-particle reaction data produced in the US and Canada. In the period from June 2000 through May 2001, 6 neutron data transmission tapes (TRANS 1289-1294) and 13 charged-particle transmission tapes (C041-C049, P003, T006-T008) were sent containing new and corrected entries. The contract with Oak Ridge to compile neutron total cross section data has been completed. All recoverable data has been received by NNDC and are being processed or have already been added to the CSISRS database. NNDC continues to coordinate the work of the Cross Section Evaluation Working Group. ENDF/B-VI, Release 7, was distributed in June 2000. Version 6.12 of the ENDF Utility codes was also distributed in April 2001. The ENDF-102 Data Formats and Procedures Manual has been updated and is available on the NNDC Web site. Cooperation with KAERI continued on fission product evaluations, focusing on the fast neutron energy range. Thirteen preliminary evaluations have been completed. Cooperation with LANL and IAEA NDS on the development of a modular code for nuclear reaction data evaluations was initiated. The pre-equilibrium Monte Carlo code HMS was extended to account for angular momentum conservation, of importance for modeling isomer and discrete gamma-ray production. The modular code Empire was extended by adding a module based on the exciton model code DEGAS, motivated by the need to handle direct/semi-direct capture in the fast neutron energy

  15. An example of a United States Nuclear Research Center

    International Nuclear Information System (INIS)

    Bhattacharyya, S. K.

    1999-01-01

    Under the likely scenario in which public support for nuclear energy remains low and fossil fuels continue to be abundant and cheap, government supported nuclear research centers must adapt their missions to ensure that they tackle problems of current significance. It will be critical to be multidisciplinary, to generate economic value, and to apply nuclear competencies to current problems. Addressing problems in nuclear safety, D and D, nuclear waste management, nonproliferation, isotope production are a few examples of current needs in the nuclear arena. Argonne's original mission, to develop nuclear reactor technology, was a critical need for the U.S. in 1946. It would be wise to recognize that this mission was a special instance of a more general one--to apply unique human and physical capital to long term, high risk technology development in response to society's needs. International collaboration will enhance the collective chances for success as the world moves into the 21st century

  16. 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

  17. Nuclear safety research collaborations between the US and Russian Federation international nuclear safety centers

    International Nuclear Information System (INIS)

    Hill, D.J; Braun, J.C; Klickman, A.E.; Bugaenko, S.E; Kabanov, L.P; Kraev, A.G.

    2000-01-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the U.S. Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the U. S. Center at Argonne National Laboratory in October 1995. MINATOM established the Russian Center at the Research and Development Institute of Power Engineering in Moscow in July 1996. In April 1998 the Russian center became an independent, autonomous organization under MINATOM. The goals of the centers are to: cooperate in the development of technologies associated with nuclear safety in nuclear power engineering. be international centers for the collection of information important for safety and technical improvements in nuclear power engineering. maintain a base for fundamental knowledge needed to design nuclear reactors.The strategic approach that is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors

  18. Radiation Shielding Information Center: a source of computer codes and data for fusion neutronics studies

    International Nuclear Information System (INIS)

    McGill, B.L.; Roussin, R.W.; Trubey, D.K.; Maskewitz, B.F.

    1980-01-01

    The Radiation Shielding Information Center (RSIC), established in 1962 to collect, package, analyze, and disseminate information, computer codes, and data in the area of radiation transport related to fission, is now being utilized to support fusion neutronics technology. The major activities include: (1) answering technical inquiries on radiation transport problems, (2) collecting, packaging, testing, and disseminating computing technology and data libraries, and (3) reviewing literature and operating a computer-based information retrieval system containing material pertinent to radiation transport analysis. The computer codes emphasize methods for solving the Boltzmann equation such as the discrete ordinates and Monte Carlo techniques, both of which are widely used in fusion neutronics. The data packages include multigroup coupled neutron-gamma-ray cross sections and kerma coefficients, other nuclear data, and radiation transport benchmark problem results

  19. Radiation dosimetry in nuclear medicine - recent developments

    International Nuclear Information System (INIS)

    Hetherington, E.L.R.; Wood, N.R.

    1976-01-01

    This paper reviews developments in radiation dosimetry in Nuclear Medicine over the past few years. The practical scope of the Medical Internal Radiation Dose (MIRD) Committee's Schema for dose determination has been extended by the development of more realistic mathematical models of the human body, together with the improvement in basic physical data used in dose calculations. Apart from the use of the Adult Human Phantom as the basis for dose determination, models have been developed for the estimation of doses to children and to the developing foetus. The Schema has been extended to permit calculations of the dose to dynamic organs, particularly the bladder. The principle of Monte Carlo photon history simulation, which forms the basis of much of the MIRD Schema's published data, has been used at the Australian Atomic Energy Commission for the determination of complete photon dose distributions. These are more meaningful in many cases than the average doses determined by the absorbed fraction method. (author)

  20. Radiation monitoring instrumentation for nuclear power plants

    International Nuclear Information System (INIS)

    Bharath Kumar, M.

    2013-01-01

    Measurement of nucleonic signals is required to control and operate the reactor in a safe and reliable manner. To achieve this, parameters like Neutron flux, other radiation fields, contamination levels, source strength, release thru stack etc. are required to be monitored and controlled. The above are required to be monitored throughout the life of the reactor whether it is operational or in shutdown condition. In addition such monitoring is also required during decommissioning phase of the reactor as needed. To measure these parameters a large number of instruments are used in Nuclear Power Plants (NPP) which includes sensors and electronics for detecting alpha, beta, gamma and neutron radiation with qualification to withstand harsh environment

  1. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, H.D.; Lee, Y.B.; Lee, W.Y.; Park, D.W.; Chung, B.G.

    1980-01-01

    For the KAERI site, various environmental samples were collected three times a month, and the natural environmental radiation levels were also measured at each sampling point. Measurements for gross alpha and beta radioactivities of the samples were routinely measured for all samples. Strontium-90 concentrations were also analysed for the fallout and air samples collected daily basis on the roof of the main building. Accumulated exposure including the possibility of determination of low level environmental radiation field by employing thermoluminescent dosimeter, CaSO 4 : Dsub(y)-0.4 teflon disc type, at 6 posts in on-site of the KAERI. As for Kori site, at 19 points of ON, OFF-site, and at the same time the environmental radiation exposure rate at each sampling point were measured. Several environmental samples such as surface soil, pine needles, water samples, milk sample and pasture samples were collected and analysed on a quarterly basis. As a result of the survey it can be said that no significant release of radiation to the environment due to the operations of nuclear facilities including research reactor at the KAERI and power reactor at the Kori has been found during the period of the survey and monitoring. (author)

  2. The role of nuclear research centers for the introduction of a nuclear power programme

    International Nuclear Information System (INIS)

    Perovic, B.; Frlec, B.; Kundic, V.

    1977-01-01

    Full development of nuclear energy has imposed a new role on nuclear energy centers. Nuclear technology for different reactor concepts is also now in a phase of high development. Several reactor concepts have been developed for industrial use and electric power production. Development of fast reactors is still under way and needs further research efforts. Having in mind these two main guidelines, research programmes in nuclear energy centers should be geared to the development of the activities vital to the implementation of national nuclear energy programmes. In this respect, national nuclear centers should devote their attention to three major tasks. First, to establish a background for the introduction of nuclear energy into the national energy system and to support a national safety system. Second, to support the national programme by skilled manpower, to provide the basic training in nuclear technology for future staff of nuclear power stations and to assist the universities in establishing the necessary educational programme in nuclear energy. Third, to follow the development of nuclear energy technology for the fast breeder reactor concepts. This paper describes some experience in introducing a new programme to the national nuclear energy centers in Yugoslavia. Recently, Yugoslavia has started building its first nuclear power station. Further introduction of nuclear power stations in the national electric energy system is also planned. This implies the need to reconsider the current nuclear energy programme in the nuclear energy centers. It has been decided to evaluate past experience and further needs for research activities regarding the nuclear power programme. Yugoslavia has three main nuclear energy centers whose activities are devoted to the development of national manpower in the field of nuclear sciences. Besides these three organizations, there are several others whose activities are concentrated on specific tasks in nuclear technology. In the

  3. Continuous monitoring system for environmental {gamma} radiation near nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Hua, Jin; Qingyu, Yue; Wenhai, Wang [Academia Sinica, Beijing, BJ (China). Inst. of Atomic Energy

    1996-06-01

    The continuous monitoring system which is used for the environmental routine and accident emergency {gamma} radiation monitoring near nuclear facility is described. The continuous monitoring system consists of a high pressurized ionization chamber, integrated weak current amplifier, V/F converter and intelligent data recorder. The data gained by recorder can be transmitted to a PC through a standard RS-232-C interface for the data handling and graph plotting. This continuous monitoring system has the functions of alarm over threshold and recorded output signal of detector and temperature. The measuring range is from 10 nGy{center_dot}h{sup -1} to 10 mGy{center_dot}h{sup -1} because a high insulation switch atomically changed measuring ranges is used. The monitoring system has been operating continuously for a long time with high stability and reliability. (5 figs., 2 tabs.).

  4. The main activities and scientific collaboration possibilities at Ankara Nuclear research and training center

    International Nuclear Information System (INIS)

    Yucel, H.; Turhan, S.; Zararsiz, A.; Oksuz, B.S.

    2004-01-01

    Full text: Founded in 1964, Ankara Nuclear Research and Training Center (ANRTC) conducts and facilitates the scientific activities including training (summer practice, MSc and Ph D studies in physics and chemistry, IAEA fellowship programs etc.), research and other studies in nuclear and related fields. As it's a part of main duties, ANRTC has analysis on the variety of samples, and radiation protection services commercially, for radiation workers in state, public and private sectors. Research, development and application projects implemented in this Center have mostly been supported by State Planning Organization (SPO) and Turkish Atomic Energy Authority (TAEA). In addition to the projects there are on going collaborative studies with some national Universities and International Atomic Energy Agency. The main activities carried out in ANRTC can be summarized as: studies on experimental nuclear physics, application of nuclear techniques such as XRF, XRD, Gamma, Alpha, etc. for environmental pollutants, archaeological and geological dating, elemental and crystal structural analyses, studies on the detection of irradiated foodstuff by ESR, development of accident dosimeters to be used in the case of a nuclear or radiological accident, and radiation matter interaction studies. In near future, for young scientists, there will be new collaboration possibilities related to accelerator-based applications, especially the new production methods of radioisotopes and their radiopharmaceuticals by using a cyclotron when our 30 MeV p / 15MeV d cyclotron facility project is underway

  5. Radiation dose registration and epidemiological study for workers of nuclear institutions in Japan

    International Nuclear Information System (INIS)

    Kumatori, T.

    1992-01-01

    The first nuclear reactor was operated in 1957 at Tokai-mura in Japan. Since then radiation dose of workers has been controlled by nuclear institutions according to the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors. However, many nuclear power plants and other nuclear facilities were built, resulting in the remarkable increase of workers in controlled areas. Further, periodical inspection and repair work at nuclear facilities were carried out by employees of subcontractors, who were engaged in such work at many different facilities, so that it was getting more and more difficult to obtain accurate information of radiation dose on these workers. In order to meet this situation, the open-quotes Radiation Dose Registration Center for Workersclose quotes (RADREC) was established in November 1977 within the open-quotes Radiation Effects Associationclose quotes (REA), which was founded in September 1960 for the purpose of supporting the research on radiation effects and radiation protection. In January 1978, RADREC was designated by the Government as an organization to preserve the records on exposure of radiation workers, which was linked up with the registration system

  6. Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers

    International Nuclear Information System (INIS)

    Hill, D. J.; Braun, J. C.; Klickman, A. E.; Bougaenko, S. E.; Kabonov, L. P.; Kraev, A. G.

    2000-01-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous organization under MINATOM. The goals of the center are to: Cooperate in the development of technologies associated with nuclear safety in nuclear power engineering; Be international centers for the collection of information important for safety and technical improvements in nuclear power engineering; and Maintain a base for fundamental knowledge needed to design nuclear reactors. The strategic approach is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors. The two centers started conducting joint research and development projects in January 1997. Since that time the following ten joint projects have been initiated: INSC databases--web server and computing center; Coupled codes--Neutronic and thermal-hydraulic; Severe accident management for Soviet-designed reactors; Transient management and advanced control; Survey of relevant nuclear safety research facilities in the Russian Federation; Computer code validation for transient analysis of VVER and RBMK reactors; Advanced structural analysis; Development of a nuclear safety research and development plan for MINATOM; Properties and applications of heavy liquid metal coolants; and Material properties measurement and assessment. Currently, there is activity in eight of these projects. Details on each of these

  7. Annual report of Nuclear Emergency Assistance and Training Center. April 1, 2011 - March 31, 2012

    International Nuclear Information System (INIS)

    Katagiri, Hiromi; Okuno, Hiroshi; Okamoto, Akiko; Ikeda, Takeshi; Tamura, Kenichi; Nagakura, Tomohiro; Nakanishi, Chika; Yamamoto, Kazuya; Abe, Minako; Sato, Sohei; Kawakami, Takeshi; Kikuchi, Masayuki; Sumiya, Akihiro; Matsusaka, Masaru

    2012-08-01

    When a nuclear emergency occurs in Japan, the Japan Atomic Energy Agency (JAEA) has the responsibility of providing technical support to the National government, local governments, police, fire stations and nuclear operators etc., because the JAEA has been designated as the Designated Public Institution under the Basic Act on Disaster Control Measures and the Act on Response to Armed Attack Situations, etc.. The Nuclear Emergency Assistance and Training Center (NEAT) of JAEA provides a comprehensive range of technical support activities to an Off-Site Center in case of a nuclear emergency. Specifically, NEAT gives technical advice and information, dispatches specialists as required, and supplies the National Government and local governments with emergency equipments and materials. NEAT provides various exercise and training courses concerning nuclear disaster prevention to those personnel taking an active part in emergency response organizations at normal times. NEAT also researches on nuclear disaster prevention and cooperates with international organizations. Concerning the assistance to the Accident at Fukushima Nuclear Power Station caused by the Great East Japan Earthquake on 11 March, 2011, JAEA has assisted activities including environmental radiation monitoring, environmental radioactivity analyses, and response to telephone inquiries from residents etc., with utmost effort. NEAT has served as the center of these supporting activities of JAEA. This annual report summarized these activities of JAEA/NEAT in the fiscal year 2011. (author)

  8. Centers for Disease Control and Prevention (CDC) Radiation Hazard Scale Data Product Review Feedback Report

    Energy Technology Data Exchange (ETDEWEB)

    Askin, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Buddemeier, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Alai, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Yu, K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-09-20

    In support of the Department of Energy (DOE) National nuclear Security Administration (NNSA) and the Centers for Disease Control and Prevention (CDC), Lawrence Livermore National Laboratory (LLNL) assisted in the development of new data templates for disseminating and communicating FRMAC1 data products using the CDC Radiation Hazard Scale communication tool. To ensure these data products will be useful to stakeholders during a radiological emergency, LLNL facilitated opportunities for product socialization and review.

  9. 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

  10. Summary of Prometheus Radiation Shielding Nuclear Design Analyses , for information

    International Nuclear Information System (INIS)

    J. Stephens

    2006-01-01

    This report transmits a summary of radiation shielding nuclear design studies performed to support the Prometheus project. Together, the enclosures and references associated with this document describe NRPCT (KAPL and Bettis) shielding nuclear design analyses done for the project

  11. Radiation protection organization in Guangdong Nuclear Power Station (GNPS)

    International Nuclear Information System (INIS)

    Yang Maochun

    1993-01-01

    The French way of radiation protection management has been adopted by Guangdong Nuclear Power Station (GNPS) but there are some differences. In this paper author describes radiation protection organization in GNPS, special measures having been taken and the present status

  12. Radiation safety and protection on the nuclear power plants

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Bogorad, V.I.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Litvinskaya, T.V.; Slepchenko, A.Yu.

    2008-01-01

    The main issues of the radiation safety and protection provision on the nuclear power plants are considered in this monograph. The description of the basic sources of the radiation danger on NPPs, the principles, the methods and the means of the safety and radiation monitoring provision are shown. The special attention is paid to the issues of the ionizing radiation regulation

  13. Radiation protection in Swiss nuclear installations; Strahlenschutz in Schweizer Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Hammer, J.; Brunell, M. [Eidgenoessisches Nuklearsicherheitsinspektorat ENSI, Brugg (Switzerland)

    2015-07-01

    Well developed measures on operational radiation protection within Swiss nuclear installations will be presented. The focus lays on competent authority actions. Results of the last ten years, including events on radiation issues, will be discussed. Finally a view on challenges for radiation protection personnel with respect to a renewed Swiss radiation protection legislation based on recent ICRP recommendations will be given.

  14. Atomic, Nuclear and Molecular Research Center CICANUM

    International Nuclear Information System (INIS)

    Loria Meneses, Luis Guillermo

    2011-01-01

    CICANUM has a Gamma Spectroscopy Laboratory, has been the laboratory official, appointed by the Ministerio de Agricultura in Costa Rica to analyze export products (for human consumption and animal), also, to determine radioactive contamination. The Laboratory has four systems using germanium detectors and canberra technology, including software Genie 2000 to establish the activity of cesium, iodine and natural gamma emitters in solid or liquid samples for food products, sediments and rocks. This Laboratory belongs to the Universidad de Costa Rica which has different institutes and research centers

  15. Assuaging Nuclear Energy Risks: The Angarsk International Uranium Enrichment Center

    International Nuclear Information System (INIS)

    Myers, Astasia

    2011-01-01

    The recent nuclear renaissance has motivated many countries, especially developing nations, to plan and build nuclear power reactors. However, domestic low enriched uranium demands may trigger nations to construct indigenous enrichment facilities, which could be redirected to fabricate high enriched uranium for nuclear weapons. The potential advantages of establishing multinational uranium enrichment sites are numerous including increased low enrichment uranium access with decreased nuclear proliferation risks. While multinational nuclear initiatives have been discussed, Russia is the first nation to actualize this concept with their Angarsk International Uranium Enrichment Center (IUEC). This paper provides an overview of the historical and modern context of the multinational nuclear fuel cycle as well as the evolution of Russia's IUEC, which exemplifies how international fuel cycle cooperation is an alternative to domestic facilities.

  16. Radiation exposure on residents due to semipalatinsk nuclear tests

    International Nuclear Information System (INIS)

    Takada, J.; Hoshi, M.; Nagatomo, T.

    2000-01-01

    Accumulated external radiation doses for residents near Semipalatinsk nuclear test site of the former USSR are presented as a results of the first study by thermoluminescence technique for bricks sampled at several settlements between 1995 and 1997. The external doses which we evaluated from brick dose were up to ∼100 cGy for resident. The external doses at several points in the center of Semipalatinsk city were ∼60 cGy that was remarkably high comparing with the previously reported value based on the military data. A total of 459 nuclear explosions were conducted by the former Union of Soviet Socialist Republics (USSR) from 1949 to 1989 at the Semipalatinsk nuclear test site (SNTS) Kazakhstan, including 87 atmospheric, 26 on the ground, and 364 underground explosions. Total energy release of about 18 Mt equivalent of trinitrotoluene is eleven hundreds times of Hiroshima atomic bomb. However previous reports concerning the effects of radiation on residents near the SNTS based on data provided by the Defense Department of the former USSR do not have direct experimental data concerning effective equivalent dose. They just measured some doses for particular settlements after some nuclear explosions. These do not indicate integrated dose for the residents due to the whole explosions. The technique of thermoluminescence dosimetry (TLD) which had been successfully applied to the dosimetry on Hiroshima and Nagasaki atomic bombs, enabled us to evaluate accumulated external gamma ray doses at specific places due to whole nuclear explosions in the Semipalatinsk test site. TLD technique is well-established one for not only instantaneous exposure like in A-bombs (Hiroshima and Nagasaki) but also prolonged exposure like in dating. Moreover this technique was applicable for dosimetry study of radioactive fallout as shown in studies of Chernobyl accident. The way of external dose estimation from TLD doses for brick will be discussed in case of radioactive fallout. We will

  17. Bibliography, subject index, and author index of the literature examined by the Radiation Shielding Information Center (Reactor and Weapons Radiation Shielding). [1973--1976

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    An indexed bibliography is presented of literature selected by the Radiation Shielding Information Center since the previous volume was published in 1974 in the area of radiation transport and shielding against radiation from nuclear reactors, x-ray machines, radioisotopes, nuclear weapons (including fallout), and low-energy accelerators (e.g., neutron generators). In addition to lists of literature titles by subject categories (accessions 3501-4950), author and keyword indexes are given. Most of the literature selected for Vol. V was published in the years 1973 to 1976.

  18. Bibliography, subject index, and author index of the literature examined by the radiation shielding information center. Volume 6. Reactor and weapons radiation shielding

    International Nuclear Information System (INIS)

    1980-05-01

    An indexed bibliography is presented of literature selected by the Radiation Shielding Information Center since the previous volume was published in 1978 in the area of radiation transport and shielding against radiation from nuclear reactors, x-ray machines, radioisotopes, nuclear weapons (including fallout), and low energy accelerators (e.g., neutron generators). The bibliography was typeset from data processed by computer from magnetic tape files. In addition to lists of literature titles by subject categories (accessions 4951-6200), an author index is given

  19. Bibliography, subject index, and author index of the literature examined by the Radiation Shielding Information Center (Reactor and Weapons Radiation Shielding)

    International Nuclear Information System (INIS)

    1978-01-01

    An indexed bibliography is presented of literature selected by the Radiation Shielding Information Center since the previous volume was published in 1974 in the area of radiation transport and shielding against radiation from nuclear reactors, x-ray machines, radioisotopes, nuclear weapons (including fallout), and low-energy accelerators (e.g., neutron generators). In addition to lists of literature titles by subject categories (accessions 3501-4950), author and keyword indexes are given. Most of the literature selected for Vol. V was published in the years 1973 to 1976

  20. Excitation of nuclear states by synchrotron radiation

    International Nuclear Information System (INIS)

    Olariu, Albert

    2003-01-01

    We study the excitation of nuclear states by gamma ray beams of energy up to 200 keV produced as synchrotron radiation. We consider the possibility to populate an excited state |i> in two steps, from the ground state |g> to an intermediary state |n> which decays by gamma emission or internal conversion to a lower state |i>. The aim of this study is to establish that the probability P 2 of the two-step transition |g> → |n> → |i> should be greater than the probability P 1 of the direct transition |g> → |i>. The probabilities P 1 and P 2 correspond to a radiation pulse of duration equal to the half-time of the state |i>. We have written a computer program in C++ which computes the probability P 2 , the ratio P 2 /P 1 and the rate C 2 of the two-step transitions for any nuclei and different configurations of states. The program uses a database which contains information on the energy levels, half-lives, spins and parities of nuclear states and on the relative intensities of the nuclear transitions. If the half-lives or the relative intensities are not known the program uses the Weisskopf estimates for the transition half-lives. An interpolation program of internal conversion coefficients has also been used. We listed the values obtained for P 2 , P 2 /P 1 and C 2 in a number of cases in which P 2 is significant from the 2900 considered cases. The states |i> and |n> have the energies E i and E n , the corresponding half-lives being t i and t n . The spectral density of the synchrotron radiation has been considered to be 10 12 photons cm -2 s -1 eV -1 . We listed only the cases for which the relative intensities of the transitions from levels |n> and |i> to lower states are known. The calculations carried out in this study allowed us to identify nuclei for which P 2 has relatively great values. In the listed cases P 2 /P 1 >>1, so that the two-step excitation by synchrotron radiation is more efficient than the direct excitation |g> → |i>. For a sample having 10

  1. Knowledge management: Role of the the Radiation Safety Information Computational Center (RSICC)

    Science.gov (United States)

    Valentine, Timothy

    2017-09-01

    The Radiation Safety Information Computational Center (RSICC) at Oak Ridge National Laboratory (ORNL) is an information analysis center that collects, archives, evaluates, synthesizes and distributes information, data and codes that are used in various nuclear technology applications. RSICC retains more than 2,000 software packages that have been provided by code developers from various federal and international agencies. RSICC's customers (scientists, engineers, and students from around the world) obtain access to such computing codes (source and/or executable versions) and processed nuclear data files to promote on-going research, to ensure nuclear and radiological safety, and to advance nuclear technology. The role of such information analysis centers is critical for supporting and sustaining nuclear education and training programs both domestically and internationally, as the majority of RSICC's customers are students attending U.S. universities. Additionally, RSICC operates a secure CLOUD computing system to provide access to sensitive export-controlled modeling and simulation (M&S) tools that support both domestic and international activities. This presentation will provide a general review of RSICC's activities, services, and systems that support knowledge management and education and training in the nuclear field.

  2. A management plan for hospitals and medical centers facing radiation incidents

    Directory of Open Access Journals (Sweden)

    Fereshteh Davari

    2015-01-01

    Full Text Available Background: Nowadays, application of nuclear technology in different industries has largely expanded worldwide. Proportionately, the risk of nuclear incidents and the resulting injuries have, therefore, increased in recent years. Preparedness is an important part of the crisis management cycle; therefore efficient preplanning seems crucial to any crisis management plan. Equipped with facilities and experienced personnel, hospitals naturally engage with the response to disasters. The main purpose of our study was to present a practical management pattern for hospitals and medical centers in case they encounter a nuclear emergency. Materials and Methods: In this descriptive qualitative study, data were collected through experimental observations, sources like Safety manuals released by the International Atomic Energy Agency and interviews with experts to gather their ideas along with Delphi method for polling, and brainstorming. In addition, the 45 experts were interviewed on three targeted using brainstorming and Delphi method. Results: We finally proposed a management plan along with a set of practicality standards for hospitals and medical centers to optimally respond to nuclear medical emergencies when a radiation incident happens nearby. Conclusion: With respect to the great importance of preparedness against nuclear incidents adoption and regular practice of nuclear crisis management codes for hospitals and medical centers seems quite necessary.

  3. A management plan for hospitals and medical centers facing radiation incidents.

    Science.gov (United States)

    Davari, Fereshteh; Zahed, Arash

    2015-09-01

    Nowadays, application of nuclear technology in different industries has largely expanded worldwide. Proportionately, the risk of nuclear incidents and the resulting injuries have, therefore, increased in recent years. Preparedness is an important part of the crisis management cycle; therefore efficient preplanning seems crucial to any crisis management plan. Equipped with facilities and experienced personnel, hospitals naturally engage with the response to disasters. The main purpose of our study was to present a practical management pattern for hospitals and medical centers in case they encounter a nuclear emergency. In this descriptive qualitative study, data were collected through experimental observations, sources like Safety manuals released by the International Atomic Energy Agency and interviews with experts to gather their ideas along with Delphi method for polling, and brainstorming. In addition, the 45 experts were interviewed on three targeted using brainstorming and Delphi method. We finally proposed a management plan along with a set of practicality standards for hospitals and medical centers to optimally respond to nuclear medical emergencies when a radiation incident happens nearby. With respect to the great importance of preparedness against nuclear incidents adoption and regular practice of nuclear crisis management codes for hospitals and medical centers seems quite necessary.

  4. 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

  5. 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

  6. 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

  7. 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

  8. Western New York Nuclear Service Center study. Companion report

    International Nuclear Information System (INIS)

    1978-01-01

    A one-year study of the Western new York Nuclear Service Center was conducted, including consideration of the following options: (1) Federal technical and financial aid in support of decommissioning high-level waste disposal operations; (2) Federal operation for the purpose of decommissioning existing facilities and disposing of existing high-level wastes, including a demonstration program for the solidification of high-level wastes for permanent burial; (3) permanent Federal ownership of and responsibility for all or part of the Western new York Nuclear Service Center, and Federal receipt of the license from the present co-licensees; and (4) use of the Western New York Nuclear Service Center for other purposes. Environmental impacts and institutional aspects are also covered

  9. Development of a Risk-Based Decision-Support-Model for Protecting an Urban Medical Center from a Nuclear Explosion

    International Nuclear Information System (INIS)

    Ben-Dor, G.; Shohet, I.M.; Ornai, D.; Brosh, B.

    2014-01-01

    Nuclear explosion is the worst man-made physical threat on the human society. The nuclear explosion includes several consequences, some of them are immediate and others are long term. The major influences are: long duration blast, extreme thermal release, nuclear radiations, and electro-magnetic pulse (EMP). Their damage range is very wide. When nuclear explosion occurs above or in an urban area it is possible that one or more medical centers will be affected. Medical centers include several layers of structures defined by their resistance capacity to the nuclear explosion influences, beginning with the structure's frame and ending with different systems and with vulnerable medical critical infrastructures such as communications, medical gas supply, etc. A comprehensive literature survey revealed that in spite of the necessity and the importance of medical centers in the daily life and especially in emergency and post nuclear explosion, there is a lack of research on this topic

  10. Activities and cooperation opportunities at Cekmece Nuclear Research and Training Center

    International Nuclear Information System (INIS)

    Can, S.

    2004-01-01

    Turkey's familiarization with nuclear energy began in July 1955, when it signed a bilateral agreement with the USA to cooperate in the 'peaceful uses of nuclear energy'. In 1956, the Turkish Atomic Energy Commission (TAEK) was created. Cekmece Nuclear Research and Training Center (CNAEM) was formally established in 1962. Turkey's first research reactor, a pool-type 1 MW reactor at CNAEM site, known as TR-1, went critical in 1962 and was shut down in September 1977. Strong collaborations with national and international organizations have been achieved for the promotion of the peaceful uses of nuclear energy and its applications in Turkey. Meanwhile the TR-2 reactor (5 MW) was commissioned in 1984 in order to meet the increasing demand of radioisotopes.CNAEM as a subsidiary of TAEK is charged to perform R and D activities on whole area of nuclear science and technology, such as research reactor, nuclear safety, nuclear fuel technology and fuel analysis codes, nuclear materials, NDT, nuclear electronics, accelerator, radiobiology, cytogenetics (bio dosimetry), radioecology, marine radioactivity, radiation safety, dosimetry, radioactive waste management, calibration of nuclear instruments, environmental monitoring. Possible cooperation fields between CNAEM and other institutions are as follows: measurements of radioactivity in the environment, radioecological studies of radioactivity levels in environmental samples, indoor radon measurements, development and production of radiopharmaceuticals, radiation cytogenetics (bio dosimetry), training in NDT, certification of industrial workers who use non-destructive testing devices, production of UO 2 and (U,Th)O 2 based fuel material, development and construction of radiation measurement instrument, analysis of all kind of uranium and thorium, training on processing and storage of low level radioactive waste

  11. Activities and cooperation opportunities at Cekmece nuclear research and training center

    International Nuclear Information System (INIS)

    Can, S.

    2004-01-01

    Full text: Turkey's familiarization with nuclear energy began in July 1955, when it signed a bilateral agreement with the USA to cooperate in the p eaceful uses of nuclear energy . In 1956, the Turkish Atomic Energy Commission (TAEK) was created. Cekmece Nuclear Research and Training Center (CNAEM) was formally established in 1962. Turkey's first research reactor, a pool-type 1 MW reactor at CNAEM site, known as TR-1, went critical in 1962 and was shut down in September 1977. Strong collaborations with national and international organizations have been achieved for the promotion of the peaceful uses of nuclear energy and its applications in Turkey. Meanwhile the TR-2 reactor (5 MW) was commissioned in 1984 in order to meet the increasing demand of radioisotopes.CNAEM as a subsidiary of TAEK is charged to perform R and D activities on whole area of nuclear science and technology, such as research reactor, nuclear safety, nuclear fuel technology and fuel analysis codes, nuclear materials, NDT, nuclear electronics, accelerator, radiobiology, cytogenetics (bio dosimetry), radioecology, marine radioactivity, radiation safety, dosimetry, radioactive waste management, calibration of nuclear instruments, environmental monitoring. Possible cooperation fields between CNAEM and other institutions are as follows: measurements of radioactivity in the environment, radioecological studies of radioactivity levels in environmental samples, indoor radon measurements, development and production of radiopharmaceuticals, radiation cytogenetics (bio dosimetry), training in NDT, certification of industrial workers who use non-destructive testing devices, production of UO 2 and (U,Th)O 2 based fuel material, development and construction of radiation measurement instrument, analysis of all kind of uranium and thorium, training on processing and storage of low level radioactive waste

  12. 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...

  13. Upgrade the website of Nuclear Training Center for online training

    International Nuclear Information System (INIS)

    Nguyen Minh Duc; Nguyen Thuy Hang; Nguyen Thi Lien; Luu Thi Thu Hoa; Pham Thi Thu Trang

    2017-01-01

    In 2016, Nuclear Training Center (NTC) proposed the task of improving and upgrading NTC website’s technology for better performance, more attractive interface and more accessible information to site visitors. This website will be designed to meet the demand for integrated online training site, integrated training management page later. For this task, it is expected to build a website with full modules, English interface of website and especially, the professional website to apply online training technology and tightly integrated close to the present site of a nuclear training center. (author)

  14. Nuclear Information and Documentation Center (CIDN): in search for excellence

    International Nuclear Information System (INIS)

    Romandia G, M.R.L.

    1994-01-01

    The present situation in the National Institute of Nuclear Research (ININ) implies both the organic reestructuration and the redefinition of objectives: in congruence with this evolution, the nuclear information and documentation center (CIDN) has to be adapted to the information needs that will require the new researching lines and at the same time look for the operating excellence in its services and activities. This paper is made with the purpose to do some considerations and proposals about the internal organization of CIDN through the quality circles and actions intended to reinforce the work perform by the information centers network of energetic sector (IMP, ININ, IIE). (Author)

  15. Automatization of the radiotherapy treatment at Nuclear Medicine Center

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  16. Radiation protection in biological investigation centers. Problematic, development and perspectives

    International Nuclear Information System (INIS)

    Macias, M.T.; Pina, R.; Usera, F.

    1998-01-01

    The radiological risk derivatives from the radioisotope techniques accomplished in the different investigation lines developed in the Centers object of this work, have necessary made establishing an organization that assure some adequate protection conditions in the use of the ionizing radiations

  17. Nuclear Energy Center Site Survey, 1975. Executive summary

    International Nuclear Information System (INIS)

    1976-01-01

    The Nuclear Energy Center Site Survey is a study of a potential alternative siting approach for nuclear power and fuel-cycle facilities, an approach that would cluster sizable groups of such facilities on a relatively small number of sites. The largest aggregation of reactors on a single site being planned today is four, and this quad is assumed (for comparative study purposes) to be the typical dispersed site by the year 2000. Three basic types of nuclear energy centers are considered: power-plant centers, consisting of 10 to 40 nuclear electric generating units of 1200-megawatt electric capacity each; fuel-cycle centers, consisting of fuel reprocessing plants, mixed-oxide fuel fabrication facilities, and radioactive waste management facilities; and combined centers, containing both power plants and fuel-cycle facilities. The results of the general site-location screening efforts are shown on a United States map that shows the locations of large areas identified as likely to contain suitable candidate sites for power NECs, on the basis of four coarse screening criteria: water resources, seismic activity, population density, and statutory excluded lands

  18. Present situation of occupational radiation exposure in nuclear power plants

    International Nuclear Information System (INIS)

    Imabori, Akira

    1979-01-01

    The present situation of the radiation exposure of workers, including both employes and subcontractors, in the nuclear power plants in Japan, is presented. Twenty seven nuclear power reactors in operation and under construction are tabulated with the name, the owner, the electric output and the commissioning year of each plant. The results of exposure of the workers in these plants are shown, classifying the dose rate into less than 0.5 rem, 0.5 - 1.5 rem, 1.5 - 2.5 rem, 2.5 - 5 rem and more than 5 rem, and the workers into employes and subcontractors. It is noted that the exposure dose of the subcontractors occupies about 88% of all exposure dose, and the exposure is concentrated during regular inspection period. The exposure dose of about 80% of the workers is less than 0.5 rem, and no one was irradiated more than 5 rem in a year. The total exposure dose, which has especially the tendency of increasing with extended maintenance period and decreasing during plant operation period, shows also the trend of increasing with the lapse of operation years. As for the point of view of whole exposure dose, the value is 0.06 -- 0.43 man-rem/10 6 kWh in 1976 FY. It is considered to be necessary to grasp the total exposure dose of each worker wandering from one plant to another, and the central registration center for the workers in radioactive environment was established in 1978. The whole exposure dose data of each worker are stored in the central computer in this center. This system is highly appreciated in radiation exposure management. The total exposure dose is related to the rate of utilization of nuclear plants, and it is expected to decrease with the decrease of plant outage. (Nakai, Y.)

  19. 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)

  20. National Nuclear Center of the Republic of Kazakstan (NNC RK)

    International Nuclear Information System (INIS)

    Vagin, S.P.

    1994-01-01

    National Nuclear Centre is independent complex scientific and technical establishment of republic subordinate and it is attached to National Academy of Sciences of the Republic of Kazakstan. Date of foundation - 1993. General Director - Cherepnin Yu.S., Scientific leader - Takibaev Zh.S. In it structure there are Inst. of Radiation Safety and Ecology, Inst. of Atomic Energy, Inst. of Nuclear Physics, Inst. Geophysical Researches, Regional Medical and Diagnostic Centre, Research Labs. of BN-350 industrial reactor (scientific leadership), Joint-Stock Co., industrial and commercial enterprises, scientific services of former Semipalatinsk test site, geophysical observatories etc. The main goals of the NNC: a conversion of former Semipalatinsk test site and using of it scientific and technical potential in the national economy; a liquidation of nuclear weapon test consequences; a development of safe nuclear power engineering in Kazakstan; a fundamental and applied researches in the different fields of nuclear science and technology; a carrying out the inspection to nuclear weapon testing and non-satanical nuclear explosions on the test sites of other countries; a training of highly skilled specialists for nuclear power engineering, nuclear science and technology

  1. Regulation of nuclear radiation exposures in India

    Energy Technology Data Exchange (ETDEWEB)

    Mishra, U.C. E-mail: ucmishra@yahoo.com

    2004-07-01

    India has a long-term program of wide spread applications of nuclear radiations and radioactive sources for peaceful applications in medicine, industry, agriculture and research and is already having several thousand places in the country where such sources are being routinely used. These places are mostly outside the Department of Atomic Energy (DAE) installations. DAE supplies such sources. The most important application of nuclear energy in DAE is in electricity generation through nuclear power plants. Fourteen such plants are operating and many new plants are at various stages of construction. In view of the above mentioned wide spread applications, Indian parliament through an Act, called Atomic Energy Act, 1964 created an autonomous body called Atomic Energy Regulatory Board (AERB) with comprehensive authority and powers. This Board issues codes, guides, manuals, etc., to regulate such installations so as to ensure safe use of such sources and personnel engaged in such installations and environment receives radiation exposures within the upper bounds prescribed by them. Periodic reports are submitted to AERB to demonstrate compliance of its directives. Health, Safety and Environment Group of Bhabha Atomic Research Centres, Mumbai carries out necessary surveillance and monitoring of all installations of the DAE on a routine basis and also periodic inspections of other installations using radiation sources. Some of the nuclear fuel cycle plants like nuclear power plants and fuel reprocessing involve large radioactive source inventories and have potential of accidental release of radio activity into the environment, an Environmental Surveillance Laboratory (ESL) is set up at each such site much before the facility goes into operation. These ESL's collect baseline data and monitor the environment throughout the life of the facilities including the de- commissioning stage. The data is provided to AERB and is available to members of the public. In addition, a

  2. Regulation of nuclear radiation exposures in India

    International Nuclear Information System (INIS)

    Mishra, U.C.

    2004-01-01

    India has a long-term program of wide spread applications of nuclear radiations and radioactive sources for peaceful applications in medicine, industry, agriculture and research and is already having several thousand places in the country where such sources are being routinely used. These places are mostly outside the Department of Atomic Energy (DAE) installations. DAE supplies such sources. The most important application of nuclear energy in DAE is in electricity generation through nuclear power plants. Fourteen such plants are operating and many new plants are at various stages of construction. In view of the above mentioned wide spread applications, Indian parliament through an Act, called Atomic Energy Act, 1964 created an autonomous body called Atomic Energy Regulatory Board (AERB) with comprehensive authority and powers. This Board issues codes, guides, manuals, etc., to regulate such installations so as to ensure safe use of such sources and personnel engaged in such installations and environment receives radiation exposures within the upper bounds prescribed by them. Periodic reports are submitted to AERB to demonstrate compliance of its directives. Health, Safety and Environment Group of Bhabha Atomic Research Centres, Mumbai carries out necessary surveillance and monitoring of all installations of the DAE on a routine basis and also periodic inspections of other installations using radiation sources. Some of the nuclear fuel cycle plants like nuclear power plants and fuel reprocessing involve large radioactive source inventories and have potential of accidental release of radio activity into the environment, an Environmental Surveillance Laboratory (ESL) is set up at each such site much before the facility goes into operation. These ESL's collect baseline data and monitor the environment throughout the life of the facilities including the de- commissioning stage. The data is provided to AERB and is available to members of the public. In addition, a multi

  3. Annual report of Nuclear Emergency Assistance and Training Center. April 1, 2010 - March 31, 2011

    International Nuclear Information System (INIS)

    Katagiri, Hiromi; Okuno, Hiroshi; Sawahata, Masayoshi; Ikeda, Takeshi; Sato, Sohei; Terakado, Naoya; Nagakura, Tomohiro; Nakanishi, Chika; Fukumoto, Masahiro; Yamamoto, Kazuya; Abe, Minako; Kawakami, Takeshi; Kikuchi, Masayuki; Sumiya, Akihiro; Matsusaka, Masaru

    2011-12-01

    When a nuclear emergency occurs in Japan, the Japan Atomic Energy Agency (JAEA) has the responsibility of providing technical support to the National government, local governments, police, fire station and license holders etc., because the JAEA is designated a Public Organization conforming to the Basic Law on Emergency Preparedness and the Basic Plan for Disaster Countermeasures. The Nuclear Emergency Assistance and Training Center (NEAT) of JAEA provides a comprehensive range of technical support activities to an Off-Site Center in case of a nuclear emergency. Specifically, NEAT gives technical advice and information, dispatch specialists as required, supplies emergency equipment and materials to the National Government and local governments. NEAT provides various lectures and training courses concerning nuclear disaster prevention for those personnel taking an active part in emergency response organizations at normal time. NEAT also researches on nuclear disaster prevention and cooperates with international organizations. Concerning about the assistance to the Accident of Fukushima No.1 Nuclear Power Station caused by the Great East Japan Earthquake at 11 March, 2011, JAEA assisted activities including environmental radiation monitoring, environmental radioactivity analyses, resident public consulting etc., with its full scale effort. NEAT served as the center of these supporting activities of JAEA. This annual report summarized these activities of JAEA/NEAT in the fiscal year 2010. (author)

  4. Bibliography, subject index, and author index of the literature examined by the Radiation Shielding Information Center. Volume 7

    Energy Technology Data Exchange (ETDEWEB)

    Trubey, D.K.; Roussin, R.W.; Gustin, A.B.

    1983-08-01

    An indexed bibliography of open literature selected by the Radiation Shielding Information Center since the previous volume was published in 1980 is presented in the area of radiation transport and shielding against radiation from nuclear reactors (fission and fusion), x-ray machines, radioisotopes, nuclear weapons (including fallout, and low energy accelerators (e.g., neutron generators). The bibliography was typeset from computer files constituting the RSIC Storage and Retrieval Information System. In addition to lists of literature titles by subject categories (accessions 6201-10156), an author index is given. Most of the literature selected for Volume VII was published in the years 1977 to 1981.

  5. Bibliography, subject index, and author index of the literature examined by the Radiation Shielding Information Center. Volume 7

    International Nuclear Information System (INIS)

    Trubey, D.K.; Roussin, R.W.; Gustin, A.B.

    1983-08-01

    An indexed bibliography of open literature selected by the Radiation Shielding Information Center since the previous volume was published in 1980 is presented in the area of radiation transport and shielding against radiation from nuclear reactors (fission and fusion), x-ray machines, radioisotopes, nuclear weapons (including fallout, and low energy accelerators (e.g., neutron generators). The bibliography was typeset from computer files constituting the RSIC Storage and Retrieval Information System. In addition to lists of literature titles by subject categories (accessions 6201-10156), an author index is given. Most of the literature selected for Volume VII was published in the years 1977 to 1981

  6. Establishment of exposure dose assessment laboratory in National Radiation Emergency Medical Center (NREMC)

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Jae Ryong; Ha, Wi Ho; Yoon, Seok Won; Han, Eun Ae; Lee, Seung Sook [Korea Institute of Radiological and Medical Sciences, Seoul (Korea, Republic of)

    2011-10-15

    As unclear industry grown, 432 of the nuclear power plants are operating and 52 of NPPs are under construction currently. Increasing use of radiation or radioisotopes in the field of industry, medical purpose and research such as non-destructive examination, computed tomography and x-ray, etc. constantly. With use of nuclear or radiation has incidence possibility for example the Fukushima NPP incident, the Goiania accident and the Chernobyl Nuclear accident. Also the risk of terror by radioactive material such as Radiological Dispersal Device(RDD) etc. In Korea, since the 'Law on protection of nuclear facilities and countermeasure for radioactive preparedness was enacted in 2003, the Korean institute of Radiological and Medical Sciences(KIRAMS) was established for the radiation emergency medical response in radiological disaster due to nuclear accident, radioactive terror and so on. Especially National Radiation Emergency Medical Center(NREMC) has the duty that is protect citizens from nuclear, radiological accidents or radiological terrors through the emergency medical preparedness. The NREMC was established by the 39-article law on physical protection of nuclear material and facilities and measures for radiological emergencies. Dose assessment or contamination survey should be performed which provide the radiological information for medical response. For this reason, the NREMC establish and re-organized dose assessment system based on the existing dose assessment system of the NREMC recently. The exposure dose could be measured by physical and biological method. With these two methods, we can have conservative dose assessment result. Therefore the NREMC established the exposure dose assessment laboratory which was re-organized laboratory space and introduced specialized equipment for dose assessment. This paper will report the establishment and operation of exposure dose assessment laboratory for radiological emergency response and discuss how to enhance

  7. The 1988 activity report of the Nuclear Research Center of Strasbourg

    International Nuclear Information System (INIS)

    1989-01-01

    The 1988 activity report of Nuclear Research Center of Strasbourg (France) is presented. 1988 is characterized by significant technical development activities in the field of heavy ion collisions. Several aspects involving the Vivitron system development and objectives are underlined. The main research fields are those on high angular momentum and superplasticity, layer model and nucleon transfer, nuclei far from steady state, scattering model and fusion cross sections. The research programs of the Nuclear Physics, High Energies, Chemistry and Radiation Physics Divisions are presented. Concerning technology transfer, the investigations on accelerators and dosimetry are included. International cooperation main aspects, papers, congress communications and conferences are reported [fr

  8. Assessing the need for a routine monitoring program in three Nuclear Medicine centers in Chile

    International Nuclear Information System (INIS)

    Astudillo, R.; Hermosilla, A.; Diaz-Londono, G.; Garcia, M.

    2015-01-01

    The workers performing different activities with radionuclides in nuclear medicine centers are at potential risk of external exposure and internal contamination. The IAEA Safety Guide No. RS-G-1.2 proposed criteria for determining the need for a routine monitoring program to assess internal contamination. For this purpose, an Excel template containing the IAEA criteria was applied in three nuclear medicine centers in Chile. The results show that it is necessary to carry out a routine monitoring program for five workers who handle 131 I and three for 99m Tc. We propose to implement this template at a national level in order to improve the conditions of radiation protection in the participating centers. (authors)

  9. Annual report of Nuclear Technology and Education Center. April 1, 2007-March 31, 2008

    International Nuclear Information System (INIS)

    2009-03-01

    This annual report summarizes the activities of Nuclear Technology and Education Center (NuTEC) of Japan Atomic Energy Agency (JAEA) in the fiscal year 2007. This is the third year since the inauguration of JAEA, and NuTEC now flexibly designs and carries out training courses upon request while carrying out the annually scheduled training programs. During this period, the number of trainees completing the domestic training courses was 466, and that for staff technical training was 694. Three prep-examination training courses for '1st class radiation protection supervisor', 'Nuclear fuel protection supervisor' and 'Professional engineer on nuclear and radiation' which were opened only for staff members were newly opened to the public. JAEA continued its cooperative activities with universities; cooperation with graduate school of University of Tokyo, cooperative graduate school program with 14 graduate schools and 1 under-graduate school, and Nuclear HRD Program initiated by MEXT and METI implemented since 2007. Joint course has started networking 3 universities utilizing the Japan Nuclear Education Network, and trial experimental courses for students from newly participating universities were offered. International cooperation was also conducted as scheduled. Joint training course and Instructor training program were carried out bilaterally with Indonesia, Thailand and Vietnam. Human Resources Development Workshop under the Forum for Nuclear Cooperation in Asia was arranged, and Asian Nuclear Training and Education Program to enhance the matching of the needs and available training program of the participating countries were discussed. (author)

  10. 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)

  11. Internal radiation dose in diagnostic nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Roedler, H D; Kaul, A; Hine, G J

    1978-01-01

    Absorbed dose values per unit administered activity for the most frequently used radipharmaceuticals and methods were calculated according to the MIRD concept or compiled from literature and were tabulated in conventional as well as in the SI-units recently introduced. The data are given for critical or investigated organs, ovaries, testes and red bone marrow. Where available, dose values for newborns, infants and children are included. Additionally, mean values of administered activity are listed. The manner in which to estimate the radiation dose to the patient is to multiply the tabulated dose values per unit administered activity with the corresponding mean or the actually administered activity. The methods are arranged in correlation with the following nuclear medical subspecialities: 1. Endocrinology 2. Neurology, 3. Osteomyology, 4. Gastroenterology, 5. Nephrology, 6. Pulmonology, 7. Hematology, 8. Cardiology/Angiology.

  12. Nuclear Cross Sections for Space Radiation Applications

    Science.gov (United States)

    Werneth, C. M.; Maung, K. M.; Ford, W. P.; Norbury, J. W.; Vera, M. D.

    2015-01-01

    The eikonal, partial wave (PW) Lippmann-Schwinger, and three-dimensional Lippmann-Schwinger (LS3D) methods are compared for nuclear reactions that are relevant for space radiation applications. Numerical convergence of the eikonal method is readily achieved when exact formulas of the optical potential are used for light nuclei (A = 16) and the momentum-space optical potential is used for heavier nuclei. The PW solution method is known to be numerically unstable for systems that require a large number of partial waves, and, as a result, the LS3D method is employed. The effect of relativistic kinematics is studied with the PW and LS3D methods and is compared to eikonal results. It is recommended that the LS3D method be used for high energy nucleon-nucleus reactions and nucleus-nucleus reactions at all energies because of its rapid numerical convergence and stability for both non-relativistic and relativistic kinematics.

  13. General activities of JAERI nuclear data center and Japanese nuclear data committee

    International Nuclear Information System (INIS)

    Fukahori, Tokio

    1999-01-01

    The nuclear data center of Japan Atomic Energy Research Institute (JAERI/NDC) is playing the role of Japanese domestic nuclear data center and gateway to foreign data centers. As the domestic nuclear data center, activities of JAERI/NDC are 1) compiling the Japanese Evaluated Nuclear Data Library (JENDL) for both general and special purposes, 2) importing and exporting nuclear data, 3) nuclear data services for the domestic users, and 4) organizing japanese Nuclear Data Committee (JNDC) as a secretariat. Compiled JENDL General Purpose Files up to now are JENDL-1, 2, 3, 3.1 and 3.2. The data for 340 nuclei in the energy range from 10 -5 eV to 20 MeV are available in JENDL-3.2. JENDL Special Purpose Files were also prepared in order to meet the requests from the specified application fields. JNDC has about 140 members. JNDC consists of Main Committee, Steering Committee, Subcommittee on Nuclear Data, Subcommittee on Reactor Constants, Subcommittee on Nuclear Fuel Cycle and Standing Groups. Above subcommittees are performing essential evaluation for the files described above, checking the JENDL files through the benchmark and integral testing as well as considering the standard group constant, and considering about evaluation of decay heat and nuclide generation/depletion and fission product yields. (author)

  14. 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

  15. A reference center for evaluation and assistance of radiation victims

    International Nuclear Information System (INIS)

    Valverde, Nelson J.L.; Oliveira, A. Alexandre; Peregrino, Augusto A.; Almeida, Carlos E.V. de

    1995-01-01

    The medical assistance of of accidentally exposed individuals to ionizing radiation demands a highly qualified support, considering human, organizational and materials resources. Such a need has been highlighted since the Goiania Radiation Accident in 1987. The Reference Center for Evaluation and Assistance of Radiation Victims - CRAAR was designed within the framework of the Laboratory of Radiological Sciences - LCR of the University of the State of Rio de Janeiro - UFRJ. Its main purposes are no coordinate the medical tertiary response in a radiation accident and to serve as a training site for all personnel that may respond to such a condition. This paper describes the three-level scheme of assistance adopted by CRAAR and its insertion in the National Radiological Emergency Assistance System under development by the Health Ministry. (author). 15 refs

  16. A reference center for evaluation and assistance of radiation victims

    International Nuclear Information System (INIS)

    Lima Valverde, Nelson Jose de; Peregrino, Antonio Augusto; Almeida, Carlos Eduardo V. de

    1995-01-01

    The medical assistance of accidentally exposed individuals to ionizing radiation demands a highly qualified support, considering human, organizational and material resources. Such a needed has been highlighted since the Goiania Radiation Accident in 1987. The Reference Center for Evaluation and Assistance of Radiation Victims - CRAAR was designed within the framework of the Laboratory of Radiological Sciences - LCR of the University of the State of Rio de Janeiro - UERJ. Its main purposes are to coordinate the medical tertiary response in a radiation accident and to serve as a training site for all personnel that may respond to such a condition. This paper describes the three-level scheme of assistance adopted by CRAAR and its insertion in the National Radiological Emergency Assistance System under development by the Health Ministry. (author). 15 refs

  17. NNDC [National Nuclear Data Center] on-line services documentation

    International Nuclear Information System (INIS)

    Dunford, C.L.; Burrows, T.W.; Tuli, J.K.

    1987-01-01

    This document summarizes and describes how to access the on-line services available from the National Nuclear Data Center (NNDC) located at Brookhaven National Laboratory. The services are available free of cost to US Department of Energy, its contractors and others who support the NNDC or supply data to the NNDC. Four of the center's data bases are now accessible to non-NNDC scientists via remote connection to the center's VAX 11/780. To use this service, you must have a terminal with access by either a telephone line or the PHYSNET network. A VT100 terminal or a terminal with VT-100 emulation is recommended but not required

  18. Bituminization of radioactive wastes at the Nuclear Research Center Karlsruhe

    International Nuclear Information System (INIS)

    Hild, W.; Kluger, W.; Krause, H.

    1976-05-01

    A summary is given of the main operational experience gained at the Nuclear Research Center Karlsruhe in 4 years operation of the bituminization plant for evaporator concentrates from low- and medium level wastes. At the same time some of the essential results are compiled that have been obtained in the R + D activities on bituminization. (orig.) [de

  19. 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

  20. Regional radiation protection center in the Federal Republic of Germany - Tasks and Organization

    International Nuclear Information System (INIS)

    Koelzer, W.

    1988-01-01

    In the Federal Republic of Germany 220,000 staff members are classified at the moment as occupationally radiation exposed persons. For the maintenance of industrial health and safety for the workers in the companies and for the medical, professional and social rehabilitaion after an accident the so-called ''Berufsgenossenschaften'' (professional trade associations) are responsible. For employees in nuclear industry two trade associations are competent: - the Trade Association for Precision Engineering and Electrical Engineering for the 6,000 employees in nuclear power plants, - the Trade Association of the Chemical Industry for the 4,000 employees in fuel element fabrication and the reprocessing companies. In case of an accident workers from service companies e.g. construction and installation companies could be affected as well. Therefore these trade associations have founded a couple of years ago an ''Institute for Radiation Protection''. A special task of this institute is First Aid to overexposed people in case of radiation accidents. In addition, it organizes the 24-hours-service of the seven Regional Radiation Protection Centers of Federal Republic of Germany. The institute provides special training of radiation protection physicians and occupationally radiation exposed persons. (author) [pt

  1. 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

  2. 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.

  3. 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.)

  4. GPU Nuclear Corporation's radiation exposure management system

    International Nuclear Information System (INIS)

    Slobodien, M.J.; Bovino, A.A.; Perry, O.R.; Hildebrand, J.E.

    1984-01-01

    GPU Nuclear Corporation has developed a central main frame (IBM 3081) based radiation exposure management system which provides real time and batch transactions for three separate reactor facilities. The structure and function of the data base are discussed. The system's main features include real time on-line radiation work permit generation and personnel exposure tracking; dose accountability as a function of system and component, job type, worker classification, and work location; and personnel dosemeter (TLD and self-reading pocket dosemeters) data processing. The system also carries the qualifications of all radiation workers including RWP training, respiratory protection training, results of respirator fit tests and medical exams. A warning system is used to prevent non-qualified persons from entering controlled areas. The main frame system is interfaced with a variety of mini and micro computer systems for dosemetry, statistical and graphics applications. These are discussed. Some unique dosemetry features which are discussed include assessment of dose for up to 140 parts of the body with dose evaluations at 7,300 and 1000 mg/cm 2 for each part, tracking of MPC hours on a 7 day rolling schedule; automatic pairing of TLD and self-reading pocket dosemeter values, creation and updating of NRC Forms 4 and 5, generation of NRC required 20.407 and Reg Guide 1.16 reports. As of July 1983, over 20 remote on-line stations were in use with plans to add 20-30 more by May 1984. The system provides response times for on-line activities of 2-7 seconds and 23 1/2 hours per day ''up time''. Examples of the various on-line and batch transactions are described

  5. Nuclear Energy Center Site Survey, 1975. Part III. Technical considerations

    International Nuclear Information System (INIS)

    1976-01-01

    Studies of the technical feasibility of nuclear energy centers (NECs) and the comparison between NEC technical feasibility and that of nuclear facilities on dispersed sites are reviewed. The conclusions related to technical feasibility of NEC are summarized. Technical feasibility was found to rest mainly on five major issues: heat dissipation, transmission, facility construction, radiological impact, and environmental impact. Although general conclusions can be reached in these five areas, it is recognized that they are interdependent, and detailed site-by-site analysis will be necessary. Some general conclusions on technical feasibility of NECs are presented, then detailed conclusions derived from the technical evaluation of NECs compared to dispersed site facilities are presented. The findings of this study on each of the five major feasibility issues are then discussed in sequence. The study concludes that nuclear energy centers, as defined herein, are technically feasible

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

    International Nuclear Information System (INIS)

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

    1980-01-01

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

  7. Guideline on radiation protection requirements for ionizing radiation shielding in nuclear power plants

    International Nuclear Information System (INIS)

    1988-01-01

    The guideline which entered into force on 1 May 1988 stipulates the radiation protection requirements for shielding against ionizing radiation to be met in the design, construction, commissioning, operation, and decommissioning of nuclear power plants

  8. Radiation silver paramagnetic centers in a beta-alumina crystal

    International Nuclear Information System (INIS)

    Badalyan, A.G.; Zhitnikov, R.A.

    1985-01-01

    Silver paramagnetic centers in a β-alumina crystal, formed after X-ray radiation at 77 K, are investigated by the EPR method. Silver enters the β-alumina crystal, substituting sodium and potassium ions in a mirror plane. Crystals with substitution from 0.1 to 100% of alkali metal ions by Ag + ions are investigated. Silver atomic centers (Ag 0 -centers), formed by electron capture with the Ag + ion, are firstly detected and investigated in the β-alumina. Hole Ag 2+ -centers are investigated and detected in crystals with high concentration of Ag + . By studying the orientation dependence of a g-factor it is established that hole capture by the Ag + ion is accompanied by Ag 2+ ion displacement from the position, Ag + being primarity taken up (Beavers-Roth or anti- Beavers-Roth) to the position between two oxygen ions in the mirror plane

  9. Decommissioning Operations at the Cadarache Nuclear Research Center

    International Nuclear Information System (INIS)

    Gouhier, E.

    2008-01-01

    Among the different activities of the CEA research center of Cadarache, located in the south of France, one of the most important involves decommissioning. As old facilities close, decommissioning activity increases. This presentation will give an overview of the existing organization and the different ongoing decommissioning and cleanup operations on the site. We shall also present some of the new facilities under construction the purpose of which is to replace the decommissioned ones. Cadarache research center was created on October 14, 1959. Today, the activities of the research center are shared out among several technological R and D platforms, essentially devoted to nuclear energy (fission and fusion) Acting as a support to these R and D activities, the center of Cadarache has a platform of services which groups the auxiliary services required by the nuclear facilities and those necessary to the management of nuclear materials, waste, nuclear facility releases and decommissioning. Many old facilities have shut down in recent years (replaced by new facilities) and a whole decommissioning program is now underway involving the dismantling of nuclear reactors (Rapsodie, Harmonie), processing facilities (ATUE uranium treatment facility, LECA UO 2 facility) as well as waste treatment and storage facilities (INB37, INB 56. In conclusion: other dismantling and cleanup operations that are now underway in Cadarache include the following: - Waste treatment and storage facilities, - Historical VLLW and HLW storage facility, - Fissile material storage building, - Historical spent fuel storage facility. Thanks to the project organization: - Costs and risks on these projects can be reduced. - Engineers and technicians can easily move from one project to another. In some cases, when a new facility is under construction for the purpose of replacing a decommissioned one, some of the project team can integrate the new facility as members of the operation team. Today

  10. Los Alamos Neutron Science Center (LANSCE) Nuclear Science Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, Ronald Owen [Los Alamos National Laboratory; Wender, Steve [Los Alamos National Laboratory

    2015-06-19

    The Los Alamos Neutron Science Center (LANSCE) facilities for Nuclear Science consist of a high-energy "white" neutron source (Target 4) with 6 flight paths, three low-energy nuclear science flight paths at the Lujan Center, and a proton reaction area. The neutron beams produced at the Target 4 complement those produced at the Lujan Center because they are of much higher energy and have shorter pulse widths. The neutron sources are driven by the 800-MeV proton beam of the LANSCE linear accelerator. With these facilities, LANSCE is able to deliver neutrons with energies ranging from a milli-electron volt to several hundreds of MeV, as well as proton beams with a wide range of energy, time and intensity characteristics. The facilities, instruments and research programs are described briefly.

  11. 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

  12. Nuclear energy and radiation protection law: no. 14 1987

    International Nuclear Information System (INIS)

    1987-01-01

    The full text of Jordan's Nuclear Energy and Radiation Protection Law, no. 14 1987. The law's 39 articles govern all aspects organizing the utilization of nuclear energy and radiation protection activities in the country; including terms and conditions for licensing activities and personnel, and the import, export, and disposal of radioactive sources. The law establishes for the purpose of implementing its regulations, a consultative technical committee and a radiation protection board, both in the Ministry of Energy and Mineral Resources

  13. 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

  14. Cyberattack analysis through Malaysian Nuclear Agency experience as nuclear research center

    International Nuclear Information System (INIS)

    Mohd Dzul Aiman Aslan; Mohd Fauzi Haris; Saaidi Ismail; Nurbahyah Hamdan

    2011-01-01

    As a nuclear research center, Nuclear Malaysia is one of the Critical National Information Infrastructure (CNII) in the country. One of the easiest way to launch a malicious attack is through the online system, whether main web site or online services. Recently, we also under port scanning and hack attempts from various sources. This paper will discuss on analysis based on Nuclear Malaysia experience regarding these attempts which keep arising nowadays. (author)

  15. Genetical effects of radiations from products of nuclear explosions

    Energy Technology Data Exchange (ETDEWEB)

    Spiers, F W

    1955-01-01

    Relative radiation dose-rates to man and to Drosophila are discussed. Data previously presented by Prof. J.B.S. Haldane on the genetical effects of radiation resulting from nuclear explosions are reviewed. A reply from Prof. Haldane presents revised calculations of radiation dose rates.

  16. Nuclear safety and radiation protection in the German Democratic Republic

    International Nuclear Information System (INIS)

    Sitzlack, G.; Scheel, H.

    1976-01-01

    The radiation protection organization in the GDR is outlined laying emphasis on the tasks of the National Board of Nuclear Safety and Radiation Protection. In addition to the basic tasks, the various forms of radiation protection monitoring, the management of radioactive wastes, and international responsibilities are briefly explained. (author)

  17. Present status of the Nuclear Maintenance Training Center

    International Nuclear Information System (INIS)

    Kotani, Fumio

    1995-01-01

    The education and training to keep and improve the knowledge and skills of the maintenance personnel and to hand down the skills undoubtedly play important roles in safe operation and increased reliability to a nuclear power station. The Nuclear Maintenance Training Center (hereafter called the Center) provides a variety of education and training curriculums based on the levels and abilities of the trainees. The Center aims to enhance the personnel's maintenance technique by offering the curriculums on maintenance basic education for operators and supporting education and training for the personnel of contractors. The Center has two main features: first, it has the actual components or the equipment similar to the actual components which will enable the practical training; second, we regard the past troubles as valuable experiences and, therefore, focuses on the education to prevent recurrence of troubles by teaching the trainees the meaning and necessity of the training they take. For eleven years since the establishment of the Center, it has been utilized by the total number of about 60,000 people. As for the tasks in the future, the Center is expected to vitalize itself to give attractive education and training and become more actively involved in development of the maintenance personnel with the adequate knowledge and skills. (author)

  18. Earth Radiation Budget Research at the NASA Langley Research Center

    Science.gov (United States)

    Smith, G. Louis; Harrison, Edwin F.; Gibson, Gary G.

    2014-01-01

    In the 1970s research studies concentrating on satellite measurements of Earth's radiation budget started at the NASA Langley Research Center. Since that beginning, considerable effort has been devoted to developing measurement techniques, data analysis methods, and time-space sampling strategies to meet the radiation budget science requirements for climate studies. Implementation and success of the Earth Radiation Budget Experiment (ERBE) and the Clouds and the Earth's Radiant Energy System (CERES) was due to the remarkable teamwork of many engineers, scientists, and data analysts. Data from ERBE have provided a new understanding of the effects of clouds, aerosols, and El Nino/La Nina oscillation on the Earth's radiation. CERES spacecraft instruments have extended the time coverage with high quality climate data records for over a decade. Using ERBE and CERES measurements these teams have created information about radiation at the top of the atmosphere, at the surface, and throughout the atmosphere for a better understanding of our climate. They have also generated surface radiation products for designers of solar power plants and buildings and numerous other applications

  19. Calculations and analysis of the radiation protection of PET/CT Center

    International Nuclear Information System (INIS)

    Ivanova, S.; Artinyan, A.

    2015-01-01

    Positron Emission Tomography (PET) has been available in number of centers for more than 25 years, but its use was not wide spread until 10 years ago. In Bulgarian PET/CT was installed for the first time in 2009 in Nuclear Medicine Department in University Hospital St. Marina in Varna, Bulgaria. As a physicists the aim for us was to consider and calculate the shielding so that to protect the people and the staff. The purpose of this paper is calculating and analysis of the radiation protection and shielding of Nuclear Medicine Center including PET/CT center situated in University Hospital St. Marina in Varna, Bulgaria. Following the Recommendation of International Commission of Radiation Protection (ICRP) Report 60, Report 73, American Association of Physics in Medicine (AAPM) Task Group 108: PET and PET/CT Shielding Requirements, Medical Physics, DIN 6844-3, Installation of Nuclear Medicine; Radiation protection calculation and the Bulgarian regulations in NM, the new Department was made. The design of the Existing Department was renovated following the requirements for PET/CT Center. The shielding was calculated for imaging room as well as the uptake room, resting room, the PET control room, places above and under the facility, patient WCs and other surrounding laboratories and stuff cabinets. The radiotracer used for the examinations is fluoro-2-desixyglucose (FDG). FDG is labeled with F-18, whose time of flight is only 109min, but it is positron emitting. The energy of annihilation is 511keV. The aim was achieved. The Department was opened. It is working now with about 15 patients every day. The dose rates measured with personal TLD’s for the last 5 years for the stuff are under 3mSv. As the average dose is around 1mSv, and the doses over 1mSv are only for nurses who injected the FDG. (authors)

  20. Energy Frontier Research Center, Center for Materials Science of Nuclear Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Todd R. Allen

    2011-12-01

    This is a document required by Basic Energy Sciences as part of a mid-term review, in the third year of the five-year award period and is intended to provide a critical assessment of the Center for Materials Science of Nuclear Fuels (strategic vision, scientific plans and progress, and technical accomplishments).

  1. National Nuclear Center of the Republic of Kazakhstan in the system of nuclear terrorism counteractions at Kazakhstan territory

    International Nuclear Information System (INIS)

    Tukhvatulin, Sh.T.; Zhotabayev, Zh.R.; Azarov, V.A.; Silayev, M.E.

    2002-01-01

    authorities and reduction of their power and capabilities, a general threat of terrorist acts at companies using nuclear and radiation technologies has increased. In addition, due to its geographical position, the Republic of Kazakhstan is a transit state between Europe and Asia. That is why, numerous cases of transit shipment and sale attempts of nuclear materials from other states including the former SU republics were recorded here (e.g., fuel elements from Chernobyl NPP). The above demonstrates an unprejudiced necessity of arranging an efficient counteraction system against nuclear terrorism in the Republic of Kazakhstan. The current Kazakhstan system of nuclear and radioactive materials control does not meet the present-day requirements. Its efficiency and capabilities should obviously be increased. This will allow avoiding considerable losses by existing economical figures and potential political losses in the international relations. After collapse of the Soviet Union, major nuclear research institutions and branches left at the territory of independent Kazakhstan were consolidated into a uniform organization: the Republican State Enterprise National Nuclear Center of the Republic of Kazakhstan. At present, four institutions are functioning under the aegis of the Center. By this time, many directions of the Center activity are related or contribute to potential nuclear terrorism counteractions. Among the wide range of these activities, the major ones are worth mentioning, both performed and in process: The project on elimination of the last nuclear device at the former Semipalatinsk Test-Site territory; The projects on weapons of mass destruction infrastructure elimination. In particular, projects related to closure and permanent sealing of defense tunnels used and prepared for nuclear weapon testing; The project on irreversible shut-down and decommissioning with following long-term conservation of BN-350 fast power reactor in Aktau; The project on the high plutonium

  2. 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)

  3. Information report on the nuclear safety and radiation protection of the Aube center for short-lived low- and intermediate-level wastes storage - 2011. Annual report in the framework of article 21 of the Act on nuclear transparency and safety

    International Nuclear Information System (INIS)

    2012-06-01

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

  4. Basic radiation effects in nuclear power electronics technology

    International Nuclear Information System (INIS)

    Gover, J.E.; Srour, J.R.

    1985-05-01

    An overview is presented of the effects of radiation in microelectronics technology. The approach taken throughout these notes is to review microscopic phenomena associated with radiation effects and to show how these lead to macroscopic effects in semiconductor devices and integrated circuits. Bipolar integrated circuits technology is reviewed in Appendix A. Appendix B gives present and future applications of radiation-tolerant microelectronics in nuclear power applications as well as the radiation tolerance requirements of these applications

  5. The project of Esfahan Nuclear Technology Center (ENTEC) and the transfer of nuclear tecnology in Iran

    International Nuclear Information System (INIS)

    Khazaneh, Reza

    1977-01-01

    In 1974, the Atomic Energy Organization of Iran (AEOI) decided to set up a Nuclear Technology Center on Esfahan (ENTEC) in collaboration with France's Technicatome Company and the CEA. This center is scheduled to go into operation during 1976-1980. The purposes for setting up ENTEC are threefold: a. to give scientific and technical support to the operation of nuclear power plants and nuclear industries in Iran. b. to carry out research and development in the area of nuclear technology on an industrial level. c. to give supplementary education and training to the manpower needs for the AEOI. To carry out the program of technology transfer, temporary laboratories have been set up in Tehran for engineers, technicians and training programs have been organized primarily in France. The ENTEC project will also include a school for education of junior scientists and engineers in the field of nuclear technology

  6. 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.)

  7. 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

  8. 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.

  9. 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)

  10. Waste management at the Karlsruhe Nuclear Research Center

    International Nuclear Information System (INIS)

    Hoehlein, G.; Lins, W.

    1982-01-01

    In the Karlsruhe Nuclear Research Center the responsibility for waste management is concentrated in the Decontamination Department which serves to collect and transport all liquid waste and solid material from central areas in the center for further waste treatment, clean radioactive equipment for repair and re-use or for recycling of material, remove from the liquid effluents any radioactive and chemical pollutants as specified in legislation on the protection of waters, convert radioactive wastes into mechanically and chemically stable forms allowing them to be transported into a repository. (orig./RW)

  11. 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)

  12. Personnel radiation safety in nuclear power plants

    International Nuclear Information System (INIS)

    Elkert, J.

    1979-05-01

    The principal contributions to the radiation doses of the Swedish power reactor personnel are identified. The possi bilities to reduce these doses are examined. The radiation doses are analyzed according to different personnel categories, specific maintenance operations or inspections and to different radiation activities. Suggestions are given for reducing the radiation doses. (L.E.)

  13. Assessment of PWR plutonium burners for nuclear energy centers

    International Nuclear Information System (INIS)

    Frankel, A.J.; Shapiro, N.L.

    1976-06-01

    The purpose of the study was to explore the performance and safety characteristics of PWR plutonium burners, to identify modifications to current PWR designs to enhance plutonium utilization, to study the problems of deploying plutonium burners at Nuclear Energy Centers, and to assess current industrial capability of the design and licensing of such reactors. A plutonium burner is defined to be a reactor which utilizes plutonium as the sole fissile addition to the natural or depleted uranium which comprises the greater part of the fuel mass. The results of the study and the design analyses performed during the development of C-E's System 80 plant indicate that the use of suitably designed plutonium burners at Nuclear Energy Centers is technically feasible

  14. List of scientific publications, Nuclear Research Center Karlsruhe 1984

    International Nuclear Information System (INIS)

    1985-04-01

    The report abstracted contains a list of works published in 1984. Papers not in print yet are listed separately. Patent entries take account of all patent rights granted or published in 1984, i.e. patents or patent specifications. The list of publications is classified by institutes. The project category lists but the respective reports and studies carried out and published by members of the project staff concerned. Also listed are publications related to research and development projects of the 'product engineering project' (PFT/Projekt 'Fertigungstechnik'). With different companies and institutes cooperating, PFT is sponsored by Nuclear Research Center Karlsruhe GmbH. The latter is also responsible for printing above publications. Moreover the list contains the publications of a branch of the Bundesforschungsanstalt fuer Ernaehrung which is located on the KfK-premises. The final chapter of the list summarizes publications dealing with guest-experiments and research at Nuclear Research Center Karlsruhe. (orig./PW) [de

  15. Equipment for nuclear medical centers, production capabilities of Rosatom enterprises

    International Nuclear Information System (INIS)

    Gavrish, Yu. N.; Koloskov, S. A.; Smirnov, V. P.; Strokach, A. P.

    2015-01-01

    Analysis of the capabilities of the State Corporation Rosatom enterprises on the development and production of diagnostic and therapeutic equipment for nuclear medicine centers is presented. Prospects of the development of accelerator equipment for the production of a wide range of radioisotope products are shown, and the trends of its development are determined. A comparative analysis of the technical parameters of domestic tomographs and devices for brachytherapy with foreign counterparts is given

  16. Equipment for nuclear medical centers, production capabilities of Rosatom enterprises

    Science.gov (United States)

    Gavrish, Yu. N.; Koloskov, S. A.; Smirnov, V. P.; Strokach, A. P.

    2015-12-01

    Analysis of the capabilities of the State Corporation Rosatom enterprises on the development and production of diagnostic and therapeutic equipment for nuclear medicine centers is presented. Prospects of the development of accelerator equipment for the production of a wide range of radioisotope products are shown, and the trends of its development are determined. A comparative analysis of the technical parameters of domestic tomographs and devices for brachytherapy with foreign counterparts is given.

  17. List of scientific publications of Nuclear Research Center Karlsruhe 1983

    International Nuclear Information System (INIS)

    1984-04-01

    This report contains the titles of the publications edited in the year 1983. The scientific and technical-scientific publications of the Nuclear Research Center Karlsruhe are printed as books, as original contributions in scientific or technical specialists' journals, as scripts for habilitation, thesis, scripts for diploma, as patents, as KfK-Reports (KfK=Kernforschungszentrum Karlsruhe) and are being presented as lectures on scientific meetings. No further separate abstracts of this list of publications were prepared. (orig./HBR) [de

  18. Twenty-fifth anniversary of the Juelich Nuclear Research Center

    International Nuclear Information System (INIS)

    Haefele, W.

    1982-01-01

    On December 10, 1981, KFA Juelich celebrated its 25th year of existence; on December 11, 1956, the land parliament of North Rhine Westphalia had decided in favour of the erection of a joint nuclear research facility of the land of North Rhine Westphalia. In contrast to other nuclear research centers, the Juelich centre was to develop and operate large-scale research equipment and infrastructure for joint use by the universities of the land. This cooperation has remained an important characteristic in spite of the independent scientific work of KFA institutes, Federal government majorities, and changes in research fields and tasks. KFA does fundamental research in nuclear and plasma physics, solid state research, medicine, life sciences, and environmental research; other activities are R + D tasks for the HTR reactor and its specific applications as well as energy research in general. (orig.) [de

  19. History of the Iraqi Nuclear Center of Tuwaitha

    International Nuclear Information System (INIS)

    Fabbri, Silvio

    2009-01-01

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

  20. Westinghouse Nuclear Core Design Training Center - a design simulator

    International Nuclear Information System (INIS)

    Altomare, S.; Pritchett, J.; Altman, D.

    1992-01-01

    The emergence of more powerful computing technology enables nuclear design calculations to be done on workstations. This shift to workstation usage has already had a profound effect in the training area. In 1991, the Westinghouse Electric Corporation's Commercial Nuclear Fuel Division (CNFD) developed and implemented a Nuclear Core Design Training Center (CDTC), a new concept in on-the-job training. The CDTC provides controlled on-the-job training in a structured classroom environment. It alllows one trainer, with the use of a specially prepared training facility, to provide full-scope, hands-on training to many trainees at one time. Also, the CDTC system reduces the overall cycle time required to complete the total training experience while also providing the flexibility of individual training in selected modules of interest. This paper provides descriptions of the CDTC and the respective experience gained in the application of this new concept

  1. 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)

  2. 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)

  3. 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)

  4. RECENT ACTIVITIES AT THE CENTER FOR SPACE NUCLEAR RESEARCH FOR DEVELOPING NUCLEAR THERMAL ROCKETS

    International Nuclear Information System (INIS)

    O'Brien, Robert C.

    2001-01-01

    Nuclear power has been considered for space applications since the 1960s. Between 1955 and 1972 the US built and tested over twenty nuclear reactors/ rocket-engines in the Rover/NERVA programs. However, changes in environmental laws may make the redevelopment of the nuclear rocket more difficult. Recent advances in fuel fabrication and testing options indicate that a nuclear rocket with a fuel form significantly different from NERVA may be needed to ensure public support. The Center for Space Nuclear Research (CSNR) is pursuing development of tungsten based fuels for use in a NTR, for a surface power reactor, and to encapsulate radioisotope power sources. The CSNR Summer Fellows program has investigated the feasibility of several missions enabled by the NTR. The potential mission benefits of a nuclear rocket, historical achievements of the previous programs, and recent investigations into alternatives in design and materials for future systems will be discussed.

  5. Annual report of Nuclear Human Resource Development Center. April 1, 2015 - March 31, 2016

    International Nuclear Information System (INIS)

    2017-07-01

    This annual report summarizes the activities of Nuclear Human Resource Development Center (NuHRDeC) of Japan Atomic Energy Agency (JAEA) in the fiscal year (FY) 2015. In FY 2015, we were actively engaged in organizing special training courses in response to external training needs, cooperating with universities, and offering international training courses for Asian countries in addition to the regular training programs at NuHRDeC. In accordance to the annual plan for national training, we conducted training courses for radioisotopes and radiation engineers, nuclear energy engineers, and national qualification examinations, as well as for officials in Nuclear Regulatory Authority and prefectural and municipal officials in Fukushima as outreach activities in order to meet the training needs from the external organizations. We continued to enhance cooperative activities with universities, such as the acceptance of postdoctoral researchers, the cooperation according to the cooperative graduate school system, including the acceptance of students from Nuclear Professional School of University of Tokyo. Furthermore, through utilizing the remote education system, the joint course was successfully held with seven universities, and the intensive summer course and the practical exercise at Nuclear Fuel Cycle Engineering Laboratories were also conducted as part of the collaboration network with universities. The Instructor Training Program (ITP) was continually offered to the ITP participating countries (Bangladesh, China, Indonesia, Kazakhstan, Malaysia, Mongolia, Philippines, Saudi Arabia, Sri Lanka, Thailand, Turkey and Viet Nam) in FY2015 under contact with Ministry of Education, Culture, Sports, Science and Technology. As part of the ITP, the Instructor Training Course and the Nuclear Technology Seminar were organized at NuHRDeC such as “Reactor Engineering Course” and “Basic Radiation Knowledge for School Education Seminar”. Eight and eleven countries

  6. 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

  7. Titanium Loop Heat Pipes for Space Nuclear Radiators, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — This Small Business Innovation Research Phase I project will develop titanium Loop Heat Pipes (LHPs) that can be used in low-mass space nuclear radiators, such as...

  8. 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

  9. Requirements of radiation protection and safety for nuclear medicine services

    International Nuclear Information System (INIS)

    1989-01-01

    The requirements of radiation protection and safety for nuclear medicine services are established. The norms is applied to activities related to the radiopharmaceuticals for therapeutics and 'in vivo' diagnostics purposes. (M.C.K.) [pt

  10. The design of intelligentized nuclear radiation monitoring detector

    International Nuclear Information System (INIS)

    Meng Yan; Fang Zongliang; Wen Qilin; Li Lirong; Hu Jiewei; Peng Jing

    2010-01-01

    This paper introduced an intelligentized nuclear radiation monitoring detector. The detector contains GM tubes, high voltage power supply and MCU circuit. The detector connect terminal via reformative serial port to provide power, accept the data and sent the command. (authors)

  11. NNDC [National Nuclear Data Center] support for fusion nuclear data needs

    International Nuclear Information System (INIS)

    Dunford, C.L.

    1988-01-01

    The National Data Center (NNDC) located at Brookhaven National Laboratory is an outgrowth of the Sigma Center founded by D.J. Hughes to compile low energy neutron reaction data in the 1950's. The center has played a lead role in the production of evaluated nuclear data (ENDF/B) for the United States nuclear power program. This data file, now in its sixth version, is produced as a cooperative effort of many DOE funded organizations via the Cross Section Evaluation Working Group (GSEWG). The NNDC's role, in addition to providing the structure and leadership for CSEWG, is to supply compiled bibliographic and experimental data and provide file processing, checking, distribution and documentation services. In the past, the NNDC has also produced nuclear data evaluations.lt. slash

  12. Radiation safety knowledge of medical center radiology technologists in southern Taiwan

    Energy Technology Data Exchange (ETDEWEB)

    Su Wen-Chuan; Huang Ying-Fong; Chen Cheng-Chung; Chang Pao-Shu [Kaohsiung Medical University, Taiwan (China)

    2000-05-01

    People who live in Taiwan are getting more and more afraid of radiation. Sometimes the phobia results from distorted knowledge. Radiology technologists, in one hand, are more well-educated in radiation and, in the other hand, have more chance to expose to radiation when they are operating radiation producing medical instruments in their daily life. So we are interested in whether they have enough knowledge to protect themselves. We pick up the radiology technology board examination to make the questionnaire for this study. The population is the radiology technologists who work at department of diagnostic radiology, of radiation therapy and nuclear medicine in medical centers. Statistics is then used to see the relationship between knowledge and the factors including gender, age and career period. Based on statistics, we find out that there is significant correlation between the knowledge with age or education level. Elder or lower education level ones has worse knowledge. Continued education may be highly recommended for radiology technologists to avoid occupational radiation injury. (author)

  13. Radiation safety knowledge of medical center radiology technologists in southern Taiwan

    International Nuclear Information System (INIS)

    Su Wen-Chuan; Huang Ying-Fong; Chen Cheng-Chung; Chang Pao-Shu

    2000-01-01

    People who live in Taiwan are getting more and more afraid of radiation. Sometimes the phobia results from distorted knowledge. Radiology technologists, in one hand, are more well-educated in radiation and, in the other hand, have more chance to expose to radiation when they are operating radiation producing medical instruments in their daily life. So we are interested in whether they have enough knowledge to protect themselves. We pick up the radiology technology board examination to make the questionnaire for this study. The population is the radiology technologists who work at department of diagnostic radiology, of radiation therapy and nuclear medicine in medical centers. Statistics is then used to see the relationship between knowledge and the factors including gender, age and career period. Based on statistics, we find out that there is significant correlation between the knowledge with age or education level. Elder or lower education level ones has worse knowledge. Continued education may be highly recommended for radiology technologists to avoid occupational radiation injury. (author)

  14. Verifying a nuclear weapon`s response to radiation environments

    Energy Technology Data Exchange (ETDEWEB)

    Dean, F.F.; Barrett, W.H.

    1998-05-01

    The process described in the paper is being applied as part of the design verification of a replacement component designed for a nuclear weapon currently in the active stockpile. This process is an adaptation of the process successfully used in nuclear weapon development programs. The verification process concentrates on evaluating system response to radiation environments, verifying system performance during and after exposure to radiation environments, and assessing system survivability.

  15. Introduction to symposium 'radiation protection at nuclear facilities'

    International Nuclear Information System (INIS)

    Stricker, L.

    1996-01-01

    An introduction to the symposium 'radiation protection of nuclear facilities' on Wednesday, April 17, 1996 in Vienna has been given. The number of operating reactors and the total collective dose per reactor in OECD countries has been discussed. The evolution of the total collective dose associated with the replacement of steam generators at nuclear power reactors from 1979 to 1995 is presented. The background and culture of radiation protection, regulatory aspects, strategic formulation, plan management policy and organization responsibilities are discussed generally. (Suda)

  16. Joint nuclear safety research projects between the US and Russian Federation International Nuclear Safety Centers

    International Nuclear Information System (INIS)

    Bougaenko, S.E.; Kraev, A.E.; Hill, D.L.; Braun, J.C.; Klickman, A.E.

    1998-01-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) formed international Nuclear Safety Centers in October 1995 and July 1996, respectively, to collaborate on nuclear safety research. Since January 1997, the two centers have initiated the following nine joint research projects: (1) INSC web servers and databases; (2) Material properties measurement and assessment; (3) Coupled codes: Neutronic, thermal-hydraulic, mechanical and other; (4) Severe accident management for Soviet-designed reactors; (5) Transient management and advanced control; (6) Survey of relevant nuclear safety research facilities in the Russian Federation; (8) Advanced structural analysis; and (9) Development of a nuclear safety research and development plan for MINATOM. The joint projects were selected on the basis of recommendations from two groups of experts convened by NEA and from evaluations of safety impact, cost, and deployment potential. The paper summarizes the projects, including the long-term goals, the implementing strategy and some recent accomplishments for each project

  17. 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

  18. 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)

  19. Personnel Radiation Protection at the ITER Nuclear Fusion Facility

    Energy Technology Data Exchange (ETDEWEB)

    Coniglio, A.; Sandri, S. [ENEA, Radiation Protection Institute, Frascati (Italy); D' Arienzo, M. [RFX, Padova (Italy)

    2006-07-01

    The hosting site for the ITER nuclear fusion experiment was finally chosen in France (Cadarache). The radiation protection program for the ITER personnel involved into operation and maintenance activities will be then tested in the near future. Related studies were mainly carried out during the last ten years and important assessments were performed at the Frascati ENEA Research Center in Italy. In this ambit individual and collective doses to the operators were calculated for different categories of working activities involving more and less critical systems. The radiation protection organization was outlined and the related program was proposed. A short review of the analyses performed in this field by the Italian investigators of the ENEA Radiation Protection Institute is shown here. The principal parameter taken into account in these evaluations was the collective dose due to the different working activities. This quantity has been assessed considering the following radiological source terms: a) the prompt radiation during the plasma burning phase, b) the gamma radiation due to the neutron activation of the solid structures, c) the activated corrosion products (ACPs) generated in the water cooling system (WCS) by corrosion of the inner wall of the piping under the neutron flux, d) tritium concentration in the atmosphere of the working premises. Individual doses have been integrated over the different worker typology, considering the design evolution for the different systems and the required person power. Ordinary, inspection and maintenance activities were taken into account to assess the person power, sometime also construction, plant modifications and unscheduled maintenance were included in the working activities list. The collective dose assessed for ITER fusion projects has been compared with that of the fission power stations and analogies and differences have been pointed out. In this review the dose assessment process is recalled starting from the

  20. Personnel Radiation Protection at the ITER Nuclear Fusion Facility

    International Nuclear Information System (INIS)

    Coniglio, A.; Sandri, S.; D'Arienzo, M.

    2006-01-01

    The hosting site for the ITER nuclear fusion experiment was finally chosen in France (Cadarache). The radiation protection program for the ITER personnel involved into operation and maintenance activities will be then tested in the near future. Related studies were mainly carried out during the last ten years and important assessments were performed at the Frascati ENEA Research Center in Italy. In this ambit individual and collective doses to the operators were calculated for different categories of working activities involving more and less critical systems. The radiation protection organization was outlined and the related program was proposed. A short review of the analyses performed in this field by the Italian investigators of the ENEA Radiation Protection Institute is shown here. The principal parameter taken into account in these evaluations was the collective dose due to the different working activities. This quantity has been assessed considering the following radiological source terms: a) the prompt radiation during the plasma burning phase, b) the gamma radiation due to the neutron activation of the solid structures, c) the activated corrosion products (ACPs) generated in the water cooling system (WCS) by corrosion of the inner wall of the piping under the neutron flux, d) tritium concentration in the atmosphere of the working premises. Individual doses have been integrated over the different worker typology, considering the design evolution for the different systems and the required person power. Ordinary, inspection and maintenance activities were taken into account to assess the person power, sometime also construction, plant modifications and unscheduled maintenance were included in the working activities list. The collective dose assessed for ITER fusion projects has been compared with that of the fission power stations and analogies and differences have been pointed out. In this review the dose assessment process is recalled starting from the

  1. The role of the National INIS Center in presenting Macedonian nuclear and nuclear related sciences

    International Nuclear Information System (INIS)

    Sejmenova-Gichevska, Marija

    2007-01-01

    The Republic of Macedonia is 95th Member State of INIS and its participation in this cooperative decentralized system started in 1996 when the Macedonian INIS Center was established to be operated by the National and University Library 'Kliment Ohridski' in Skopje. The main objective of this study is to give an overview of the Macedonian nuclear and nuclear related scientific thought presented in the INIS Database. A statistical analysis of the Macedonian INIS Center's contribution to the INIS Database for the period of its constitution to 2006, by quantifying and reviewing the language, publication type and INIS subject categories of the submitted records is presented. (author)

  2. 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)

  3. Current research and development at the Nuclear Research Center Karlsruhe

    International Nuclear Information System (INIS)

    Kuesters, H.

    1982-01-01

    The Nuclear Research Center Karlsruhe (KfK) is funded to 90% by the Federal Republic of Germany and to 10% by the State of Baden-Wuerttemberg. Since its foundation in 1956 the main objective of the Center is research and development (R and D) in the aera of the nuclear technology and about 2/3 of the research capacity is now devoted to this field. Since 1960 a major activity of KfK is R and D work for the design of fast breeder reactors, including material research, physics, and safety investigations; a prototype of 300 MWe is under construction now in the lower Rhine Valley. For enrichment of 235 U fissile material KfK developed the separation nozzle process; its technical application is realized within an international contract between the Federal Republic of Germany and Brazil. Within the frame of the European Programme on fusion technology KfK develops and tests superconducting magnets for toroidal fusion systems; a smaller activity deals with research on inertial confinement fusion. A broad research programme is carried through for safety investigations of nuclear installations, especially for PWRs; this activity is supplemented by research and development in the field of nuclear materials' safeguards. Development of fast reactors has to initiate research for the reprocessing of spent fuel and waste disposal. In the pilot plant WAK spent fuel from LKWs is reprocessed; research especially tries e.g. to improve the PUREX-process by electrochemical means, vitrification of high active waste is another main activity. First studies are being performed now to clarify the necessary development for reprocessing fast reactor fuel. About 1/3 of the research capacity of KfK deals with fundamental research in nuclear physics, solid state physics, biology and studies on the impact of technology on environment. Promising new technologies as e.g. the replacement of gasoline by hydrogen cells as vehicle propulsion are investigated. (orig.)

  4. Hiroshima Synchrotron Radiation Center - An outline and scientific activities

    CERN Document Server

    Taniguchi, M

    2003-01-01

    High energy-resolution and low-temperature photoemission spectroscopies (DELTA E=4.5-20 meV and T=6-300 K) have been started on undulator beamlines at Hiroshima Synchrotron Radiation Center with a compact light source. Beamlines for high energy-resolution photoemission spectroscopy and their application to direct observation of pseudogap formation in Kondo systems (CeRhAs, CeRhSb, CePtSn and CeNiSn, LaNiSn) are presented.

  5. Education in radiation, radioactivity, and nuclear science

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  6. Education in radiation, radioactivity, and nuclear science

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  7. Energy Frontier Research Center, Center for Materials Science of Nuclear Fuels

    International Nuclear Information System (INIS)

    Allen, Todd R.

    2011-01-01

    The Office of Science, Basic Energy Sciences, has funded the INL as one of the Energy Frontier Research Centers in the area of material science of nuclear fuels. This document is the required annual report to the Office of Science that outlines the accomplishments for the period of May 2010 through April 2011. The aim of the Center for Material Science of Nuclear Fuels (CMSNF) is to establish the foundation for predictive understanding of the effects of irradiation-induced defects on thermal transport in oxide nuclear fuels. The science driver of the center's investigation is to understand how complex defect and microstructures affect phonon mediated thermal transport in UO2, and achieve this understanding for the particular case of irradiation-induced defects and microstructures. The center's research thus includes modeling and measurement of thermal transport in oxide fuels with different levels of impurities, lattice disorder and irradiation-induced microstructure, as well as theoretical and experimental investigation of the evolution of disorder, stoichiometry and microstructure in nuclear fuel under irradiation. With the premise that thermal transport in irradiated UO2 is a phonon-mediated energy transport process in a crystalline material with defects and microstructure, a step-by-step approach will be utilized to understand the effects of types of defects and microstructures on the collective phonon dynamics in irradiated UO2. Our efforts under the thermal transport thrust involved both measurement of diffusive phonon transport (an approach that integrates over the entire phonon spectrum) and spectroscopic measurements of phonon attenuation/lifetime and phonon dispersion. Our distinct experimental efforts dovetail with our modeling effort involving atomistic simulation of phonon transport and prediction of lattice thermal conductivity using the Boltzmann transport framework.

  8. Pakistan nuclear safety and radiation protection regulation 1990

    International Nuclear Information System (INIS)

    1990-01-01

    In this act regulations of nuclear safety and radiation protection in Pakistan has been explained. A legal and licensing procedure to handle protection of nuclear materials, processing storage of radioactive products has been described under this regulation. In these regulations full explanation of accidental exposure, delegation of powers and record keeping/waste disposal of radioactive has been given. (A.B.)

  9. Nuclear and radiation safety assurance federal target programme management system

    International Nuclear Information System (INIS)

    Kryukov, O.V.; Vasil'ev, V.A.; Nikishin, D.A.; Linge, I.I.; Obodinskij, A.N.

    2012-01-01

    The Federal Program Nuclear and Radiation Safety Assurance for 2008-2015 is presented. Specifics of Federal target program management as well as changes to program management are discussed. Data on evaluation of management effectiveness is given. Further efforts to resolve the nuclear legacy problem in Russia are also presented [ru

  10. Report on nuclear and radiation safety in Slovenia in 1999

    International Nuclear Information System (INIS)

    Lovincic, D.

    2000-09-01

    The Slovenian Nuclear Safety Administration (SNSA) has prepared Report on Nuclear and Radiation Safety in Slovenia in 1999. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia.

  11. Pakistan nuclear safety and radiation protection ordinance-1984

    International Nuclear Information System (INIS)

    1984-01-01

    An act to provide the regulations of nuclear safety and radiation protection in Pakistan has been explained. A legal and licensing procedure to handle production of nuclear materials, processing, storage of radioactive products and wastes has been described under this regulation. (A.B.)

  12. 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)

  13. Nuclear and radiation techniques - state of art and development trends

    International Nuclear Information System (INIS)

    Chmielewski, A.G.

    1995-01-01

    The state of art and development trends of nuclear and radiation techniques in Poland and worldwide have been presented. Among them the radiometric gages, radiation technologies, radiotracer methods and measuring systems for pipeline and vessels, brightness control have been described and their applications in industry, agriculture, health and environment protection have been shown and discussed. 35 refs, 1 fig

  14. Is natural background or radiation from nuclear power plants leukemogenic?

    International Nuclear Information System (INIS)

    Cronkite, E.P.

    1989-01-01

    The objective in this review is to provide some facts about normal hemopoietic cell proliferation relevant to leukemogenesis, physical, chemical, and biological facts about radiation effects with the hope that each person will be able to decide for themselves whether background radiation or emissions from nuclear power plants and facilities significantly add to the spontaneous leukemia incidence. 23 refs., 1 tab

  15. A radiation monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Iwai, Masaru; Nakamori, S.; Ikeda, H.; Oda, M.

    1974-01-01

    Safety with respect to radiation is vital factor, particularly in view of the increasing number of nuclear power plants. For this purpose, a radiation monitoring system is provided to perform constant supervision. This article describes the purpose, installation location, specifications and circuitry of a system which is divided into three units: the process monitor, area monitor and off-site monitor. (auth.)

  16. Radiation and ecological safety of nuclear fuel cycle installations

    International Nuclear Information System (INIS)

    Barbasheva, S.V.

    1995-01-01

    Nuclear power plants (NPP) and radioactive waste facilities safety issues are discussed; Chernobyl NPP personnel radiation doses for 1986 are indicated; radiation contamination of environment by Am-241 is investigated; data on radioactive contamination in southern part of Kiev Poles'e are considered

  17. Organization of radiation protection in German nuclear power stations

    International Nuclear Information System (INIS)

    1989-01-01

    Using the operating handbooks of the nuclear power stations in West Germany, an examination was carried out of how far the existing organisational structure for radiation protection fulfils the requirements for protection and whether a standardisation of the organisation would provide improvements for the protection of the personnel and for the practicability of the radiation protection organisation. In particular, the parts 'Personnel operating organisation', 'Radiation protection order' and 'Maintenance order' of the operating handbook were evaluated and an audit was made of the radiation protection organisation. In general, the result of the assessment is that the organisation of radiation protection does not contradict the orders, guidelines and regulations in any of the nuclear power stations examined. Corresponding to the possibilities of regulating details of the radiation protection organisation within the undertaking, the target of 'protection of the personnel against radioactive irradiation' is achieved by the various organisation structures which are largely equal to the given example. (orig./HP) [de

  18. 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

  19. Materials characterization center workshop on the irradiation effects in nuclear waste forms

    International Nuclear Information System (INIS)

    Roberts, F.P.; Turcotte, R.P.; Weber, W.J.

    1981-01-01

    The Workshop on Irradiation Effects in Nuclear Waste Forms sponsored by the Materials Characterization Center (MCC) brought together experts in radiation damage in materials and waste-management technology to review the problems associated with irradiation effects on waste-form integrity and to evaluate standard methods for generating data to be included in the Nuclear Waste Materials Handbook. The workshop reached the following conclusions: the concept of Standard Test for the Effects of Alpha-Decay in Nuclear Waste Solids, (MCC-6) for evaluating the effects of alpha decay is valid and useful, and as a result of the workshop, modifications to the proposed procedure will be incorpoated in a revised version of MCC-6; the MCC-6 test is not applicable to the evaluation of radiation damage in spent fuel; plutonium-238 is recommended as the dopant for transuranic and defense high-level waste forms, and when high doses are required, as in the case of commercial high-level waste forms, 244 Cm can be used; among the important property changes caused by irradiation are those that lead to greater leachability, and additionally, radiolysis of the leachant may increase leach rates; research is needed in this area; ionization-induced changes in physical properties can be as important as displacement damage in some materials, and a synergism is also likely to exist from the combined effects of ionization and displacement damage; and the effect of changing the temperature and dose rates on property changes induced by radiation damage needs to be determined

  20. Status and problem for Nuclear Power Plant Maintenance Training Center

    International Nuclear Information System (INIS)

    Nanjoh, Takuo

    1991-01-01

    The Nuclear Power Plant Maintenance Training Center of Kansai Electric Power Co., Inc. was founded in October, 1983, and seven years elapsed since then. The education and training of 37,000 persons were carried out to meet the situation in the plants and to enhance the facilities. Though the main policy of the practical training for preventing the recurrence of troubles does not change, the situation changed from the time of the foundation, and the role has expanded, including PA activities. The see-through plant model installed for technical education in April, 1989 is the about 1/25 scale model of the actual machine with two loops, which actually generates steam and slight electric power, and is useful for promoting the understanding of nuclear power generation theory. It accomplishes the important role that the visitors to the Center (7500 persons in 1989 fiscal year) understand the mechanism of nuclear power generation. In 1990, the education curriculum, the method of education, the time of education and so on are reviewed, aiming at the improvement of education. The execution of education and training, the training of practical techniques, the reflection of the examples of troubles to education, and the expansion of facilities are reported. (K.I.)

  1. Waste management of the Nuclear Technology Development Center - CDTN

    International Nuclear Information System (INIS)

    Miaw, S.T.W.; Oliveira Lopes, M.J. de; Tello, C.C.O. de; Silva, E.M.P. da; Guzella, M.F.R.; Reis, L.C.A.; Menezes Cussiol, N.A. de

    1993-01-01

    Liquid and solid wastes of low radiation level are produced at the Nuclear Technology Development Centre (CDTN). Trying to minimise the waste volume and to give proper treatment, the wastes, are segregated at their origin according their radiological, chemistry and physical characteristics. The Radioactive Waste Program was established in 1983 based on CNEN resolution 6/73 and more recently modernized following CNEN Norm NE-6.05. This paper describes all activities involved in CDTN's Program. (B.C.A.). 6 refs, 02 tabs, 01 fig

  2. Neutron spectrometry by diamond detector for nuclear radiation

    International Nuclear Information System (INIS)

    Kozlov, S.F.; Konorova, E.A.; Barinov, A.L.; Jarkov, V.P.

    1975-01-01

    Experiments on fast neutron spectrometry using the nuclear radiation diamond detector inside a horizontal channel of a water-cooled and water-moderated reactor are described. It is shown that the diamond detector enables neutron spectra to be measured within the energy range of 0.3 to 10 MeV against reactor gamma-radiation background and has radiation resistance higher than that of conventional semiconductor detectors. (U.S.)

  3. 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

  4. Ordinance on the Finnish Centre of Radiation and Nuclear Safety

    International Nuclear Information System (INIS)

    1990-01-01

    This Ordinance was adopted in implementation of the 1983 Act setting up the Finnish Centre for Radiation and Nuclear Safety and the 1987 Nuclear Energy Act and entered into force on 1 November 1990. The Ordinance specifies the tasks of the Centre, as provided under both Acts, and gives it several supplementary responsibilities. In addition to its overall competence in respect of radiation safety, the Centre will carry out research into and supervise the health effects of radiation and maintain a laboratory for national measurements in that field. The Ordinance also sets out the Centre's organisation chart and the staff duties [fr

  5. Provision of operational radiation protection services at nuclear power plants

    International Nuclear Information System (INIS)

    1990-01-01

    The purpose of this publication is to provide practical guidance on establishing and maintaining a radiation protection programme for a nuclear power plant that is consistent with the optimization process recommended in the Basic Safety Standards. This publication is written with a view to providing guidance to every person associated with the radiation protection programme for a nuclear power plant and develops the theme that radiation protection requires the commitment of all plant staff, including higher levels of executive management. 12 refs, 2 figs

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

    International Nuclear Information System (INIS)

    Liu Xinhua; Xu Chunyan

    2013-01-01

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

  7. Sustainability indicators to nuclear research centers in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Alves, Simone F.; Feliciano, Vanusa Maria D.; Barreto, Alberto A., E-mail: symonfonseca@yahoo.com.br, E-mail: vmfj@cdtn.br, E-mail: aab@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2015-07-01

    The relevance and applicability of sustainability indicators have been discussed in various international and national debates through forums, conferences, seminars and lectures. The information obtained from the use of these indicators is essential to the decision-making process, contributing to the creation of discussion channels and interaction with society; also it is useful for the design and implementation of environmental education programs, perception and risk communication. So far, at least in Brazil, existing indicators for the nuclear area are related only to power generation, as performance and safety in radioactive waste management. According to this reality we see the need to build indicators that contribute to the assessment of environmental, social, cultural, economic and institutional performance of a nuclear innovation and research institute in Brazil. This work aims to highlight, through literature review, the importance of developing sustainability indicators appropriate to nuclear research centers in Brazil, revealing how much they are strategic to measuring the sustainability of these endeavours. The main finding, after the literature review, is that this type of indicator is important not only to identify positive or negative impacts of a project focused on the research and innovation of nuclear area, but also for assessment of his commitment to the sustainable development. (author)

  8. Sustainability indicators to nuclear research centers in Brazil

    International Nuclear Information System (INIS)

    Alves, Simone F.; Feliciano, Vanusa Maria D.; Barreto, Alberto A.

    2015-01-01

    The relevance and applicability of sustainability indicators have been discussed in various international and national debates through forums, conferences, seminars and lectures. The information obtained from the use of these indicators is essential to the decision-making process, contributing to the creation of discussion channels and interaction with society; also it is useful for the design and implementation of environmental education programs, perception and risk communication. So far, at least in Brazil, existing indicators for the nuclear area are related only to power generation, as performance and safety in radioactive waste management. According to this reality we see the need to build indicators that contribute to the assessment of environmental, social, cultural, economic and institutional performance of a nuclear innovation and research institute in Brazil. This work aims to highlight, through literature review, the importance of developing sustainability indicators appropriate to nuclear research centers in Brazil, revealing how much they are strategic to measuring the sustainability of these endeavours. The main finding, after the literature review, is that this type of indicator is important not only to identify positive or negative impacts of a project focused on the research and innovation of nuclear area, but also for assessment of his commitment to the sustainable development. (author)

  9. 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.)

  10. Electric power transmission for a Hanford Nuclear Energy Center (HNEC)

    International Nuclear Information System (INIS)

    Harty, H.; Dowis, W.J.

    1983-06-01

    The original study of transmission for a Hanford Nuclear Energy Center (HNEC), which was completed in September 1975, was updated in June 1978. The present 1983 revision takes cognizance of recent changes in the electric power situation of the PNW with respect to: (1) forecasts of load growth, (2) the feasibility of early use of 1100 kV transmission, and (3) the narrowing opportunities for siting nuclear plants in the region. The purpose of this update is to explore and describe additions to the existing transmission system that would be necessary to accommodate three levels of generation at HNEC. Comparisons with a PNW system having new thermal generating capacity distributed throughout the marketing region are not made as was done in earlier versions

  11. Dating ancient monuments by nuclear radiation

    International Nuclear Information System (INIS)

    Goedicke, C.

    2000-01-01

    In the fifties and sixties several disciplines dealing with chronologies but lacking precise methods of measurements (geology, biology, archaeology and art history) became aware of the radioactive decay as a tool of measuring elapsed time. Among the disciplines that benefit most from physical methods archaeology has to be named first. So was archaeological work revolutionised by the introduction of the C-14 dating method. A wider selection of material became datable after the introduction of luminescence techniques using the effect of nuclear radiation on semiconductors. These minerals are widespread among archaeological materials. In ancient monuments, the objective of this paper, semiconductors almost exclusively form the material basis. Over the last four millennia wood, stone, mortar and fired bricks have been used for the construction of buildings. After discussing methods taking wood as a dating material, a broader view will be given on the results achieved by luminescence dating of fired bricks, mortar and stone. For many years brick dating was performed by thermoluminescence, the recipes followed those of ceramic dating. Preferably multiple aliquot additive dose protocols were used on polymineral fine grain fractions (1-10 μm). It was expected that the error in dating monuments would be smaller compared to ceramic dating, because of the constancy of the environmental conditions which a brick experiences during its lifetime. However, the variability of firing temperatures in brick kilns overthrows this advantage. Therefore, the demands of art historians to fall short of an error margin of 5% could generally not be fulfilled. Especially in medieval or renaissance times the temporal resolution of thermoluminescence is inferior to traditional stylistic dating as long as specific stylistic forms are present. New optical luminescence techniques and a new philosophy of dose evaluation, based on single aliquot regeneration protocols, produce less scatter, and in

  12. Effects of beta/gamma radiation on nuclear waste glasses

    Energy Technology Data Exchange (ETDEWEB)

    Weber, W.J. [Pacific Northwest National Lab., Richland, WA (United States)

    1997-07-01

    A key challenge in the disposal of high-level nuclear waste (HLW) in glass waste forms is the development of models of long-term performance based on sound scientific understanding of relevant phenomena. Beta decay of fission products is one source of radiation that can impact the performance of HLW glasses through the interactions of the emitted {beta}-particles and g-rays with the atoms in the glass by ionization processes. Fused silica, alkali silicate glasses, alkali borosilicate glasses, and nuclear waste glasses are all susceptible to radiation effects from ionization. In simple glasses, defects (e.g., non-bridging oxygen and interstitial molecular oxygen) are observed experimentally. In more complex glasses, including nuclear waste glasses, similar defects are expected, and changes in microstructure, such as the formation of bubbles, have been reported. The current state of knowledge regarding the effects of {beta}/{gamma} radiation on the properties and microstructure of nuclear waste glasses are reviewed. (author)

  13. Effects of beta/gamma radiation on nuclear waste glasses

    International Nuclear Information System (INIS)

    Weber, W.J.

    1997-01-01

    A key challenge in the disposal of high-level nuclear waste (HLW) in glass waste forms is the development of models of long-term performance based on sound scientific understanding of relevant phenomena. Beta decay of fission products is one source of radiation that can impact the performance of HLW glasses through the interactions of the emitted β-particles and g-rays with the atoms in the glass by ionization processes. Fused silica, alkali silicate glasses, alkali borosilicate glasses, and nuclear waste glasses are all susceptible to radiation effects from ionization. In simple glasses, defects (e.g., non-bridging oxygen and interstitial molecular oxygen) are observed experimentally. In more complex glasses, including nuclear waste glasses, similar defects are expected, and changes in microstructure, such as the formation of bubbles, have been reported. The current state of knowledge regarding the effects of β/γ radiation on the properties and microstructure of nuclear waste glasses are reviewed. (author)

  14. 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

  15. Teaching Nuclear Radiation and the Poisoning of Alexander Litvinenko

    Science.gov (United States)

    Lapp, David R.

    2008-03-01

    The recent international story about the death of the former KGB agent Alexander Litvinenko has more than just a few wondering about radiation poisoning and the sinister sounding polonium-210. I was preparing to begin a nuclear radiation unit the Monday after Thanksgiving 2006. As it turned out, Litvinenko died Thanksgiving Day after a short and terrible three-week illness. Having the story continue to unfold throughout the next two weeks of the new unit provided a daily opportunity for students to see the relevance of what we were doing in class. My students were able to have meaningful and informed conversations with their peers and parents over an important international event. They even began to feel a bit like authorities themselves when listening to experts respond to media questions about polonium-210 and nuclear radiation in general. This paper discusses some of the ways that the story of Litvinenko was used while presenting the topic of nuclear radiation.

  16. Radiation protection for population in case of nuclear weapon terrorism

    International Nuclear Information System (INIS)

    Takada, Jun

    2004-01-01

    A radiation disaster was predicted in case of 1 kt nuclear weapon terrorism on the surface. Despite small size, serious radiation exposure became clear in a range more than 10 km that can't be by an aerial explosion. This kind of exposure comes from radioactive fallout of fission products, not from direct nuclear radiation. This spreads to a lee area. More than 1,000,000 population receive a serious dose including fatal dose if the nuclear disaster occurs in Tokyo is expected. If adequate radiation protection applies to the population, 70% of victim may be saved. A method to be effective as this kind of protection is escape from a danger zone by the subway after more than one hour sheltering in a concrete building. (author)

  17. Ongkharak Nuclear Research Center-the role of the consultant

    International Nuclear Information System (INIS)

    Jacobi, A.; De Haller, L.

    1998-01-01

    The Ongkharak Nuclear Research Center Project is known to have started on 26 June 1997. At that date the Contract for the turnkey delivery of the three nuclear facilities, the Reactor Island [RI] , Isotope Production Facility [IPF] and the Waste Processing and Storage Facilities [WPSF], was signed by the Office of the Atomic Energy for Peace [OAEP] with General Atomics [GA]. The involvement of Atomic Consultant - Electrowatt Engineering Ltd. (EWE) - already started more than 2 years earlier than the official start of this ambitious project. Since mid 1995 EWE has been serving in a variety of functions and has been requested to perform numerous tasks in support of OAEP. By acting in the function of the Consultant, EWE was aiming firstly to help the project to proceed as quickly as possible. Secondly EWE was overseeing constantly that the quality of the Center, once finished, will meet the present state of the art, will be licensable in Thailand (or elsewhere) and will be internationally recognised as a safe, reliable and modern research and production installation. The role of EWE covers a multitude of engineering disciplines, such as architecture; civil, mechanical, nuclear, I and C and electrical engineering; nuclear and reactor physics; chemistry and radiopharmacy; economy and price estimation. Besides, EWE has to use its skills in conducting and/or supervising large projects, e.g., by appropriate scheduling, QA surveys, licensing support, document control, etc. Furthermore, EWE is actively involved in know-how transfer to Thai engineers and scientists by working in close co-operation with OAEP's project personnel and - if required - by giving special training courses. This paper presents some highlights as well as routine activities performed by EWE so far in the Project

  18. 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)

  19. Current NDT activities at Cekmece Nuclear Research and Training Center

    International Nuclear Information System (INIS)

    Ekinci, S.

    2004-01-01

    Nondestructive testing (NDT) activities at Cekmece Nuclear Research and Training Center (CNAEM) has been initiated in the Industrial Application Department of the Center which was established in 1976 as the Radioisotope Applications Group for Industry. The Department started its first NDT activity with industrial radiography. The NDT activities have been developed by the support of various national (State Planning Organization (DPT)) and international (IAEA and UNDP) projects. Today, there are five basic NDT techniques (radiography, ultrasonic, magnetic particle, liquid penetrant and eddy current) used in the Industrial Application Department. The Department arranges routinely NDT qualification courses according to ISO 9712 and TS EN 473 standards for level 1 and 2 for Turkish Industry. It also carries out national DPT and IAEA Technical Co-operation projects and gives NDT services in the laboratory and in the field. Digital radiography and digital ultrasonic techniques are being used in advanced NDT applications. This paper describes the NDT activities of CNAEM. (author)

  20. A minimum attention control center for nuclear power plants

    International Nuclear Information System (INIS)

    Meijer, C.H.

    1986-01-01

    Control Centers for Nuclear Power Plants have characteristically been designed for maximum attention by the operating staffs of these plants. Consequently, the monitoring, control and diagnostics oriented cognitive activities by these staffs, were mostly ''data-driven'' in nature. This paper addresses a control center concept, under development by Combustion Engineering, that promotes a more ''information-driven'' cognitive interaction process between the operator and the plant. The more ''intelligent'' and therefore less attentive nature of such interactive process utilizes computer implemented cognitive engineered algorithms. The underlying structure of these algorithms is based upon the Critical Function/Success Path monitoring principle. The paper highlights a typical implementation of the minimum attention concept for the handling of unfamiliar safety related events. (author)

  1. Nuclear power plant radiation: personnel safety aspects

    International Nuclear Information System (INIS)

    Roekmantara, Roestan

    1975-01-01

    Reactor using water as coolant, moderator, and heat transfer can produce a sufficiently great internal and external radiation caused by contamination. The process of contamination and actions that must be taken to avoid radiation workers from receiving more than the maximum permissible dose are presented. (author)

  2. Science, society, and America's nuclear waste: Unit 2, Ionizing radiation

    International Nuclear Information System (INIS)

    1992-01-01

    ''Science, Society and America's Nuclear Waste'' is a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  3. 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

  4. 7. Annual seminar of the scientific initiation of the Center for Development of Nuclear Technology. Abstracts; 7. Seminario anual de iniciacao cientifica do Centro de Desenvolvimento da Tecnologia Nuclear. Resumos

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-07-01

    This seminar presents the Scientific Initiation Program developed at the CDTN - Brazilian Center for the Development of Nuclear Technology and focuses on activities of the sectors of: radiopharmaceutical production; radiation applied to health; waste management; structural integrity; environment; nanotechnology and nuclear materials; reactor technology; mineral technology; reactor and analytical techniques.

  5. Establishment of Experimental Equipment for Training of Professionals in the Nuclear Radiation Measurement

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, S. K.; Seo, K. W.; Joo, Y. C.; Kim, I. C.; Woo, C. K.; Yoo, B. H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-09-15

    The main purpose of this project is to establish experimental equipment for training of professionals and students in the field of radiation measurement, and settle the foundation for the advanced education system and program. The priority for the experimental equipment had been deduced by reviewing of the Nuclear Training and Education Center of KAERI and other country's training courses. Equipment for training of radiation professionals are High-Purity Germanium spectroscopic systems, alpha analyzers, and hand-held gamma/neutron inspector systems. For the basic experiments, electric personal dosimeters and a reader, radiation survey meters, and various alpha, beta and gamma radiation isotopes have been equipped. Some old or disused equipment and devices were disposed and re-arranged, and a new experiment lab had been settled for gamma spectroscopy. Along with the preparation of equipment, 14 experimental modules have been selected for practical and essential experiments training to professionals from industries, universities and research organizations. Among the modules, 7 important experiment notes had been prepared in Korea and also in English. As a consequence, these advanced radiation experimental setting would be a basis to cooperate with IAEA or other countries for international training courses. These activities would be a foundation for our contribution to the international nuclear society and for improving our nuclear competitiveness. The experimental equipment and application notes developed in this study will be used also by other training institutes and educational organizations through introducing and encouraging to use them to the nuclear society.

  6. Establishment of Experimental Equipment for Training of Professionals in the Nuclear Radiation Measurement

    International Nuclear Information System (INIS)

    Ahn, S. K.; Seo, K. W.; Joo, Y. C.; Kim, I. C.; Woo, C. K.; Yoo, B. H.

    2008-09-01

    The main purpose of this project is to establish experimental equipment for training of professionals and students in the field of radiation measurement, and settle the foundation for the advanced education system and program. The priority for the experimental equipment had been deduced by reviewing of the Nuclear Training and Education Center of KAERI and other country's training courses. Equipment for training of radiation professionals are High-Purity Germanium spectroscopic systems, alpha analyzers, and hand-held gamma/neutron inspector systems. For the basic experiments, electric personal dosimeters and a reader, radiation survey meters, and various alpha, beta and gamma radiation isotopes have been equipped. Some old or disused equipment and devices were disposed and re-arranged, and a new experiment lab had been settled for gamma spectroscopy. Along with the preparation of equipment, 14 experimental modules have been selected for practical and essential experiments training to professionals from industries, universities and research organizations. Among the modules, 7 important experiment notes had been prepared in Korea and also in English. As a consequence, these advanced radiation experimental setting would be a basis to cooperate with IAEA or other countries for international training courses. These activities would be a foundation for our contribution to the international nuclear society and for improving our nuclear competitiveness. The experimental equipment and application notes developed in this study will be used also by other training institutes and educational organizations through introducing and encouraging to use them to the nuclear society

  7. Continuing training program in radiation protection in biological research centers

    International Nuclear Information System (INIS)

    Escudero, R.; Hidalgo, R.M.; Usera, F.; Macias, M.T.; Mirpuri, E.; Perez, J.; Sanchez, A.

    2008-01-01

    The use of ionizing radiation in biological research has many specific characteristics. A great variety of radioisotopic techniques involve unsealed radioactive sources, and their use not only carries a risk of irradiation, but also a significant risk of contamination. Moreover, a high proportion of researchers are in training and the labor mobility rate is therefore high. Furthermore, most newly incorporated personnel have little or no previous training in radiological protection, since most academic qualifications do not include training in this discipline. In a biological research center, in addition to personnel whose work is directly associated with the radioactive facility (scientific-technical personnel, operators, supervisors), there are also groups of support personnel The use of ionizing radiation in biological research has many specific characteristics. A great variety of radioisotopic techniques involve unsealed radioactive sources, and their use not only carries a risk of irradiation, but also a significant risk of contamination. Moreover, a high proportion of researchers are in training and the labor mobility rate is therefore high. Furthermore, most newly incorporated personnel have little or no previous training in radiological protection, since most academic qualifications do not include training in this discipline. In a biological research center, in addition to personnel whose work is directly associated with the radioactive facility (scientific-technical personnel, operators, supervisors), there are also groups of support personnel maintenance and instrumentation workers, cleaners, administrative personnel, etc. who are associated with the radioactive facility indirectly. These workers are affected by the work in the radioactive facility to varying degrees, and they therefore also require information and training in radiological protection tailored to their level of interaction with the installation. The aim of this study was to design a

  8. Radiation

    International Nuclear Information System (INIS)

    2013-01-01

    The chapter one presents the composition of matter and atomic theory; matter structure; transitions; origin of radiation; radioactivity; nuclear radiation; interactions in decay processes; radiation produced by the interaction of radiation with matter

  9. Nuclear and radiation safety in Slovenia. Annual report 1997

    International Nuclear Information System (INIS)

    1998-01-01

    The Slovenian Nuclear Safety Administration (SNSA), in co-operation with the Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiation Safety in the Republic of Slovenia for 1997. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia. Contributions to the report were furthermore prepared by competent authorities in the field of nuclear safety: the Agency for Radwaste Management (ARAO), the Milan Copic Nuclear Training Centre, etc. The report contains 17 chapters. (author)

  10. Report on nuclear and radiation safety in Slovenia in 1997

    International Nuclear Information System (INIS)

    1998-06-01

    The Slovenian Nuclear Safety Administration (SNSA), in co-operation with the Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiation Safety in the Republic of Slovenia for 1997. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia. Contributions to the report were furthermore prepared by competent authorities in the field of nuclear safety: the Agency for Radwaste Management (ARAO), the Milan Copic Nuclear Training Centre, etc. The report contains 19 chapters.

  11. The IAEA Nuclear Data Center its role in the International Scientific Community

    International Nuclear Information System (INIS)

    Lorenz, A.

    1976-07-01

    The role of the IAEA Nuclear Data Section as an international data information and analysis center for the co-ordination of the world-wide collection, exchange and dissemination of nuclear data is described. Emphasis is put on the recent activities of the center in the assessment of nuclear data needs in various branches of science and technology, and on its projected development as a global referral center for nuclear data. (author)

  12. Establishing control over nuclear materials and radiation sources in Georgia

    International Nuclear Information System (INIS)

    Basilia, G.

    2010-01-01

    Regulatory control over radiation sources in Georgia was lost after disintegration of the Soviet Union. A number of radiation accidents and illegal events occurred in Georgia. From 1999 Nuclear and Radiation Safety Service of the Ministry of Environmental Protection and Natural Resources is responsible for regulatory control over radiation sources in Georgia. US NRC Regulatory Assistance Program in Georgia Assist the Service in establishing long term regulatory control over sources. Main focuses of US NRC program are country-wide inventory, create National Registry of sources, safe storage of disused sources, upgrade legislation and regulation, implementation licensing and inspection activities

  13. NNDC Stand: Activities and Services of the National Nuclear Data Center

    International Nuclear Information System (INIS)

    Pritychenko, B.; Arcilla, R.; Burrows, T.W.; Dunford, C.L.; Herman, M.W.; McLane, V.; Oblozinsky, P.; Sonzogni, A.A.; Tuli, J.K.; Winchell, D.F.

    2005-01-01

    The National Nuclear Data Center (NNDC) collects, evaluates, and disseminates nuclear physics data for basic nuclear research, applied nuclear technologies including energy, shielding, medical and homeland security. In 2004, to answer the needs of nuclear data users community, NNDC completed a project to modernize data storage and management of its databases and began offering new nuclear data Web services. The principles of database and Web application development as well as related nuclear reaction and structure database services are briefly described

  14. What Students Think About (Nuclear) Radiation - Before and After Fukushima

    Science.gov (United States)

    Neumann, S.

    2014-06-01

    Preparing successful science lessons is very demanding. One important aspect a teacher has to consider is the students' previous knowledge about the specific topic. This is why research about students' preconceptions has been, and continues to be, a major field in science education research. Following a constructivistic approach [R. Duit et al., International handbook of research on conceptual change, p. 629 (2008)], helping students learn is only possible if teachers know about students' ideas beforehand. Studies about students' conceptions regarding the major topics in physics education (e.g. mechanics, electrodynamics, optics, thermodynamics), are numerous and well-documented. The topic radiation, however, has seen very little empirical research about students' ideas and misconceptions. Some research was conducted after the events of Chernobyl [P. Lijnse et al., International Journal of Science Education 12, 67 (1990); B. Verplanken, Environment and Behavior 21, 7 (1989)] and provided interesting insight into some of the students' preconceptions about radiation. In order to contribute empirical findings to this field of research, our workgroup has been investigating the conceptions students have about the topic radiation for several years [S. Neumann et al., Journal of Science Education and Technology 21, 826 (2012)]. We used children's drawings and conducted short follow-up interviews with students (9 - 12 years old) and more detailed interviews with 15-year-old students. Both studies were originally done before the events in Fukushima and replicated a year later. We not only asked students about their general associations and emotions regarding the term radiation, but also examined the students' risk perceptions of different types of radiation. Through the use of open-ended questions we were able to examine students' conceptions about different types of radiation (including nuclear) that could be a hindrance to student learning. Our results show that students

  15. Current Trends in Nuclear and Radiation Sensing

    International Nuclear Information System (INIS)

    McHugh, Harold R.; Quam, William

    2009-01-01

    This paper provides a brief overview of radiation detector history, a summary of the present state of the art, and some speculation on future developments in this field. Trends in the development of radiation detectors over the years are analyzed. Rapid progress in detection technology was experienced between WWII and the 1970s. Since then, fewer dramatic improvements have been seen. The authors speculate about the reasons for this trend and where the technology might take us in the next 20 years. Requirements for radiation detection equipment have changed drastically since 9/11; this demand is likely to accelerate detector development in the near future

  16. 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.

  17. Resolution 26/97 Creating of the Protection and Hygiene Radiation Center Presupuested Unit

    International Nuclear Information System (INIS)

    1997-01-01

    The Center of Protection and Hygiene of the Radiations (CPHR) had been created in 1995 (Resolution 128) as Unit of Investigation Development (UID), belonging to the Nuclear Executive Secretary of Matters (SEAN). The objective of the present resolution is to create it now as Unit Bud gotten Center, science unit and integral technique of the Agency of Nuclear Energy (AEN), belonging to the Ministry of Science Technology and environment (CITMA) that has as generic objective to develop in the country the scientific-technical base of to the protection and the radiological security, guaranteeing with it that the applications pacify of the nuclear techniques is developed in harmony with the politics of protection of the health of the workers, the population in general and the environment, in agreement with the technical scientific advances and the international recommendations of this sphere. It also includes the specific objectives of the CPHR, their functions, the services scientific-technicians that it can toast, the entrance date into effect of the law (1 January 1997) and the final dispositions

  18. Twenty-fifth anniversary of the Karlsruhe Nuclear Research Center

    International Nuclear Information System (INIS)

    Harde, R.

    1981-01-01

    The Karlsruhe Nuclear Research Center was founded on July 19, 1956. The initial company, in which the Federal Republic of Germany held a 30% interest, the State of Baden-Wuerttemberg 20%, and German industry 50%, was founded mainly for the purposes of building and operating a German-designed research reactor. In 1959, the Gesellschaft fuer Kernforschung mbH was founded for execution of the research and development activities, in which the Federal Republic of Germany held 75%, the State of Baden-Wuerttemberg 25% of the shares. The two companies were merged in 1963, after industry had donated its holdings in the initial company to the new company. In 1972, the financial holdings of the Federal Government were raised to 90%. On January 1, 1978, the company was named Kernforschungszentrum Karlsruhe GmbH (KfK). Over the past 25 years, KfK has received approx. DM 7 billion out of public funds. Important milestones in the development of nuclear technology in the Federal Republic contributed by KfK include the development of the fast breeder line and responsibility for construction of the first German fast breeder reactor, KNK; development of reprocessing technologies and responsibility for construction of the first German reprocessing plant, WAK; development of a uranium enrichment technique (separation nozzle method); important contributions to reactor safety, fusion research, and training in nuclear technology. (orig.) [de

  19. Innovation Priorities in Nuclear and Radiation Technologies in Russia. View from Skolkovo

    International Nuclear Information System (INIS)

    Fertman, A.; Kovalevich, D.; Turtikov, V.; Zaytseva, N.

    2012-01-01

    The direction for the modernization and technological development of 'Nuclear Technologies' sector of the Russian economy comprises a group of scientific and engineering subjects (atomic engineering, technologies on the basis of radiation, change of properties of materials, radiation resistant microelectronics, etc.), and serves as the foundation of one of the most high-tech industries. The innovative development of nuclear technologies is an integral condition for the strengthening (and in some directions of conquering) a country's position as a global technological leader and preservation of defensive capability of the nation. For this reason, nuclear technologies became one of the priority areas for the activity of the Skolkovo Center. The wide opportunities offered by the application of nuclear technologies were already clear at the deployment stage of the 'Nuclear Project - 1'. In 1958, at the 2nd International conference on the peaceful use of nuclear energy in Geneva, the USSR presented more than 200 reports and communiques in all civil use of atomic energy directions.One of the major results of the development of the nuclear branch have become the developments in the sphere of control of radiation and magnetic fields (radiation technologies). This group of technologies have actively developed in collaboration with design and manufacturing of different types of equipment, including accelerators, neutron generators, lasers, HF-systems, detectors of particles and radiation, microscopes and telescopes, microwave microelectronics, etc. Today these technologies and equipment are used in a variety of other (non-power and not military) markets - and the list of these markets grows constantly. Among the fastest growing ones, we can list the markets of nuclear medicine, sterilization and disinfection, safety and non-destructive testing, ecology and water processing, extraction and the processing of minerals. Historically, the development of nuclear technologies

  20. Occupational radiation exposure in nuclear medicine

    International Nuclear Information System (INIS)

    Gloebel, B.; Muth, H.; Keller, K.D.; Hector, G.; Lehnen, H.

    1982-01-01

    In a large hospital (University Hospital, Homburg/Saar, 2000 beds) the use of radionuclides was determined with the aim of a balance of the radionuclide flow through the clinic and the resulting radiation exposure for the persons involved. (author)

  1. Data for radiation protection and nuclear data

    International Nuclear Information System (INIS)

    Yamaguchi, Yasuhiro; Endo, Akira; Sakamoto, Yukio

    2001-01-01

    Various conversion coefficients have been used in external and internal dosimetry in radiation protection practices. Radiation doses in the human body cannot be directly measured in general situation and the conversion coefficient has been used to correlate the human body dose with physical quantities such as radioactivity, particle fluence and other dosimetric quantities to be used to describe the radiation field. Fluence-to-organ dose conversion coefficients have been calculated using Monte Carlo radiation transport codes in conjunction with an anthropomorphic mathematical phantom. Neutron and photon interaction cross-section libraries are indispensable for these calculations. ICRP Publication 74 gives tables of conversion coefficients for estimation of organ doses and effective dose for photons, neutrons and electrons. Based on these results, shielding calculation parameters have been prepared for simple and easy dose estimation in radiation facilities. Dose factors, organ doses and effective dose per unit intake of radionuclide, have been also calculated for internal dosimetry purpose. ICRP Publications 68 and 72 give tables of dose factors for a variety of radionuclides. Revision of radiation data library has been made to reflect updated information on radionuclides to internal dosimetry. (author)

  2. Energy Frontier Research Center, Center for Materials Science of Nuclear Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Todd R. Allen, Director

    2011-04-01

    The Office of Science, Basic Energy Sciences, has funded the INL as one of the Energy Frontier Research Centers in the area of material science of nuclear fuels. This document is the required annual report to the Office of Science that outlines the accomplishments for the period of May 2010 through April 2011. The aim of the Center for Material Science of Nuclear Fuels (CMSNF) is to establish the foundation for predictive understanding of the effects of irradiation-induced defects on thermal transport in oxide nuclear fuels. The science driver of the center’s investigation is to understand how complex defect and microstructures affect phonon mediated thermal transport in UO2, and achieve this understanding for the particular case of irradiation-induced defects and microstructures. The center’s research thus includes modeling and measurement of thermal transport in oxide fuels with different levels of impurities, lattice disorder and irradiation-induced microstructure, as well as theoretical and experimental investigation of the evolution of disorder, stoichiometry and microstructure in nuclear fuel under irradiation. With the premise that thermal transport in irradiated UO2 is a phonon-mediated energy transport process in a crystalline material with defects and microstructure, a step-by-step approach will be utilized to understand the effects of types of defects and microstructures on the collective phonon dynamics in irradiated UO2. Our efforts under the thermal transport thrust involved both measurement of diffusive phonon transport (an approach that integrates over the entire phonon spectrum) and spectroscopic measurements of phonon attenuation/lifetime and phonon dispersion. Our distinct experimental efforts dovetail with our modeling effort involving atomistic simulation of phonon transport and prediction of lattice thermal conductivity using the Boltzmann transport framework.

  3. Environmental radiation monitoring of nuclear sites by thermoluminescent dosimeters (TLD)

    International Nuclear Information System (INIS)

    Duftschmid, K.E.; Strachotinsky, Ch.

    1978-04-01

    The measurement of environmental radiation doses around nuclear facilities requires the detection of few mrem/year. The properties of the automatic TLD-system Harshaw Mod. 2271 for such measurements have been evaluated under practical conditions and optimized techniques derived. The automatic TLD-system is based on LiF dosimeter cards with two crystals providing gamma and beta dose values. Limit of detection defined as three standard deviations of residuel dose is 1,2 mR. Automatic readout combined with electronic data evaluation are especially useful for large monitoring networks. Practical intercomparisons of this dosimeter with bulb-type CaF 2 detectors have been performed showing good agreement of both detector. Although bulb-dosimeters proved to be extremely sensitive with a limit of detection at 0,012 mR which makes them very suitable for very short exposure times, the automatic LiF system is superior in regards of man power requirement if monthly monitoring periods are sufficient. The system has been tested in practice during two international intercomparisons performed by the US Department of Energy - Health and Safety Laboratory New York and the Physikalisch Technische Bundesanstalt Braunschweig, Germany, showing excellent agreement. Furthermore a routine monitoring network consisting of 12 measurement positions around the Research Center Seibersdorf has been operated with this technique since more than two years. (author)

  4. Environmental radiation monitoring around Korea nuclear fuel company

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Myung Ho; Lee, Chang Woo; Choi, Gyun Sik; Lee, Won Yun; Park, Hyu Gok; Park, Do Won [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-01-01

    Environmental Radiation Monitoring was carried out with measurement of environmental radiation and environmental radioactivity analysis around Korea Nuclear Fuel Company. Environmental Radiation rates measured by portable ERM and accumulated dose rates measured by TLD were on the same level as those measured in the previous years. Total alpha and beta concentrations in the air particulates showed the similar values in all sampling points. The concentration of uranium isotopes in soils and underground waters were measured similar to natural uranium values. The concentration of uranium isotopes in surface waters and sediments around the nuclear facilities were somewhat higher than those from reference site. The concentrations of uranium isotopes in rain water and foods such as rices and vegetables were similar to natural uranium level, the environment around the nuclear facilities has been contaminated only to an insignificant extent. It is estimated that the environmental impact resulting from the operation of KNFC in 2001 was negligible. 31 refs., 30 figs., 41 tabs. (Author)

  5. 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)

  6. Radiation exposure from nuclear medicine studies in children

    International Nuclear Information System (INIS)

    Hach, A.; Reber, H.; Hahn, K.

    1994-01-01

    Nuclear medical examinations of children have to be performed with special regard to the problems of radiation protection because of the high radiation sensitivity esp. of infants and young children. The present contribution describes how any unnecessary radiation exposure can be avoided by the correct choice and planning of a nuclear medical study, by using the appropriate radiopharmaceutical as well as by the exact calculation of the amount of activity applied, depending on body surface resp. body weight of the child. A technically optimized method which employs the best technical equipment and personnel, being specially trained for working with children, are important conditions to achieve optimal results of nuclear medical tests. Due to the difficulties of direct dose measurements, large variations in the biokinetic behaviour of radiopharmaceuticals and the restriction to standard phantoms, individual dose calculations or dose estimations in pediatrics cause great problems. This is reflected by often large variations of dosimetrical data given in the literature. (orig.) [de

  7. Epidemiological studies on radiation carcinogenesis in human populations following acute exposure: nuclear explosions and medical radiation

    International Nuclear Information System (INIS)

    Fabrikant, J.I.

    1981-05-01

    The current knowledge of the carcinogenic effect of radiation in man is considered. The discussion is restricted to dose-incidence data in humans, particularly to certain of those epidemiological studies of human populations that are used most frequently for risk estimation for low-dose radiation carcinogenesis in man. Emphasis is placed solely on those surveys concerned with nuclear explosions and medical exposures

  8. 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)

  9. Radiation effects on organic materials in nuclear plants. Final report

    International Nuclear Information System (INIS)

    Bruce, M.B.; Davis, M.V.

    1981-11-01

    A literature search was conducted to identify information useful in determining the lowest level at which radiation causes damage to nuclear plant equipment. Information was sought concerning synergistic effects of radiation and other environmental stresses. Organic polymers are often identified as the weak elements in equipment. Data on radiation effects are summarized for 50 generic name plastics and 16 elastomers. Coatings, lubricants, and adhesives are treated as separate groups. Inorganics and metallics are considered briefly. With a few noted exceptions, these are more radiation resistant than organic materials. Some semiconductor devices and electronic assemblies are extremely sensitive to radiation. Any damage threshold including these would be too low to be of practical value. With that exception, equipment exposed to less than 10 4 rads should not be significantly affected. Equipment containing no Teflon should not be significantly affected by 10 5 rads. Data concerning synergistic effects and radiation sensitization are discussed. The authors suggest correlations between the two effects

  10. Nuclear radiation-warning detector that measures impedance

    Science.gov (United States)

    Savignac, Noel Felix; Gomez, Leo S; Yelton, William Graham; Robinson, Alex; Limmer, Steven

    2013-06-04

    This invention is a nuclear radiation-warning detector that measures impedance of silver-silver halide on an interdigitated electrode to detect light or radiation comprised of alpha particles, beta particles, gamma rays, X rays, and/or neutrons. The detector is comprised of an interdigitated electrode covered by a layer of silver halide. After exposure to alpha particles, beta particles, X rays, gamma rays, neutron radiation, or light, the silver halide is reduced to silver in the presence of a reducing solution. The change from the high electrical resistance (impedance) of silver halide to the low resistance of silver provides the radiation warning that detected radiation levels exceed a predetermined radiation dose threshold.

  11. Nuclear and radiation emergency evaluation and decision-making support system for ministry of environmental protection

    International Nuclear Information System (INIS)

    Yue Huiguo; Lin Quanyi; Zhang Jiangang

    2010-01-01

    This article introduces the design features and main functions of The Nuclear and Radiation Emergency Evaluation and Decision Support System. The Ministry of Environmental Protection will construct a complete set of evaluation and decision-making system at the Nuclear Safety Center of Ministry of Environmental Protection to cope with the sudden event. The system will provide a comprehensive technical support for the consequence evaluation and decision-making of anti-terrorism event according to the responsibility of MEP in the sudden event, with the data provided by the MEP's anti-terrorism information platform. (authors)

  12. Training sessions for radiation protection. A singular occasion to analyze the risk perception by nuclear workers

    International Nuclear Information System (INIS)

    Escudie, M.

    1986-04-01

    The training sessions for radiation protection - given on the one hand to employees of the decontamination and storage action section, of the nuclear center of Saclay, and on the other hand to technicians of low and medium activity laboratories - represent a goog ground to test hypotheses mentioned at the origin of the analysis of the perception of risk by the nuclear workers undertaken by the Laboratoire d'Etude du Facteur Humain (L.E.F.H., Human Factor Analysis Laboratory) of the Commissariat a l'Energie Atomique (CEA, Atomic Energy Commission of France)

  13. Nuclear medicine and the environment: radiation interactions

    International Nuclear Information System (INIS)

    Schmelter, R.F.

    1986-01-01

    The effect of radiation interactions on the environment may be considered from the perspective of the purely physical phenomena occurring or from the effects the interactions produce in organized biological systems. The physical processes by which radiation interacts with the environment are quite well defined. Although these processes differ depending upon the nature (either electromagnetic or particulate) of the primary radiation, the ultimate result is the production in the medium of high-speed, secondary charged particles. Some of the energy of these particles is absorbed by the medium, while a portion may be lost as bremsstrahlung. The energy that is absorbed produces excitation and ionization, which can be disruptive to biological systems. The effects produced by ionizing radiations at the biochemical, cellular, and organ level are less well defined. Nevertheless, available data indicate that certain generalizations are possible. For example, given the ubiquitous nature of water in tissues, macromolecules, regardless of their structural types, tend to serve as acceptors of the energy and products of water radiolysis. However, a deeper insight into the consequences of irradiation requires an understanding of the interplay of such parameters as the type and energy of the radiation, and the dose and rate of its application. Furthermore, at the cellular level, the type and age of the irradiated cells, the concentration of oxygen in their environment, and their cell-cycle phase are all important factors in determining the consequences of irradiation. 72 references

  14. Recent advances in MEMS radiation detectors for improving radiation safety in nuclear reactors

    International Nuclear Information System (INIS)

    Bhisikar, Abhay

    2016-01-01

    MEMS (micro-electro-mechanical-system) is a core technology that leverages integrated circuit (IC) fabrication technology, builds ultra-miniaturized components and, enables radical new system applications. When considering MEMS radiation detectors; they are the specific micromechanical structures which are designed to sense doses of radiations. The present article reviews the most recent progress made in the domain of MEMS ionizing radiation sensors at international level for nuclear reactors which can be relevant to Indian context. (author)

  15. Environmental radiation monitoring system in nuclear power station

    International Nuclear Information System (INIS)

    Matsuoka, Sadazumi; Tadachi, Katsuo; Endo, Mamoru; Yuya, Hiroshi

    1983-01-01

    At the time of the construction of nuclear power stations, prior to their start of operation, the state of environmental radiation must be grasped. After the start of the power stations, based on those data, the system of environmental radiation monitoring is established. Along with the construction of Kashiwazaki-Kariwa Nuclear Power Station, The Tokyo Electric Power Co., Inc. jointly with Fujitsu Ltd. has developed a high-reliability, environmental radiation monitoring system, and adopted ''optical data highways'' using optical fiber cables for communication. It consists of a central monitoring station and 11 telemeter observation points, for collecting both radiation and meteorological data. The data sent to the central station through the highways are then outputted on a monitoring panel. They are analyzed with a central processor, and the results are printed out. (Mori, K.)

  16. Microstructural characterization of radiation effects in nuclear materials

    CERN Document Server

    2017-01-01

    Microstructural Characterization of Radiation Effects in Nuclear Materials provides an overview into experimental techniques that can be used to examine those effects (both neutron and charged particle) and can be used by researchers, technicians or students as a tool to introduce them to the various techniques. The need to examine the effect of radiation on materials is becoming increasingly important as nuclear energy is emerging as a growing source of renewable energy. The book opens with a discussion of why it is important to study the effects of radiation on materials and looks at current and future reactor designs and the various constraints faced by materials as a result of those designs. The book also includes an overview of the radiation damage mechanisms. The next section explores the various methods for characterizing damage including transmission electron microscopy, scanning transmission electron microscopy, analytical electron microscopy, electron backscatter diffraction, atom probe tomography,...

  17. Evaluation of radionuclide calibrator performance with Tc-99m and I-123 in nuclear medicine centers

    International Nuclear Information System (INIS)

    Ahn, Ji Young; Kim, Gwe Ya; Yang, Hyun Kyu; Lim, Chun Il; Lee, Hyun Koo; Kim, Byung Tae; Jeong, Hee Kyo

    2004-01-01

    To minimize unnecessary radiation dose to patients, it is important to ensure that the radiopharmaceutical administered is accurately measured. Tc-99m is one of the popular radionuclide used in nuclear medicine and I-123 is also used widely in nuclear medicine. To investigate the level of measurement performance and to provide the participants with a traceable standard to check and review their calibration factors for these particular radionuclides, Korean Food and Drug Administration (KFDA) as a national secondary standard dosimetry laboratory conducted comparison program for Tc-99m and I-123 in nuclear medicine centers. 72 nuclear medicine centers (78 calibrators) participated in the comparison program for Tc-99m in 2003 and 37 centers (41 calibrators) for I-123 in 2004. For a comparison, Tc-99m and I-123 were accurately sub-divided into a series of 4 ml aliquots in 10 ml P6 vial and delivered to participants. Participants were invited to assay their P6 vial in each of their radionuclide calibrators and to report their results directly to KFDA. For the evaluation of raionuclide, KFDA used NPL-CRC radionuclide calibrator that is traceable to NPL (National Physical Laboratory) primany standard. The difference between the value reported by the hospital (A h ospital) and of the KFDA (A k fda) is expressed as a percent deviation (DEV (%) = 100 (A h ospital - A k fda)/A k fda). If there were calibrators over 10 % deviations, those were checked again with the same procedure. In Tc-99m, 65% of the calibrators showed deviations within 5 % and 18 % were in the range of 5 % < | DEV | ≤10 %, and 17 % were over 10 % deviations. In I-123, 41 % of the calibrators were within ±5 % and 29 % were in the range of 5 % < | DEV | ≤10 % and 30 % were over 10 %. The results have shown that such comparisons are necessary to improve the accuracy of the measurement and to identify radionuclide calibrators that are malfunctioning

  18. Radiation protection in the Czechoslovak nuclear power plants

    International Nuclear Information System (INIS)

    Singer, J.; Koc, J.; Hynek, J.; Trousil, J.

    1987-01-01

    The radiation monitoring by means of the central information system and of autonomous, portable and laboratory devices as well as a brief characteristic of the nuclear power plant radiation fields are described. The new personal dosimetric film and thermoluminescent badges and the method (including the block diagram) for personal dose evaluation are also introduced. Internal contamination monitoring is performed by means of a whole-body counter and excreta sample analysis. Monitoring the influence of effluents from nuclear power plants on environment in Czechoslovakia is based on significant radionuclide measurements in ventilation stacks and in the environment, also by means of the telemetric system, all in connection with mathematical models. (author)

  19. Education in radiation and nuclear technology. Ready for the future?

    International Nuclear Information System (INIS)

    Schoenmuth, T.; Alt, S.; Wodarczack, F.; Heidrich, U.; Kratzsch, A.

    2013-01-01

    The revision of teaching strategies for the field of study 'Radiation and Nuclear Engineering' at the University of Applied Sciences Zittau/Goerlitz is an attractive design with excellent career opportunities to choose from. Thus, the students benefit not least from solid foundations of the general power engineering undergraduates. Additionally it should be noted that on one hand the current developments (e.g. regenerative power generation, power transmission system requirements and energy storage) are increasingly in demand. On the other hand the use of radiation and nuclear installations and facilities is essential - but this will respectively by social constraints currently not represented or shown as an attractive career field. (orig.)

  20. Electronic detection of nuclear radiations; Deteccion Electronica de radiaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Campos, J

    1972-07-01

    This report is the first draft of one of the chapters of a book being prepared under the title: Topics on Practical Nuclear Physics. It is published as a report because of i ts immediate educational value and in order to include in its final draft the suggestions of the readers. (Author)

  1. Report on nuclear and radiation safety in Slovenia in 2000

    International Nuclear Information System (INIS)

    Lovincic, D.

    2001-09-01

    The Slovenian Nuclear Safety Administration (SNSA), in co-operation with the Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiation Safety in the Republic of Slovenia for 2000. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia.

  2. Nuclear and radiation safety in Slovenia. Annual report 2000

    International Nuclear Information System (INIS)

    Lovincic, D.

    2001-09-01

    The Slovenian Nuclear Safety Administration (SNSA), in co-operation with the Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiation Safety in the Republic of Slovenia for 2000. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia. (author)

  3. The computerized radiation control system for the nuclear power plant

    International Nuclear Information System (INIS)

    Hunamoto, H.; Sato, T.; Taniguchi, K.

    1993-01-01

    Major works of Radiation control in nuclear power plant consist of occupational exposure control, radiation monitoring of working areas and surveillance of monitoring equipment, environmental monitoring and so on. Since a large amount of data will be generated from these works, therefore use of high performance computers will be indispensable. The systematization is presently being advanced in The Japan Atomic Power Company from this viewpoint and the project is being realized smoothly. The actual state is introduced

  4. Utility survey on nuclear power plant siting and nuclear energy centers

    International Nuclear Information System (INIS)

    Cope, D.F.; Bauman, H.F.

    1977-01-01

    Most of the large U.S. utilities were surveyed by telephone and mail on questions concerning nuclear power plant siting and nuclear energy centers (NECs). The main purpose of the survey was for guidance of ERDA's NEC program. The questions covered the following topics: availability of sites; impact of environmental and other restraints; plans for development of multi-unit sites; interest in NEC development; interest in including fuel-cycle facilities in NECs; and opinions on the roles desired for the state and Federal governments in power plant siting. The main conclusion of the survey was that, while many utilities were considering multiple-unit sites of 2 to 5 units, none were planning larger energy centers at the present time. However, several expressed interest in NECs as a long-range future development

  5. 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)

  6. Calculation of heat generation due to nuclear radiation in nuclear reactors

    International Nuclear Information System (INIS)

    Torres, L.M.R.; Gomes, I.C.; Maiorino, J.R.

    1986-01-01

    The study is performed for caculating nuclear heating due to the interaction of neutrons and gamma-rays with matter. Modifications were implemented in the ANISN code, that solves the one-dimensional transport equation using the discrete ordinate method, to include nuclear heating calculations. Tests of the implemented modifications were performed in problems of nuclear heating due to radiation energy deposition in a fusion reactor. (Author) [pt

  7. Innovation research on the safety supervision system of nuclear and radiation safety in Jiangsu province

    International Nuclear Information System (INIS)

    Zhang Qihong; Lu Jigen; Zhang Ping; Wang Wanping; Dai Xia

    2012-01-01

    As the rapid development of nuclear technology, the safety supervision of nuclear and radiation becomes very important. The safety radiation frame system should be constructed, the safety super- vision ability for nuclear and radiation should be improved. How to implement effectively above mission should be a new subject of Provincial environmental protection department. Through investigating the innovation of nuclear and radiation supervision system, innovation of mechanism, innovation of capacity, innovation of informatization and so on, the provincial nuclear and radiation safety supervision model is proposed, and the safety framework of nuclear and radiation in Jiangsu is elementally established in the paper. (authors)

  8. Radiation leakage in nuclear ship 'MUTSU'

    International Nuclear Information System (INIS)

    Ando, Yoshio; Miyasaka, Shun-ichi; Takeuchi, Kiyoshi.

    1975-01-01

    Associated with the radiation leakage in MUTSU occurred in September 1974, this report reviews the shielding design for MUTSU, radiation measurement and inspection activities by a survey group, and 2 dimensional analysis on the behavior of fast neutrons to shielding based on Ssub(N) codes. In the first part, the purpose and the structure of the primary and the secondary shields of MUTSU are briefly illustrated. In the second part, the progress of the series of affairs is explained, starting from zero power criticality experiment, through discovery of radiation leakage in output-increasing test, sending of a survey group for various measurement and inspection, and finally to the conclusion drawn by the survey group. In the third part, various numerical analyses performed to investigate into the leakage are illustrated with their results. The transport codes used were ANISN, TWOTRAN, SPAN, and PALLAS-2DCY. As a result of those inspection and calculation, it was found that the radiation leakage was due to fast neutrons coming through the gap between the reactor vessel and the primary shield. (Aoki, K.)

  9. Initial Human Response to Nuclear Radiation

    Science.gov (United States)

    1982-04-01

    symptomatic response to radiation. In the second phase, the models will be used to infer performance effects. DNA staff members Cyrus Knowles and David ...P. Setty ATTN: K. Schwartz ATTN: J. NcGahan Kamn Tempo System Planning Corp ATTN: R. Miller ATTN: J. JonesATTN: G. Perks Kamen Tempo AiT: S. Shrier

  10. Quality management system of Saraykoy Nuclear Research and Training center

    International Nuclear Information System (INIS)

    Gurellier, R.; Akchay, S.; Zararsiz, S.

    2014-01-01

    Full text : Technical competence and national/international acceptance of independency of laboratories is ensured by going through accreditations. It provides decreasing the risk of a slowdown in international trade due to unnecessary repetition of testing and analyses. It also eliminates the cost of additional experiments and analyses. Saraykoy Nuclear Research and Training Center (SANAEM) has performed intensive studies to establish an effective and well-functioning QMS (Quality Management System) by full accordance with the requirements of ISO/IEC 17025, since the begining of 2006. Laboratories, especially serving to public health studies and important trade duties require urgent accreditation. In this regard, SANAEM has established a quality management system and performed accreditation studies

  11. Role of public health center for nuclear disaster

    International Nuclear Information System (INIS)

    Okada, Tsuyoshi

    2012-01-01

    The role of public health center such as surveillance screening, mass decontamination, health consultation and management, and dosage of stable iodine tablets are thought by Nuclear Safety Commission in 2008. The pollution screening and decontamination, internal exposure screening and valuation, dosage of iodine tablets, health consultation of residents and risk communication, comparative evaluation of health risks, health management under the low dose exposure are discussed to handle problems by the government and local government, and to protect the right to know information. In order to prepare the serious health hazard, the children's thyroid gland test and internal exposure test and the follow-up system have to be practiced by the local government. (S.Y.)

  12. Training in nuclear and radiation safety in Latin American and Caribbean

    International Nuclear Information System (INIS)

    Papadopulos, S.; Diaz, O.; Larcher, A.; Echenique, L.; Nicolas, R.; Lombardi, R.; Quintana, G.

    2013-01-01

    From thirty-three years, Argentina has taken the commitment to train professionals in the field of nuclear and radiation safety for the care and protection of workers and public in general. Sponsored by the IAEA and supported by the Faculty of Engineering of the University of Buenos Aires (FIUBA), an undertaking was made to encourage the training of scientists and experts in the countries of the region in order to establish a strong safety culture in radiation in individuals and maintaining high standards of safety practices using ionizing radiation. In 2012, the Graduate Course in Radiation Protection and Safety of Radiation Sources has acquired the status of 'Specialization' of the FIUBA, a category that further hierarchies skills training in the subject. This is a highly anticipated achievement by the implications for academic institutions, national and regional level, contributing to the strengthening of the Regional Training Center for Latin America and the Caribbean, acknowledged in a long-term agreement between the IAEA and Argentina in September 2008. Due to increased demand for nuclear activity, it is important to continue and deepen further training in radiological and nuclear areas. In order to satisfy both national and regional needs a process of increase on training offer training is being carried out, under the jurisdiction frame of the Nuclear Regulatory Authority. This paper presents the achievements of the country so far as regards training of human resource in radiation protection and nuclear safety in the region and highlights the challenges ahead for the extension of the offer in education and training. (author)

  13. Laboratory for Calibration of Gamma Radiation Measurement Instruments (LabCal) of Institute of Chemical, Biological, Radiological and Nuclear Defense (IDQBRN) from Brazilian Army Technology Center (CTEx); Laboratorio de Calibracao de Instrumentode Medicao de Radiacao Gama (LabCal) do IDQBRN do CTEx

    Energy Technology Data Exchange (ETDEWEB)

    Amorim, Aneuri de; Balthar, Mario Cesar V.; Santos, Avelino; Vilela, Paulo Ricardo T. de; Oliveira, Luciano Santa Rita; Penha, Paulo Eduardo C. de Oliveira; Gonzaga, Roberto Neves; Andrade, Edson Ramos de; Oliveira, Celio Jorge Vasques de; Fagundes, Luiz Cesar S., E-mail: aneurideamorim@gmail.com [Centro Tecnologico do Exercito (DQBRN/CTEx), Rio de Janeiro, RJ (Brazil). Instituto de Defesa Quimica, Biologica, Radiologica e Nuclear

    2016-07-01

    This paper describes the calibration laboratory deployment steps (LABCAL) gamma ionizing radiation measuring instruments in the Army Technology Center, CTEx. Initially the calibration of radiation monitors will be held in the dosimetric quantity air kerma and operational quantity ambient dose equivalent H*(d). The LABCAL / CTEx has not yet authorized by CASEC / CNEN. This laboratory aims to calibrate the ionizing radiation instruments used by the Brazilian Army. (author)

  14. Academic Career Selection and Retention in Radiation Oncology: The Joint Center for Radiation Therapy Experience

    International Nuclear Information System (INIS)

    Balboni, Tracy A.; Chen, M.-H.; Harris, Jay R.; Recht, Abram; Stevenson, Mary Ann; D'Amico, Anthony V.

    2007-01-01

    Purpose: The United States healthcare system has witnessed declining reimbursement and increasing documentation requirements for longer than 10 years. These have decreased the time available to academic faculty for teaching and mentorship. The impact of these changes on the career choices of residents is unknown. The purpose of this report was to determine whether changes have occurred during the past decade in the proportion of radiation oncology trainees from a single institution entering and staying in academic medicine. Methods and Materials: We performed a review of the resident employment experience of Harvard Joint Center for Radiation Therapy residents graduating during 13 recent consecutive years (n = 48 residents). The outcomes analyzed were the initial selection of an academic vs. nonacademic career and career changes during the first 3 years after graduation. Results: Of the 48 residents, 65% pursued an academic career immediately after graduation, and 44% remained in academics at the last follow-up, after a median of 6 years. A later graduation year was associated with a decrease in the proportion of graduates immediately entering academic medicine (odds ratio, 0.78; 95% confidence interval, 0.65-0.94). However, the retention rate at 3 years of those who did immediately enter academics increased with a later graduation year (p = 0.03). Conclusion: During a period marked by notable changes in the academic healthcare environment, the proportion of graduating Harvard Joint Center for Radiation Therapy residents pursuing academic careers has been declining; however, despite this decline, the retention rates in academia have increased

  15. Estimates of the radiation environment for a nuclear rocket engine

    International Nuclear Information System (INIS)

    Courtney, J.C.; Manohara, H.M.; Williams, M.L.

    1992-01-01

    Ambitious missions in deep space, such as manned expeditions to Mars, require nuclear propulsion if they are to be accomplished in a reasonable length of time. Current technology is adequate to support the use of nuclear fission as a source of energy for propulsion; however, problems associated with neutrons and gammas leaking from the rocket engine must be addressed. Before manned or unmanned space flights are attempted, an extensive ground test program on the rocket engine must be completed. This paper compares estimated radiation levels and nuclear heating rates in and around the rocket engine for both a ground test and space environments

  16. The design of nuclear radiation measuring instrument of embedded network

    International Nuclear Information System (INIS)

    Zhang Huaiqiang; Ge Liangquan; Xiong Shengqing

    2009-01-01

    The design and realization of nuclear radiation measuring instrument is introduced. Due to the current nuclear instrument often used serial interface to communicate the PC, it is widely used for simple design and easy operation. However, as the demand of remote data acquisition and the call of sharing resources, the design of embedded the TCP/IP protocol stack into MCU, it may send the nuclear signal in Internet. Some devices that link each other with the network can be networked. The design is not only realizing remote data acquisition and sharing resources, but also reducing costs and improving the maintainability of the system. (authors)

  17. Telephone consultations on exposure to nuclear disaster radiation

    International Nuclear Information System (INIS)

    Yashima, Sachiko; Chida, Koichi

    2014-01-01

    The Fukushima nuclear disaster occurred on March 11, 2011. For about six weeks, I worked as a counselor for phone consultations regarding radiation risk. I analyzed the number of consultations, consultations by telephone, and their changing patterns with elapse of time, to assist with consultations about risk in the future. There were a large number of questions regarding the effects of radiation, particularly with regard to children. We believe that counseling and risk communication are the key to effectively informing the public about radiation risks. (author)

  18. Some problems concerning the radiation protection in nuclear power stations

    International Nuclear Information System (INIS)

    Bozoky, L.

    1977-01-01

    The appearance and fast spreading of the nuclear power stations raised new and difficult questions in connection with the theoretical bases of radiation protection. The new standpoint of the International Commission on Radiological Protection is that both the workers at a pile and the inhabitants take less risk because of ionizing radiation than they usually take in everyday life. The maximum dose which can be permitted remained 5 rem/year for those who professionally deal with ionizing radiation and 0.5 rem/year for the groups in special situation. (V.N.)

  19. Planning nuclear energy centers under technological and demand uncertainty

    International Nuclear Information System (INIS)

    Meier, P.M.; Palmedo, P.F.

    1976-01-01

    The question considered is whether new nuclear power plants should be located in nuclear energy centers, or ''power parks'' with co-located fabrication and reprocessing facilities. That issue has been addressed in a recent study by the Nuclear Regulatory Commission and remains under investigation at Brookhaven and elsewhere. So far, however, the advisability of this policy has been analyzed primarily within the framework of a single view of the future. Suggestions of the types of questions that should be asked regarding this policy if it is properly to be viewed as an example of decision making under uncertainty are made. It is concluded that ''A consideration of the various uncertainties involved in the question of dispersed vs. remote siting of energy facilities introduces a number of new elements into the analysis. On balance those considerations provide somewhat greater support for the clustered concept. The NEC approach seems to provide somewhat greater flexibility in accomodating possible future electricity generating technologies. Increased regulatory and construction efficiencies possible in an NEC reduces the impact of demand uncertainty as does the lower costs associated with construction acceleration or deceleration.'' It is also noted that, in the final analysis, ''it is the public's perception of the relative costs and benefits of a measure that determine the acceptability or unacceptability of a particular innovation,'' not the engineer's cost/benefit analysis. It is further noted that if the analysis can identify limits on analytical methods and models, it will not make the job of energy decision-making any easier, but it may make the process more responsive to its impact on society

  20. Radiation doses to patients from nuclear medicine examinations

    International Nuclear Information System (INIS)

    Boehm, K.; Boehmova, I.

    2014-01-01

    Public Health Authority of the Slovak Republic, Bratislava The exposure of the population to ionizing radiation is rising rapidly, nearly exclusively due to increasing medical use of radiation, including diagnostic methods of nuclear medicine. In 2012 Public health authority of the Slovak republic (PHA SR) performed a survey about the population exposure from nuclear medicine procedures. The primary objectives of this survey were to assess the frequency of different nuclear medicine procedures, determine the average activities administered by nuclear medicine procedures and compare them with the national diagnostic reference levels and determine the annual collective effective dose to the Slovak population from nuclear medicine. The effective dose calculation was based on the methodology of the ICRP32, ICRP80 and ICRP106. In Slovak republic are 11 nuclear medicine departments. The collected data of activities administered by different procedures correspond to 100 % of nuclear medicine departments. The total number of procedures included in the study was 36 250. The most commonly performed procedure was bone scintigraphy (35.9%), followed by lung perfusion and ventilation scintigraphy (17.0%), static and dynamic renal scintigraphy (13.0%), whole-body positron emission tomography of tumors with PET radiopharmaceuticals (11.6%), myocardial perfusion (8.8%), thyroid scintigraphy (6.2%), parathyroid scintigraphy (2.1%), scintigraphy of tumors (2.1%), scintigraphy of the liver and spleen (0.8%), brain perfusion (0.7%) and examination of the gastrointestinal system (0.3%). (authors)

  1. Radiation Detection System for Prevention of Radiological and Nuclear Terrorism

    International Nuclear Information System (INIS)

    Kwak, Sung-Woo; Yoo, Ho-Sik; Jang, Sung-Sun; Kim, Jae-Kwang; Kim, Jung-Soo

    2007-01-01

    After the September 11 terrorist attack, the threat of a potential for a radiological or nuclear terrorist attack became more apparent. The threats relating to radiological or nuclear materials include a Radiological Dispersion Device (RDD), an Improved Nuclear Device (IND) or a State Nuclear Device (such as a Soviet manufactured suitcase nuclear weapon). For more effective countermeasures against the disaster, multilayer protection concept - prevention of smuggling of radioactive or nuclear material into our country through seaports or airports, detection and prevention of the threat materials in transit on a road, and prevention of their entry into a target building - is recommended. Due to different surrounding circumstances of where detection system is deployed, different types of radiation detection systems are required. There have been no studies on characteristics of detection equipment required under Korean specific conditions. This paper provides information on technical requirements of radiation detection system to achieve multi-layer countermeasures for the purpose of protecting the public and environment against radiological and nuclear terrorism

  2. Center of thermal-physical data for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Bobkov, V P; Blokhin, A I; Ivashkevich, A A; Katan, I B; Peskov, O L; Pan' kov, V M; Savanin, N K; Sal' nikova, O V; Khrushcheva, E N; Kirova, T S

    1982-09-01

    The specific features of a specialized Center of thermal-physical data (CTD) are considered. The center has been created for data acquisition, storage and analysis and working out recommendations on the following NPP thermal physics sections: hydrodynamics of channel flows (monophase laminar and turbulent, and two-phase flows, hydrodynamic vibrations) heat exchange in NPP elements, thermohydraulic calculations of nuclear reactor cores, heat exchangers, steam generators and NPP cooling system elements, coolant properties (water and steam, liquid metals and gases). On the CTD data base an automated system ASKhOD, oriented to EC computer, is created. The ASKhoD software ensures data allocation on magnetic tapes or other carriers, automated renewal and data relocation, data search in compliance with a specified set of signs, data processing for the purpose of their estimation or obtaining optimized model constants. Different publications in home and foreign magazines, conference, seminar materials, organization preprints serve as the data sources used for the formation of the ASKhOD data base.

  3. Center of thermal-physical data for nuclear power plants

    International Nuclear Information System (INIS)

    Bobkov, V.P.; Blokhin, A.I.; Ivashkevich, A.A.; Katan, I.B.; Peskov, O.L.; Pan'kov, V.M.; Savanin, N.K.; Sal'nikova, O.V.; Khrushcheva, E.N.; Kirova, T.S.

    1982-01-01

    The specific features of a specialized Center of thermal-physical data (CTD) are considered. The center has been created for data acquisition, storage and analysis and working out recommendations on the following NPP thermal physics sections: hydrodynamics of channel flows (monophase laminar and turbulent, and two-phase flows, hydrodynamic vibrations) heat exchange in NPP elements, thermohydraulic calculations of nuclear reactor cores, heat exchangers, steam generators and NPP cooling system elements, coolant properties (water and steam, liquid metals and gases). On the CTD data base an automated system ASKhOD, oriented to EC computer, is created. The ASKhoD software ensures data allocation on magnetic tapes or other carriers, automated renewal and data relocation, data search in compliance with a specified set of signs, data processing for the purpose of their estimation or obtaining optimized model constants. Different publications in home and foreign magazines, conference, seminar materials, organization preprints serve as the data sources used for the formation of the ASKhOD data base

  4. Progress report of Cekmece Nuclear Research and Training Center for 1981

    International Nuclear Information System (INIS)

    1982-01-01

    Presented are the research works carried out in 1981 in Energy, Radiological Safety, Radioisotope, Application of Nuclear Techniques and Basic Research of Cekmece Nuclear Research and Training Center. (author)

  5. Semi-annual report of Nuclear Technology and Development Center (CDTN) - July to December 1988

    International Nuclear Information System (INIS)

    1989-01-01

    The main activities developed by the several divisions of Nuclear Technology Development Center (CDTN) are described, including areas of reactor tecnologies, fuel cycle, materials and component, nuclear safety and tecnical substructure. (C.G.C.) [pt

  6. Effective nuclear and radiation emergency planning

    International Nuclear Information System (INIS)

    Grlicarev, I.

    2000-01-01

    The paper describes how to develop a balanced emergency plan, which realistically reflect the interfaces with various emergency organizations. The use of resources should be optimized with focusing on the most likely accidents. The pitfalls of writing an emergency plan without ''big picture'' in mind should be avoided. It is absolutely essential to have a clear definition of responsibilities and to have proper understanding of the tasks in between all counterparts in the emergency preparedness. Special attention should be paid to off-site part of the nuclear emergency preparedness, because the people involved in it usually receive less training than the on-site personnel and they are not specialized for nuclear emergencies but deal with all sorts of emergencies. (author)

  7. Annual report of Nuclear Human Resource Development Center. April 1, 2012 - March 31, 2013

    International Nuclear Information System (INIS)

    2014-03-01

    This annual report summarizes the activities of Nuclear Human Resource Development Center (NuHRDeC) of Japan Atomic Energy Agency (JAEA) in the fiscal year 2012. In this fiscal year, we flexibly designed training courses corresponding with the needs from outside, while organizing the annually scheduled training programs, and also actively addressed the challenging issues on human resource development, such as to enhance the collaboration with academia and to organize international training for Asian countries. The number of trainees who completed the domestic training courses in 2012 was increased to 525, which is 30 percent more than the previous year. And also, in order to respond to the Tokyo Electric Power Company (TEPCO)'s Fukushima No.1 nuclear power plant accident, we also organized the special training courses on radiation survey for the subcontracting companies working with TEPCO, and the training courses on decontamination work for the construction companies in Fukushima prefecture. The total number of attendees in these special courses was more than 4,000 persons. JAEA continued its cooperative activities with universities. In respect of the cooperation with graduate school of University of Tokyo, we accepted 14 students and cooperatively conducted practical exercises for nuclear major. Furthermore, we also actively continued cooperation on practical exercises for students of universities which were signed in Nuclear HRD Program. In terms of the collaboration network with universities, the joint course was held with six universities through utilizing the remote education system. Furthermore, the intensive course at Okayama University, Fukui University, and practical exercise at Nuclear Fuel Cycle Engineering Laboratories of JAEA were also conducted. In respect of International training, NuHRDeC continuously implemented the Instructor Training Program (ITP) by receiving the annual sponsorship from MEXT. In fiscal year 2012, eight countries (i

  8. Report on nuclear and radiation safety in Slovenia in 2001

    International Nuclear Information System (INIS)

    Janzekovic, H.

    2002-01-01

    The Slovenian Nuclear Safety Administration (SNSA) has prepared a Report on Nuclear and Radiation Safety in Slovenia for 2001 as a regular form of reporting to the citizens of the Republic of Slovenia on the activities related to the nuclear fuel cycle and the use of the ionising sources. The report has been prepared in collaboration with the Health Inspectorate of the Republic of Slovenia (HIRS), the Administration for Civil Protection and Disaster Relief (ACPDR), the Pool for Assurance and Reinsurance of Liability for Nuclear Damage and the Pool for Decommissioning of the NPP Krsko and for the Radwaste Disposal from the NPP Krsko. The reports of the Agency for Radioactive Waste Management (ARAO), the Institute of Oncology, the Department of Nuclear Medicine of the Medical Centre Ljubljana and the technical support organisations are also included. The SNSA made no crucial modifications to the reports of the above mentioned institutions. The modifications were made just facilitate a reading of the reports.

  9. Nuclear and radiation safety in Slovenia. Annual report 2001

    International Nuclear Information System (INIS)

    Janzekovic, H.

    2002-01-01

    The Slovenian Nuclear Safety Administration (SNSA) has prepared a Report on Nuclear and Radiation Safety in Slovenia for 2001 as a regular form of reporting to the citizens of the Republic of Slovenia on the activities related to the nuclear fuel cycle and the use of the ionising sources. The report has been prepared in collaboration with the Health Inspectorate of the Republic of Slovenia (HIRS), the Administration for Civil Protection and Disaster Relief (ACPDR), the Pool for Assurance and Reinsurance of Liability for Nuclear Damage and the Pool for Decommissioning of the NPP Krsko and for the Radwaste Disposal from the NPP Krsko. The reports of the Agency for Radioactive Waste Management (ARAO), the Institute of Oncology, the Department of Nuclear Medicine of the Medical Centre Ljubljana and the technical support organisations are also included. The SNSA made no crucial modifications to the reports of the above mentioned institutions. The modifications were made just facilitate a reading of the reports. (author)

  10. Micronuclei Frequencies in Lymphocytes of Nuclear Malaysia Radiation Workers

    International Nuclear Information System (INIS)

    Mohd Rodzi Ali; Aisyah Mohd Yusof; Rahimah Abdul Rahim; Juliana Mahamat Napiah; Yahaya Talib; Shafii Khamis

    2016-01-01

    The objective of the study is to investigate the frequency of cell aberration in lymphocytes of the Nuklear Malaysia radiation workers. A total of 58 blood samples were collected from the radiation workers during their routine medical examination. The donor age range is between 23 to 58 years, 31 male and 27 female. Blood samples were cultured according to the standard protocol recommended by the International Atomic Energy Agency. The mean micronuclei (MN) is 23.5 ± 0.9 MN/ 1000 binucleate, with the median value of 24 MN/ 1000 binucleate. The lowest number of MN was 9, and the highest was 43. There is no correlation between the number of MN in blood and yearly cumulative dose for radiation workers. The results indicate the MN expression due to small radiation exposure is almost negligible in Nuclear Malaysia radiation workers. (author)

  11. Physics contributions to radiation protection in nuclear power plants

    International Nuclear Information System (INIS)

    Krueger, F.W.

    1980-01-01

    Physical research and physical methods can essentially contribute to radiation protection in nuclear power plants. With their aid, properties of radiation sources can be determined, and calculations of radiation shields can be performed. In the present paper, such tasks are analyzed, the state of the art of their solution is evaluated, and trends of further work are shown. Focal points of the present study are the calculation of properties of radiation sources outside the reactor (fission products, activated corrosion products, decontamination facilities for contaminated media), exact and engineering methods for calculating radiation fields also in inhomogeneous shields, and classification of concretes for gamma-ray shielding. Objectives, possibilities, and problems of standardization of such activities are discussed. (author)

  12. Nuclear radiation detection with superconducting tunnel junctions

    International Nuclear Information System (INIS)

    Kurakado, Masahiko

    1984-01-01

    Since the gap energy of superconductors is as small as 1 meV and 1/1000 of that of semiconductors, it is expected that the number of electron-hole pairs produced in superconductors by radiation is several thousands times as many as the pairs in semiconductors. Therefore, high sensitivity and high resolution radiation detectors may be manufactured by using superconductors. A computer simulation of the cascade excitation process of electrons was carried out. The experimental study was performed by using Sn junctions. The variation of transient voltage was measured by the constant current method. The alpha particles from Po-210 were measured, and the generation of quasi particles was confirmed. The relaxation time of signals was measured by using pulsed laser beam. It was found that the superconductors just after the incidence of radiation became nonequilibrium. The typical alpha spectra were obtained by cooling the superconductors to 0.32 K. The detector is still under development. The problem is leakage current. (Kato, T.)

  13. 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

  14. Center of Nuclear Physics Data (CNPD), RFNC-VNIIEF

    International Nuclear Information System (INIS)

    Taova, S.

    2011-01-01

    high-precision numerical methods. The procedure of optimum potential automatic search at describing elastic scattering data was implemented and is being under test now. It is planned to present the early calculation results on differential cross sections at the conference 'Nucleus-2011'. The works on obtaining the calculated reaction cross sections with the EMPIRE code are being continued in our Center. The constantly update program version available through the Internet CVN protocol is used. General The report entitled 'Center of Nuclear Physics Data in VNIIEF' was presented last year in Saint-Petersburg at the 60th Meeting on Nuclear Spectroscopy and Nuclear Structure 'Nucleus 2010. Methods of Nuclear Physics for Femto - and Nanotechnologies'. The Center staff takes an active part in preparation of the 61st conference 'Nucleus-2011' which will be held in Sarov, October 10-14, 2011. (author)

  15. Considerations on radiation protection and accidents in nuclear medicine

    International Nuclear Information System (INIS)

    Lima, Carla Flavia de; Avelar, Artur Canella; Campos, Tarcisio P.R.

    2001-01-01

    The present study presents the radiation protection in the services of nuclear medicine in relation to the design of the services, manipulation of sources, cares with the patient, accomplishment of procedures and definition of accidents and incidents; besides approaching the CNEN requirements

  16. Nuclear data for radiation damage assessment and related safety aspects

    International Nuclear Information System (INIS)

    Kocherov, N.P.

    1989-12-01

    The IAEA Advisory Group Meeting on Nuclear Data for Radiation Damage Assessment and Related Safety Aspects was held at the IAEA Headquarters in Vienna, 19-22 September 1989. This report contains the conclusions and recommendations of this meeting. The papers which the participants prepared for and presented at the meeting will be published as an IAEA Technical Document. (author)

  17. Australian Radiation Protection and Nuclear Safety Regulations 1999

    International Nuclear Information System (INIS)

    1999-01-01

    This document contains statutory rules made under the Australian Radiation and Nuclear Safety Act 1998 defining how specified standards to be observed, practices and procedures to be followed and measures to be taken by controlled persons in relation to activities relating to controlled facilities, as well as in relation to dealings with controlled apparatus or controlled material

  18. Australian Radiation Protection and Nuclear Safety Regulations 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    This document contains statutory rules made under the Australian Radiation and Nuclear Safety Act 1998 defining how specified standards to be observed, practices and procedures to be followed and measures to be taken by controlled persons in relation to activities relating to controlled facilities, as well as in relation to dealings with controlled apparatus or controlled material

  19. Single-chip microcomputer application in nuclear radiation monitoring instruments

    International Nuclear Information System (INIS)

    Zhang Songshou

    1994-01-01

    The single-chip microcomputer has advantage in many respects i.e. multiple function, small size, low-power consumption,reliability etc. It is widely used now in industry, instrumentation, communication and machinery. The author introduced usage of single-chip microcomputer in nuclear radiation monitoring instruments for control, linear compensation, calculation, changeable parameter presetting and military training

  20. Non-combustible nuclear radiation shields with high hydrogen content

    International Nuclear Information System (INIS)

    Hall, W.C.; Peterson, J.M.

    1978-01-01

    The invention relates to compositions, methods of production, and uses of non-combustible nuclear radiation shields, with particular emphasis on those containing a high concentration of hydrogen atoms, especially effective for moderating neutron energy by elastic scatter, dispersed as a discontinuous phase in a continuous phase of a fire resistant matrix

  1. The IAEA safety standards for radiation, waste and nuclear safety

    International Nuclear Information System (INIS)

    Gonzalez, Abel J.

    1997-01-01

    This paper presents a brief description of the standards for radiation, waste and nuclear safety established by the International Atomic Energy Agency (IAEA). It provides a historical overview of their development and also summarizes the standards' current preparation and review process. The final paragraphs offer an outlook on future developments. (author)

  2. Research on international cooperation for nuclear and radiation safety

    International Nuclear Information System (INIS)

    Cheng Jianxiu

    2013-01-01

    This paper describes the importance and related requirements of international cooperation on nuclear and radiation safety, analyzes the current status, situation and challenges faced, as well as the existing weakness and needs for improvement, and gives some proposals for reference. (author)

  3. Towards an international regime on radiation and nuclear safety

    International Nuclear Information System (INIS)

    Gonzalez, A.J.

    2000-01-01

    The 1990s have seen the de facto emergence of what might be called an 'international regime on nuclear and radiation safety'. It may be construed to encompass three key elements: legally binding international undertakings among States; globally agreed international safety standards; and provisions for facilitating the application of those standards. While nuclear and radiation safety are national responsibilities, governments have long been interested in formulating harmonised approaches to radiation and nuclear safety. A principal mechanism for achieving harmonisation has been the establishment of internationally agreed safety standards and the promotion of their global application. The development of nuclear and radiation safety standards is a statutory function of the IAEA, which is unique in the United Nations system. The IAEA Statute expressly authorises the Agency 'to establish standards of safety' and 'to provide for the application of these standards'. As the following articles and supplement in this edition of the IAEA Bulletin point out, facilitating international conventions; developing safety standards; and providing mechanisms for their application are high priorities for the IAEA. (author)

  4. Medical intervention in case of nuclear or radiation event

    International Nuclear Information System (INIS)

    Blanc, J.; Bourguignon, M.; Carli, P.; Carosella, E.; Challeton de Vathaire, C.; Court, L.; Ducousso, R.; Facon, A.; Fleutot, J.B.; Goldstein, P.; Gourmelon, P.; Herbelet, G.; Kolodie, H.; Lallemand, J.; Martin, J.C.; Menthonnex, P.; Masse, R.; Origny, S.; Pasnon, J.; Peton Klein, D.; Rougy, C.; Schoulz, D.; Romet, G.; Telion, C.; Vrousos, C.

    2002-01-01

    This guide aims to be a practical tool for intervenors in case of nuclear or radiation accident. It proposes many sheets to favor the reactivity and the implementing of adapted measures. It concerns the course of action to take in case of irradiation accident or contamination and the reception in medical structure or a hospital. (A.L.B.)

  5. Radiation protection monitoring for #betta#-radiation at the Juelich Nuclear Research Centre

    International Nuclear Information System (INIS)

    Keller, M.; Heinzelmann, M.

    1983-01-01

    A complete system for radiation protection monitoring also includes #betta#-radiation monitoring. This requires suitable dose rate meters, personal dosemeters and last but not least detailed information about possible radiation exposure due to #betta#-radiation. Since there are at present no suitable #betta#-dosemeters available on the market yet, a large nuclear research centre such as the KFA Juelich, where radioactive substances are being handled by more than 1600 persons, has the task of developing and deploying suitable dosemeters. The centre's accomplishments in this area are described

  6. Materials Characterization Center. Second workshop on irradiation effects in nuclear waste forms. Summary report

    International Nuclear Information System (INIS)

    Weber, W.J.; Turcotte, R.P.

    1982-01-01

    The purpose of this second workshop on irradiations effects was to continue the discussions initiated at the first workshop and to obtain guidance for the Materials Characterization Center in developing test methods. The following major conclusions were reached: Ion or neutron irradiations are not substitutes for the actinide-doping technique, as described by the MCC-6 Method for Preparation and Characterization of Actinide-Doped Waste Forms, in the final evaluation of any waste form with respect to the radiation effects from actinide decay. Ion or neutron irradiations may be useful for screening tests or more fundamental studies. The use of these simulation techniques as screening tests for actinide decay requires that a correlation between ion or neutron irradiations and actinide decay be established. Such a correlation has not yet been established and experimental programs in this area are highly recommended. There is a need for more fundamental studies on dose-rate effects, temperature dependence, and the nature and importance of alpha-particle effects relative to the recoil nucleus in actinide decay. There are insufficient data presently available to evaluate the potential for damage from ionizing radiation in nuclear waste forms. No additional test methods were recommended for using ion or neutron irradiations to simulate actinide decay or for testing ionization damage in nuclear waste forms. It was recognized that additional test methods may be required and developed as more data become available. An American Society for Testing and Materials (ASTM) Task Group on the Simulation of Radiation Effects in Nuclear Waste Forms (E 10.08.03) was organized to act as a continuing vehicle for discussions and development of procedures, particularly with regard to ion irradiations

  7. Reporting nuclear power plant operation to the Finnish Centre for Radiation and Nuclear Safety

    International Nuclear Information System (INIS)

    1997-01-01

    The Finnish Centre for Radiation and Nuclear safety (STUK) is the authority in Finland responsible for controlling the safety of the use of nuclear energy. The control includes, among other things, inspection of documents, reports and other clarification submitted to the STUK, and also independent safety analyses and inspections at the plant site. The guide presents what reports and notifications of the operation of the nuclear facilities are required and how they shall be submitted to the STUK. The guide does not cover reports to be submitted on nuclear material safeguards addressed in the guide YVL 6.10. Guide YVL 6.11 presents reporting related to the physical protection of nuclear power plants. Monitoring and reporting of occupational exposure at nuclear power plants is presented in the guide YVL 7.10 and reporting on radiological control in the environment of nuclear power plants in the guide YVL 7.8

  8. Provenance of nuclear radioactivity radiation and hazardous health risks

    International Nuclear Information System (INIS)

    Sakhuja, Geeta

    2016-01-01

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

  9. Management of Low-Level Radioactive Waste from Research, Hospitals and Nuclear Medical Centers in Egypt - 13469

    Energy Technology Data Exchange (ETDEWEB)

    Hasan, M.A.; Selim, Y.T.; Lasheen, Y.F. [Hot Labs and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)

    2013-07-01

    The application of radioisotopes and radiation sources in medical diagnosis and therapy is an important issue. Physicians can use radioisotopes to diagnose and treat diseases. Methods of treatment, conditioning and management of low level radioactive wastes from the use of radiation sources and radioisotopes in hospitals and nuclear medicine application, are described. Solid Radioactive waste with low-level activity after accumulation, minimization, segregation and measurement, are burned or compressed in a compactor according to the international standards. Conditioned drums are transported to the interim storage site at the Egyptian Atomic Energy Authority (EAEA) represented in Hot Labs and Waste Management Center (HLWMC) for storage and monitoring. (authors)

  10. The use of nuclear reactor in radiation biology

    International Nuclear Information System (INIS)

    Ujeno, Yowri

    1991-01-01

    The Kyoto University Reactor (KUR) is widely used not only in biology, but also in applied biology, today. These studies were surveyed in the present paper and the future possibility to use KUR in radiation biology was discussed. The researches on the effects of thermal neutrons on various normal tissues, the biological effects of neutrons except thermal neutrons, especially intermediate neutrons between thermal and high speed neutrons or cold neutrons, the adaptive response of cells to thermal neutron radiation, the application of nuclear reactor-produced radionuclides including 195m Pt to biology, and the mutation in botanical science and so on, should be continued using nuclear reactor. The necessity of nuclear reactor in biology and applied biology is emphasized. (author)

  11. Controlling occupational radiation exposure at operating nuclear power stations

    International Nuclear Information System (INIS)

    Dickson, H.W.; Oakes, T.W.; Shank, K.E.

    1977-01-01

    The historical development of the philosophy of keeping the radiation exposure of workers at light-water reactors as low as reasonably achievable (ALARA) is presented. A review is made of some of the ALARA activities of the Nuclear Regulatory Commission, the Energy Research and Development Administration, and various nuclear installations. Data compiled by the NRC show that routine and special maintenance at light-water reactors accounts for 72 percent of all occupational exposure at these sites. The role that Oak Ridge National Laboratory has taken in ALARA research is presented, with emphasis placed on a study of valve malfunctions at light-water reactors. The valve study indicates a trend toward decreasing valve reliability over the past few years. Finally a cost--benefit analysis of radiation dose reduction is discussed. The rationale for assigning a cost per man-rem based on the radiation exposure level that is encountered is presented

  12. Measurement of gamma radiation doses in nuclear power plant environment

    International Nuclear Information System (INIS)

    Bochvar, I.A.; Keirim-Markus, I.B.; Sergeeva, N.A.

    1976-01-01

    Considered are the problems of measuring gamma radiation dose values and the dose distribution in the nuclear power plant area with the aim of estimating the extent of their effect on the population. Presented are the dosimeters applied, their distribution throughout the controlled area, time of measurement. The distribution of gamma radiation doses over the controlled area and the dose alteration with the increase of the distance from the release source are shown. The results of measurements are investigated. The conclusion is made that operating nuclear power plants do not cause any increase in the gamma radiation dose over the area. Recommendations for clarifying the techniques for using dose-meters and decreasing measurement errors are given [ru

  13. Prospects for coherently driven nuclear radiation by Coulomb excitation

    International Nuclear Information System (INIS)

    Karamyan, S.A.; Carroll, J.J.

    2006-01-01

    Possible experiments are discussed in which the Coulomb excitation of nuclear isomers would be followed by sequential energy release. The possibility of the coherent Coulomb excitation of nuclei ensconced in a crystal by channeled relativistic heavy projectiles is considered. The phase shift between neighbor-nuclei excitations can be identical to the photon phase shift for emission in forward direction. Thus, the elementary string of atoms can radiate coherently with emission of characteristic nuclear γ rays and the intensity of the radiation could be increased due to the summation of amplitudes. The Moessbauer conditions should be important for this new type of collective radiation that could be promising in the context of the γ-lasing problem

  14. Radiation and Thermal Ageing of Nuclear Waste Glass

    Energy Technology Data Exchange (ETDEWEB)

    Weber, William J [ORNL

    2014-01-01

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

  15. Environmental radiation monitoring around Korea Nuclear Fuel Company

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Myung Ho; Lee, Chang Woo; Choi, Yong Ho; Cho, Yueng Hyun; Choi, Gyun Sik [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-12-01

    Environmental Radiation Monitoring was carried out with measurement of environmental radiation and environmental radioactivity analysis around Korea Nuclear Fuel Company. Environmental Radiation rates measured by Portable ERM and accumulated dose rates measured by TLD were same level compared with past years. Total alpha and beta concentrations in the air particulates showed the similar values in all sampling points. The concentration of uranium isotopes in soils and underground waters were measured similar to natural uranium values. The concentration of uranium isotopes in surface waters and sediments decreased with increasing distances from the point of discharge. The concentrations of uranium isotopes in rain water and foods such as rices and vegetables were not detected or measured similar to natural uranium level. Hence, the environment around the nuclear facilities in Korea has been contaminated only to an insignificant extent, although a small amount of disequilibated uranium was detected within 4 km downstream of the point of discharge of KNFC. 31 refs., 26 figs., 42 tabs. (Author)

  16. Calibration of radiation monitors at nuclear power plants

    International Nuclear Information System (INIS)

    Boudreau, L.; Miller, A.D.; Naughton, M.D.

    1994-03-01

    This work was performed to provide guidance to the utilities in the primary and secondary calibration of the radiation monitoring systems (RMS) installed in nuclear power plants. These systems are installed in nuclear power plants to monitor ongoing processes, identify changing radiation fields, predict and limit personnel radiation exposures and measure and control discharge of radioactive materials to the environment. RMS are checked and calibrated on a continuing basis to ensure their precision and accuracy. This report discusses various approaches towards primary and secondary calibrations of the RMS equipment in light of accepted practices at typical power plants and recent interpretations of regulatory guidance. Detailed calibration techniques and overall system responses, trends, and practices are discussed. Industry, utility, and regulatory sources were contacted to create an overall consensus of the most reasonable approaches to optimizing the performance of this equipment

  17. Radiation dosimetry for medical management in nuclear/radiological disaster

    International Nuclear Information System (INIS)

    Narayan, Pradeep

    2012-01-01

    ; quartz, sand, stones and man made materials such as glasses, bricks, tiles and ceramics from the close proximity of exposed individual can be examined using TL techniques for estimating the radiation doses to the public. TL techniques have been employed to these materials after exposing them with gamma radiation and the results have been found promising. The current trends in methodologies and techniques of radiation dosimetry for medical management of nuclear/radiological disaster will be presented. (author)

  18. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, H.D.; Lee, W.Y.; Park, D.W.

    1981-01-01

    Measurements and monitoring of the environmental radiation levels, as well as radioactivity of the various environmental samples were carried out three times a month in the on-site and the off-site around the KAERI site. Measurements were made for both gross alpha and beta radioactivity of all environmental samples. Gross beta measurements were made for radioactivity of the fallout, airborne particulates and precipitations which were collected on a daily basis on the roof of the main building. Measurements of the accumulated doses were also carried out at 10 posts on a bimonthly basis by employing thermoluminescent dosimeters

  19. Calculating the cost of research and Development in nuclear and radiation safety

    International Nuclear Information System (INIS)

    Matsulevich, N.Je.; Nosovs'ka, A.A.

    2010-01-01

    Methodological support assessing the cost of research and development in the area of nuclear and radiation safety regulation is considered. Basic methodological recommendations for determining labor expenditures for research and development in nuclear and radiation safety are provided.

  20. Establishment of radiation protection and safety programme in Nuclear Medicine

    International Nuclear Information System (INIS)

    Chene, E.

    2014-04-01

    Radiation is useful because of its ability to penetrate tissue, allowing imaging of internal structures. However radiation may produce harmful biological effects. Observations of exposed human populations and animal experimentation indicate that exposure to low levels of radiation over a period of time may lead to stochastic radiation effects. Exposures to high levels of radiation above threshold also leads to deterministic effects. Establishment of radiation protection and safety programme and implement it without fail may help prevent deterministic effect and limit chances of stochastic effects. This is achieved by assigning responsibilities to the proposed organizational structure, management commitment to safety culture by providing continuous education and training to employees, regular reviewing and auditing of radiation safety policies. Occupational, public and environmental radiation exposure is further achieved by implementation of set local rules and operational procedures, proper management of radioactive waste and safe transport of radioactive material. Medical radiation exposure is achieved by justified procedures, optimization of doses, guidance levels, quality assurance and quality control programme through image quality, radiopharmaceutical quality and records keeping of radiation doses, calibration certificates of equipment used, equipment service and test certificates. Diagnostic radiopharmaceuticals must deliver the minimum possible radiation dose to the patient while therapeutic radiopharmaceuticals must deliver the maximum dose to the target organ or tissue, while minimizing the dose to non-target tissues such as the bone marrow. Special considerations shall be given to pregnant and breast-feeding patients. The proper facility design and shielding of a nuclear medicine facility shall further provide for the radiation protection to the worker, the patient, public and the environment. Precautions should be given to radioactive patients as there