Existing and future international standards for the safety of radioactive waste disposal

International Nuclear Information System (INIS)

Linsley, G.

1999-01-01

In this paper the essential features of the current international safety standards are summarised and the issues being raised for inclusion in future standards are discussed. The safety standards of the IAEA are used as the basis for the review and discussion. The IAEA has established a process for establishing international standards of safety for radioactive waste management through its Radioactive Waste Safety Standards (RADWASS) programme. The RADWASS documents are approved by a comprehensive process involving regulatory and other experts from all concerned IAEA Member States. A system of committees for approving the IAEAs safety standards has been established. For radioactive waste safety the committee for review and approval is the Waste Safety Standards Advisory Committee (WASSAC). In 1995 the IAEA published 'The Principles of Radioactive Waste Management' as the top level document in the RADWASS programme. The report sets out the basis principles which most experts believe are fundamental to the safe management of radioactive wastes

Educational support programs: Office of Civilian Radioactive Waste Management

International Nuclear Information System (INIS)

Williamson, R.C.

1989-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) currently sponsors two educationally related programs: the Radioactive Waste Management Fellowship Program and the Radioactive Waste Management Research Program for Historically Black Colleges and Universities (HBCU). The graduate fellowship program was implemented in 1985 to meet the US Department of Energy's (DOE's) expected manpower needs for trained scientists and engineers to assist in carrying out the activities of the Nuclear Waste Policy Act. It is recognized that a shortage of master's and doctoral level scientists and engineers in disciplines supportive of the nation's high-level radioactive waste management (RWM) program may impede the DOE's ability to properly carry out its mission under the act. The fellowship program encourages talented undergraduate students to enter graduate programs designed to educate and train them in fields directly related to RWM. The program supports graduate students in various disciplines, including nuclear science and engineering, health physics, and certain area of geology and chemical engineering. It also encourages universities to support and improve research activities and academic programs related to the management of spent nuclear fuel and high-level radioactive waste

Radioactive materials packaging standards and regulations: Making sense of it all

International Nuclear Information System (INIS)

Pope, R.B.; Rawl, R.R.

1989-01-01

Numerous regulations and standards, both national and international, apply to the packaging and transportation of radioactive material. These are legal and technical prerequisites to practically every action that a designer or user of a radioactive material transportation package will perform. The identity and applicability of these requirements and the bodies that formulate them are also not readily understood. This paper addresses the roles that various international bodies play in developing and implementing the various regulations and standards. It uses the US regulatory and standards-making bodies to illustrate how international requirements feed the domestic control of packaging and transport. It explains the scope and interactions between domestic and international regulatory and standards agencies and summarizes the status and major standards activities at the international level. The overview provided by this paper will be valuable to designers and users of radioactive material packages for better understanding and use of both standards and regulations, and for complying with regulatory requirements in the radioactive materials transportation field. 11 refs., 2 figs

Preliminary Calculation of the Indicators of Sustainable Development for National Radioactive Waste Management Programs

International Nuclear Information System (INIS)

Cheong, Jae Hak; Park, Won Jae

2003-01-01

As a follow up to the Agenda 21's policy statement for safe management of radioactive waste adopted at Rio Conference held in 1992, the UN invited the IAEA to develop and implement indicators of sustainable development for the management of radioactive waste. The IAEA finalized the indicators in 2002, and is planning to calculate the member states' values of indicators in connection with operation of its Net-Enabled Waste Management Database system. In this paper, the basis for introducing the indicators into the radioactive waste management was analyzed, and calculation methodology and standard assessment procedure were simply depicted. In addition, a series of innate limitations in calculation and comparison of the indicators was analyzed. According to the proposed standard procedure, the indicators for a few major countries including Korea were calculated and compared, by use of each country's radioactive waste management framework and its practices. In addition, a series of measures increasing the values of the indicators was derived so as to enhance the sustainability of domestic radioactive waste management program.

Developing international safety standards for the geological disposal of radioactive waste

International Nuclear Information System (INIS)

Metcalf, P.

2001-01-01

In the context of the International Atomic Energy Agency's (IAEA) programme to create a corpus of internationally accepted Radioactive Waste Safety Standards (RADWASS), focus is currently being placed on establishing standards for the 'geological disposal of radioactive waste'. This is a challenging task and to help the standards development process there is a need to stimulate discussion of some of the associated scientific and technical issues. A number of position papers developed in recent years by a subgroup of the Waste Safety Standards Committee (WASSC), the subgroup on Principles and Criteria for Radioactive Waste Disposal, address many of the relevant issues. These include a common safety based framework for radioactive waste disposal, appropriate time frames for safety assessment, different possible indicators of long-term safety, the safety implications of reversibility and retrievability, the assessment of possible human intrusion into the repository, the role and limitations of institutional control, establishing reference critical groups and biospheres for long-term assessment, and what is meant by 'compliance' with the standards. These papers will be discussed at a Specialists Meeting to be held at the IAEA in June 2001 as a means of establishing the extent to which they enjoy the general support of experts. In order to broaden that consensus, the conclusions reached at the Specialists Meeting on the issues listed above will be presented and discussed with participants at a number of international meetings. Later this year, a draft safety standard on the geological disposal of radioactive waste which takes account of the consensus positions reached through the various consultations will be submitted for the consideration of Waste Safety Standards Committee (WASSC), the officially approved body within the IAEA for the review and approval of waste safety standards. The Committee is made up of government appointed radioactive waste regulators

Establishment and application of standard devices for radioactivity measurement

International Nuclear Information System (INIS)

Zhou Changgui; Li Xingyuan; Chen Zigen

1991-03-01

In order to establish the radioactivity measurement standards a 4πβ-γ coincidence apparatus and a 4πγ ionization chamber have been installed in the laboratory. The 4πβ-γ coincidence apparatus is for absolute measurement, and its uncertainty is ±(0.3∼5)%. The 4πγ ionization chamber is for working standard, and its uncertainty is ±(1∼5)%. The combination of these devices can meet the quality requirements controlled by National Verification System in the transfer of radioactivity values

Development of a Comprehensive Radioactive Waste Management Program in the Kingdom of Morocco

International Nuclear Information System (INIS)

Abderrahim, Bouhi; Bouchta, Moussaif; El Maati, Mouldoura; Touria, Lambarki; Touria, El Ghailassai; Fischer, R.

2009-01-01

The Kingdom of Morocco has been a signatory of the International Atomic Energy Agency (IAEA) Joint Convention on the Management of Spent Fuel and Radioactive Waste since 1999. In fact Morocco was the first African country to ratify the joint convention. The Centre National de Energie des Sciences et des Techniques Nucleaires (CNESTEN) has been designated as the lead entity within the country for radioactive waste management. Morocco is in the process of receiving authorization to begin operating a new 2 MW MARK-II TRIGA research reactor at its Nuclear Energy Research Center (CENM) in Maamora. With the commissioning of the research reactor imminent, the waste management program has been preparing to disposition waste streams from the reactor, associated research operations, production of radioisotopes and anticipated future needs. The center is also the designated collection and storage facility for radioactive waste generated in the country, primarily spent sealed sources. This paper focuses on developing a radioactive waste management program that meets international standards in a class C country as described in Selection of Efficient Options for Processing and Storage of Radioactive Waste in Countries with Small Amounts of Waste Generation (class C countries are countries with research reactors but without nuclear power plants). In building their radioactive waste management program Morocco has made good use of experts from the IAEA and under a Sister Laboratory Agreement has worked with waste management personnel from the United States. This cooperative approach has provided assistance to Morocco in developing a safe and compliant program. Developing waste stream disposition pathways for all possible waste types can be especially challenging given the lack of commercial waste management infrastructure within the country. This paper will detail how waste management decisions are made, the waste management technology that was selected and how waste conditioning

Uses of ANSI/HPS N13.12-1999, "Surface and Volume Radioactivity Standards for Clearance" and Comparison with Existing Standards

Energy Technology Data Exchange (ETDEWEB)

Stansbury, Paul S.; Strom, Daniel J.

2001-04-30

In August of 1999, the American National Standards Institute (ANSI) approved a standard for clearance of materials contaminated with residual levels of radioactivity. "Clearance," as used in the standard, means the movement of material from the control of a regulatory agency to a use or disposition that has no further regulatory controls of any kind. The standard gives derived screening levels (DSLs) in Bq/g and Bq/cm2 for 50 radionuclides. Items or materials with residual surface and volume radioactivity levels below the DSLs can be cleared, that is, managed without regard to their residual radioactivity. Since federal agencies are to use voluntary, industry standards developed by the private sector whenever possible, the standard should play an important role in DOE's regulatory process. The thrust of this report is to explain the standard, make simple observations on its usefulness to DOE, and to explore uses of the standard within DOE facilities beyond the clearance of radioactive materials.

Radiological Threat Reduction (RTR) program: implementing physical security to protect large radioactive sources worldwide

International Nuclear Information System (INIS)

Lowe, Daniel L.

2004-01-01

The U.S. Department of Energy's Radiological Threat Reduction (RTR) Program strives to reduce the threat of a Radiological Dispersion Device (RDD) incident that could affect U.S. interests worldwide. Sandia National Laboratories supports the RTR program on many different levels. Sandia works directly with DOE to develop strategies, including the selection of countries to receive support and the identification of radioactive materials to be protected. Sandia also works with DOE in the development of guidelines and in training DOE project managers in physical protection principles. Other support to DOE includes performing rapid assessments and providing guidance for establishing foreign regulatory and knowledge infrastructure. Sandia works directly with foreign governments to establish cooperative agreements necessary to implement the RTR Program efforts to protect radioactive sources. Once necessary agreements are in place, Sandia works with in-country organizations to implement various security related initiatives, such as installing security systems and searching for (and securing) orphaned radioactive sources. The radioactive materials of interest to the RTR program include Cobalt 60, Cesium 137, Strontium 90, Iridium 192, Radium 226, Plutonium 238, Americium 241, Californium 252, and Others. Security systems are implemented using a standardized approach that provides consistency through out the RTR program efforts at Sandia. The approach incorporates a series of major tasks that overlap in order to provide continuity. The major task sequence is to: Establish in-country contacts - integrators, Obtain material characterizations, Perform site assessments and vulnerability assessments, Develop upgrade plans, Procure and install equipment, Conduct acceptance testing and performance testing, Develop procedures, and Conduct training. Other tasks are incorporated as appropriate and commonly include such as support of reconfiguring infrastructure, and developing security

A study of production of radioactive environmental reference materials used for proficiency testing program in Taiwan

International Nuclear Information System (INIS)

Peng, En-Chi; Wang, Jeng-Jong

2013-01-01

To realise radioactive environmental reference materials in Taiwan, seven environmental materials of soil, water, vegetation, meat, airborne particles (filter paper), milk and mushroom samples that are frequently encountered were used to establish the preparation of the reference materials. These seven environmental materials were collected, checked for freedom from radioactivity and prepared according to their properties. The preparation was carried out by using activity about 10–100 times that of the minimum detectable activity (MDA) in routine measurements in the radioactive standard used to spike the inactive material and this standard is traceable to national ionising radioactivity standards (TAF, 2004). To demonstrate sample traceability to the added standard, each sample was carefully measured and its uncertainty evaluated. Based on the recommendations of ISO Guide 35 for evaluation of reference materials and with the above assessment and verification procedures, the uncertainties (k=1) of the spike activity used in making reference materials were: 60 Co≤4.6%, 134 Cs≤4.7%, 137 Cs≤5.0%, total β≤0.6% and 3 H≤1.3%. - Highlights: • Seven kinds environmental materials were used to establish the production of the RMs. • Spiking the traceable standard radioactive source to the blank substance. • Each sample was carefully evaluated for its uncertainty. • The performance of the RMs was estimated with the Proficiency Testing program report. • The ability of the environment RMs in the configuration is quite good

DCHAIN: A user-friendly computer program for radioactive decay and reaction chain calculations

International Nuclear Information System (INIS)

East, L.V.

1994-05-01

A computer program for calculating the time-dependent daughter populations in radioactive decay and nuclear reaction chains is described. Chain members can have non-zero initial populations and be produced from the preceding chain member as the result of radioactive decay, a nuclear reaction, or both. As presently implemented, chains can contain up to 15 members. Program input can be supplied interactively or read from ASCII data files. Time units for half-lives, etc. can be specified during data entry. Input values are verified and can be modified if necessary, before used in calculations. Output results can be saved in ASCII files in a format suitable for including in reports or other documents. The calculational method, described in some detail, utilizes a generalized form of the Bateman equations. The program is written in the C language in conformance with current ANSI standards and can be used on multiple hardware platforms

Development of criteria and standards for management of low-level radioactive waste

International Nuclear Information System (INIS)

Grey, A.E.; Falconer, K.L.

1980-08-01

The basic need for criteria and standards for radioactive waste management is to ensure compliance with Federal and State regulations applicable to this activity. In addition, criteria and standards can establish the parameters by which a radioactive waste disposal site is selected, the form in which the waste is to be disposed, how a disposal site is to be operated, and how that site is to be closed when it reaches the end of its useful life. For developing criteria and standards, this report discusses the nature of low-level radioactive waste and the role government agencies play in regulating its management. It describes subject areas for which criteria and standards could be developed, current and evolving requirements, and future suggested analyses

The Canadian approach to nuclear codes and standards. A CSA forum for development of standards for CANDU: radioactive waste management and decommissioning

International Nuclear Information System (INIS)

Shin, T.; Azeez, S.; Dua, S.

2006-01-01

Together with the Canadian Standards Association (CSA), industry stakeholders, governments, and the public have developed a suite of standards for CANDU nuclear power plants that generate electricity in Canada and abroad. In this paper, we will describe: CSA's role in national and international nuclear standards development; the key issues and priority projects that the nuclear standards program has addressed; the new CSA nuclear committees and projects being established, particularly those related to waste management and decommissioning; the hierarchy of nuclear regulations, nuclear, and other standards in Canada, and how they are applied by AECL; the standards management activities; and the future trends and challenges for CSA and the nuclear community. CSA is an accredited Standards Development Organization (SDO) and part of the international standards system. CSA's Nuclear Strategic Steering Committee (NSSC) provides leadership, direction, and support for a standards committee hierarchy comprised of members from a balanced matrix of interests. The NSSC strategically focuses on industry challenges; a new nuclear regulatory system, deregulated energy markets, and industry restructuring. As the first phase of priority projects is nearing completion, the next phase of priorities is being identified. These priorities address radioactive waste management, environmental radiation management, decommissioning, structural, and seismic issues. As the CSA committees get established in the coming year, members and input will be solicited for the technical committees, subcommittees, and task forces for the following related subjects: Radioactive Waste Management; a) Dry Storage of Irradiated Fuel; b) Short-Term Radioactive Waste Management; c) Long-Term Storage and Disposal of Radioactive Waste. 2. Decommissioning Nuclear Power is highly regulated, and public scrutiny has focused Codes and Standards on public and worker safety. Licensing and regulation serves to control

Radioactive material package test standards and performance requirements - public perception

International Nuclear Information System (INIS)

Pope, R.B.; Shappert, L.B.; Rawl, R.R.

1992-01-01

This paper addresses issues related to the public perception of the regulatory test standards and performance requirements for packaging and transporting radioactive material. Specifically, it addresses the adequacy of the package performance standards and testing for Type B packages, which are those packages designed for transporting the most hazardous quantities and forms of radioactive material. Type B packages are designed to withstand accident conditions in transport. To improve public perception, the public needs to better understand: (a) the regulatory standards and requirements themselves, (b) the extensive history underlying their development, and (c) the soundness of the technical foundation. The public needs to be fully informed on studies, tests, and analyses that have been carried out worldwide and form the basis of the regulatory standards and requirements. This paper provides specific information aimed at improving the public perception of packages test standards

Radioactive standards and calibration methods for contamination monitoring instruments

Energy Technology Data Exchange (ETDEWEB)

Yoshida, Makoto [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1997-06-01

Contamination monitoring in the facilities for handling unsealed radioactive materials is one of the most important procedures for radiation protection as well as radiation dose monitoring. For implementation of the proper contamination monitoring, radiation measuring instruments should not only be suitable to the purpose of monitoring, but also be well calibrated for the objective qualities of measurement. In the calibration of contamination monitoring instruments, quality reference activities need to be used. They are supplied in different such as extended sources, radioactive solutions or radioactive gases. These reference activities must be traceable to the national standards or equivalent standards. On the other hand, the appropriate calibration methods must be applied for each type of contamination monitoring instruments. In this paper, the concepts of calibration for contamination monitoring instruments, reference sources, determination methods of reference quantities and practical calibration methods of contamination monitoring instruments, including the procedures carried out in Japan Atomic Energy Research Institute and some relevant experimental data. (G.K.)

Radioactivity standards for drinking water

International Nuclear Information System (INIS)

Sastry, V.N.; Mahadevan, T.N.; Nair, R.N.; Krishnamoorthy, T.M.; Nambi, K.S.V.

1995-01-01

The Bureau of Indian Standards (BIS) had issued drinking water specifications for radioactivity in 1991 as 0.1 Bq/L for gross α and 1 pCi/L for gross β. The specification for gross β should have been 1 Bq/L, however the basis for arriving at these standards were not clearly stated. The radiological basis for fixing the Drinking Water Standards (DWS) has, therefore, been reviewed in the present work. The values derived now for gross α (0.01 Bq/L) and gross β (0.34 Bq/L) are different from the values given above. In addition, the DWS for some important radionuclides using the ingestion dose factors applicable to members of the general public (adult as well as children) are given here. It is hoped that the presently suggested values will be accepted by the Atomic Energy Regulatory Board and adopted by the BIS in the near future. (author). 14 refs., 2 tabs., 2 ills

National Bureau of Standards health physics radioactive material shipment survey, packaging, and labelling program under ICAO/IATA and DOT regulations

International Nuclear Information System (INIS)

Sharp, D.R.; Slaback, L.A.

1984-01-01

NBS routinely ships many radionuclides in small to moderate activities, with many shipments containing mixtures of radionuclides in a variety of combinations. The ICAO/IATA shipping regulations (and the new DoT regulations on their model) specify individual shipping parameters for every radionuclide. As a result, quality control in the shipment of these radioactive packages has become difficult to maintain. The authors have developed a computer program that will guide a Health Physics technician through package surveys and give exact packaging and labelling instructions. The program is a 27 kilobyte user-friendly BASIC program that runs on an Epson-HX20 notebook computer with microcassette drive and 16 kilobyte memory expansion unit. This small computer is more manageable than the regulation books for which it will be substituted and will be used in routine radioactive shipments

Management of radioactive fuel wastes: the Canadian disposal program

International Nuclear Information System (INIS)

Boulton, J.

1978-10-01

This report describes the research and development program to verify and demonstrate the concepts for the safe, permanent disposal of radioactive fuel wastes from Canadian nuclear reactors. The program is concentrating on deep underground disposal in hard-rock formations. The nature of the radioactive wastes is described, and the options for storing, processing, packaging and disposing of them are outlined. The program to verify the proposed concept, select a suitable site and to build and operate a demonstration facility is described. (author)

Experience with local lymph node assay performance standards using standard radioactivity and nonradioactive cell count measurements.

Science.gov (United States)

Basketter, David; Kolle, Susanne N; Schrage, Arnhild; Honarvar, Naveed; Gamer, Armin O; van Ravenzwaay, Bennard; Landsiedel, Robert

2012-08-01

The local lymph node assay (LLNA) is the preferred test for identification of skin-sensitizing substances by measuring radioactive thymidine incorporation into the lymph node. To facilitate acceptance of nonradioactive variants, validation authorities have published harmonized minimum performance standards (PS) that the alternative endpoint assay must meet. In the present work, these standards were applied to a variant of the LLNA based on lymph node cell counts (LNCC) run in parallel as a control with the standard LLNA with radioactivity measurements, with threshold concentrations (EC3) being determined for the sensitizers. Of the 22 PS chemicals tested in this study, 21 yielded the same results from standard radioactivity and cell count measurements; only 2-mercaptobenzothiazole was positive by LLNA but negative by LNCC. Of the 16 PS positives, 15 were positive by LLNA and 14 by LNCC; methylmethacrylate was not identified as sensitizer by either of the measurements. Two of the six PS negatives tested negative in our study by both LLNA and LNCC. Of the four PS negatives which were positive in our study, chlorobenzene and methyl salicylate were tested at higher concentrations than the published PS, whereas the corresponding concentrations resulted in consistent negative results. Methylmethacrylate and nickel chloride tested positive within the concentration range used for the published PS. The results indicate cell counts and radioactive measurements are in good accordance within the same LLNA using the 22 PS test substances. Comparisons with the published PS results may, however, require balanced analysis rather than a simple checklist approach. Copyright © 2011 John Wiley & Sons, Ltd.

Plasma vitrification program for radioactive waste treatment

International Nuclear Information System (INIS)

Hung, Tsungmin; Tzeng, Chinchin; Kuo, Pingchun

1998-01-01

In order to treat radioactive wastes effectively and solve storage problems, INER has developed the plasma arc technology and plasma process for various waste forms for several years. The plasma vitrification program is commenced via different developing stages through nine years. It includes (a) development of non-transferred DC plasma torch, (b) establishment of a lab-scale plasma system with home-made 100kW non-transferred DC plasma torch, (c) testing of plasma vitrification of simulated radioactive wastes, (d) establishment of a transferred DC plasma torch delivering output power more than 800 kW, (e) study of NOx reduction process for the plasma furnace, (f) development of a pilot-scale plasma melting furnace to verify the vitrification process, and (g) constructing a plasma furnace facility in INER. The final goal of the program is to establish a plasma processing plant with capacity of 250 kg/hr to treat the low-level radioactive wastes generated from INER itself and domestic institutes due to isotope applications. (author)

Standardization of {sup 32}P radioactive solution

Energy Technology Data Exchange (ETDEWEB)

Marques, Caio Pinheiros; Koskinas, Marina Fallone; Almeida, Jamille da Silveira; Yamazaki, Ione M.; Dias, Mauro da Silva, E-mail: cpmarques@usp.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2016-07-01

The standardization of {sup 32}P radioactive solution using three different methods is presented. The disintegration rate was determined by the CIEMAT/NIST and TDCR methods in liquid scintillator systems and self-absorption extrapolation method using 4π(PC)-β system. The results obtained for the activity of the {sup 32}P solution were compared and they agree within the experimental uncertainties. (author)

Radioactive Waste Management Research Program Plan for high-level waste: 1987

International Nuclear Information System (INIS)

1987-05-01

This plan will identify and resolve technical and scientific issues involved in the NRC's licensing and regulation of disposal systems intended to isolate high level hazardous radioactive wastes (HLW) from the human environment. The plan describes the program goals, discusses the research approach to be used, lays out peer review procedures, discusses the history and development of the high level radioactive waste problem and the research effort to date and describes study objectives and research programs in the areas of materials and engineering, hydrology and geochemistry, and compliance assessment and modeling. The plan also details the cooperative interactions with international waste management research programs. Proposed Earth Science Seismotectonic Research Program plan for radioactive waste facilities is appended

Spanish program on disposal of radioactive wastes

International Nuclear Information System (INIS)

Lopez Perez, B.; Ramos Salvador, L.; Martines Martinez, A.

1977-01-01

The Spanish Energetic Program assumes an installed nuclear electrical power of 23.000 MWe by the year 1985. Therefore, Spain is making an effort in the managment of radioactive wastes, that can be synthesized in the following points: 1.- Make-up and review of the regulation on the management of radioactive wastes. 2.- Development of the processes and equipment for the treatment of solid, liquid and gaseous wastes from the CNEN ''Juan Vigon'', as well as those from the Nuclear Center of Soria. Solidification studies of RAA wastes arisen from the reprocessing. 3.- Evaluation of radioactive waste treatment systems of the new installed nuclear power plants. Assistance to the nuclear and radioactive facilities operators. 4.- Increase the storage capacity of the pilot repository for solid radioactive wastes of categories 1 and 2 IAEA, located in Sierra Albarrana. Studies of adequate geological formation for storage of solid wastes of IAEA categories 3 and 4. 5.- Studies about long term surface storage systems for solidified RAA wastes arisen from the reprocessing [es

Determination of standards for transportation of radioactive material by aircrafts

International Nuclear Information System (INIS)

1978-01-01

These provisions are established on the basis of the Enforcement Regulation for the Law on Aviation. Terms are explained, such as exclusive loading and containers. Spontaneously ignitable liquid radioactive materials and the radioactive substances required to be contained in special vessels and others particularly operated during the transport, are excluded from the radioactive materials permissible for transport. The radioactive substances required to be transported as radioactive loadings don't include empty vessels used to contain radioactive materials and other things contaminated by such materials, when they conform to the prescriptions. The technical standards on radioactive loadings are defined, such as maximum radiation dose rate of 0.5 millirem per hour on the surface of L type loadings, 200 millirem per hour for A, and 1000 millirem per hour at the distance of 1 m for BM and BU types, respectively. Confirmation of the safeness of radioactive loadings may be made through the written documents prepared by the competent persons acknowledged by the Minister of Transport. The requisite of fissile loadings is that such loadings shall not reach critical state during the transport in the specified cases. Radioactive loadings or the containers with such loadings shall be loaded so that the safeness of such loadings is not injured by movement, overturn and fall during the transport. The maximum radiation dose rate of the containers with radioactive loadings shall not be more than 200 millirem per hour on the surface. The written documents describing the handling method and other matters for attention and the measures to be taken on accidents shall be carried with for the transport of radioactive loadings. (Okada, K.)

Treatment and disposal of radioactive wastes from nuclear power plants. Research programs

International Nuclear Information System (INIS)

1992-09-01

The report presents programs for research, development and demonstration concerning radioactive waste disposal in underground facilities. The main topics are: Radioactive waste management, radioactive waste storage, capsules, environmental impacts, risk assessment, radionuclide migration, radioactive waste disposal, decommissioning, cost, and international cooperation. (129 refs.)

Environmental sampling program for a solar evaporation pond for liquid radioactive wastes

International Nuclear Information System (INIS)

Romero, R.; Gunderson, T.C.; Talley, A.D.

1980-04-01

Los Alamos Scientific Laboratory (LASL) is evaluating solar evaporation as a method for disposal of liquid radioactive wastes. This report describes a sampling program designed to monitor possible escape of radioactivity to the environment from a solar evaporation pond prototype constructed at LASL. Background radioactivity levels at the pond site were determined from soil and vegetation analyses before construction. When the pond is operative, the sampling program will qualitatively and quantitatively detect the transport of radioactivity to the soil, air, and vegetation in the vicinity. Possible correlation of meteorological data with sampling results is being investigated and measures to control export of radioactivity by biological vectors are being assessed

Research program on radioactive wastes - Overview report 2012

International Nuclear Information System (INIS)

Brander, S.

2013-01-01

This short report issued by the Swiss Federal Office of Energy (SFOE) takes a look at the work done within the framework of the Swiss Research Program on Radioactive Wastes. The program was developed in 2006/2007 by the various federal institutes and commissions involved together with an university of applied sciences. Points investigated included long-term aspects, the planning of deep repositories, opinion building and acceptance as well as depository concepts. Highlights in the research and development areas are discussed, including knowledge conservation, marking concepts, storage of radioactive wastes, repository conception, monitoring and sociological aspects. National and international co-operation in these areas are reported on

Standard guide for sampling radioactive tank waste

CERN Document Server

American Society for Testing and Materials. Philadelphia

2011-01-01

1.1 This guide addresses techniques used to obtain grab samples from tanks containing high-level radioactive waste created during the reprocessing of spent nuclear fuels. Guidance on selecting appropriate sampling devices for waste covered by the Resource Conservation and Recovery Act (RCRA) is also provided by the United States Environmental Protection Agency (EPA) (1). Vapor sampling of the head-space is not included in this guide because it does not significantly affect slurry retrieval, pipeline transport, plugging, or mixing. 1.2 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

The International Atomic Energy Agency (IAEA) standards and recommendations on radioactive waste and transport safety

International Nuclear Information System (INIS)

Warnecke, E.; Rawl, R.

1996-01-01

The International Atomic Energy Agency (IAEA) publishes standards and recommendations on all aspects of nuclear safety in its Safety Series, which includes radioactive waste management and transport of radioactive materials. Safety Series documents may be adopted by a State into its national legal framework. Most of the States used the IAEA transport regulations (Safety Series No. 6) as a basis for their national regulation. The two highest ranking documents of the Radioactive Waste Safety Standards (RADWASS) programme, the Safety Fundamentals and the Safety Standard on the national waste management system, have been published. Both provide impetus into the waste management safety convention, a legally binding document for signatory states, which is being drafted. The already existing Convention on Nuclear Safety covers the management of radioactive waste at land-based civil nuclear power plants. (author) 1 fig., 18 refs

R and D program of the Spanish National Company for Radioactive Wastes management

International Nuclear Information System (INIS)

Astudillo, J.

1993-01-01

The second R+D program of the Spanish National Company for Radioactive Wastes Management (ENRESA) has a whole budget of 56 million $ for the period 1991-1995. This program is included within the Spanish Energy Plan (PEN-91) and encompasses four main areas: 1) Low and medium level radioactive wastes 2) High level radioactive wastes 3) Decommissioning and dismantling of nuclear installations 4) Radiological protection The Spanish program is coordinated with policies of international organizations: CEC,OECD and IAEA

An automated LS(β)- NaI(Tl)(γ) coincidence system as absolute standard for radioactivity measurements.

Science.gov (United States)

Joseph, Leena; Das, A P; Ravindra, Anuradha; Kulkarni, D B; Kulkarni, M S

2018-07-01

4πβ-γ coincidence method is a powerful and widely used method to determine the absolute activity concentration of radioactive solutions. A new automated liquid scintillator based coincidence system has been designed, developed, tested and established as absolute standard for radioactivity measurements. The automation is achieved using PLC (programmable logic controller) and SCADA (supervisory control and data acquisition). Radioactive solution of 60 Co was standardized to compare the performance of the automated system with proportional counter based absolute standard maintained in the laboratory. The activity concentrations determined using these two systems were in very good agreement; the new automated system can be used for absolute measurement of activity concentration of radioactive solutions. Copyright © 2018. Published by Elsevier Ltd.

Risk assessment based on current release standards for radioactive surface contamination

International Nuclear Information System (INIS)

Chen, S.Y.

1993-09-01

Standards for uncontrolled releases of radioactive surface contamination have been in existence in the United States for about two decades. Such standards have been issued by various agencies, including the US Department of Energy. This paper reviews the technical basis of published standards, identifies areas in need of revision, provides risk interpretations based on current technical knowledge and the regulatory environment, and offers suggestions for improvements

Environmental Assessment Radioactive Source Recovery Program

International Nuclear Information System (INIS)

1995-01-01

In a response to potential risks to public health and safety, the U.S. Department of Energy (DOE) is evaluating the recovery of sealed neutron sources under the Radioactive Source Recovery Program (RSRP). This proposed program would enhance the DOE's and the U.S. Nuclear Regulatory Commission's (NRC's) joint capabilities in the safe management of commercially held radioactive source materials. Currently there are no federal or commercial options for the recovery, storage, or disposal of sealed neutron sources. This Environmental Assessment (EA) analyzes the potential environmental impacts that would be expected to occur if the DOE were to implement a program for the receipt and recovery at the Los Alamos National Laboratory (LANL), Los Alamos, New Mexico, of unwanted and excess plutonium-beryllium ( 238 Pu-Be) and americium-beryllium ( 241 Am-Be) sealed neutron sources. About 1 kg (2.2 lb) plutonium and 3 kg (6.6 lb) americium would be recovered over a 15-year project. Personnel at LANL would receive neutron sources from companies, universities, source brokers, and government agencies across the country. These neutron sources would be temporarily stored in floor holes at the CMR Hot Cell Facility. Recovery reduces the neutron emissions from the source material and refers to a process by which: (1) the stainless steel cladding is removed from the neutron source material, (2) the mixture of the radioactive material (Pu-238 or Am-241) and beryllium that constitutes the neutron source material is chemically separated (recovered), and (3) the recovered Pu-238 or Am-241 is converted to an oxide form ( 238 PuO 2 or 241 AmO 2 ). The proposed action would include placing the 238 PuO 2 or 241 AmO 2 in interim storage in a special nuclear material vault at the LANL Plutonium Facility

Programs of recovery of radioactive wastes from the trenches and land decontamination of the radioactive waste storage center

International Nuclear Information System (INIS)

Jimenez D, J.; Reyes L, J.

1999-06-01

In this report there are the decontamination program of the land of the Radioactive Waste Storage Center, the Program of Recovery of the radioactive waste of the trenches, the recovery of polluted bar with cobalt 60, the recovery of minerals and tailings of uranium and of earth with minerals and tailings of uranium, the recovery of worn out sealed sources and the waste recovery with the accustomed corresponding actions are presented. (Author)

Germanium detector calibration according to the standard NF M 60-810 without using radioactive sources

Energy Technology Data Exchange (ETDEWEB)

Duda, J. M.; Garell, I.; Losset, Y.; Vichot, L. [CEA de Valduc, Service de Protection Contre Les Rayonnements, 21110 Is sur Tille (France); Chazalet, J.; Tauvel, Y.; Poulet, F. [IUP Genie des Systemes Industriels, Universite Blaise Pascal, Departement de Physique, 24 avenue des Landais, 63177 Aubiere Cedex (France)

2009-07-01

In-situ gamma ray spectrometry is used to determine the specific activities of natural and artificial radioactive nuclides in the soil with a good accuracy. This method is very interesting for environmental measurements and leads to soil determination activity. It is a cheaper method than analysis of great amounts of soil samples in the laboratory. As there is no standard soil, detection efficiency can be estimated using either statistical tools or combination of radioactive point sources calibration thanks to mathematical models of NF-M-60-810 standard representing the radionuclide distribution in soil. Experimental determination of detection efficiency requires a large number of operations involving the handling of radioactive standards in the energy range from 0.06 - 2 MeV. For these reasons, detection efficiency model has been determined without using radioactive sources. In order to reduce analytical time and to simplify the efficiency detector calibration, it is possible to associate numerical and deterministic methods and to get a relative accuracy below 25 per cent

Radioactive Waste Management Fellowship Program: Summary of program activities for calendar year 1986

International Nuclear Information System (INIS)

1987-01-01

This document describes a graduate fellowship program designed to guide future scientists and engineers toward a career in high level radioactive waste management. Oak Ridge Associated Universities administers this program on behalf of 17 participating universities. The report summarizes the background and qualifications of the last year's applicants and awardees and provides examples of the distributed literature describing the program. 8 figs

Standards and guidelines pertinent to the development of decommissioning criteria for sites contaminated with radioactive material

International Nuclear Information System (INIS)

Dickson, H.W.

1978-08-01

A review of existing health and safety standards and guidelines has been undertaken to assist in the development of criteria for the decontamination and decommissioning of property contaminated with radioactive material. During the early years of development of the nuclear program in the United States, a number of sites were used which became contaminated with radioactive material. Many of these sites are no longer useful for nuclear activities, and the U.S. DOE desires to develop criteria for the management of these sites for future uses. Radiation protection standards promulgated by ICRP, NCRP, and ANSI have been considered. Government regulations, from the Code of Federal Regulations and the legal codes of various states, as well as regulatory guidelines with specific application to decommissioning of nuclear facilities also have been reviewed. In addition, recommendations of other scientific organizations such as the National Academy of Sciences/National Research Council Advisory Committee on the Biological Effects of Ionizing Radiations and the United Nations Scientific Committee on the Effects of Atomic Radiation were considered. Finally, a few specific recommendations and discussions from current literature were included. 28 references

Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Environmental monitoring and surveillance programs

International Nuclear Information System (INIS)

Denham, D.H.; Stenner, R.D.; Eddy, P.A.; Jaquish, R.E.; Ramsdell, J.V. Jr.

1988-07-01

Licensing of a facility for low-level radioactive waste disposal requires the review of the environmental monitoring and surveillance programs. A set of review criteria is recommended for the US Nuclear Regulatory Commission (NRC) staff to use in each monitoring phase---preoperational, operational, and post operational---for evaluating radiological and selected nonradiological parameters in proposed environmental monitoring and surveillance programs at low-level waste disposal facilities. Applicable regulations, industry standards, and technical guidance on low-level radioactive waste are noted throughout the document. In the preoperational phase, the applicant must demonstrate that the environmental monitoring program identifies radiation levels and radionuclide concentrations at the site and also provides adequate basic data on the disposal site. Data recording and statistical analyses for this phase are addressed

Development of a package program for estimating ground level concentrations of radioactive gases

International Nuclear Information System (INIS)

Nilkamhang, W.

1986-01-01

A package program for estimating ground level concentration of radioactive gas from elevate release was develop for use on IBM P C microcomputer. The main program, GAMMA PLUME NT10, is based on the well known VALLEY MODEL which is a Fortran computer code intended for mainframe computers. Other two options were added, namely, calculation of radioactive gas ground level concentration in Ci/m 3 and dose equivalent rate in mren/hr. In addition, a menu program and editor program were developed to render the program easier to use since the option could be readily selected and the input data could be easily modified as required through the keyboard. The accuracy and reliability of the program is almost identical to the mainframe. Ground level concentration of radioactive radon gas due to ore program processing in the nuclear chemistry laboratory of the Department of Nuclear Technology was estimated. In processing radioactive ore at a rate of 2 kg/day, about 35 p Ci/s of radioactive gas was released from a 14 m stack. When meteorological data of Don Muang (average for 5 years 1978-1982) were used maximum ground level concentration and the dose equivalent rate were found to be 0.00094 p Ci/m 3 and 5.0 x 10 -10 mrem/hr respectively. The processing time required for the above problem was about 7 minutes for any case of source on IBM P C which was acceptable for a computer of this class

Development of radioactive standards in epoxy matrix for the control of quality of activimeters

International Nuclear Information System (INIS)

Fragoso, Maria da Conceicao de Farias; Monteiro, Luciane Carollyne de Oliveira Reis; Oliveira, Marcia Liane de

2016-01-01

In the present study, a new approach for development of the standards for positron emitting radionuclides in epoxy matrix is presented. Different formulations were prepared using epoxy resin (bisphenol A diglycidyl ether - DGEBA) and curing agents, to immobilize the radioactive material. The efficiency curve and standard sample methods were applied for activity determination of a long-lived positron emitter ("2"2Na). Satisfactory results were obtained in the 3"r"d combination. Thus, these radioactive standards can be used to evaluate the metrological behavior of the systems used for the measurement of the radiopharmaceuticals (activimeters) in the production centers and in nuclear medicine services. (author)

Recommended regulatory program plan for low-level radioactive waste management in Maryland

International Nuclear Information System (INIS)

1986-01-01

The National Program for Low-Level Radioactive Waste Management was instituted by the US Department of Energy to assist the states in carrying out this new federal policy. Based on the premise that the safe disposal of low-level waste is technologically feasible and that states have the necessary degree of authority to set management policy, the National Program is helping them to develop a responsive, comprehensive regulatory program. The State of Maryland is actively engaged with the National Program in its efforts to form a comprehensive management program. The purpose of this plan is to review existing statutory and regulatory program responsibilities and provide a recommended management scheme for low-level radioactive waste

Proposals for the Radioactive Substances (Basic Safety Standards) (England and Wales) Regulations 2000 and the Radioactive Substances (Basic Safety Standards) (England and Wales) Direction 2000. Consultative document

International Nuclear Information System (INIS)

2000-01-01

This document contains proposals for changes to the Radioactive Substances Act 1993 (RSA 93) and proposals for a Direction to be given to the Environment Agency in order to implement aspects of the European Directive 96/29/Euratom concerned with the control of radioactive waste. The Directive lays down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionising radiation. With the Government pledged to making government more accessible and responsive, an important feature of this approach is effective consultation with all interested organisations. This leads to more realistic and robust proposals, which is particularly important when dealing with proposed legislation. In March this year, the Government published a consultation paper 'The Radioactive Substances Act 1993: Implementing the Revised Basic Safety Standards Directive Euratom 96/29.' This sought comments on the basic principles for change - including the setting of levels of radioactivity below which radioactive material should be considered outside the framework of regulatory control. This document forms the second stage of the consultation process with the aim of gathering views on the proposed legal instruments to implement the Directive. This document: explains the background to the proposed regulations (paragraphs 8-13); summarises the results of the consultation on principles (paragraphs 14-24); describes the proposed changes (paragraphs 25-36); includes draft Regulations (paragraphs 27-29); includes a draft Direction to the Environment Agency (paragraphs 30-36); describes the next steps (paragraphs 37-39); includes a draft Regulatory Impact Assessment (paragraphs 40-41). In general, the devolved administrations in Scotland, Wales and Northern Ireland have assumed responsibility for environmental issues and hence management of radioactive waste policies and legislation affecting their respective countries. However, this

Historic low-level radioactive waste federal policies, programs and oversight

International Nuclear Information System (INIS)

Blanchette, M.; Kenney, J.; Zelmer, B.

2011-01-01

'Full text:' The management of radioactive waste is one of the most serious environmental problems facing Canadians. From the early industrial uses of radioactive material in the 1930s to the development of nuclear power reactors and the medical and experimental use of radio-isotopes today, there has been a steady accumulation of waste products. Historic waste is low-level radioactive waste for which the federal government has accepted responsibility for long-term management. This paper will outline the policy framework used to govern institutional and financial arrangements for the disposal of radioactive waste by waste producers and owners and the major radioactive projects in which the Government of Canada is currently involved. It will provide an overview of the organizations established for the management of historic radioactive waste and NRCan's oversight role. Finally, an overview of the historic waste program activities managed on behalf of the federal government through these organizations in the Port Hope area, the Greater Toronto Area, in Fort McMurray, Alberta and along the Northern Transportation Route is provided. Canada's Policy Framework for Radioactive Waste, sets out principles that govern the institutional and financial arrangements for disposal of radioactive waste by waste producers and owners. According to the Policy Framework: The federal government will ensure that radioactive waste disposal is carried out in a safe, environmentally sound, comprehensive, cost-effective and integrated manner; The federal government has the responsibility to develop policy, to regulate, and to oversee producers and owners; and, The waste producers and owners are responsible, in accordance with the principle of 'polluter pays', for the funding, organization, management and operation of disposal and other facilities required for their wastes. Arrangements may be different for nuclear fuel waste, low-level radioactive waste and

Understanding radioactive waste

International Nuclear Information System (INIS)

Murray, R.L.

1981-12-01

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

Understanding radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Murray, R.L.

1981-12-01

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

Development of international standards for instrumentation used for detection of illicit trafficking of radioactive material

International Nuclear Information System (INIS)

Voytchev, M.; Chiaro, P.; Radev, R.

2006-01-01

Subcommittee 45 B 'Radiation Protection Instrumentation' of the International Electrotechnical Commission (I.E.C.) is charged with the development of international standards for instrumentation used for monitoring of illicit trafficking of radioactive material through international boarders and territories, as well as inside countries. Currently three I.E.C. standards are in advanced stages of development. They are expected to be approved and published in 2006-2007. The international participation and the main characteristics of the following three standards are discussed and presented: I.E.C. 62327 'Hand-held Instruments for the Detection and Identification of Radionuclides and Additionally for the Indication of Ambient Dose Equivalent Rate from Photon Radiation', I.E.C. 62401 'Alarming Personal Radiation Devices for Detection of Illicit Trafficking of Radioactive Material' and I.E.C. 62244 'Installed Radiation Monitors for the Detection of Radioactive and Special Nuclear Materials at National Borders'

Quality assurance requirements and description for the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

1992-01-01

The Quality Assurance Requirements and Description (QARD) is the principal quality assurance document for the Civilian Radioactive Waste Management Program (Program). It establishes the minimum requirements for the Quality Assurance Program. The QARD contains regulatory requirements and program commitments necessary for the development of an effective quality assurance program. Quality assurance implementing documents must be based on, and consistent with, QARD requirements. The QARD applies to the following: (1) acceptance of spent nuclear fuel and high-level radioactive waste; (2) transport of spent nuclear fuel and high-level radioactive waste; (3) the Monitored Retrievable Storage (MRS) facility through application for an operating license; (4) Mined Geologic Disposal System (MGDS), including the site characterization activities (exploratory studies facility (ESF) and surface based testing), through application for an operating license; (5) the high-level-waste form from production through acceptance. Section 2.0 defines in greater detail criteria for determining work subject to QARD requirements. The QARD is organized into sections, supplements, appendices, and a glossary. The sections contain requirements that are common to all Program elements. The supplements contain requirements for specialized activities. The appendices contain requirements that are specific to an individual Program element. The glossary establishes a common vocabulary for the Quality Assurance Program

Approach and issues toward development of risk-based release standards for radioactive scrap metal recycle and reuse

International Nuclear Information System (INIS)

Chen, S.Y.; Nieves, L.A.; Nabelssi, B.K.; LePoire, D.J.

1994-01-01

The decontamination and decommissioning of nuclear facilities is expected to generate large amounts of slightly radioactive scrap metal (RSM). It is likely that some of these materials will be suitable for recycling and reuse. The amount of scrap steel from DOE facilities, for instance, is estimated to be more than one million tons (Hertzler 1993). However, under current practice and without the establishment of acceptable recycling standards, the RSM would be disposed of primarily as radioactive low-level waste (LLW). In the United States, no specific standards have been developed for the unrestricted release of bulk contaminated materials. Although standards for unrestricted release of radioactive surface contamination (NRC 1974) have existed for about 20 years, the release of materials is not commonly practiced because of the lack of risk-based justifications. Recent guidance from international bodies (IAEA 1988) has established a basis for deriving risk-based release limits for radioactive materials. It is important, therefore, to evaluate the feasibility of recycling and associated issues necessary for the establishment of risk-based release limits for the radioactive metals

Developing an ANSI [American National Standards Institute] standard for semitrailers used to transport radioactive materials

International Nuclear Information System (INIS)

Gregory, P.

1990-01-01

A proposed new American National Standards Institute (ANSI) standard has been prepared which establishes requirements for the design, fabrication, and maintenance of semitrailers used in the highway transport of weight-concentrated radioactive loads. A weight-concentrated load is any payload which exceeds 1,488 kilograms per lineal meter (1,000 lb/ft) over any portion of the semitrailer. The proposed standard also provides detailed procedures for in-service inspections, as well as requirements for testing and quality assurance. The standard addresses only semitrailers, excluding the tractor. Trailers already in service may be certified as complying with the standard if they meet the requirements of the standard. This standard is intended to provide guidance and acceptance criteria needed to establish a uniform minimum level of performance for the designer, manufacturer, owner, operator, and shipper. This standard is not intended to apply to special, non-routine shipments of a one-time or occasional nature which require special permitting. The background and history of the standard are traced and a summary discussion of the standard is provided in this article

Radioactive waste management: review on clearance levels and acceptance criteria legislation, requirements and standards.

Science.gov (United States)

Maringer, F J; Suráň, J; Kovář, P; Chauvenet, B; Peyres, V; García-Toraño, E; Cozzella, M L; De Felice, P; Vodenik, B; Hult, M; Rosengård, U; Merimaa, M; Szücs, L; Jeffery, C; Dean, J C J; Tymiński, Z; Arnold, D; Hinca, R; Mirescu, G

2013-11-01

In 2011 the joint research project Metrology for Radioactive Waste Management (MetroRWM)(1) of the European Metrology Research Programme (EMRP) started with a total duration of three years. Within this project, new metrological resources for the assessment of radioactive waste, including their calibration with new reference materials traceable to national standards will be developed. This paper gives a review on national, European and international strategies as basis for science-based metrological requirements in clearance and acceptance of radioactive waste. © 2013 Elsevier Ltd. All rights reserved.

Implementation of a management applied program for solid radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Lee, Y. H.; Kim, T. K.; Kang, I. S.; Cho, H. S.; Son, J. S. [KAERI, Taejon (Korea, Republic of)

2004-07-01

Solid radioactive wastes are generated from the Post-irradiated Fuel Examination Facility, the Irradiated Material Examination Facility, the Research Reactor, and the laboratories at KAERI. A data collection of a solid radioactive waste treatment process of a research organization became necessary while developing the RAWMIS(Radioactive Waste Management Integration System) which it can generate personal history management for efficient management of a waste, documents, all kinds of statistics. This paper introduces an input and output application program design to do to database with data in the results and a stream process of a treatment that analyzed the waste occurrence present situation and data by treatment process. Data on the actual treatment process that is not limited experiment improve by a document, human traces, saving of material resources and improve with efficiency of tracking about a radioactive waste and a process and give help to radioactive waste material balance and inventory study.

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

Science.gov (United States)

Chen, S Y; Napier, Bruce

2016-02-01

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

Development of international standards for instrumentation used for detection of illicit trafficking of radioactive material

Energy Technology Data Exchange (ETDEWEB)

Voytchev, M. [Institut de Radioprotection et de Surete Nucleaire (IRSN/DSU/SERAC/CTHIR), 91 - Gif sur Yvette (France); Chiaro, P. [Oak Ridge National Lab., TN (United States); Radev, R. [LLNL, Livermore, CA (United States)

2006-07-01

Subcommittee 45 B 'Radiation Protection Instrumentation' of the International Electrotechnical Commission (I.E.C.) is charged with the development of international standards for instrumentation used for monitoring of illicit trafficking of radioactive material through international boarders and territories, as well as inside countries. Currently three I.E.C. standards are in advanced stages of development. They are expected to be approved and published in 2006-2007. The international participation and the main characteristics of the following three standards are discussed and presented: I.E.C. 62327 'Hand-held Instruments for the Detection and Identification of Radionuclides and Additionally for the Indication of Ambient Dose Equivalent Rate from Photon Radiation', I.E.C. 62401 'Alarming Personal Radiation Devices for Detection of Illicit Trafficking of Radioactive Material' and I.E.C. 62244 'Installed Radiation Monitors for the Detection of Radioactive and Special Nuclear Materials at National Borders'.

Quality assurance for packaging of radioactive and hazardous materials

International Nuclear Information System (INIS)

Gustafson, L.D.

1986-01-01

The Department of Energy (DOE) has required for many years that quality assurance programs be established and implemented for the packaging of radioactive and hazardous materials. This paper identifies various requirement principles and related actions involved in establishing effective quality assurance for packaging of radioactive and hazardous materials. A primary purpose of these quality assurance program activities is to provide assurance that the packaging and transportation of hazardous materials, which includes radioactive and fissile materials, are in conformance with appropriate governmental regulations. Applicable regulations include those issued by the Nuclear Regulatory Commission (NRC), the Department of Transportation (DOT), and the Environmental Protection Agency (EPA). DOE Order 5700.6A establishes that quality assurance requirements are to be applied in accordance with national consensus standards where suitable ones are available. In the nuclear area, ANSI/ASME NQA-1 is the preferred standard

Dental Assisting Program Standards.

Science.gov (United States)

Georgia Univ., Athens. Dept. of Vocational Education.

This publication contains statewide standards for the dental assisting program in Georgia. The standards are divided into 12 categories: foundations (philosophy, purpose, goals, program objectives, availability, evaluation); admissions (admission requirements, provisional admission requirements, recruitment, evaluation and planning); program…

EPA's LLW standards program: Below regulatory concern criteria development

International Nuclear Information System (INIS)

Holcomb, W.F.; Gruhlke, J.M.

1987-01-01

The Environmental Protection Agency (EPA) is developing generally applicable environmental standards for land disposal of low-level radioactive wastes. These standards will include criteria for determining which wastes have sufficiently low levels of radioactivity to be considered ''Below Regulatory Concern'' (BRC) in regards to their radiation hazard. Risk assessments to support the BRC criteria include an analysis of 18 surrogate radioactive waste streams, generated by nuclear power reactors and other fuel cycle facilities, industrial, medical and educational facilities, and consumers. Deregulated disposal alternatives, such as sanitary landfills, municipal dumps, incinerators and on-site landfills, situated in diverse demographic settings are used in the analysis. A number of waste streams which contributed only small doses or fractions of a health effect over 10,000 years were identified. Disposal of such wastes without consideration of their very low radioactivity could result in significant cost savings to the commercial fuel cycle and government operations as well as to medical, educational, and industrial facilities, and with minimal risk to the public. The concept of BRC wastes appears both feasible and cost effective

Solid, low-level radioactive waste certification program

International Nuclear Information System (INIS)

Grams, W.H.

1991-11-01

The Hanford Site solid waste treatment, storage, and disposal facilities accept solid, low-level radioactive waste from onsite and offsite generators. This manual defines the certification program that is used to provide assurance that the waste meets the Hanford Site waste acceptance criteria. Specifically, this program defines the participation and responsibilities of Westinghouse Hanford Company Solid Waste Engineering Support, Westinghouse Hanford Company Quality Assurance, and both onsite and offsite waste generators. It is intended that waste generators use this document to develop certification plans and quality assurance program plans. This document is also intended for use by Westinghouse Hanford Company solid waste technical staff involved in providing assurance that generators have implemented a waste certification program. This assurance involves review and approval of generator certification plans, and review of generator's quality assurance program plans to ensure that they address all applicable requirements. The document also details the Westinghouse Hanford Company Waste Management Audit and Surveillance Program. 5 refs

Determination of plutonium in highly radioactive liquid waste by spectrophotometry using neodymium as an internal standard for safeguards analysis. Japan support program for agency safeguards (JASPAS) JC-19

International Nuclear Information System (INIS)

Taguchi, Shigeo; Surugaya, Naoki; Sato, Soichi; Kurosawa, Akira; Watahiki, Masaru; Hiyama, Toshiaki

2006-06-01

A spectrophotometric determination using neodymium as an internal standard was developed for safeguards verification analysis of plutonium in highly radioactive liquid waste which is produced by the reprocessing of spent nuclear fuel. The internal standard is used as a means to analyze plutonium and also to authenticate the instrument conditions. The method offers reduced sample preparation and analysis time compared to isotope dilution mass spectrometry. The sample was mixed with a known amount of internal standard. Subsequently, plutonium was quantitatively oxidized to Pu(VI) by the addition of Ce(IV) for spectrophotometry. Plutonium concentration was calculated from a relation between Nd(III)/Pu(VI) molar extinction coefficient ratio and their absorbance ratio. The relative expanded uncertainty of the repeated analysis (n=5) was 8.9% (coverage factor k=2) for a highly radioactive liquid waste sample (173 mg L -1 ). The determination limit was 6 mg L -1 (ten fold's the standard deviation). This method was validated through comparison experiments with isotope dilution mass spectrometry. The analytical results of plutonium in highly radioactive liquid waste using this method were agree well with values obtained using isotope dilution mass spectrometry. The proposed method can be applied to independent on-site safeguards analysis at the Tokai Reprocessing Plant. (author)

Study of relationship between radioactivity distribution, contamination burden and quality standard, accommodate energy of code river Yogyakarta

International Nuclear Information System (INIS)

Agus Taftazani and Muzakky

2009-01-01

Study of relationship between distribution, contamination burden of gross β radioactivity and natural radionuclide in water and sediment sample from 11 observation station Code river to quality standard and maximum capacity of Code river have been done. Natural radio nuclides identification and gross β radioactivity measurement of condensed water, dry and homogeneous sediment powder (past through 100 mesh sieve) samples have been done by using spectrometer and GM counter. Radioactivity data was analyzed descriptive with histogram to show the spreading pattern of data. Contamination burden data, quality standard and maximum capacity of river Code was to descriptive analyzed by line diagram to knowing relationship between contamination burden, quality standard, and maximum capacity of Code river. The observation of water and sediment at 11 observation station show that the emitter natural radionuclides: 210 Pb, 212 Pb, 214 Pb, 226 Ra, 208 Tl, 214 Bi, 228 Ac and 40 K were detected. The analytical result conclusion was that the pattern spread of average activity gross β and were increase from upstream to downstream of the Code river samples. Contamination burden, quality standard and maximum capacity of radionuclide activity of 210 Pb, 212 Pb, 226 Ra and 228 Ac were more smaller than quality standard of river water according to regulation of Nuclear Energy Regulatory Agency 02/Ka-BAPETEN/V-99 concerning quality standard of radioactivity. It’s mean that Code river still in good contamination burden for the four radionuclides. (author)

Objectives, standards and criteria for radioactive waste disposal in the European Community

International Nuclear Information System (INIS)

Orlowski, S.; Schaller, K.H.

1989-01-01

The present report, edited by a working group within the framework of the European Commission research programme on radioactive waste management and disposal, reviews the objectives, standards and criteria for radioactive waste disposal in the European Community with a view to identifying common features and differences in the regulatory frameworks of its Member States. Suggestions for possible harmonization are made. A few common general principles form the basis for legal and regulatory measures. These principles apply to and are discussed for the following: radiation protection (with the systems of dose limitation and control), ethical and sociological questions, environmental and natural resources protection, and nuclear safeguards. A description is given of the implementation of common principles, standards and requirements at Community level, in line with requirements laid down in the European Community Treaties, and in international conventions and recommendations. This is followed by a review of the implementation of basic criteria by national safety authorities. Regulatory measures and national policies, and the approaches used in devising criteria are discussed for both near-surface disposal of low-level waste, and for deep geological disposal of waste in continental geological formations. Finally, the roles and duties of the operators of radioactive waste facilities are reported. More detailed information on particular aspects is presented in the annexes

Implementation of a management applied program for liquid radioactive waste treatment

International Nuclear Information System (INIS)

Lee, Y. H.; Ann, S. J.; Jo, H. S.; Son, J. S.

2003-01-01

A data collection of a liquid radioactive waste treatment process of a research organization became necessary while developing the RAWMIS(Radioactive Waste Management Integration System) which it can generate personal history management for efficient management of a waste, documents, all kinds of statistics. This paper introduces an input and output application program design to do to database with data in the results and a stream process of a treatment that analyzed the waste occurrence present situation and data by treatment process. Data on the actual treatment process that is not limited experiment improve by a document, human traces, saving of material resources and improve with efficiency of tracking about a radioactive waste and a process and give help to radioactive waste material valance and inventory study

Determination of quality standard of cemented radioactive wastes

International Nuclear Information System (INIS)

Johan, B.

1997-01-01

The standard determination of cemented low activity radioactive waste has been carried out. This study was intended to find the quality of immobilized product as a guaranty to the public and the environmental safety. As preliminary study, there parameters type have been studied i.e, the density, compressive strength and the leaching rate. By adopted the formulations of advanced country and field data, it can be concluded that the cementation waste should have the density, p, between 1.70 and 2.50 g.cm - 3, the compressive strength, S, between 20 and 50 N.mm - 2, the leaching rates R n between 1.70 x 10 - 2 and 2.50 x 10 - 3 g.cm - 2.day - 1 and after 150 days leaching time the leaching rate R n - 3 g.cm - 2.day - 1. This study is expected to be used to propose the Indonesian National Standard (INS) (author)

Program integration on the Civilian Radioactive Waste Management System

International Nuclear Information System (INIS)

Trebules, V.B.

1995-01-01

The recent development and implementation of a revised Program Approach for the Civilian Radioactive Waste Management System (CRWMS) was accomplished in response to significant changes in the environment in which the program was being executed. The lack of an interim storage site, growing costs and schedule delays to accomplish the full Yucca Mountain site characterization plan, and the development and incorporation of a multi-purpose (storage, transport, and disposal) canister (MPC) into the CRWMS required a reexamination of Program plans and priorities. Dr. Daniel A. Dreyfus, the Director of the Office of Civilian Radioactive Waste Management (OCRWM), established top-level schedule, targets and cost goals and commissioned a Program-wide task force of DOE and contractor personnel to identify and evaluate alternatives to meet them. The evaluation of the suitability of Yucca Mountain site by 1998 and the repository license application data of 2001 were maintained and a target date of January 1998 for MPC availability was established. An increased multi-year funding profile was baselined and agreed to by Congress. A $1.3 billion reduction in Yucca Mountain site characterization costs was mandated to hold the cost to $5 billion. The replanning process superseded all previous budget allocations and focused on program requirements and their relative priorities within the cost profiles. This paper discusses the process for defining alternative scenarios to achieve the top-level program goals in an integrated fashion

The new orphaned radioactive sources program in the United States

International Nuclear Information System (INIS)

Naraine, N.; Karhnak, J.M.

1998-01-01

Exposure of the public to uncontrolled radioactive sources has become an significant concern to the United States (US) Government because of the continuous increase in the number of sources that are being found, sometimes without proper radiation markings. This problem is primarily due to inadequate control, insufficient accountability, and improper disposal of radioactive materials. The US Environmental Protection Agency (EPA) has funded a cooperative 'orphaned' source initiative with the Conference of Radiation Control Program Directors (CRCPD) to bring under control unwanted sources and thus reduce the potential for unnecessary exposure to the public, workers and the environment. The program is being developed through the cooperative efforts of government agencies and industry, and will provide a quick and efficient method to bring orphaned sources under control and out of potentially dangerous situations. (author)

Developing an ANSI standard for semitrailers used to transport radioactive materials

International Nuclear Information System (INIS)

Gregory, P.

1990-01-01

A proposed new American National Standards Institute (ANSI) standard has been prepared which establishes requirements for the design, fabrication, and maintenance of semitrailers used in the highway transport of weight-concentrated radioactive loads. A weight-concentrated load is any payload which exceeds 1,488 kilograms per lineal meter (1,000 lb/ft) over any portion of the semitrailer. The proposed standard also provides detailed procedures for in-service inspections, as well as requirements for testing and quality assurance. The standard addresses only semitrailers, excluding the tractor. Trailers already in service may be certified as complying with the standard if they meet the requirements of the standard. This standard is intended to provide guidance and acceptance criteria needed to establish a uniform minimum level of performance for the designer, manufacturer, owner, operator, and shipper. This standard is not intended to apply to special, non-routine shipments of a one-time or occasional nature which require special permitting. The background and history of the standard are traced and a summary discussion of the standard is provided in this article

USEPA consideration of human intrusion in setting radioactive waste disposal standards

International Nuclear Information System (INIS)

Egan, D.J.; Hadlock, C.R.

1989-01-01

In 1985, the United States Environmental Protection Agency (USEPA) promulgated standards for the disposal of spent nuclear fuel and high-level and transuranic radioactive wastes (40 CFR Part 191). These standards placed limits, called containment requirements, on the projected releases of radioactivity due to both normal and accidental events for 10,000 years after disposal. The standards also contained qualitative assurance requirements that described the role foreseen for both active and passive institutional controls. They included both requirements for such institutional controls and limitations on the ways that they could be relied upon. This paper describes these assumptions about institutional controls made by the USEPA, and it discusses the types of future societies that would be consistent with such assumptions. The paper also reviews the USEPA's approach towards assessing the long-term performance of mined geologic repositories. In these assessments, the risks caused by inadvertent human intrusion into the area of a repository usually dominate the risks projected from other release scenarios. The assumptions made about inadvertent intrusion are discussed, and they are related to the policies regarding institutional controls. The disposal standards that the USEPA promulgated in 1985 were overturned by a Federal court in 1987, and the Agency is now preparing revised standards for public review and comment. These are expected to by published in 1990. However, the approaches regarding institutional controls and human intrusion are expected to remain the same as those used in 1985. Some paragraphs (selected by the NEA Secretariat) of 40 CFR Part 191, subpart B (as of 1985 version) with particular relevance to human intrusion are cited

Selection of optimal treatment procedures for non-standard radioactive waste arising from decommissioning of NPP after accident

Energy Technology Data Exchange (ETDEWEB)

Strážovec, Roman, E-mail: strazovec.roman@javys.sk [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia); JAVYS, a.s., Tomášikova 22, 821 02 Bratislava (Slovakia); Hrnčíř, Tomáš [DECOM, a.s., Sibírska 1, 917 01 Trnava (Slovakia); Lištjak, Martin [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia); VUJE, a.s., Okružná 5, 918 64 Trnava (Slovakia); Nečas, Vladimír [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia)

2016-05-15

The decommissioning of nuclear power plants is becoming a standard industrial activity where the optimization processes of partial activities are inevitable mainly for technical and economic reasons. In Slovakia, the decommissioning of A1 NPP is very specific case because A1 NPP is rare type of NPP (prototype) and furthermore its operation was affected by the accident. A large number of specific non-standard radioactive waste, such as long-time storage cases (hereinafter LSC), that is not usually present within the decommissioning projects of NPP with a regular termination of operation, represent one of the significant consequences of the accident and issues arisen from follow-up activities. The presented article describes the proposal of processing and conditioning of non-standard radioactive waste (such as LSC), together with description of methodology applied in the proposal for update of waste acceptance criteria for the processing and conditioning of radioactive waste (hereinafter RAW) within Bohunice Radioactive waste Treatment and Conditioning Centre (hereinafter RWTC). The results of performed detailed analysis are summarized into new waste acceptance criteria for technological lines keeping in mind safety principles and requirements for protection of operating personnel, the public and the environment.

Study on the establishment of technical standards of radioactive wastes (annual report)

International Nuclear Information System (INIS)

Kim, Jhin Wung; Hwang, Y. S.; Kim, S. H.; Yoo, J. H.; Lee, I. H.; Yang, H. B.; Rhim, J. K.

1997-03-01

From 1989, KAERI and KINS have worked together to set up national regulations to safely manage radioactive wastes. This year project covers 3 items : 1) post-closure surveillance criteria and closure criteria for disposal of LLW wastes, 2) standard format and contents of safety analysis report for spent fuel interim storage, and 3) review of existing regulations. Results from detailed research shall be used to set up the MOST notices on the safe management of radioactive wastes. Even though this project has been stopped after the national rearrangement on the management of LLW, KINS which jointly has studied this project shall independently study it in the future. (author)

PROGER - Management program for radioactive wastes in research institutions

International Nuclear Information System (INIS)

Ferreira, Rubemar S.; Costa, Maria Regina Ferro; Ramos Junior, Anthenor C.; Esposito, Irapoan; Vaz, Solange dos Reis e; Pontedeiro, Elizabeth May; Gomes, Carlos de Almeida

1997-01-01

This article demonstrates the feasibility of a program, denominated PROGER, and aimed at the improvement of radioactive waste management activities in research institutions in Brazil. This program involves implementation, correction and updating of waste management techniques in those institutions that already possess a waste management system or its full set-up for the institutions where it is non-existent. Partial results are presented, concerning characteristics and quantities of wastes, and the methodology utilized by PROGER discussed

Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages

International Nuclear Information System (INIS)

1993-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Historically Black Colleges and Universities Radioactive Waste Management Research Program: Summary of activities, 1985-1986

International Nuclear Information System (INIS)

1986-01-01

This report summarizes the 1985 to 1986 activities of the Historically Black Colleges and Universities (HBCUs) Radioactive Waste Management Research Program sponsored by the Office of Civilian Radioactive Waste Management of the US Department of Energy (DOE). The first set of three awards was made in September,1984. In September, 1985, two of these projects were renewed and a new proposal was funded. The program has been enthusiastically received by the community of HBCUs and the program sponsor

The support for a purification of water contaminated with radioactivity, and problems of the radioactivity standard in an emergency situation at the stricken area 2011 Great East Japan Earthquake

International Nuclear Information System (INIS)

Maeda, Yoshiaki

2011-01-01

The accident of the Fukushima Daiichi Nuclear Station of Tokyo Electric Power Company associated with the Great East Japan Earthquake incurred severe situation, where lifeline was cut off due to the discharge of a large amount of radioactive substances. In particular, the supply of safe foods and drinking water in radiation-polluted areas is urgently required. The authors have been developing up to now Crystal Valley water purifier and CV-Rescue water purifier that can purify well-water unsuitable for drinking due to contamination with toxic substances and produce drinkable water with safety without anxiety. This paper introduces the processes, in which verification test was performed to confirm that the above purifiers can be used for the removal of radioactivity discharged from the Great East Japan Earthquake this time, the validity of these purifiers was clarified, and these purifiers have actually been used for supporting water supply. This paper especially points out that a problem exists in the various standards on radioactivity that were temporarily determined in face of emergency of radiation pollution due to the nuclear power station accident this time. In these standards, the temporary standard on radioactive iodine 131 in drinking water is too high compared with the standards of WHO and those of advanced countries like U.S.A. It also points out the problem that radioactive substances in drinking water have not been removed yet. (O.A.)

INEEL Radioactive Liquid Waste Reduction Program

International Nuclear Information System (INIS)

Millet, C.B.; Tripp, J.L.; Archibald, K.E.; Lauerhauss, L.; Argyle, M.D.; Demmer, R.L.

1999-01-01

Reduction of radioactive liquid waste, much of which is Resource Conservation and Recovery Act (RCRA) listed, is a high priority at the Idaho National Technology and Engineering Center (INTEC). Major strides in the past five years have lead to significant decreases in generation and subsequent reduction in the overall cost of treatment of these wastes. In 1992, the INTEC, which is part of the Idaho National Environmental and Engineering Laboratory (INEEL), began a program to reduce the generation of radioactive liquid waste (both hazardous and non-hazardous). As part of this program, a Waste Minimization Plan was developed that detailed the various contributing waste streams, and identified methods to eliminate or reduce these waste streams. Reduction goals, which will reduce expected waste generation by 43%, were set for five years as part of this plan. The approval of the plan led to a Waste Minimization Incentive being put in place between the Department of Energy Idaho Office (DOE-ID) and the INEEL operating contractor, Lockheed Martin Idaho Technologies Company (LMITCO). This incentive is worth $5 million dollars from FY-98 through FY-02 if the waste reduction goals are met. In addition, a second plan was prepared to show a path forward to either totally eliminate all radioactive liquid waste generation at INTEC by 2005 or find alternative waste treatment paths. Historically, this waste has been sent to an evaporator system with the bottoms sent to the INTEC Tank Farm. However, this Tank Farm is not RCRA permitted for mixed wastes and a Notice of Non-compliance Consent Order gives dates of 2003 and 2012 for removal of this waste from these tanks. Therefore, alternative treatments are needed for the waste streams. This plan investigated waste elimination opportunities as well as treatment alternatives. The alternatives, and the criteria for ranking these alternatives, were identified through Value Engineering meetings with all of the waste generators. The most

Factor of radioactive waste on nuclear power program

International Nuclear Information System (INIS)

Syed Abdul Malik Syed Zain

2009-01-01

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

Importance of the Primary Radioactivity Standard Laboratory and Implementation of its Quality Management

Science.gov (United States)

Sahagia, Maria; Razdolescu, Anamaria Cristina; Luca, Aurelian; Ivan, Constantin

2007-04-01

The paper presents some specific aspects of the implementation of the quality management in the Radionuclide Metrology Laboratory, from IFIN-HH, the owner of the primary Romanian standard in radioactivity. The description of the accreditation, according to the EN ISO/IEC 17025:2005, is presented.

Importance of the Primary Radioactivity Standard Laboratory and Implementation of its Quality Management

International Nuclear Information System (INIS)

Sahagia, Maria; Razdolescu, Anamaria Cristina; Luca, Aurelian; Ivan, Constantin

2007-01-01

The paper presents some specific aspects of the implementation of the quality management in the Radionuclide Metrology Laboratory, from IFIN-HH, the owner of the primary Romanian standard in radioactivity. The description of the accreditation, according to the EN ISO/IEC 17025:2005, is presented

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

International Nuclear Information System (INIS)

Sukiman Sarmani

2002-01-01

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

Research program on radioactive wastes 2013-2016

International Nuclear Information System (INIS)

Berner, U.; Bossart, P.; Brander, S.; Schaub, P.; Frank, E.; Hugi, M.; Holocher, J.; Schlüchter, Ch.

2013-06-01

This report issued by the Swiss Federal Office of Energy (SFOE) takes a look at the work done within the framework of the 2012 Swiss Research Program on radioactive wastes. The implementation program for the period 2013 - 2016 is discussed. Long-term aspects such as knowledge conservation and marking concepts are investigated and regional participation in the planning of repositories is discussed. Environmental protection, the planning of repositories and the definition of their content are discussed. Monitoring concepts and emergency closure in crisis situations are also looked at. The associated material technologies and repository design are discussed. Finally, ethical considerations and environmental policies are discussed. Two appendices include information on the timelines involved as well as information on the players involved and their areas of competence

Issues related to the USEPA probabilistic standard for geologic disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Okrent, D.

1993-01-01

This paper asks whether some of the fundamental bases for the 1985 USEPA standard on disposal of high level radioactive wastes (40 CFR Part 191) warrant re-examination. Similar questions also apply to the bases for the radioactive waste disposal requirements proposed by most other countries. It is suggested that the issue of intergenerational equity has been dealt with from too narrow a perspective. Not only should radioactive and nonradioactive hazardous waste disposal be regulated from a consistent philosophic basis, but the regulation of waste disposal itself should be embedded in the broader issues of intergenerational conservation of options, conservation of quality, and conservation of access. (author). 25 refs

Issues relating to safety standards on the geological disposal of radioactive waste. Proceedings of a specialists meeting

International Nuclear Information System (INIS)

2002-06-01

Within the International Atomic Energy Agency focus is currently being placed on establishing safety standards for the geological disposal of radioactive waste. This is a challenging task and a Specialists Meeting was held from 18 to 22 June 2001 with the intention of providing a mechanism for promoting discussion on some of the associated scientific and technical issues and as a means of developing the consensus needed for establishing the standards. The meeting used, as its basis, a number of position papers developed in recent years with the help of a subgroup of the Waste Safety Standards Committee (WASSC), the subgroup on Principles and Criteria for Radioactive Waste Disposal, together with selected relevant regional and national papers. The report contains the summaries of the sessions of the Specialists Meeting together with the conclusions drawn relevant to the establishment of standards. The sessions of the Meeting addressed the following topics: Common framework for radioactive waste disposal; Making the safety case - demonstrating compliance; Safety indicators; Reference critical groups and biospheres; Human intrusion; Reversibility and retrievability; Monitoring and institutional control. The publication contains 26 individual presentations delivered by participants. Each of these presentations was indexed separately

Standards for Adult Education ESL Programs

Science.gov (United States)

TESOL Press, 2013

2013-01-01

What are the components of a quality education ESL program? TESOL's "Standards for Adult Education ESL Programs" answers this question by defining quality components from a national perspective. Using program indicators in eight distinct areas, the standards can be used to review an existing program or as a guide in setting up a new…

Michigan high-level radioactive waste program. Technical progress report for 1985

International Nuclear Information System (INIS)

1986-01-01

In 1985, five crystalline rock formations located in Michigan's Upper Peninsula were under consideration in the regional phase of the Department of Energy's (DOE) search for the site of the nation's second high-level radioactive waste repository. The Michigan Department of Public Health has been designated by the Governor as lead state agency in matters related to high-level radioactive waste (HLRW). Mr. Lee E. Jager, Chief of the Department's Bureau of Environmental and Occupational Health, has been designated as the state contact person in this matter, and the Bureau's Division of Radiological Health, Office of Radioactive Waste Management (ORWM), has been designated to provide staff support. Recognizing that adequate state involvement in the various aspects of the Federal high-level radioactive waste (HLRW) programs would require a range of expertise beyond the scope of any single state agency, Governor Blanchard established the High-Level Radioactive Waste Task Force in 1983. In support of the Task Force efforts concerning the implementation of its change, the Department negotiated and concluded an agreement with the DOE, under which federal funds are provided to support state HLRW activities. This report outlines state activities for the calendar year 1985, funded under that agreement

Radioactivity metrology

International Nuclear Information System (INIS)

Legrand, J.

1979-01-01

Some aspects of the radioactivity metrology are reviewed. Radioactivity primary references; absolute methods of radioactivity measurements used in the Laboratoire de Metrologie des Rayonnements Ionisants; relative measurement methods; traceability through international comparisons and interlaboratory tests; production and distribution of secondary standards [fr

Radioactive Waste Management in the European Union: Initiatives for New Legislation

International Nuclear Information System (INIS)

Taylor, D.

2003-01-01

Improving the management of radioactive waste in the European Union is a major theme of the ''nuclear package'' recently adopted by the European Commission. Included in the package are proposals for new legislation that would bring about the development of common safety standards in Europe covering the full nuclear sector, segregated funds to cover all nuclear liabilities that remain after the operating lifetime of an installation and clearly defined waste programs for radioactive waste management in each of the Member States of the Union. Included in these programs must be firm dates for a number decision points leading to disposal of all forms of radioactive waste. The package also puts significant emphasis on more, and better coordinated, research on radioactive waste management as the present levels are thought to be inadequate

Data Processing and Programming Applied to an Environmental Radioactivity Laboratory

International Nuclear Information System (INIS)

Trinidad, J. A.; Gasco, C.; Palacios, M. A.

2009-01-01

This report is the original research work presented for the attainment of the author master degree and its main objective has been the resolution -by means of friendly programming- of some of the observed problems in the environmental radioactivity laboratory belonging to the Department of Radiological Surveillance and Environmental Radioactivity from CIEMAT. The software has been developed in Visual Basic for applications in Excel files and it solves by macro orders three of the detected problems: a) calculation of characteristic limits for the measurements of the beta total and beta rest activity concentrations according to standards MARLAP, ISO and UNE and the comparison of the three results b) Pb-210 and Po-210 decontamination factor determination in the ultra-low level Am-241 analysis in air samples by alpha spectrometry and c) comparison of two analytical techniques for measuring Pb-210 in air ( direct-by gamma spectrometry- and indirect -by radiochemical separation and alpha spectrometry). The organization processes of the different excel files implied in the subroutines, calculations and required formulae are explained graphically for its comprehension. The advantage of using this kind of programmes is based on their versatility and the ease for obtaining data that lately are required by tables that can be modified as time goes by and the laboratory gets more data with the special applications for describing a method (Pb-210 decontamination factors for americium analysis in air) or comparing temporal series of Pb-210 data analysed by different methods (Pb-210 in air). (Author)

Proceedings of the international symposium on radioactive waste disposal: Health and environmental criteria and standards

International Nuclear Information System (INIS)

Hultcrantz, K.

1999-04-01

The co-organisers of the International Symposium on Health and Environmental Criteria and Standards for Radioactive Waste Disposal are pleased to present these proceedings. This Symposium succeeded in bringing together a wide range of participants and perspectives in order to address in a common forum the technical and non-technical issues related to long-term storage of radioactive waste. The papers presented herein reflect both the diversity of the participants and the complexity of the issues addressed. The sessions, panels, and papers developed for the symposium focused on some of the daunting challenges posed by long-term isolation and storage of high level radioactive waste. Panel sessions addressed the basic principles of criteria and standards, the context of the risks involved, and an overview of relevant philosophical, social, and ethical issues. Paper sessions considered national laws, policies and experiences; criteria formulation; environmental protection; compliance; human intrusion; and fundamental philosophical, social, and ethical issues. The presentations stimulated lively discussion and debate, and the contributors received valuable feedback. The interplay between technical and social aspects reflected in some papers and in the discussion highlights the changing role of the public in radioactive waste issues. The average citizen has become more aware of and more involved in radioactive waste matters in recent years. Solutions that were previously analysed through a technological lens are now being viewed in a much broader perspective that better addresses the concerns of local communities as well as national and international interests. Public involvement must begin earlier, last longer, and improve in quality so as to create an ongoing dialogue and debate rather than cycles of dictates and discord. The symposium has offered suggestions as to how government, industry, and the public can foster a broader dialogue on the formulation and

Analysis of the qualification test standards for small radioactive material shipping packages

International Nuclear Information System (INIS)

McClure, J.D.

1978-01-01

The study compares the severity of the existing regulatory standards which are used to license radioactive material (RAM) shipping packages with the severity of transportation accidents. The basic findings of the study indicate that the present regulatory standards provide significantly higher levels of protection for surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It was also determined that crush can occur in all of the transport modes and is not presently included in existing regulations for accident conditions. Test proposals are included for the surface transport mode (truck, rail) and the air transport mode

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

International Nuclear Information System (INIS)

2008-03-01

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

Benefits of standard format and content for approval of packaging for radioactive material

International Nuclear Information System (INIS)

Pstrak, D.; Osgood, N.

2004-01-01

The U.S. Nuclear Regulatory Commission (NRC) uses Regulatory Guide 7.9, ''Standard Format and Content of Part 71 Applications for Approval of Packaging for Radioactive Material'' to provide recommendations on the preparation of applications for approval of Type B and fissile material packages. The purpose of this Regulatory Guide is to assist the applicant in preparing an application that demonstrates the adequacy of a package in meeting the 10 CFR Part 71 packaging requirements. NRC recently revised Regulatory Guide 7.9 to reflect current changes to the regulations in Part 71 as a result of a recent rulemaking that included changes to the structural, containment, and criticality requirements for packages. Overall, the NRC issues Regulatory Guides to describe methods that are acceptable to the NRC staff for implementing specific parts of the NRC's regulations, to explain techniques used by the NRC staff in evaluating specific problems, and to provide guidance to applicants. It is important to note the specific purpose of this Regulatory Guide. As the name indicates, this Guide sets forth a standard format for application submission that is acceptable to the NRC staff that, when used by the applicant, will accomplish several objectives. First, use of the guide provides a consistent and repeatable approach that indicates the information to be provided by the applicant. Second, the organization of the information in the application will assist the reviewer(s) in locating information. Ultimately, accomplishing these objectives will help to ensure the completeness of the information in the application as well as decrease the review time. From an international perspective, use of a standard format approach could enhance the efficiency with which Competent Authorities certify and validate packages for use in the packaging and transportation of radioactive material worldwide. This streamlined approach of preparing package applications could ultimately lead to uniform

Summary report of the state surveillance program on the transportation of radioactive materials

International Nuclear Information System (INIS)

1977-11-01

From 1973 to 1976, a surveillance program was conducted in New Jersey, Oregon, Missouri, New York, Illinois, Texas, Louisiana, South Carolina, Minnesota, and New York City to provide training support for State radiation personnel and to determine actual radiation exposure conditions and radioactive material package handling practices through the terminals of air carriers and freight forwarders. NRC and DOT along with the participating States, developed the surveillance program. In general, the results did not indicate a public health or safety problem due to the transportation of radioactive materials. Some employees of several freight forwarders, are, however, receiving annual exposures in excess of 500 mrem. Recommendations are given

Assessment of the indicator of sustainable development for radioactive waste management

International Nuclear Information System (INIS)

Jung, J. H.; Park, W. J.

2003-01-01

As a follow up to the agenda 21's policy statement for safe management of radioactive waste adopted at Rio Conference held in 1992, the UN invited the IAEA to develop and implement indicators of sustainable development for the management of radioactive waste. The IAEA finalized the indicators in 2002, and is planning to calculate the member states' values of indicator in connection with operation of its Net-Enabled Waste Management Database system. In this paper, the basis for introducing the indicators into the radioactive waste management was analyzed, and calculation methodology and standard assessment procedure were simply depicted. According to the proposed standard procedure, the indicators for some countries including Korea were calculated and compared, by use of each country's radioactive waste management framework and its practices. In addition, a series of measures increasing the values of the indicators was derived so as to enhance the sustainability of domestic radioactive waste management program

Improvement program of state supervision system for radioactive and nuclear installations

International Nuclear Information System (INIS)

Cardenas, J.

1993-01-01

The current program begins as part of a policy to take care of the development of the cuban nuclear program and with the objective of improving the state supervision system of nuclear and radioactive facilities on the basis of the national experience, good skills internationally accepted and taking into account IAEA recommendations. The program develops the following topics: reorientation and restructure of state supervision, review of the current nuclear legislature, update of regulations of facility safety and qualification and training of state supervision personnel

The Constitution, waste facility performance standards, and radioactive waste classification: Is equal protection possible?

Energy Technology Data Exchange (ETDEWEB)

Eye, R.V. [Kansas Dept. of Health and Environment, Topeka, KS (United States)

1993-03-01

The process for disposal of so-called low-level radioactive waste is deadlocked at present. Supporters of the proposed near-surface facilities assert that their designs will meet minimum legal and regulatory standards currently in effect. Among opponents there is an overarching concern that the proposed waste management facilities will not isolate radiation from the biosphere for an adequate length of time. This clash between legal acceptability and a perceived need to protect the environment and public health by requiring more than the law demand sis one of the underlying reasons why the process is deadlocked. Perhaps the most exhaustive public hearing yet conducted on low-level radioactive waste management has recently concluded in Illinois. The Illinois Low-Level Radioactive Waste Disposal Facility Sitting Commission conducted 71 days of fact-finding hearings on the safety and suitability of a site near Martinsville, Illinois, to serve as a location for disposition of low-level radioactive waste. Ultimately, the siting commission rejected the proposed facility site for several reasons. However, almost all the reasons were related, to the prospect that, as currently conceived, the concrete barrier/shallow-land burial method will not isolate radioactive waste from the biosphere. This paper reviews the relevant legal framework of the radioactive waste classification system and will argue that it is inadequate for long-lived radionuclides. Next, the paper will present a case for altering the classification system based on high-level waste regulatory considerations.

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

International Nuclear Information System (INIS)

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

2000-01-01

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

A users guide to the radioactive waste inventory program 'DATABASE'

International Nuclear Information System (INIS)

Prince, G.A.; Tymons, B.J.

1984-09-01

The program computes an inventory of radioactive waste accumulation in a form such that a variety of interrogation, collation and summary functions can be used to access the stored information. Database is designed to be used online, that is the user will communicate with it at a computer terminal, and the program will display the result of each enquiry. It has the potential to automate much of the searching and adding up which was involved in compiling and using waste inventories in the past. (author)

Methods for estimating costs of transporting spent fuel and defense high-level radioactive waste for the civilian radioactive waste management program

International Nuclear Information System (INIS)

Darrough, M.E.; Lilly, M.J.

1989-01-01

The US Department of Energy (DOE), through the Office of Civilian Radioactive Waste Management, is planning and developing a transportation program for the shipment of spent fuel and defense high-level waste from current storage locations to the site of the mined geologic repository. In addition to its responsibility for providing a safe transportation system, the DOE will assure that the transportation program will function with the other system components to create an integrated waste management system. In meeting these objectives, the DOE will use private industry to the maximum extent practicable and in a manner that is cost effective. This paper discusses various methodologies used for estimating costs for the national radioactive waste transportation system. Estimating these transportation costs is a complex effort, as the high-level radioactive waste transportation system, itself, will be complex. Spent fuel and high-level waste will be transported from more than 100 nuclear power plants and defense sites across the continental US, using multiple transport modes (truck, rail, and barge/rail) and varying sizes and types of casks. Advance notification to corridor states will be given and scheduling will need to be coordinated with utilities, carriers, state and local officials, and the DOE waste acceptance facilities. Additionally, the waste forms will vary in terms of reactor type, size, weight, age, radioactivity, and temperature

Draft directive on the management of radioactive wastes based on deep geological disposal

International Nuclear Information System (INIS)

Anon.

2010-01-01

The European Commission works on a legal framework to assure that all the member states apply the same standards in all the stages of the management of spent fuels and radioactive wastes till their definitive disposal. The draft propositions are the following. The standards to follow are those proposed by the IAEA. First, each member state has to set a national program dedicated to the management of radioactive wastes. This program will have to detail: the chosen solution, the description of the project, a time schedule, costs and financing. Secondly, the exportation of nuclear wastes for definitive disposal is not allowed unless the 2 countries have agreed to build a common nuclear waste disposal center. Thirdly, the population will have to be informed on the project and will have to take part in the decision process. Fourthly, the standards set by IAEA will be enforced by law. There is a broad consensus between scientists and international organizations like IAEA to consider that the disposal in deep geological layers of high-level radioactive wastes is the most adequate solution. (A.C.)

PWR-GALE, Radioactive Gaseous Release and Liquid Release from PWR

International Nuclear Information System (INIS)

Chandrasekaran, T.; Lee, J.Y.; Willis, C.A.

1988-01-01

1 - Description of program or function: The PWR-GALE (Boiling Water Reactor Gaseous and Liquid Effluents) Code is a computerized mathematical model for calculating the release of radioactive material in gaseous and liquid effluents from pressurized water reactors (PWRs). The calculations are based on data generated from operating reactors, field tests, laboratory tests, and plant-specific design considerations incorporated to reduce the quantity of radioactive materials that may be released to the environment. 2 - Method of solution: GALE calculates expected releases based on 1) standardized coolant activities derived from ANS Standards 18.1 Working Group recommendations, 2) release and transport mechanisms that result in the appearance of radioactive material in liquid and gaseous waste streams, 3) plant-specific design features used to reduce the quantities of radioactive materials ultimately released to the environs, and 4) information received on the operation of nuclear power plants. 3 - Restrictions on the complexity of the problem: The liquid release portion of GALE uses subroutines taken from the ORIGEN (CCC-217) to calculate radionuclide buildup and decay during collection, processing, and storage of liquid radwaste. Memory requirements for this part of the program are determined by the large nuclear data base accessed by these subroutines

Management plan for the Nuclear Standards Program

International Nuclear Information System (INIS)

1979-11-01

This Management Plan was prepared to describe the manner in which Oak Ridge National Laboratory will provide technical management of the Nuclear Standards Program. The organizational structure that has been established within ORNL for this function is the Nuclear Standards Management Center, which includes the Nuclear Standards Office (NSO) already in existence at ORNL. This plan is intended to support the policies and practices for the development and application of technical standards in ETN projects, programs, and technology developments as set forth in a standards policy memorandum from the DOE Program Director for Nuclear Energy

Radiation protection program of Petrobras

International Nuclear Information System (INIS)

Signorini, M.

1988-01-01

Risks present in oil industry require specific control programs, specialy when using radioactive sources. Main uses of ionizing radiation in oil industry are in process control systems, industrial radiography and oilwell logging. A comprehensive and sistemic program is presented in order to assure the safe use of ionizing radiation in these activities. Principal subjects of this program are the control of radioactive sources, personel training in order to difuse knowledge at operations level and procedures standardization. (author) [pt

United States Program on Spent Nuclear Fuel and High-Level Radioactive Waste Management

International Nuclear Information System (INIS)

Stewart, L.

2004-01-01

The President signed the Congressional Joint Resolution on July 23, 2002, that designated the Yucca Mountain site for a proposed geologic repository to dispose of the nation's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The United States (U.S.) Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is currently focusing its efforts on submitting a license application to the U.S. Nuclear Regulatory Commission (NRC) in December 2004 for construction of the proposed repository. The legislative framework underpinning the U.S. repository program is the basis for its continuity and success. The repository development program has significantly benefited from international collaborations with other nations in the Americas

The standard for program management

CERN Document Server

2017-01-01

The Standard for Program Management – Fourth Edition differs from prior editions by focusing on the principles of good program management. Program activities have been realigned to program lifecycle phases rather than topics, and the first section was expanded to address the key roles of program manager, program sponsor and program management office. It has also been updated to better align with PMI’s Governance of Portfolios, Programs, and Projects: A Practice Guide.

Pilot internship program on radioactive waste at Vanderbilt University

International Nuclear Information System (INIS)

1988-01-01

The fourth year of the program began with the selection of the new interns. Mailings were sent to prospective graduate students and rising juniors at Vanderbilt University with grade point averages of 3.0 or better (out of 4.0) advertising the availability of internships in radioactive waste disposal. New interns were selected. All of the interns selected in the fourth year chose to return to Vanderbilt after their field assignment

A program for evolution from storage to disposal of radioactive wastes at CRNL

International Nuclear Information System (INIS)

Dixon, D.F.

1985-10-01

This report reviews past and current radioactive waste management practices at the Chalk River Nuclear Laboratories (CRNL) and outlines the proposed future program. For nearly 40 years, radioactive wastes have been generated at CRNL and have also been received there on a continuing basis from hospitals, industries, universities and miscellaneous other sources across Canada. The solid wastes now at CRNL have been either stored or buried and their total consolidated volume is approaching 50 000 m 3 . Much of that waste will require disposal as will the future wastes of similar character. The waste management program plan describes the proposed development of safe disposal facilities which could be built on site to accommodate most, if not all, of the radioactive wastes for which CRNL has responsibility. Three reference disposal concepts, each potentially capable of accepting a portion of the wastes, are described. One of these, the intrusion-resistant shallow land burial (SLB) concept, could be suitable for disposal of most of the CRNL wastes. It is proposed that a prototype SLB facility be designed, constructed and operated on the CRNL property and filled by 1992 to provide a focus for disposal research and development programs and to accumulate experience in all aspects of waste management. 53 refs

Beneficial role of conflict in radioactive waste management programs

International Nuclear Information System (INIS)

Payne, B.A.; Williams, R.G.

1985-01-01

Of the technical, political, and social problems associated with radioactive waste management, least is known about the latter two. Lay persons tend to generalize negative attitudes about other nuclear activity to radioactive waste management. Thus, conflict appears inevitable between the general public, citizen action groups, and decision-makers on radioactive waste management. The basis of conflict, we believe, can be found in the value orientation of certain groups and in differing perceptions of risk. Research on similar controversial issues reveals that conflict may be beneficial in the long run by contributing to the public's participation level and understanding of the issues, and to the decision-makers' appreciation of the lay perspective. The paper is in three parts. First, we review the sources of conflict over radioactive waste management issues. The negative attitudes and fears of the public toward different types of projects involving radioactivity, value conflicts, and differential perceptions of risk are cited as sources. Next we discuss the consequences of conflict in terms of sociological theory. Finally, we discuss how conflict can be directed and managed to produce an informed decision-making process. When the public is sensitized to an issue, when prevailing attitudes on the issue are negative, and when perceived risks are high - all of which are characteristic of waste management issues - specific steps should be taken to establish a legitimate process of communication and interaction between the public and the sponsor agency. When conflict is recognized as inevitable, the goal of a communications program is no longer to avoid it. It is to use the increased awareness to increase knowledge about waste management issues and public participation in decisions so that the final solution is acceptable at some level to all parties

The development of the American national standard, ''control of radioactive surface contamination on materials, equipment and facilities to be released for uncontrolled use''

International Nuclear Information System (INIS)

Shapiro, J.

1980-01-01

The American National Standard, Control of Radioactive Surface Contamination on Materials, Equipment and Facilities to be Released for Uncontrolled Use, was developed under the procedures of ANSI for ANSI Main Committee N13 (Radiation Protection) by a working group of the Health Physics Society Standards Committee. This standard provides criteria for the control of materials, equipment and facilities contaminated with radioactivity proposed to be released for uncontrolled use. Permissible contamination limits are specified as well as methods assessing the levels of contamination. This paper reviews the proceedings of the Subcommittee on Radioactive Surface Contamination, the comments received by reviewers of the standard, the resolution of the committee, and the bases for reaching the final limits, recommendations, and measurement procedures. (H.K.)

BASIC Program for the calculation of radioactive activities

International Nuclear Information System (INIS)

Cortes P, A.; Tejera R, A.; Becerril V, A.

1990-04-01

When one makes a measure of radioactive activity with a detection system that operates with a gamma radiation detector (Ge or of NaI (Tl) detector), it is necessary to take in account parameters and correction factors that making sufficiently difficult and tedious those calculations to using a considerable time by part of the person that carries out these measures. Also, this frequently, can to take to erroneous results. In this work a computer program in BASIC language that solves this problem is presented. (Author)

1994 DOE Technical Standards Program Workshop: Proceedings

International Nuclear Information System (INIS)

Spellman, D.J.

1994-01-01

The DOE Technical Standards Program has been structured to provide guidance and assistance for the development, adoption, and use of voluntary standards within the Department. OMB Circular A-119, ''Federal Participation in the Development and Use of Voluntary Standards'' establishes the policy to be followed in working with voluntary standards bodies, and in adopting and using voluntary standards whenever feasible. The DOE Technical Standards Program is consistent with this policy and is dedicated to the task of promoting its implementation. The theme of this year's workshop is ''Standards Initiatives in Environmental Management fostering the development and use of industry standards for safe, environmentally responsible operations.'' The objective of the workshop is to increase the participant's awareness of the standardization activities taking place nationally and internationally and the impact of these activities on their efforts, and to facilitate the exchange of experiences, processes, and tools for implementing the program. Workshop sessions will include presentations by industry and Government notables in the environment, safety, and health arena with ample opportunity for everyone to ask questions and share experiences. There will be a breakout session which will concentrate on resolution of issues arising from the implementation of the DOE Technical Standards Program and a plenary session to discuss the plans developed by the breakout groups. Many organizations provide services and products which support the development, processing, distribution, and retrieval of standards. Those organizations listed at the end of the agenda will have exhibits available for your perusal throughout the workshop. Last year's workshop was very successful in stimulating an understanding of an interest in the standards program. This year, we hope to build on that success and provide an environment for the synergism of ideas to enhance the program and advance its implementation

Nuclear Data Verification and Standardization

Energy Technology Data Exchange (ETDEWEB)

Karam, Lisa R.; Arif, Muhammad; Thompson, Alan K.

2011-10-01

The objective of this interagency program is to provide accurate neutron interaction verification and standardization data for the U.S. Department of Energy Division of Nuclear Physics programs which include astrophysics, radioactive beam studies, and heavy-ion reactions. The measurements made in this program are also useful to other programs that indirectly use the unique properties of the neutron for diagnostic and analytical purposes. These include homeland security, personnel health and safety, nuclear waste disposal, treaty verification, national defense, and nuclear based energy production. The work includes the verification of reference standard cross sections and related neutron data employing the unique facilities and capabilities at NIST and other laboratories as required; leadership and participation in international intercomparisons and collaborations; and the preservation of standard reference deposits. An essential element of the program is critical evaluation of neutron interaction data standards including international coordinations. Data testing of critical data for important applications is included. The program is jointly supported by the Department of Energy and the National Institute of Standards and Technology.

Status of the IAEA safety standards programme

International Nuclear Information System (INIS)

2002-01-01

This presentation describes the status of the IAEA safety standards program to May 2002. The safety standards program overcome whole main nuclear implementations as General safety, Nuclear safety, Radiation safety, Radioactive waste safety, and Transport safety. Throughout this report the first column provides the list of published IAEA Safety Standards. The second gives the working identification number (DS) of standards being developed or revised. The bold type indicates standard issued under the authority the Board of Governors, others are issued under authority of the Director General. The last column provides the list of Committees, the first Committee listed has the lead in the preparation and review of the particular standard

Evaluation of alternatives for high-level and transuranic radioactive- waste disposal standards

International Nuclear Information System (INIS)

Klett, R.D.; Gruebel, M.M.

1992-12-01

The remand of the US Environmental Protection Agency's long-term performance standards for radioactive-waste disposal provides an opportunity to suggest modifications that would make the regulation more defensible and remove inconsistencies yet retain the basic structure of the original rule. Proposed modifications are in three specific areas: release and dose limits, probabilistic containment requirements, and transuranic-waste disposal criteria. Examination of the modifications includes discussion of the alternatives, demonstration of methods of development and implementation, comparison of the characteristics, attributes, and deficiencies of possible options within each area, and analysis of the implications for performance assessments. An additional consideration is the impact on the entire regulation when developing or modifying the individual components of the radiological standards

14 CFR 151.99 - Modifications of programming standards.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Modifications of programming standards. 151... (CONTINUED) AIRPORTS FEDERAL AID TO AIRPORTS Project Programming Standards § 151.99 Modifications of programming standards. The Director, Airports, Service, or the Regional Director concerned may, on individual...

Directory of certificates of compliance for radioactive materials packages. Volume 3, Revision 14: Report of NRC approved quality assurance programs for radioactive materials packages

International Nuclear Information System (INIS)

1994-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

The regulatory control of radioactive sources in Argentina

International Nuclear Information System (INIS)

Rojkind, Roberto Hector

1997-01-01

Argentina has been conducting nuclear activities for more than forty years, and as early as in 1956 established a Regulatory Authority. Procedures for compliance monitoring and enforcement have been in use in the regulatory control of radioactive sources, and regulatory standards and regulations had been set in Argentina, before the accident in Goiania. The conclusions drawn from that accident encouraged in Argentina the improvement of some regulatory procedures and helped to enhance the quality of the regulatory process. Therefore, the effectiveness of the control of spent radioactive sources has gradually increased, and enforcement actions to prevent radioactive sources ending up in the public domain improved. Some lessons learned in Argentina from the accident in Goiania and the main characteristics of an effective enforcement program helpful to prevent radiological accidents in industrial, medical, research and teaching uses of radioactive sources are presented. (author)

Development of a low cost, GPS-based upgrade to a standard handheld gamma detector for mapping environmental radioactive contamination

International Nuclear Information System (INIS)

Paridaens, J.

2006-01-01

A low cost extension to a standard handheld radiation monitor was developed, allowing one to perform outdoor georeferenced gamma measurements. It consists of a commercial wireless Bluetooth[reg] GPS receiver, a commercial RS-232 to Bluetooth[reg] converter combined with a standard Bluetooth[reg] enabled pocket personal computer (PPC). The system is intended for use in difficult to access areas, typically for foot campaigns. As the operator walks, a straightforward homemade visual basic program alternately reads GPS position and gamma dose rate into the PPC, creating a data log. This allows a single operator on foot to map between 50 and 200 ha of environmental radiation per day in very rugged areas, depending on the accessibility of the terrain and the detail required. On a test field with known contamination, a spatial precision of about 5-10 m was obtainable. The device was also used to reveal complex contamination patterns in the flooding zones of a radioactively contaminated small river

Development of a low cost, GPS-based upgrade to a standard handheld gamma detector for mapping environmental radioactive contamination.

Science.gov (United States)

Paridaens, J

2006-02-01

A low cost extension to a standard handheld radiation monitor was developed, allowing one to perform outdoor georeferenced gamma measurements. It consists of a commercial wireless Bluetooth GPS receiver, a commercial RS-232 to Bluetooth converter combined with a standard Bluetooth enabled pocket personal computer (PPC). The system is intended for use in difficult to access areas, typically for foot campaigns. As the operator walks, a straightforward homemade visual basic program alternately reads GPS position and gamma dose rate into the PPC, creating a data log. This allows a single operator on foot to map between 50 and 200 ha of environmental radiation per day in very rugged areas, depending on the accessibility of the terrain and the detail required. On a test field with known contamination, a spatial precision of about 5-10 m was obtainable. The device was also used to reveal complex contamination patterns in the flooding zones of a radioactively contaminated small river.

Development of a low cost, GPS-based upgrade to a standard handheld gamma detector for mapping environmental radioactive contamination

Energy Technology Data Exchange (ETDEWEB)

Paridaens, J. [Belgian Nuclear Research Centre, SCK.CEN, Boeretang 200, B2400 Mol (Belgium)]. E-mail: jparidae@sckcen.be

2006-02-15

A low cost extension to a standard handheld radiation monitor was developed, allowing one to perform outdoor georeferenced gamma measurements. It consists of a commercial wireless Bluetooth[reg] GPS receiver, a commercial RS-232 to Bluetooth[reg] converter combined with a standard Bluetooth[reg] enabled pocket personal computer (PPC). The system is intended for use in difficult to access areas, typically for foot campaigns. As the operator walks, a straightforward homemade visual basic program alternately reads GPS position and gamma dose rate into the PPC, creating a data log. This allows a single operator on foot to map between 50 and 200 ha of environmental radiation per day in very rugged areas, depending on the accessibility of the terrain and the detail required. On a test field with known contamination, a spatial precision of about 5-10 m was obtainable. The device was also used to reveal complex contamination patterns in the flooding zones of a radioactively contaminated small river.

Developing a public involvement policy for the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

Smith, S.; Summerson, J.; Gleason, M.E.; Reyes, P.C.

1994-01-01

The Civilian Radioactive Waste Management Program is entering its second decade. Given the Department of Energy's current efforts toward openness and culture change, the role of stakeholders is likely to evolve throughout the 1990s to enable greater participation by these external parties in making program decisions. Although the program has a tradition of inviting its stakeholders to review and comment on its activities, it also is known for employing on occasion what has been derisively called a open-quotes decide-announce-defendclose quotes strategy. Program efforts to involve the public have come under considerable criticism for being inadequate, inconsistent, lacking in follow-through, and offered on a sporadic and selective basis. The program is vulnerable to these criticisms because ground rules for public involvement have never been firmly established as part of the program's routine operations. This deficiency has contributed, in part, to stakeholder doubts about the program's sincerity in engaging in a meaningful dialogue with them. The program and its stakeholders both could benefit from an official public involvement policy that would serve as a guidepost for interactions between program officials and stakeholders. Such a policy, developed in concert with stakeholders, would ensure that all parties understand how stakeholder participation is to occur. This paper reviews (1) events establishing the need for a formal public involvement policy; (2) public involvement initiatives that will inform the process of developing a new policy; (3) current efforts to develop a Department of Energy public involvement policy; and (4) key elements for inclusion in a public involvement policy developed specifically for the Civilian Radioactive Waste Management Program

Standards for maintenance documentation of COSMOS programs

International Nuclear Information System (INIS)

Burstall, R.F.; Rickets, T.M.; Butland, A.T.D.

1982-06-01

The Compatible Open Shop Modular Operating Scheme (COSMOS) is used for fast reactor neutronics and subassembly distortion calculations in the UK. It provides database and databank facilities for this purpose. A large number of applications programs use these facilities. This report sets down the standards agreed for use in the preparation of maintenance documents for these programs. These standards have been developed as the result of experience with earlier more complicated standards. Some of the terminology used in this report is particular to COSMOS, but the general features of the standard may be useful to those responsible for other computer programs. (author)

National Syrian Program for Radioactive Waste Management

International Nuclear Information System (INIS)

Othman, I.; Takriti, S.

2009-06-01

A national plan for radioactive waste management has been presented. It includes identifying, transport, recording, classifying, processing and disposal. It is an important reference for radioactive waste management for those dealing with radioactive waste, and presents a complete protection to environemnt and people. (author)

Low-level waste (LLW) reclamation program for the Point Lepreau Solid Radioactive Waste Management Facility (SRWMF)

International Nuclear Information System (INIS)

Mersereau, M.; McIntyre, K.

2006-01-01

Low level radioactive waste retrieved from intermediate storage vaults at Point Lepreau Generating Station has been sorted to remove the non-radioactive portion. The program began with trials to validate procedures and equipment, followed by a production run that is on-going. Waste boxes are opened and sorted at a ventilated sorting table. The sorted waste is directed to the station's free-release ('Likely Clean') waste stream or to the radioactive waste stream, depending on activity measurements. The radioactive waste content of the sorted materials has been reduced by 96% (by mass) using this process. (author)

Low-level waste (LLW) reclamation program for the Point Lepreau Solid Radioactive Waste Management Facility (SRWMF)

Energy Technology Data Exchange (ETDEWEB)

Mersereau, M.; McIntyre, K. [Point Lepreau Generating Station, Lepreau, New Brunswick (Canada)]. E-mail: MMersereau@nbpower.com; KMcIntyre@nbpower.com

2006-07-01

Low level radioactive waste retrieved from intermediate storage vaults at Point Lepreau Generating Station has been sorted to remove the non-radioactive portion. The program began with trials to validate procedures and equipment, followed by a production run that is on-going. Waste boxes are opened and sorted at a ventilated sorting table. The sorted waste is directed to the station's free-release ('Likely Clean') waste stream or to the radioactive waste stream, depending on activity measurements. The radioactive waste content of the sorted materials has been reduced by 96% (by mass) using this process. (author)

Optimization of radioactive waste management system by application of multiobjective linear programming

International Nuclear Information System (INIS)

Shimizu, Yoshiaki

1981-01-01

A mathematical procedure is proposed to make a radioactive waste management plan comprehensively. Since such planning is relevant to some different goals in management, decision making has to be formulated as a multiobjective optimization problem. A mathematical programming method was introduced to make a decision through an interactive manner which enables us to assess the preference of decision maker step by step among the conflicting objectives. The reference system taken as an example is the radioactive waste management system at the Research Reactor Institute of Kyoto University (KUR). Its linear model was built based on the experience in the actual management at KUR. The best-compromise model was then formulated as a multiobjective linear programming by the aid of the computational analysis through a conventional optimization. It was shown from the numerical results that the proposed approach could provide some useful informations to make an actual management plan. (author)

Quality assurance program description for shipping packages of radioactive material

International Nuclear Information System (INIS)

1978-01-01

This quality assurance plan describes the quality assurance program at the Pacific Northwest Laboratory (PNL), for shipping packages of radioactive material. The purpose of this report is to describe how PNL will comply with the Code of Federal Regulations, Title 10, Part 71, Appendix E. In compliance with the instructions from the Nuclear Regulatory Commission (NRC), the 18 criteria from Appendix E are covered

The health physics programs in low-level radioactive waste management at the Institute of Nuclear Energy Research, Republic of China

International Nuclear Information System (INIS)

Chen, W-L.

1986-01-01

The primary mission of the health physics programs in low-level radioactive management is to ensure radiation safety for personnel and environment of the Institute of Nuclear Energy Research (INER), and also for the general public surrounding INER. In view of the above, the Health Physics programs in low-level radioactive waste management are divided into three sub-programs: the radiation control program, the environmental survey and bioassay program, and the radiation dosimetry supporting program. The general guidelines, responsibilities, and performance of these programs will be discussed in this paper in the following order. The responsibility of radiation control group is to conduct area monitoring and radiation surveillance for the radioactive waste treatment workers. It includes the control of radiation field level of the working area, servicing personnel dosimeters, instruction on radiation safety, and handling of radiation accidents. The responsibility of the environmental survey and bioassay group is to perform environmental surveys and bioassays. Environmental gamma monitoring stations were installed both on-site and off-site at INER. For bioassays, urine samples are taken from radioactive waste treatment workers, and for internal contamination checks of workers, total body counting systems are being used. The main responsibility of the radiation dosimetry group is to provide radiation dosimetrical support to the radiation control group and the environmental survey and bioassay group. Some typical work of the radiation dosimetry group is the qualitative assay and quantitative determination of radioactive samples, and calibration of dosimeters and survey meters

Low-level radioactive waste research program plan

International Nuclear Information System (INIS)

O'Donnell, E.; Lambert, J.

1989-11-01

The Waste Management Branch, Division of Engineering, Office of Nuclear Regulatory Research, has developed a strategy for conducting research on issues of concern to the US Nuclear Regulatory Commission (NRC) in its efforts to ensure safe disposal of low-level radioactive waste (LLW). The resulting LLW research program plan provides an integrated framework for planning the LLW research program to ensure that the program and its products are responsive and timely for use in NRC's LLW regulatory program. The plan discusses technical and scientific issues and uncertainties associated with the disposal of LLW, presents programmatic goals and objectives for resolving them, establishes a long-term strategy for conducting the confirmatory and investigative research needed to meet these goals and objectives, and includes schedules and milestones for completing the research. Areas identified for investigation include waste form and other material concerns, failure mechanisms and radionuclide releases, engineered barrier performance, site characterization and monitoring, and performance assessment. The plan proposes projects that (1) analyze and test actual LLW and solidified LLW under laboratory and field conditions to determine leach rates and radionuclide releases, (2) examine the short- and long-term performance of concrete-enhanced LLW burial structures and high-integrity containers, and (3) attempt to predict water movement and contaminant transport through low permeability saturated media and unsaturated porous media. 4 figs., 3 tabs

Annual radioactive waste tank inspection program -- 1993

International Nuclear Information System (INIS)

McNatt, F.G. Sr.

1994-05-01

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1993 to evaluate these vessels, and evaluations based on data accrued by inspections made since the tanks were constructed, are the subject of this report. The 1993 inspection program revealed that the condition of the Savannah River Site waste tanks had not changed significantly from that reported in the previous annual report. No new leaksites were observed. No evidence of corrosion or materials degradation was observed in the waste tanks. However, degradation was observed on covers of the concrete encasements for the out-of-service transfer lines to Tanks 1 through 8

Comparison of selected DOE and non-DOE requirements, standards, and practices for Low-Level Radioactive Waste Disposal

International Nuclear Information System (INIS)

Cole, L.; Kudera, D.; Newberry, W.

1995-12-01

This document results from the Secretary of Energy's response to Defense Nuclear Facilities Safety Board Recommendation 94--2. The Secretary stated that the US Department of Energy (DOE) would ''address such issues as...the need for additional requirements, standards, and guidance on low-level radioactive waste management. '' The authors gathered information and compared DOE requirements and standards for the safety aspects Of low-level disposal with similar requirements and standards of non-DOE entities

Standards for School Guidance Programs in Maryland.

Science.gov (United States)

Maryland State Dept. of Education, Baltimore. Div. of Compensatory, Urban, and Supplementary Programs.

This brochure is a checklist to rate school compliance with the standards for school guidance programs in Maryland, which were developed by the Maryland State Department of Education. The first set of standards addresses the philosophy and goals of school guidance programs in Maryland and the extent to which program goals and objectives are…

Realization of sanitary requirements concerning standardization of rare radioactive gas effluents at NPPs

International Nuclear Information System (INIS)

Doroshenko, G.G.; Panchenko, S.V.; Chudajkin, O.G.

1987-01-01

The paper is aimed at determination of ways for practical realization of main sanitary requirements concerning environment and population protection under NPP operation. The idea of the requirements is reduced to not increasing permissible limits for radiation doses, minimum irradiation of population and decrease of unjustified irradiation of personnel. The given problem may be fully solved only in case of studying real chacteristics of operating reactors, taking into account statistic nature of effluents of inert radioactive gases (IRG). Methods of developing a system of working and reference standards of IRG effluents at NPPs are suggested. The considered approach may be realized in practice as the All-Union state on branch standards

IAEA coordinated research program on the evaluation of solidified high-level radioactive waste products

International Nuclear Information System (INIS)

Grover, J.R.; Schneider, K.J.

1979-01-01

A coordinated research program on the evaluation of solidified high-level radioactive waste products has been active with the IAEA since 1976. The program's objectives are to integrate research and to provide a data bank on an international basis in this subject area. Results and considerations to date are presented

Radioactive contamination of environment

International Nuclear Information System (INIS)

Chytil, I.

1981-01-01

A computer model is discussed describing radioactivity transport between the source and the organism. The model is to be applied in assessing the effect of a nuclear installation on the organism. Fortran and Pascal appear to be the most appropriate computer languages. With respect to internal memory requirements, the program file is estimated to consist of a control program and a number of subprograms. Upon setting the radioactivity transport and the output requirements the control program should recall the necessary subprograms. The program file should allow the complete data file and the solutions of all possible radioactivity transport variants to be inputted. It is envisaged that several subprograms will be available for one type of radioactivity transport, this depending on different accuracy of the transport description. Thus, the requirements for input data will also differ. (Z.M.)

The preparation of radioactive sources with radioactivities of less than 110 kilobecquerels

International Nuclear Information System (INIS)

Wyllie, H.A.

1989-03-01

A description is given of the various radioactive sources prepared in the ANSTO Radioisotope Standards Laboratory and the procedures associated with their preparation. ANSTO is authorised by CSIRO to maintain the Commonwealth standard of activity of radionuclides. Counting sources are required for the standardisation of solutions of radionuclides. Calibration sources are required for equipment used to detect radioactivity, such as gamma-ray spectrometers, and can be supplied to clients in other organisations. The maximum radioactivity supplied is 110 kBq. 7 refs., 65 figs

Ratio of thyroid radioiodine uptake calculated via the physic decay rate of the standard radioactive source: a preliminary study

International Nuclear Information System (INIS)

Zeng Yu; Zhou Luyi

2010-01-01

Objectives: To compare the difference of the ratio of thyroid radioiodine ( 131 I) uptake calculated by actually measuring counts of the standard radioactive source(method 1) and by computing counts of the standard radioactive source via physic half life of 131 I (method 2). Methods: Two hundred and nine consecutive patients with Graves' Disease were prospectively recruited. The ratio of thyroid 131 I uptake was calculated by two methods at 4 h and 24 h after administration of 1.48 MBq 131 I, respectively. Paired t-test was used to compare the difference between the two methods. Results: The ratio of thyroid 131 I uptake at 4h was (32±16)% and ( 35±10)% (t=1.98, P=0.20), at 24h (72±19)% and (69±24)% ( t=1.49, P=0.23), respectively, by the two methods. Conclusion: To calculate the ratio of thyroid 131 I uptake via the physic half life of the standard radioactive resource is feasible, and can both reduce the risk of ionizing radiation to technical staff and act as verifying method for quality control of thyroid function equipment. (authors)

An integrated approach to strategic planning in the civilian high-level radioactive waste management program

International Nuclear Information System (INIS)

Sprecher, W.M.; Katz, J.; Redmond, R.J.

1992-01-01

This paper describes the approach that the Office of Civilian Radioactive Waste Management (OCRWM) of the Department of Energy (DOE) is taking to the task of strategic planning for the civilian high-level radioactive waste management program. It highlights selected planning products and activities that have emerged over the past year. It demonstrates that this approach is an integrated one, both in the sense of being systematic on the program level but also as a component of DOE strategic planning efforts. Lastly, it indicates that OCRWM strategic planning takes place in a dynamic environment and consequently is a process that is still evolving in response to the demands placed upon it

Program planning for future improvement in managing ORNL's radioactive wastes

International Nuclear Information System (INIS)

1982-01-01

This report is intended to serve as a reference document and guide in developing the long-term improvements section of ORNL's radioactive waste management plan. The report reviews ORNL's operations and future program needs in terms of currently applicable DOE regulations and also in terms of regulations and accepted practices of the commerical sector of the nuclear power industry so that the impact of potential future adoption of these regulations and standards on ORNL's operations can be fully evaluated. The principal conclusion reached after reviewing ORNL's waste management operations is that these operations are currently being conducted in a manner that does not endanger the health or safety of workers or the general public and that does not have an adverse effect on the environment. Although nineteen specific problem areas have been identified all of these problems can be attributed to one of the following: a) the legacy of past practices; b) gradual deterioration of systems which have reached (or are near to reaching) the end of their reasonable design lives; and c) potential changes in regulations applicable to ORNL. All of the programs designed to improve or correct these problem areas could be accomplished within a four year period. However, given current limitations on manpower and capital, these programs would more likely be spread out over a five to ten year period of time if they were all to be undertaken. The cost of undertaking all of these projects concurrently is estimated to be between 60 and 100 million dollars. Due to the many unknowns and uncertainties associated with the problem areas, actual total costs for specific projects could vary from those presented in this report by as much as 300 percent

The fourth radioactive waste management program of the Commission of the European Communities (1990-1994)

International Nuclear Information System (INIS)

Orlowski, S.; Schaller, K.H.; Simon, R.

1992-01-01

The fourth radioactive waste management program 1990-1994 is aimed at perfecting and demonstrating a system of management of radioactive waste, including unprocessed irradiated fuels where these are considered as waste, which will ensure, at the various stages, the best possible protection of man and the environment. In particular, research continues on the characterization and qualification of the various barriers, both engineered and natural (geological) considered in the multiple barrier disposal concept, and the findings are used to evaluate the long-term safety of this waste disposal concept. The program is implemented mainly through shared-cost research contracts with appropriate organizations, undertakings and companies - public or private - established in the European Community Member States. It is composed of two parts; Part A deals with waste management studies and associated research and development actions, whereas in Part B, the construction and operation of underground pilot and/or site validation facilities for deep geological disposal of radioactive waste open to Community joint activities are covered. (author)

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

International Nuclear Information System (INIS)

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

1992-05-01

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

Scintillation detector with anticoincidence shield for determination of the radioactive concentration of standard solutions

International Nuclear Information System (INIS)

Broda, R.; Radoszewski, T.

1982-01-01

The construction and parameters of the prototype liquid scintillation detector for disintegration rate determination of standard solutions is described. The detector is equipped with a liquid scintillation anticoincidence shield with a volume of 40 l. The instrument is placed in the building of the Radioisotope Production and Distribution Centre in the Institute of Nuclear Research at Swierk. The results of instrument background reduction are described. The counting efficiency of several beta-emitters 3 H, 63 Ni, 14 C and 90 Sr + 90 Y is given, as well as the examples of a disintegration rate determination of low radioactivity concentration of standard solutions. (author)

Site Study Plan for background environmental radioactivity, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

International Nuclear Information System (INIS)

1987-06-01

The Background Environmental Radioactivity Site Study Plan describes a field program consisting of an initial radiological survey and a radiological sampling program. The field program includes measurement of direct radiation and collection and analysis of background radioactivity samples of air, precipitation, soil, water, milk, pasture grass, food crops, meat, poultry, game, and eggs. The plan describes for each study: the need for the study, the study design, data management and use, schedule of proposed activities, and quality assurance requirements. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Project (SRP) Requirements Document. 50 refs., 11 figs., 7 tabs

Radioactive waste management - an educational challenge

International Nuclear Information System (INIS)

Tulenko, J.S.

1991-01-01

University Radioactive Waste Management educational programs are being actively advanced by the educational support activities of the Offices of Civilian Radioactive Waste Management (OCRWM) and Environmental Restoration and Waste Management (ERWM) of the DOE. The DOE fellowship program formats of funding students and requiring a practical research experience (practicum) at a DOE site has helped to combine the academic process with a practical work experience. Support for faculty in these programs is augmenting the benefits of the fellowship programs. The many job opportunities and funding sources for students which currently exists in the radioactive waste management area are fueling an increase in academic programs seeking recognition of their radioactive waste management curriculums

1996 DOE technical standards program workshop: Proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

The workshop theme is `The Strategic Standardization Initiative - A Technology Exchange and Global Competitiveness Challenge for DOE.` The workshop goal is to inform the DOE technical standards community of strategic standardization activities taking place in the Department, other Government agencies, standards developing organizations, and industry. Individuals working on technical standards will be challenged to improve cooperation and communications with the involved organizations in response to the initiative. Workshop sessions include presentations by representatives from various Government agencies that focus on coordination among and participation of Government personnel in the voluntary standards process; reports by standards organizations, industry, and DOE representatives on current technology exchange programs; and how the road ahead appears for `information superhighway` standardization. Another session highlights successful standardization case studies selected from several sites across the DOE complex. The workshop concludes with a panel discussion on the goals and objectives of the DOE Technical Standards Program as envisioned by senior DOE management. The annual workshop on technical standards has proven to be an effective medium for communicating information related to standards throughout the DOE community. Technical standards are used to transfer technology and standardize work processes to produce consistent, acceptable results. They provide a practical solution to the Department`s challenge to protect the environment and the health and safety of the public and workers during all facility operations. Through standards, the technologies of industries and governments worldwide are available to DOE. The DOE Technical Standards Program, a Department-wide effort that crosscuts all organizations and disciplines, links the Department to those technologies.

Radioactive waste management policy for nuclear power

International Nuclear Information System (INIS)

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

1998-01-01

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

The regulatory control of radioactive sources in Argentina

Energy Technology Data Exchange (ETDEWEB)

Rojkind, Roberto Hector [Autoridade Regulatoria Nuclear, Buenos Aires (Argentina)

1997-12-31

Argentina has been conducting nuclear activities for more than forty years, and as early as in 1956 established a Regulatory Authority. Procedures for compliance monitoring and enforcement have been in use in the regulatory control of radioactive sources, and regulatory standards and regulations had been set in Argentina, before the accident in Goiania. The conclusions drawn from that accident encouraged in Argentina the improvement of some regulatory procedures and helped to enhance the quality of the regulatory process. Therefore, the effectiveness of the control of spent radioactive sources has gradually increased, and enforcement actions to prevent radioactive sources ending up in the public domain improved. Some lessons learned in Argentina from the accident in Goiania and the main characteristics of an effective enforcement program helpful to prevent radiological accidents in industrial, medical, research and teaching uses of radioactive sources are presented. (author) 9 refs; e-mail: rrojkind at sede.arn.gov.br

Measurement of activity of radioactive gas

International Nuclear Information System (INIS)

Zhuo Renhong; Lei Jiarong; Wen Dezhi; Cheng Jing; Zheng Hui

2005-10-01

A set of standard instrument system with their accessories for the measurement of activity of radioactive gas have been developed. The specifications and performances of the system have been tested and examined. The conventional true values of activity of radioactive gas have been measured and its uncertainty has been assessed. The technique of the dissemination of the measurement of activity of radioactive gas has been researched. The specification and performance of the whole set of apparatus meet the requirements of the relational standard, critra, regulation, it can be regard as a work standard for the measurement of activity of radioactive gas in CAEP. (authors)

Long term industrial management of radioactive wastes in France

International Nuclear Information System (INIS)

Lavie, J.

1981-01-01

All human activities including energy generation entail the wastes. This definitely applies also to nuclear power generation. Currently the nuclear power program is very extensive, and the plans of fuel reprocessing proceed along this line. In consequence, the Government has decided on tackling the problem of industrial radioactive waste management in earnest. For the purpose, the National Radioactive Waste Management Agency (ANDRA) was created in November, 1979, within the French Atomic Energy Commission (CEA). Its main functions are the design, siting and construction of waste disposal centers and their management, the establishment of waste treatment and disposal standards, and the research and development. The following matters are described: the need for comprehensive industrial approach, the concept of industrial management, ANDRA business program, the industrial policy on waste disposal, and ANDRA financing. (J.P.N.)

Reactive Programming in Standard ML

OpenAIRE

Pucella, Riccardo

2004-01-01

Reactive systems are systems that maintain an ongoing interaction with their environment, activated by receiving input events from the environment and producing output events in response. Modern programming languages designed to program such systems use a paradigm based on the notions of instants and activations. We describe a library for Standard ML that provides basic primitives for programming reactive systems. The library is a low-level system upon which more sophisticated reactive behavi...

Radioactive material packaging performance testing

International Nuclear Information System (INIS)

Romano, T.; Cruse, J.M.

1991-02-01

To provide uniform packaging of hazardous materials on an international level, the United Nations has developed packaging recommendations that have been implemented worldwide. The United Nations packaging recommendations are performance oriented, allowing for a wide variety of package materials and systems. As a result of this international standard, efforts in the United States are being directed toward use of performance-oriented packaging and elimination of specification (designed) packaging. This presentation will focus on trends, design evaluation, and performance testing of radioactive material packaging. The impacts of US Department of Transportation Dockets HM-181 and HM-169A on specification and low-specific activity radioactive material packaging requirements are briefly discussed. The US Department of Energy's program for evaluating radioactive material packings per US Department of Transportation Specification 7A Type A requirements, is used as the basis for discussing low-activity packaging performance test requirements. High-activity package testing requirements are presented with examples of testing performed at the Hanford Site that is operated by Westinghouse Hanford Company for the US Department of Energy. 5 refs., 2 tabs

Office of Civilian Radioactive Waste Management ensuring quality assurance in the waste management program

International Nuclear Information System (INIS)

Kehew, W.J.; Barrett, L.H.

1991-01-01

This paper focuses on the Quality Assurance (QA) program of the U.S. Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). It describes the objectives and philosophy of quality assurance and the plans and activities that OCRWM is undertaking to implement a fully qualified QA program prior to beginning new site characterization activities in Nevada. This paper outlines OCRWM's plan to implement and use a well-designed and effective QA program throughout all elements of the program. (author) 1 fig., 5 refs

Relationship between internal medicine program board examination pass rates, accreditation standards, and program size.

Science.gov (United States)

Falcone, John L; Gonzalo, Jed D

2014-01-19

To determine Internal Medicine residency program compliance with the Accreditation Council for Graduate Medical Education 80% pass-rate standard and the correlation between residency program size and performance on the American Board of Internal Medicine Certifying Examination. Using a cross-sectional study design from 2010-2012 American Board of Internal Medicine Certifying Examination data of all Internal Medicine residency pro-grams, comparisons were made between program pass rates to the Accreditation Council for Graduate Medical Education pass-rate standard. To assess the correlation between program size and performance, a Spearman's rho was calculated. To evaluate program size and its relationship to the pass-rate standard, receiver operative characteristic curves were calculated. Of 372 Internal Medicine residency programs, 276 programs (74%) achieved a pass rate of =80%, surpassing the Accreditation Council for Graduate Medical Education minimum standard. A weak correlation was found between residency program size and pass rate for the three-year period (p=0.19, pInternal Medicine residency programs complied with Accreditation Council for Graduate Medical Education pass-rate standards, a quarter of the programs failed to meet this requirement. Program size is positively but weakly associated with American Board of Internal Medicine Certifying Examination performance, suggesting other unidentified variables significantly contribute to program performance.

Directory of certificates of compliance for radioactive materials packages: Summary report of NRC approved quality assurance programs for radioactive material packages

International Nuclear Information System (INIS)

1987-11-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1987. This directory makes available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Actions of radiation protection in the collection of discarded radioactive material

International Nuclear Information System (INIS)

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

2017-01-01

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

Radioactivity in consumer products

Energy Technology Data Exchange (ETDEWEB)

Moghissi, A.A.; Paras, P.; Carter, M.W.; Barker, R.F. (eds.)

1978-08-01

Papers presented at the conference dealt with regulations and standards; general and biological risks; radioluminous materials; mining, agricultural, and construction materials containing radioactivity; and various products containing radioactive sources.

Levels of concern for radioactive contaminations in soil according to soil protection standards

International Nuclear Information System (INIS)

Gellermann, R.; Barkowski, D.; Machtolf, M.

2016-01-01

In the paper the question is examined whether the established soil protection standards for carcinogenic substances are also applicable to the assessment of radioactive soil contamination. Referring to the methods applied in soil protection for evaluation of dose-effectrelations and estimations of carcinogenic risks as well as the calculation methods for test values in soil protection ''levels of concern'' for soil contamination by artificial radionuclides are derived. The values obtained are significantly larger than the values for unrestricted clearance of ground according to the German Radiation Protection Ordinance (StrlSchV). The thesis that soil is protected according to environmental standards provided that radiation protection requirements are met needs further checks but can be probably confirmed if the radiation protection requirements are clearly defined.

The analysis of the program to develop the Nuclear Waste Management System: Allocated requirements for the Office of Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

Woods, T.W.

1991-09-01

This report is volume 3, part B, of the program to satisfy the allocated requirements of the Office of Civilian Radioactive Waste Management Program, in the development of the nuclear waste management system. The report is divided into the following sections: regulatory compliance; external relations; international programs; strategic and contingency planning; contract business management; and administrative services. (CS)

Construction and equipment requirements for installations and laboratories handling unsealed radioactive materials in low and medium activity - Proposal of an Israeli standard

Energy Technology Data Exchange (ETDEWEB)

Ben-Shlomo, A; Schlesinger, T; Barshad, M [Soreq Nuclear Research Center, Yavne (Israel)

1993-10-01

Working with unsealed radioactive materials involves risks of internal or external exposure to ionizing radiation. Exposure of human beings to ionizing radiation involves adverse health effects and must be prevented or at least reduced to reasonable levels. Radiation sources in this work are unsealed radioactive materials, that may be solids, liquid or in gaseous states, and in varying toxic levels. Various works and actions that are performed on the unsealed radioactive materials have varying potentials of dispersion, contamination and exposure, so that the combination of the type of work activity, isotope characteristics and physical state dictate the internal and external exposure risks. In order to limit the exposure of the personnel of installations and laboratories which deals with unsealed radioactive materials, national and international authorities and organizations standards and procedures for the requirements of construction and equipment of such installations and laboratories. This document means to be a proposal for an Israeli standard requirements for equipment and construction of installations working with low and medium activity unsealed radioactive materials. The targets for defining the, construction and equipment, requirements are: a. Safety and proper protection of personnel and public from external and internal exposure while the work is done properly. Proper protection against the risk of contaminating the environment. c. Standardization of requirements. d. Proper design of installations and laboratories. e. Supply means for evaluation and reduction of construction costs.The equipment detailed here refers to fixed (none movable) equipment which is a part of the construction of the laboratory or installation, unless specified otherwise. The document starts with a review of the recommendations of some international organizations (WHO, IAEA, NRPB) for construction and equipment requirements for these laboratories and installations. Then the

A linear program for assessing the assignment and scheduling of radioactive wastes for disposal to sea

International Nuclear Information System (INIS)

Hutchinson, W.

1983-04-01

The report takes the form of a user guide to a computer program using linear programming techniques to aid the assignment and scheduling of radioactive wastes for disposal to sea. The program is aimed at the identification of 'optimum' amounts of each waste stream for disposal to sea without violating specific constraints values and/or fairness parameters. (author)

Strengthening the safety and security of radioactive sources worldwide: a perspective on Philippine contributions

International Nuclear Information System (INIS)

Murray, Allan

2009-01-01

Radioactive sources have been used for many decades in a wide variety of applications in all countries. The safety of radioactive sources and the associated radiation protection have been implemented by national and international programs during this time with cooperation through the IAEA intended to achieve application of minimum standards and harmonization of approach. The security of radioactive sources is however relatively new consideration. A perspective on the Philippine contributions to the safety and security of radioactive sources will be provided with reference to the following: What is radioactive source security and why it is important?; International cooperation, including the IAEA Code of Conduct; Regulation for radioactive source security; Implementation of radioactive source security measures for licenses, operators and others; Impact of regulatory and operational matters such as professional development and training, emergency preparedness and response, and radiation protection. (author)

Radioactive waste management

International Nuclear Information System (INIS)

Kawakami, Yutaka

2008-01-01

Radioactive waste generated from utilization of radioisotopes and each step of the nuclear fuel cycle and decommissioning of nuclear facilities are presented. On the safe management of radioactive waste management, international safety standards are established such as ''The Principles of Radioactive Waste Management (IAEA)'' and T he Joint Convention on the Safety of Radioactive Waste Management . Basic steps of radioactive waste management consist of treatment, conditioning and disposal. Disposal is the final step of radioactive waste management and its safety is confirmed by safety assessment in the licensing process. Safety assessment means evaluation of radiation dose rate caused by radioactive materials contained in disposed radioactive waste. The results of the safety assessment are compared with dose limits. The key issues of radioactive waste disposal are establishment of long term national strategies and regulations for safe management of radioactive waste, siting of repository, continuity of management activities and financial bases for long term, and security of human resources. (Author)

Radiation-protection standards and waste management

International Nuclear Information System (INIS)

Rowe, W.D.

1976-01-01

This paper reviews some of the difficult questions to be addressed in the development of fundamental environmental criteria and standards for radioactive waste management. A short discussion is included of the need to develop more precise definitions of terminology, better conceptualization of long-term problems, and new concepts to express risks from waste management and to evaluate the ability of proposed technical alternatives to control such risks. EPA's plans to develop fundamental environmental criteria and generally applicable environmental radiation-protection standards for waste disposal are summarized. Finally, the principal projects in EPA's planned near-future programs are reviewed in the areas of high-level waste, transuranic solid waste, low-level waste, residual decommissioning waste, ocean disposal, and wastes containing natural radioactivity

A study of science leadership and science standards in exemplary standards-based science programs

Science.gov (United States)

Carpenter, Wendy Renae

The purpose for conducting this qualitative study was to explore best practices of exemplary standards-based science programs and instructional leadership practices in a charter high school and in a traditional high school. The focus of this study included how twelve participants aligned practices to National Science Education Standards to describe their science programs and science instructional practices. This study used a multi-site case study qualitative design. Data were obtained through a review of literature, interviews, observations, review of educational documents, and researcher's notes collected in a field log. The methodology used was a multi-site case study because of the potential, through cross analysis, for providing greater explanation of the findings in the study (Merriam, 1988). This study discovered six characteristics about the two high school's science programs that enhance the literature found in the National Science Education Standards; (a) Culture of expectations for learning-In exemplary science programs teachers are familiar with a wide range of curricula. They have the ability to examine critically and select activities to use with their students to promote the understanding of science; (b) Culture of varied experiences-In exemplary science programs students are provided different paths to learning, which help students, take in information and make sense of concepts and skills that are set forth by the standards; (c) Culture of continuous feedback-In exemplary science programs teachers and students work together to engage students in ongoing assessments of their work and that of others as prescribed in the standards; (d) Culture of Observations-In exemplary science programs students, teachers, and principals reflect on classroom instructional practices; teachers receive ongoing evaluations about their teaching and apply feedback towards improving practices as outlined in the standards; (e) Culture of continuous learning-In exemplary

Overview of EPA's environmental standards for the land disposal of LLW and NARM waste - 1988

International Nuclear Information System (INIS)

Gruhlke, J.M.; Galpin, F.L.; Holcomb, W.F.

1988-01-01

The Environmental Protection Agency program to develop proposed generally applicable environmental standards for land disposal of low-level radioactive waste (LLW) and certain naturally occurring and accelerator-produced radioactive wastes has been completed. The elements of the proposed standards include the following: (a) exposure limits for predisposal management and storage operations, (b) criteria for other regulatory agencies to follow in specifying wastes that are below regulatory concern; (c) postdisposal exposure limits, (d) groundwater protection requirements, and (e) qualitative implementation requirements. In addition to covering those radioactive wastes subject to the Atomic Energy Act, the Agency also intends to propose a standard to require the disposal of high concentration, naturally occurring and accelerator-produced radioactive materials wastes exceeding 2 nCi/g, excluding a few consumer items, in regulated LLW disposal facilities

A programmatic response to the Secretary of Energy's review of the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

Benson, A.B.

1994-01-01

On January 19, 1993, in response to a question during her confirmation hearing, Secretary of Energy Hazel R. O'Leary stated that she believed that a comprehensive review of nuclear waste disposal programs and policies was needed. Her preferred approach to such a review would be to engage in a consensus-seeking effort in which all involved parties would be brought to the table to deal with contentious issues. This paper describes both the process and the separate elements of the review of the civilian radioactive waste management program conducted in 1993 and 1994 by Secretary O'Leary. The paper will trace the review beginning with the Secretary's statement at her confirmation hearing, through her interim guidance redirecting certain aspects of the program. It describes some initiatives and changes that are already underway as a result of this review. Throughout the year, stakeholders expressed their concerns, opinions, and recommendations regarding the program. These communications reflected the diversity of perspective that has become a hallmark of the radioactive waste program

Control System Radioactive Contamination in Food Samples in Poland

International Nuclear Information System (INIS)

Grabowski, D.; Kurowski, W.; Muszynski, W.; Rubel, B.; Smagala, G.; Swietochowska, J.

2001-01-01

Full text: The analyses of the level of radioactive contamination in food samples are carried out by the Service for Measurements of Radioactive Contamination (SMRC) in Poland. The Service was brought into existence in 1961. The Service comprises of a network of measurement stations and the Centre of Radioactive Contamination Measurements (CRCM). The duty of the Centre is being executed by the Central Laboratory for Radiological Protection (CLRP). The uniform methods of sampling are used in measurement stations. All important foodstuff: milk, meat, vegetables, fruit, cereals are controlled in the Service stations. The radiochemical and spectrometric methods are used to determine the activity of radioactive isotopes. The standard equipment of the measurement station is the measurement system type SAPOS-90 and multichannel analyser with scintillation or germanium detector. The structure of the Service, kinds of samples tested by each station, program of sampling in normal and during accident situation are presented in this paper. (author)

Inadequate control of world's radioactive sources

International Nuclear Information System (INIS)

2002-01-01

The radioactive materials needed to build a 'dirty bomb' can be found in almost any country in the world, and more than 100 countries may have inadequate control and monitoring programs necessary to prevent or even detect the theft of these materials. The IAEA points out that while radioactive sources number in the millions, only a small percentage have enough strength to cause serious radiological harm. It is these powerful sources that need to be focused on as a priority. In a significant recent development, the IAEA, working in collaboration with the United States Department of Energy (DOE) and the Russian Federation's Ministry for Atomic Energy (MINATOM), have established a tripartite working group on 'Securing and Managing Radioactive Sources'. Through its program to help countries improve their national infrastructures for radiation safety and security, the IAEA has found that more than 100 countries may have no minimum infrastructure in place to properly control radiation sources. However, many IAEA Member States - in Africa, Asia, Latin America, and Europe - are making progress through an IAEA project to strengthen their capabilities to control and regulate radioactive sources. The IAEA is also concerned about the over 50 countries that are not IAEA Member States (there are 134), as they do not benefit from IAEA assistance and are likely to have no regulatory infrastructure. The IAEA has been active in lending its expertise to search out and secure orphaned sources in several countries. More than 70 States have joined with the IAEA to collect and share information on trafficking incidents and other unauthorized movements of radioactive sources and other radioactive materials. The IAEA and its Member States are working hard to raise levels of radiation safety and security, especially focusing on countries known to have urgent needs. The IAEA has taken the leading role in the United Nations system in establishing standards of safety, the most significant of

U Y 105 standard use of non sealed radioactive sources in nuclear medicine: approve for Industry energy and Mining Ministry 28/6/2002 Resolution

International Nuclear Information System (INIS)

2002-01-01

Establish minimal requirements radiological safety for use non sealed radioactive sources in nuclear medicine.The present standard is used in operation or nuclear medicine practices using non sealed radioactive sources with diagnostic and therapeutic purposes in vivo and in vitro

Development of knowledge building program concerning about high-level radioactive waste disposal

International Nuclear Information System (INIS)

Kimura, Hiroshi; Yamada, Kazuhiro; Takase, Hiroyasu

2005-01-01

Acquirement of knowledge about the high-level radioactive waste (HLW) disposal is one of the important factors for public to determine the social acceptance of HLW disposal. However in Japan, public do not have knowledge about HLW and its disposal sufficiently. In this work, we developed the knowledge building program concerning about HLW disposal based on Nonaka, and Takeuchi's SECI spiral model in knowledge management, and carried to the experiment on this program. In the results, we found that the participants' knowledge about the HLW disposal increased and changed from misunderstanding' or 'assuming' to 'facts' or 'consideration' through this experimental program. These results said that the experimental program leads participants to have higher quality of knowledge about the HLW disposal. In consequence, this knowledge building program may be effective in the acquirement of high quality knowledge. (author)

Application of simulated standard spectra in natural radioactivity measurements using gamma spectrometry

International Nuclear Information System (INIS)

Narayani, K.; Pant, A.D.; Bhosle, Nitin; Anilkumar, S.; Singh, Rajvir; Pradeepkumar, K.S.

2014-01-01

Gamma ray spectrometry is one of the well known analytical techniques for environmental radioactivity measurements. Gamma spectrometer based on NaI(Tl) scintillation detectors is very popular since it offers high efficiency, low cost and case in handling. The poor energy resolution of the NaI(TI) detector is the major disadvantage making tile analysis of complex gamma ray spectra difficult. Least square method or the full spectrum analysis method is widely used for the analysis of complex spectra from scintillation detectors. The main requirement of this method is that the individual standard spectra of all nuclides expected in the complex spectrum in the same measurement geometry must be available. It is not always possible and feasible to have all the standards of nuclides in the desired geometry. A methodology based on the use of simulated standard spectra generated by Monte Carlo technique was proposed for analysis of complex spectra of nuclides. In the present work, for the analysis of 238 U, 233 Th and 40 K in soil samples, the same methodology was applied by using the simulated standard spectra in soil matrix. The details of the simulation method and results analysis of 238 U, 232 Th and 40 K in environmental samples are discussed in this paper

The design, fabrication and maintenance of semi-trailers employed in the highway transport of weight-concentrated radioactive loads

Energy Technology Data Exchange (ETDEWEB)

Huffman, D.S. [Allied-Signal Inc., Metropolis, IL (United States)

1991-12-31

Transportation of weight-concentrated radioactive loads by truck is an essential part of a safe and economical nuclear industry. This proposed standard presents guidance and performance criteria for the safe transport of these weight-concentrated radioactive loads. ANSI N14.30 will detail specific requirements for the design, fabrication, testing, in-service inspections, maintenance and certification of the semi-trailers to be employed in said service. Furthermore, guidelines for a quality assurance program are also enumerated. This standard would apply to any semi-trailer that may or may not be specifically designed to carry weight-concentrated loads. Equipment not suitable per the criteria established in the standard would be removed from service. The nature of the nuclear industry and the need for a positive public perception of the various processes and players, mandates that the highway transportation of weight-concentrated radioactive loads be standardized and made inherently safe. This proposed standard takes a giant step in that direction.

The health physics program at the National Bureau of Standards LINAC

International Nuclear Information System (INIS)

Hobbs, T.G.

1981-01-01

A three-person Accelerator Health Physics team provides continuous radiation safety service for the National Bureau of Standards 150-MeV linear electron accelerator (Linac), which operates on a five days per week, 24 hours per day schedule, with one day per month downtime scheduled for maintenance. This team also serves the synchrotron ultraviolet light radiation facility (SURF), two Van de Graaffs, some other electrostatic accelerators, and several high-energy x-ray generators. Although the Linac is not licensed by a safety-regulating agency, as is the NBS Research Reactor, Health Physics makes no distinction between the two sources in providing coverage. Various regulations do impact on operations, e.g., the NRC dose totals and effluent releases and the OSHA requirements. Film, thermoluminescent dosimeters (TLD), and direct-reading pocket dosimeters are used for personnel dosimetry. The usual array of portable and fixed radiation survey meters and activation devices and some of the high-energy multi-particle activation techniques are used for area monitoring. Environmental surveillance is performed with TLD's, tissue-equivalent ion chamber, and a grass and soil assay program. Integrated Health Physics programs for all the NBS radiation facilities do instrument calibrations, training for Health Physics and operating staffs, administrative control of radioactive materials, waste management, and data compilations

A new large-volume metal reference standard for radioactive waste management.

Science.gov (United States)

Tzika, F; Hult, M; Stroh, H; Marissens, G; Arnold, D; Burda, O; Kovář, P; Suran, J; Listkowska, A; Tyminski, Z

2016-03-01

A new large-volume metal reference standard has been developed. The intended use is for calibration of free-release radioactivity measurement systems and is made up of cast iron tubes placed inside a box of the size of a Euro-pallet (80 × 120 cm). The tubes contain certified activity concentrations of (60)Co (0.290 ± 0.006 Bq g(-1)) and (110m)Ag (3.05 ± 0.09 Bq g(-1)) (reference date: 30 September 2013). They were produced using centrifugal casting from a smelt into which (60)Co was first added and then one piece of neutron irradiated silver wire was progressively diluted. The iron castings were machined to the desirable dimensions. The final material consists of 12 iron tubes of 20 cm outer diameter, 17.6 cm inner diameter, 40 cm length/height and 245.9 kg total mass. This paper describes the reference standard and the process of determining the reference activity values. © The Author 2015. Published by Oxford University Press.

Radioactivity and the French uranium bearing minerals

International Nuclear Information System (INIS)

Guiollard, P.Ch.; Boisson, J.M.; Leydet, J.C.; Meisser, N.

1998-01-01

This special issue of Regne Mineral journal is entirely devoted to the French uranium mining industry. It comprises 4 parts dealing with: the uranium mining industry in France (history, uranium rush, deposits, geologic setting, prosperity and recession, situation in 1998, ore processing); radioactivity and the uranium and its descendants (discovery, first French uranium bearing ores, discovery of radioactivity, radium and other uranium descendants, radium mines, uranium mines, atoms, elements and isotopes, uranium genesis, uranium decay, isotopes in an uranium ore, spontaneous fission, selective migration of radionuclides, radon in mines and houses, radioactivity units, radioprotection standards, new standards and controversies, natural and artificial radioactivity, hazards linked with the handling and collecting of uranium ores, conformability with radioprotection standards, radioactivity of natural uranium minerals); the French uranium bearing minerals (composition, crystal structure, reference, etymology, fluorescence). (J.S.)

The radioactive waste management program of The Commission of the European Communities: Past, present, and future trends

International Nuclear Information System (INIS)

Orlowski, S.M.

1983-01-01

The radioactive waste management program started in the mid-1970s is being carried out by the Commission of European Communities (CEC) Joint Research Centre and by research bodies within the European community under CEC coordination and partial financing. The program deals with the management of the radioactive waste resulting from uranium-plutonium fuel cycle. During its first phase (1973-1979), various treatment and conditioning processes were investigated; high temperature incineration and acid digestion of alpha-bearing waste, immobilization of highly active waste in borosilicate glasses, inter alia, appeared promising. Geological disposal was recognized as a feasible option; transmutation of long-lived products did not appear to be an advantageous alternative to geological disposal, and the studies were discontinued. The second phase (1980-1984) of the program is a followup to the first. The needs of the European nuclear industry and of the national radioactive waste agencies or operators recently created are, however, taken into account. The continuity of the RandD effort is ensured by a ''Community plan of action on waste management,'' (1980-1992). A third phase, 1984-1989, should demonstrate the availability and validity of the waste management techniques and be convincing about their safety

Forecasting of the radioactive material transport demand for the Brazilian Nuclear Program and the security aspects

International Nuclear Information System (INIS)

Meldonian, Nelson Leon

1979-01-01

In the nuclear fuel cycle, a lot of radioactive materials are produced. These radioactive materials must be transported in order to promote the integration of the fuel cycle units. Considerations about the transport characteristics of radioactive material were made for each section of the fuel cycle. These considerations were based on the experience of several countries and in accordance with the International Atomic Energy Agency regulations. A prediction of transport demands for the Brazilian Nuclear Program until year 2.010 was made. The prediction refers mainly to the quantity of radioactive material produced in each section of the cycle the quantity of vehicles needed for the transport of these materials. Several safety aspects were considered specially, the accidents predictions for years 2.000 and 2.010. The accident probability in Brazilian railroads and highways was compared with that of the USA. (author)

Special Education Compliance: Program Review Standards and Indicators.

Science.gov (United States)

Missouri State Dept. of Elementary and Secondary Education, Jefferson City. Div. of Special Education.

This manual contains special education standards and indicators for educating children with disabilities in Missouri. It is divided into four main sections. Section 1 contains special education compliance standards based upon the federal Office of Special Education Programs Continuous Improvement Monitoring Program clusters and indicators. The…

Conservation Law Enforcement Program Standardization

National Research Council Canada - National Science Library

Rogers, Stan

2004-01-01

The ultimate goal of standardization is to develop a safe and effective program that is recognized within the USAF, DoD, and by other Federal and state law enforcement agencies, and the general public...

An overview of U.S. plant performance improvement through effective radioactive waste management

International Nuclear Information System (INIS)

Sieberling, R.; Lyons, P.W.

1986-01-01

Radioactive waste volumes in the United States commercial nuclear power industry have declined over the last five years after increasing steadily in the late 1970's. This decline is considered to be especially significant because major backfits/modifications and major component repair/replacement at U.S. nuclear power stations have been accomplished during this period. This paper analyzes the key reasons for this performance and outlines the positive effects that this trend has upon overall nuclear plant performance. In reviewing plant performance data, there appears to be a direct correlation between overall plant performance and radioactive waste performance. For example, plants with high capacity factors, strong industrial safety programs, low collective man-rem, and good contamination controls, generally have a history of low radioactive waste volumes. The reasons for this excellent performance is the result of direct management and supervisory involvement in plant operations, implementation of high standards of performance, and monitoring performance against these standards. Using the techniques outlined in this paper, the U.S. nuclear power industry can continue to reduce the volume of low-level solid radioactive waste being generated

UNIDOSE - a computer program for the calculation of individual and collective doses from airborne radioactive pollutants

International Nuclear Information System (INIS)

Karlberg, O.; Schwartz, H.; Forssen, B.-H.; Marklund, J.-E.

1979-01-01

UNIDOSE is a program system for calculating the consequences of a radioactive release to the atmosphere. The program is applicable for computation of dispersion in a rnage of 0 - 50 km from the release point. The Gaussion plume model is used for calculating the external dose from activity in the atmosphere, on the ground and the internal dose via inhalation. Radioactive decay, as well as growth and decay of daughter products are accounted for. The influence of dry deposition and wash-out are also considered. It is possible to treat time-dependent release-rates of 1 - 24 hours duration and constant release-rates for up to one year. The program system also contains routines for the calculation of collective dose and health effects. The system operates in a statistical manner. Many weather-situations, based on measured data, can be analysed and statistical properties, such as cumulative frequences, can be calculated. (author)

Program of environmental radiological surveillance of the radioactive wastes storage center of Maquixco in the period January-December 1991

International Nuclear Information System (INIS)

Gaso P, M.I.

1991-12-01

The primary objective of all program of environmental radiological surveillance (PVRA), it is to follow the evolution of the radioactive content of the links of the chains that constitute the different ways of transfer of the radioactivity toward the man, with the purpose of making a realistic evaluation of the environmental impact produced by the installation under surveillance. In the CADER in Mexico, only accidents or escapes of radioactivity of slow evolution can be detected. At the moment the radioactive wastes in this installation are not treated. In this report the results obtained during the year 1991 are presented. (Author)

The issue resolution process in the Civilian Radioactive Waste Transportation Program

International Nuclear Information System (INIS)

Holm, J.A.; Denny, S.

1987-01-01

The Civilian Radioactive Waste Management (OCRWM) Program consists of various technical and institutional program activities which engender concern from the general public and from policymakers at federal, state, and local levels. Most familiar are the concerns centered around selection of a site for a repository; however, the transportation portion of the OCRWM program also engenders similar concerns for safety, efficiency and effectiveness. The major Transportation institutional issues were detailed in the Institutional Plan, issued in 1986, and include topics such as liability, defense waste, routing, emergency response, risk identification and mitigation, cash integrity, inspection and enforcement of high-level waste shipments and use of overweight trucks as part of the modal mix. This paper will define the process being used to identify and resolve institutional issues, show how the technical and institutional issues interface and are addressed, and briefly describe four specific activities which illustrate the process of resolving institutional issues in the Transportation program

Determination of detailed standards for transportation of radioactive materials by ships

International Nuclear Information System (INIS)

1978-01-01

These provisions are established on the basis of the ''Regulations on the transport and storage of dangerous things by ships''. The terms used hereinafter are according to those used in the Regulations. Radioactive materials, etc., include uranium 233, uranium 235, plutonium 238, plutonium 239, plutonium 241, the compounds of such materials and the substances containing one or two and more of such materials, excluding such materials of not more than 15 grams. The permissible surface density of radioactive materials is 1/100,000 of one microcurie per cm 2 for the radioactive materials emitting alpha-ray and 1/10,000 of one microcurie per cm 2 for the radioactive materials not emitting alpha-ray. For the radioactive materials which can be transported as L type cargo, their quantity of radioactivity is defined in their solid, liquid and gaseous forms. The limit of quantity of such cargo is described in detail in the lists attached. Transporting conditions of A, BM and BU type cargos are specified respectively in the particular sections. (Okada, K.)

A perspective on demonstrating compliance with standards for disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Smith, E.D.; O'Kelley, G.D.; Sjoreen, A.L.

1985-01-01

A perspective which the authors have developed on the problem of demonstrating that geologic repositories for the disposal of high-level radioactive wastes will comply with system performance standards is discussed. Their viewpoint arises from a concern that the U.S. Environmental Protection Agency's proposed environmental standard for high-level waste disposal appears to require demonstrations of compliance which are incompatible with scientific knowledge; i.e., the standard does not take into account the likely importance of unquantifiable and unresolvable uncertainty in repository performance-assessment models. A general approach to demonstrations of compliance is proposed which is thought to be compatible with the kinds of technical information that will be available for judging long-term repository performance. The authors' approach emphasizes the importance of investigating alternative conceptual models and lines of reasoning in evaluating repository performance and the importance of subjective scientific judgment in the decision-making process. (Auth.)

Evaluation of Radioactivity in Dusty Storm

International Nuclear Information System (INIS)

Mohammed, A.S; Majeed, N. A.; Nasaer, M.H.; Hoshi, H.; Abood, M.

2013-01-01

sample had been collected from the powder of the dusty storms which had been moved over Baghdad for a different months of a year 2011 by using metal containers that had manufactured locally and had been mounted over the roof of houses in particular regions of Baghdad (Kerkh and Risafa).The radioactive concentration of dust samples had been measured and analyzed by using the Gamma Spectroscopy analyzing System which consist of high purity Germanium detector of efficiency of 40 %, resolution 2keV at 1.332 MeV (Co-60) , DSA 2000 system which protective barrier made in Canberra Company , the developed Genie 2000Program and using personal computer. The measurement system for energy calibration and efficiency had been calibrated by using a standard point sources and standard source of a multi energy made by the American Canberra company. The Marnelli geometrical shape had been used to measure the activity of the samples. Results indicated the existence of the natural radioactive isotopes such as K-40, Be-7 which has been composed of as a result of the nuclear reaction between the Cosmic ray and some other elements of the atmosphere like Oxygen and Nitrogen besides the existence of radioactive isotopes which belongs to the natural Uranium series and the natural Thorium series. Highest measurements indicated the existence of industrial radioactive isotope Cs-137.The highest value of concentration for Be-7 was (381.5 Bq/kg) at Al-Shaab region, and the highest value of concentration for K-40 was (467.7 Bq/kg) and some other radioactive isotopes which belong to the series of U-238 as follows:- Bi -214 (32.6 Bq/kg), Pb-214 (33.6 Bq/kg), and radioactive isotopes which belong to the series Th-232 as follows:- Bi-212(18.6Bq/kg), Pb-212 (18.8Bq/kg),Ac-228 (30.3 Bq/kg),the highest value of concentration for the industrial Cs-137 was (26,8 Bq/kg) it was at Al-shaab region ,and this concentration is relatively high in comparison to the levels of normal concentration which exist in

Development of a low-level radioactive waste shipper model. National Low-Level Radioactive Waste Management Program

International Nuclear Information System (INIS)

1983-03-01

During 1982, Inter/Face Associates, Inc., conducted a low-level radioactive waste management survey of Nuclear Regulatory Commission (NRC) licensees in Massachusetts for the US Department of Energy's National Low-Level Waste Management Program. In the process of conducting the survey, a model was developed, based on existing NRC license classification systems, that would identify licensees who ship low-level waste for disposal. This report presents the model and documents the procedures used in developing and testing it. After the model was tested, several modifications were developed with the goal of determining the model's ability to identify waste shippers under different parameters. The report includes a discussion of the modifications

C.E.C. program on radioactive waste management disposal and risk assessment

International Nuclear Information System (INIS)

Orlowski, S.; Girardi, F.; Bresesti, M.

1976-01-01

The Commission of the European Communities (CEC) has been involved many years with the radioactive waste problem; but a major effort started in 1973 when a specific program was given to the Commission's own laboratories (C.E.C. Joint Research Center, Ispra Establishment). This effort is very much enlarged since June 1975, when the Commission was authorized to start a coordinated program with the national laboratories of the nine member states, financed on a 50/50 basis. The contribution of the Commission for the 1975-79 plan amounts to $19 million. The overall program now involves several laboratories and does represent a significant European effort to contribute to solving a world scale problem; it is intended to promote a large international cooperation

DOE [Department of Energy]-Nuclear Energy Standards Program annual assessment, FY 1990

International Nuclear Information System (INIS)

Williams, D.L. Jr.

1990-11-01

To meet the objectives of the programs funded by the Department of Energy (DOE)-Nuclear Energy (NE) Technology Support Programs, the Performance Assurance Project Office (PAPO) administers a nuclear standards program and related activities and fosters the development and application of standards. This standards program is carried out in accordance with the principles in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980. The purposes of this effort, as set forth in three subtasks, are to (1) manage the NE Standards Program, (2) manage the development and maintenance of NE standards, and (3) operate an NE Standards Information Program. This report assesses the Performance Assurance Project Office (PAPO) activities in terms of the objectives of the Department of Energy-Nuclear Energy (DOE-NE) funded programs. To meet these objectives, PAPO administers a nuclear standards program and related activities and fosters the development and application of standards. This task is carried out in accordance with the principles set forth in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980, and DOE memorandum, Implementation of DOE Orders on Quality Assurance, Standards, and Unusual Occurrence Reporting for Nuclear Energy Programs, March 3, 1982, and with guidance from the DOE-NE Technology Support Programs. 1 tab. (JF)

NIST commitment to national MQA programs

Energy Technology Data Exchange (ETDEWEB)

Caswell, R.S. [National Institute of Standards and Technology, Gaithersburg, MD (United States)

1993-12-31

The program of the Ionizing Radiation Division, Physics Laboratory is discussed, especially relating to standards, calibrations, and measurement quality assurance (MQA). The NIST program is {open_quotes}vertically integrated,{close_quotes} meaning that activities extend from fundamental research to measurement research to supplying services and data. Typical methods NIST uses to assure the quality of the national standards are presented. Some of the programs in x-ray, gamma-ray, electron, neutron, and radioactivity research which support MQA are presented. Examples are given of MQA activities.

NIST commitment to national MQA programs

International Nuclear Information System (INIS)

Caswell, R.S.

1993-01-01

The program of the Ionizing Radiation Division, Physics Laboratory is discussed, especially relating to standards, calibrations, and measurement quality assurance (MQA). The NIST program is open-quotes vertically integrated,close quotes meaning that activities extend from fundamental research to measurement research to supplying services and data. Typical methods NIST uses to assure the quality of the national standards are presented. Some of the programs in x-ray, gamma-ray, electron, neutron, and radioactivity research which support MQA are presented. Examples are given of MQA activities

The IAEA Promotes the Application of Safety Standards and Best Practices for the Management of Radioactive Waste

International Nuclear Information System (INIS)

2014-01-01

The IAEA works to promote a high level of safety as it facilitates peaceful uses of nuclear energy worldwide. The IAEA’s Statute authorizes it to establish or adopt standards of safety for protection of health and minimization of danger to life and property, and to provide for the application of these standards. The Statute also mandates the IAEA to foster the exchange of scientific and technical information to facilitate the peaceful uses of atomic energy. To this end, the IAEA develops safety standards on different topics, including on the safety of radioactive waste management. These standards, issued in the IAEA Safety Standards Series, reflect an international consensus on what constitutes a high level of safety for protecting people from harmful effects of ionizing radiation and protecting the environment

International directory of certified radioactive sources

Energy Technology Data Exchange (ETDEWEB)

Grosse, G; Bambynek, W

1983-01-01

This directory lists the products of 16 suppliers of certified reference materials (CRM) of radioactivity as given in their catalogues. Included are only products for which certificates are delivered and whose uncertainties are given according to the rules defined in ICRU Report No. 12, ''Certification of Standardized Radioactive Sources'' (International Commission on Radiation and Measurements, Washington, 1968). Only those products are included of which the standard uncertainties according to the above rules are less than 10%. Prices of the products are not mentioned since they frequently change. The products are divided into four groups: Radioactive Solutions, Radioactive Gases, Solid Sources and Sources for Liquid Scintillation Counting).

International directory of certified radioactive sources

International Nuclear Information System (INIS)

Grosse, G.; Bambynek, W.

1983-01-01

This directory lists the products of 16 suppliers of certified reference materials (CRM) of radioactivity as given in their catalogues. Included are only products for which certificates are delivered and whose uncertainties are given according to the rules defined in ICRU Report No. 12, ''Certification of Standardized Radioactive Sources'' (International Commission on Radiation and Measurements, Washington, 1968). Only those products are included of which the standard uncertainties according to the above rules are less than 10%. Prices of the products are not mentioned since they frequently change. The products are divided into four groups: Radioactive Solutions, Radioactive Gases, Solid Sources and Sources for Liquid Scintillation Counting). (orig./WL)

Environmental radioactivity in Canada 1986

International Nuclear Information System (INIS)

1987-01-01

The radiological surveillance program of the Department of National Health and Welfare is conducted for the purpose of determining levels of environmental radioactivity in Canada and assessing the resulting population exposures. During 1986 the program was strongly influenced by radioactive fallout on Canada resulting from the Chernobyl nuclear reactor accident on April 26, 1986 in the Soviet Ukraine. The Environmental Radiation Hazards Division (ERHD) increased its frequency of analyses of environmental samples immediately following the accident. Interim screening limits for foodstuffs were developed. A measurement program for radioactivity in domestic and imported foods was implemented. The ERHD measurement program was supplemented by additional measurements conducted by many other private and government laboratories. Radiation doses to Canadian from Chernobyl fallout were extremely low with no group in the population receiving more than 10 microsieverts

DOE reassesses civilian radioactive waste management program

International Nuclear Information System (INIS)

Yates, M.

1990-01-01

This article reports on the announcement by the Department of Energy (DOE) that the opening of a high-level radioactive nuclear waste repository site will be delayed for seven years. The article discusses DOE's reassessment plan, the restructuring of the Office of Civilian Radioactive Waste Management, site access and evaluation, the Monitored Retrievable Storage Commission proposal, and the industry's response

Actions of a protocol for radioactive waste management

International Nuclear Information System (INIS)

Sousa, Joyce Caroline de Oliveira; Andrade, Idalmar Gomes da Silva; Frazão, Denys Wanderson Pereira; Abreu, Lukas Maxwell Oliveira de; França, Clyslane Alves; Macedo, Paulo de Tarso Silva de

2017-01-01

Radioactive wastes are all those materials generated in the various uses of radioactive materials, which can not be reused and which have radioactive substances in quantities that can not be treated as ordinary waste. All management of these wastes must be carried out carefully, including actions ranging from its collection to the point where they are generated to their final destination. However, any and all procedures must be carried out in order to comply with the requirements for the protection of workers, individuals, the public and the environment. The final product of the study was a descriptive tutorial on the procedures and actions of a standard radioactive waste management protocol developed from scientific publications on radiation protection. The management of radioactive waste is one of the essential procedures in the radiological protection of man and the environment where the manipulation of radioactive materials occurs. The standard radioactive management protocol includes: collection, segregation of various types of wastes, transport, characterization, treatment, storage and final disposal. The radioactive wastes typology interferes with sequencing and the way in which actions are developed. The standardization of mechanisms in the management of radioactive waste contributes to the radiological safety of all those involved

A computer program to calculate the committed dose equivalent after the inhalation of radioactivity

International Nuclear Information System (INIS)

Van der Woude, S.

1989-03-01

A growing number of people are, as part of their occupation, at risk of being exposed to radiation originating from sources inside their bodies. The quantification of this exposure is an important part of health physics. The International Commission on Radiological Protection (ICRP) developed a first-order kinetics compartmental model to determine the transport of radioactive material through the human body. The model and the parameters involved in its use, are discussed. A versatile computer program was developed to do the following after the in vivo measurement of either the organ- or whole-body activity: calculate the original amount of radioactive material which was inhaled (intake) by employing the ICRP compartmental model of the human body; compare this intake to calculated reference levels and state any action to be taken for the case under consideration; calculate the committed dose equivalent resulting from this intake. In the execution of the above-mentioned calculations, the computer program makes provision for different aerosol particle sizes and the effect of previous intakes. Model parameters can easily be changed to take the effects of, for instance, medical intervention into account. The computer program and the organization of the data in the input files are such that the computer program can be applied to any first-order kinetics compartmental model. The computer program can also conveniently be used for research on problems related to the application of the ICRP model. 18 refs., 25 figs., 5 tabs

DOE standard: The Department of Energy Laboratory Accreditation Program for radiobioassay

International Nuclear Information System (INIS)

1998-12-01

This technical standard describes the US Department of Energy Laboratory Accreditation Program (DOELAP) for Radiobioassay, for use by the US Department of Energy (DOE) and DOE Contractor radiobioassay programs. This standard is intended to be used in conjunction with the general administrative technical standard that describes the overall DOELAP accreditation process--DOE-STD-1111-98, Department of Energy Laboratory Accreditation Program Administration. This technical standard pertains to radiobioassay service laboratories that provide either direct or indirect (in vivo or in vitro) radiobioassay measurements in support of internal dosimetry programs at DOE facilities or for DOE and DOE contractors. Similar technical standards have been developed for other DOELAP dosimetry programs. This program consists of providing an accreditation to DOE radiobioassay programs based on successful completion of a performance-testing process and an on-site evaluation by technical experts. This standard describes the technical requirements and processes specific to the DOELAP Radiobioassay Accreditation Program as required by 10 CFR 835 and as specified generically in DOE-STD-1111-98

Intruder dose pathway analysis for the onsite disposal of radioactive wastes: the ONSITE/MAXI1 computer program

International Nuclear Information System (INIS)

Napier, B.A.; Peloquin, R.A.; Kennedy, W.E. Jr.; Neuder, S.M.

1984-10-01

Because of uncertainties associated with assessing the potential risks from onsite burials of radioactive waste, the US Nuclear Regulatory Commission (NRC) has amended its regulations to provide greater assurance that buried radioactive material will not present a hazard to public health and safety. The amended regulations now require licensees to apply for approval of proposed procedures for onsite disposal pursuant to 10 CFR 20.302. The NRC technically reviews these requests on a case-by-case basis. These technical reviews require modeling potential pathways to man and projecting radiation dose commitments. This document contains a summary of our efforts to develop human-intrusion scenarios and to modify a version of the MAXI computer program for potential use by the NRC in reviewing applications for onsite radioactive waste disposal. The documentation of the ONSITE/MAXI computer program is written for two audiences. The first (Audience A) includes persons concerned with the mathematical models and computer algorithms. The second (Audience B) includes persons concerned with exercising the computer program and scenarios for specific onsite disposal applications. Five sample problems are presented and discussed to assist the user in operating the computer program. Summaries of the input and output for the sample problems are included along with a discussion of the hand calculations performed to verify the correct operation of the computer program. Computer listings of the ONSITE/MAXI1 computer program with an abbreviated data base listing are included as Appendix 1 to this document. Finally, complete listings of the data base with listings of the special codes used to create the data base are included in Appendix 2 as a microfiche attachment to this document

Handbook of high-level radioactive waste transportation

International Nuclear Information System (INIS)

Sattler, L.R.

1992-10-01

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

Evaluating public involvement in the National Low-Level Radioactive Waste Management Program

International Nuclear Information System (INIS)

1982-09-01

The Department of Energy contracted with the Keystone Center to evaluate the effectiveness of the National Low-Level Radioactive Waste Management Program's public-involvement efforts. The Center chose six evaluators with diverse training and experience related to low-level waste management and public-participation programs. Keystone's evaluation was based on (a) observations by the evaluators who attended the National Program-sponsored strategy review meetings and fairs; (b) interviews with low-level waste generators, local government officials, state legislators, public-interest groups, and members of the general public; and (c) observations of the final National Program strategy task force meeting. The evaluators concluded that, overall, the public-participation processes yielded some very positive results - for policy development and for DOE and the EG and G staff. They judged the strategy document to be complete, concise, and helpful to public dialogue on low-level waste issues. They also made specific recommendations for improvements to the public-participation program

Standard Guide for Radiation Protection Program for Decommissioning Operations

CERN Document Server

American Society for Testing and Materials. Philadelphia

1987-01-01

1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations. 1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project. 1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan. 1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of...

Program planning for future improvement in managing ORNL's radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

1982-01-01

This report is intended to serve as a reference document and guide in developing the long-term improvements section of ORNL's radioactive waste management plan. The report reviews ORNL's operations and future program needs in terms of currently applicable DOE regulations and also in terms of regulations and accepted practices of the commerical sector of the nuclear power industry so that the impact of potential future adoption of these regulations and standards on ORNL's operations can be fully evaluated. The principal conclusion reached after reviewing ORNL's waste management operations is that these operations are currently being conducted in a manner that does not endanger the health or safety of workers or the general public and that does not have an adverse effect on the environment. Although nineteen specific problem areas have been identified all of these problems can be attributed to one of the following: a) the legacy of past practices; b) gradual deterioration of systems which have reached (or are near to reaching) the end of their reasonable design lives; and c) potential changes in regulations applicable to ORNL. All of the programs designed to improve or correct these problem areas could be accomplished within a four year period. However, given current limitations on manpower and capital, these programs would more likely be spread out over a five to ten year period of time if they were all to be undertaken. The cost of undertaking all of these projects concurrently is estimated to be between 60 and 100 million dollars. Due to the many unknowns and uncertainties associated with the problem areas, actual total costs for specific projects could vary from those presented in this report by as much as 300 percent. (DMC)

Quality assurance in nuclear medicine radioactivity measurements

International Nuclear Information System (INIS)

Sahagia, Maria; Razdolescu Anamaria Cristina

2007-01-01

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

Joint Assessment of Renewable Energy and Water Desalination Research Center (REWDC) Program Capabilities and Facilities In Radioactive Waste Management

International Nuclear Information System (INIS)

Bissani, M; Fischer, R; Kidd, S; Merrigan, J

2006-01-01

The primary goal of this visit was to perform a joint assessment of the Renewable Energy and Water Desalination Center's (REWDC) program in radioactive waste management. The visit represented the fourth technical and scientific interaction with Libya under the DOE/NNSA Sister Laboratory Arrangement. Specific topics addressed during the visit focused on Action Sheet P-05-5, ''Radioactive Waste Management''. The Team, comprised of Mo Bissani (Team Lead), Robert Fischer, Scott Kidd, and Jim Merrigan, consulted with REWDC management and staff. The team collected information, discussed particulars of the technical collaboration and toured the Tajura facility. The tour included the waste treatment facility, waste storage/disposal facility, research reactor facility, hot cells and analytical labs. The assessment team conducted the first phase of Task A for Action Sheet 5, which involved a joint assessment of the Radioactive Waste Management Program. The assessment included review of the facilities dedicated to the management of radioactive waste at the Tourja site, the waste management practices, proposed projects for the facility and potential impacts on waste generation and management

Penn State continuing education program on low-level radioactive waste disposal and management: lessons learned

International Nuclear Information System (INIS)

Vincenti, J.R.

1985-01-01

Since November of 1983, The Pennsylvania State University, Institute for Research on Land and Water Resources has provided the citizens of the Commonwealth of Pennsylvania with information on low-level radioactive waste disposal and management through a continuing education program called the PIER (Public Involvement and Education on Radiation) Program. This paper will review the form, function, and development of this continuing education program and some of the lessons learned in providing citizens of the Commonwealth with information in both formal and informal educational settings

SRS ES ampersand H standards compliance program management plan

International Nuclear Information System (INIS)

Hearn, W.H.

1993-01-01

On March 8, 1990, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 90-2 to the Secretary of Energy. This recommendation, based upon the DNFSB's initial review and evaluation of the content and implementation of standards relating to the design, construction, operations, and decommissioning of defense nuclear facilities of the Department of Energy (DOE), called for three actions: (1) identification of specific standards that apply to design, construction, operation and decommissioning of DOE facilities; (2) assessment of the adequacy of those standards for protecting public health and safety; and (3) determination of the extent to which they have and are being implemented. This document defines the elements of the SRS program required to support the HQ program in response to DNFSB Recommendation 90-2. The objective is to ensure a consistent approach for all sitewide ES and H Standards Compliance Program efforts that satisfied the intent of Recommendation 90-2 and the HQ 90-2 Implementation Plan in a cost-effective manner. The methodology and instructions for implementation of the SRS program are contained in the Standards Compliance Program Implementation Plan. The Management Plan shall be used in conjunction with the Implementation Plan

Subseabed radioactive waste disposal feasibility program: ocean engineering challenges for the 80's

International Nuclear Information System (INIS)

Talbert, D.M.

1980-11-01

The objective of the Subseabed Disposal Program is to assess the feasibility of disposing of high-level radioactive wastes or spent fuel in suitable geologic formations beneath the deep ocean floor. The program is entering a phase which will address engineering feasibility. While the current phase of the program to determine the scientific and environmental feasibility of the concept is not yet complete, activities to assess the engineering aspects are being initiated in parallel to facilitate the development of the concept on a time scale commensurate with related programs both in the United States and abroad. It is anticipated that engineering aspects will become the central focus of the program during the early 80's and will continue so through the establishment of a pilot-plant level activity which could occur by the mid-90's

Subseabed Radioactive Waste Disposal Feasibility Program: ocean engineering challenges for the 80's

International Nuclear Information System (INIS)

Talbert, D.M.

1980-01-01

The objective of the Subseabed Disposal Program is to assess the feasibility of disposing of high-level radioactive wastes or spent fuel in suitable geologic formations beneath the deep ocean floor. The program is entering a phase which will address engineering feasibility. While the current phase of the program to determine the scientific and environmental feasibility of the concept is not yet complete, activities to assess the engineering aspects are being initiated in parallel to facilitate the development of the concept on a time scale commensurate with other related programs both in the United States and abroad. It is anticipated that engineering aspects will become the central focus of the program during the early 80's and will continue so through the establishment of a pilot-plant level activity which could occur by the mid-90's

Determination of detailed standards for transportation of radioactive materials by ships

International Nuclear Information System (INIS)

1979-01-01

The notification is defined under the regulations concerning marine transport and storage of dangerous things. Radioactive materials include hereunder uranium 233 and 235, plutonium 238, 239 and 241, their compounds and those materials which contain one or more than two of such materials. Materials whose quantities or quantities of components are less than 15 grams, and natural or depleted uranium are excluded. Permissible surface concentrations are 1/100,000 micro-curie per centi-meter 2 for radioactive materials emitting alpha rays, and 1/10,000 micro-curie per centi-meter 2 for radioactive materials not emitting alpha rays. Radioactive materials to be transported as L loads shall be not dispersing solid substances or those tightly enclosed in capsules, one of whose exterior sides at least is more than 0.5 centi-meter, having other several specified features. Other kinds of liquid and gas L loads are stipulated. Limits of radioactivity of L and A loads are provided for with tables attached. Transport conditions of A, BM and BU loads are fixed with bylaws. Leakages of BM and BU loads are also prescribed. Radioactive loads shall be marked by particular signals. Measures shall be taken to control exposures, which involve measurement of doses and exposure doses on board and appointment of exposure controllers. (Okada, K.)

Regulation of naturally occurring radioactive materials (NORM) with emphasis on NORM disposal options

International Nuclear Information System (INIS)

Gray, P.

1995-01-01

Regulation of radioactive material can occur at the Federal, State, and sometimes local level. In addition to regulations at the federal and state level, there are guidelines and standards that do not carry the weight of law, yet are often referenced. Neither the Nuclear Regulatory Commission (NRC) or Environmental Protection Agency (EPA) categorically regulates NORM at this time. However, many of the existing regulations and guidelines for licensed radioactive material can be applied by states and other regulatory agencies to NORM. The primary regulations covering radioactive materials and exposures were promulgated under the Atomic Energy Act (AEA) or 1954, as amended. NRC licenses and regulates civilian use of nuclear materials to protect public health and safety and the environment. NRC makes rules and sets standards for licensees and inspects the activities of licensees to insure that they do not violate safety rules. OSHA regulations for worker protection from exposures to radioactivity are contained in 29CFR1910.96. These standards are designed to protect workers from exposure to radiation in programs other than those regulated by OSHA. The Uranium Mill Tailings Control Act, with implementing regulations found in 40CFR192 were promulgated by the EPA for cleanup of uranium mill tailings. These standards are often used by states and other agencies in regulating cleanup of NORM. EPA is currently considering regulation of NORM on NRC and DOE facilities under 40CFR195

Development of the Office of Civilian Radioactive Waste Management's Self-Assessment Program

International Nuclear Information System (INIS)

Vlahakis, J.G.; Palabrica, R.J.; Goldsmith, S.

1993-01-01

This paper describes the development and implementation of the Self-Assessment (SA) Program of the Office of Civilian Radioactive Waste Management (RW). The basis for RW's SA Program is discussed, as well as RW's approach for meeting self-assessment requirements, RW's organization for self-assessment, actions to establish RW's SA Program, and planned RW SA implementation activities. This paper also discusses how self-assessment can support programmatic decisions and actions. The RW Director has approved and issued the Self-Assessment Management Plan that describes how RW will organize and manage its SA program. He has directed Associate/Office Directors to prepare individual Implementation Plans to provide specifics on how their Offices will meet the requirements of the RW SA Program. To assist in the preparation of these Implementation Plans, the RW Self-Assessment Unit (SAU), which manages the SA Program on behalf of the RW Director, has conducted a series of SA Implementation Workshops. The SAU has also developed an Annotated Outline for SA Implementation Plans. Following issuance of Office-specific Implementation Plans, independent evaluations by the SAU are planned

A review of a radioactive material shipping container including design, testing, upgrading compliance program and shipping logistics

International Nuclear Information System (INIS)

Celovsky, A.; Lesco, R.; Gale, B.; Sypes, J.

2003-01-01

Ten years ago Atomic Energy of Canada developed a Type B(U)-85 shipping container for the global transport of highly radioactive materials. This paper reviews the development of the container, including a summary of the design requirements, a review of the selected materials and key design elements, and the results of the major qualification tests (drop testing, fire test, leak tightness testing, and shielding integrity tests). As a result of the testing, improvements to the structural, thermal and containment design were made. Such improvements, and reasons thereof, are noted. Also provided is a summary of the additional analysis work required to upgrade the package from a Type B(U) to a Type B(F), i.e. essentially upgrading the container to include fissile radioisotopes to the authorized radioactive contents list. Having a certified shipping container is only one aspect governing the global shipments of radioactive material. By necessity the shipment of radioactive material is a highly regulated environment. This paper also explores the experiences with other key aspects of radioactive shipments, including the service procedures used to maintain the container certification, the associated compliance program for radioactive material shipments, and the shipping logistics involved in the transport. (author)

UK program: glasses and ceramics for immobilization of radioactive wastes for disposal

International Nuclear Information System (INIS)

Johnson, K.D.B.

1979-01-01

The UK Research Program on Radioactive Waste Management includes the development of processes for the conversion of high-level-liquid-reprocessing wastes from thermal and fast reactors to borosilicate glasses. The properties of these glasses and their behavior under storage and disposal conditions have been examined. Methods for immobilizing activity from other wastes by conversion to glass or ceramic forms are described. The UK philosophy of final solutions to waste management and disposal is presented

Controlling radioactive waste

International Nuclear Information System (INIS)

Wurtinger, W.

1992-01-01

The guideline of the Ministry for Environmental Protection for controlling radioactive waste with a negligible development of heat defines in detail what data are relevant to the control of radioactive waste and should be followed up on and included in a system of documentation. By introducing the AVK (product control system for tracing the course of waste disposal) the operators of German nuclear power plants have taken the requirements of this guideline into account. In particular, possibilities for determining the degree of radioactivity of radioactive waste, which the BMU-guidelines call for, were put into practice by means of the programming technology of the product control system's module MOPRO. (orig.) [de

Comparative analysis of DOE Order 5820.2A, NRC, and EPA radioactive and mixed waste management requirements

International Nuclear Information System (INIS)

1991-07-01

As directed by DOE-Headquarters and DOE-Idaho, the Radioactive Waste Technical Support Program (TSP) drafted an analysis of DOE Order 5820. 2A on ''Radioactive Waste Management'' to develop guidelines and criteria for revising the Order. This comparative matrix is a follow up to the earlier analysis. This matrix comparing the requirements of DOE Order 5820.2A with Nuclear Regulatory Commission (NRC) and Environmental Protection Agency (EPA) regulations was prepared at the request of EM-30. The matrix compares DOE Order 5820.2A with the following: NRC regulations in 10 CFR Part 61 on ''Licensing Requirements for Land Disposal of Radioactive Waste''; NRC regulations in 10 CFR Part 60 on ''Disposal of High-Level Radioactive Waste in Geologic Repositories''; EPA regulations in 40 CFR Part 191 on ''Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Waste''; EPA regulations in 40 FR Part 192 on ''Health and Environmental Protection Standards for Uranium and Thorium Mill Tailing''; and EPA regulations under the Resource Conservation and Recovery Act

Decommissioning standards

International Nuclear Information System (INIS)

Crofford, W.N.

1980-01-01

EPA has agreed to establish a series of environmental standards for the safe disposal of radioactive waste through participation in the Interagency Review Group on Nuclear Waste Management (IRG). One of the standards required under the IRG is the standard for decommissioning of radioactive contaminated sites, facilities, and materials. This standard is to be proposed by December 1980 and promulgated by December 1981. Several considerations are important in establishing these standards. This study includes discussions of some of these considerations and attempts to evaluate their relative importance. Items covered include: the form of the standards, timing for decommissioning, occupational radiation protection, costs and financial provisions. 4 refs

Lessons learned from case studies of inhalation exposures of workers to radioactive aerosols

Energy Technology Data Exchange (ETDEWEB)

Hoover, M.D.; Fencl, A.F.; Newton, G.J. [and others

1995-12-01

Various Department of Energy requirements, rules, and orders mandate that lessons learned be identified, evaluated, shared, and incorporated into current practices. The recently issued, nonmandatory DOE standard for Development of DOE Lessons Learned Program states that a DOE-wide lessons learned program will {open_quotes}help to prevent recurrences of negative experiences, highlight best practices, and spotlight innovative ways to solve problems or perform work more safely, efficiently, and cost effectively.{close_quotes} Additional information about the lessons learned program is contained in the recently issued DOE handbook on Implementing U.S. Department of Energy Lessons Learned Programs and in October 1995 DOE SAfety Notice on Lessons Learned Programs. This report summarizes work in progress at ITRI to identify lessons learned for worker exposures to radioactive aerosols, and describes how this work will be incorporated into the DOE lessons learned program, including a new technical guide for measuring, modeling, and mitigating airborne radioactive particles. Follow-on work is focusing on preparation of {open_quotes}lessons learned{close_quotes} training materials for facility designers, managers, health protection professionals, line supervisors, and workers.

Lessons learned from case studies of inhalation exposures of workers to radioactive aerosols

International Nuclear Information System (INIS)

Hoover, M.D.; Fencl, A.F.; Newton, G.J.

1995-01-01

Various Department of Energy requirements, rules, and orders mandate that lessons learned be identified, evaluated, shared, and incorporated into current practices. The recently issued, nonmandatory DOE standard for Development of DOE Lessons Learned Program states that a DOE-wide lessons learned program will open-quotes help to prevent recurrences of negative experiences, highlight best practices, and spotlight innovative ways to solve problems or perform work more safely, efficiently, and cost effectively.close quotes Additional information about the lessons learned program is contained in the recently issued DOE handbook on Implementing U.S. Department of Energy Lessons Learned Programs and in October 1995 DOE SAfety Notice on Lessons Learned Programs. This report summarizes work in progress at ITRI to identify lessons learned for worker exposures to radioactive aerosols, and describes how this work will be incorporated into the DOE lessons learned program, including a new technical guide for measuring, modeling, and mitigating airborne radioactive particles. Follow-on work is focusing on preparation of open-quotes lessons learnedclose quotes training materials for facility designers, managers, health protection professionals, line supervisors, and workers

Savannah River Plant Separations Department mixed waste program

International Nuclear Information System (INIS)

Wierzbicki, W.M.

1988-01-01

The Department of Energy's (DOE) Savannah River Plant (SRP) generates radioactive and mixed waste as a result of the manufacture of nuclear material for the national defense program. The radioactive portion of the mixed waste and all nonhazardous radioactive wastes would continue to be regulated by DOE under the Atomic Energy Act. The Separations Department is the largest generator of solid radioactive waste at the Savannah River Plant. Over the last three years, the Separations Department has developed and implemented a program to characterize candidate mixed-waste streams. The program consisted of facility personnel interviews, a waste-generation characterization program and waste testing to determine whether a particular waste form was hazardous. The Separations Department changed waste-handling practices and procedures to meet the requirements of the generator standards. For each Separation Department Facility, staging areas were established, inventory and reporting requirements were developed, operating procedures were revised to ensure proper waste handling, and personnel were provided hazardous waste training. To emphasize the importance of the new requirements, a newsletter was developed and issued to all Separations supervisory personnel

Low-level radioactive waste, mixed low-level radioactive waste, and biomedical mixed waste

International Nuclear Information System (INIS)

Anon.

1994-01-01

This document describes the proceedings of a workshop entitled: Low-Level Radioactive Waste, Mixed Low-Level Radioactive Waste, and Biomedical Mixed Waste presented by the National Low-Level Waste Management Program at the University of Florida, October 17-19, 1994. The topics covered during the workshop include technical data and practical information regarding the generation, handling, storage and disposal of low-level radioactive and mixed wastes. A description of low-level radioactive waste activities in the United States and the regional compacts is presented

EPA's criteria development for radioactive waste that is Below Regulatory Concern

International Nuclear Information System (INIS)

Holcomb, W.F.; Gruhlke, J.M.

1987-01-01

The EPA's program for developing environmental standards for land disposal of low-level radioactive wastes, including a criterion for determining wastes with sufficiently low levels of radioactivity to be considered Below Regulatory Concern (BRC) has completed its risk assessment and cost-effectiveness analyses. The analyses for the BRC criterion included evaluation of general population health risks, maximum annual exposures to critical population groups, and costs of risk reduction. These risk assessments include analyses of 18 surrogate radioactive waste streams, representing both fuel cycle and non-fuel cycle facilities. Less restrictive disposal alternatives typical of those used for municipal garbage disposal, such as sanitary landfills, and situated in diverse demographic settings were used in the analyses. A number of waste types which contribute only small doses or fractions of a health effect over 10,000 years from unregulated disposal were identified. Disposal of such wastes without consideration of their very low radioactivity content results in significant cost savings. 3 references, 1 figure, 4 tables

Radioactive waste management in the USSR: A review of unclassified sources

International Nuclear Information System (INIS)

Bradley, D.J.

1991-03-01

The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of contaminated areas. Meanwhile, many treatment, solidification, and disposal options for radioactive waste management are being investigated by the Soviets

US radioactive waste management: the task ahead

International Nuclear Information System (INIS)

Bartlett, J.

1991-01-01

By the turn of the century, more than 40 000 tonnes of spent US nuclear waste will have been produced. The US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing a waste management program that meets stringent federal (EPA and NRC) protection standards. DOE began repository field studies this year at Yucca Mountain. As the Secretary of Energy called for DOE to begin spent fuel acceptance in 1998, a monitored retrievable storage (MRS) facility is planned. 1 fig

78 FR 79567 - National School Lunch Program and School Breakfast Program: Nutrition Standards for All Foods...

Science.gov (United States)

2013-12-31

... Program: Nutrition Standards for All Foods Sold in Schools as Required by the Healthy, Hunger-Free Kids... interim rule entitled National School Lunch Program and School Breakfast Program: Nutrition Standards for..., 2013 / Rules and Regulations [[Page 79567

The development of the American National Standard 'control of radioactive surface contamination on materials equipment and facilities to be released for uncontrolled use'

International Nuclear Information System (INIS)

Shapiro, J.

1980-01-01

A new standard submitted by the Health Physics Society Standards Committee to the American National Standards Institute concerning radioactive surface contamination of materials and equipment is discussed. The chronological events in the development of this standard are given. The standard provides criteria for the release for uncontrolled use of materials, equipment and facilities contaminated or potentially contaminated with radioactivity. Permissible contamination limits are specified for: 1) long lived alpha emitters except natural uranium and thorium, 2) more hazardous beta-gamma emitters, 3) less hazardous beta-gamma emitters and 4) natural uranium and thorium. A contamination reference level of 1000 dpm/100 cm 2 for 90 Sr was set as the basis for assigning limits to radionuclides presenting an ingestion hazard and other radionuclides were grouped based on the values of their maximum permissible concentration (MPC) in water relative to 90 Sr. The contamination limit for 239 Pu was chosen as the basis for assigning limits based on MPC in air to radionuclides presenting an inhalation hazard; a value of 100 dpm/100 cm 2 was adopted in the standard. An upper limit of 5000 dpm/100 cm 2 for surface contamination was selected for the standard. (UK)

A computer program for controlling a university radioactive material inventory: From confusion to computer to control

International Nuclear Information System (INIS)

Robb, D.B.; Riches, C.G.; O'Brian, M.J.; Riordan, F.J.

1984-01-01

The University of Washington is a large user of radioactive material. Over 250 authorized programs are working in over 600 labs with nearly 3500 orders of radioactive material per year. The state license sets limits on the total amount of material on campus. There are also limits on sewer disposal. To meet these needs it is necessary to know the amount of material on campus at any time. A computer program was developed which covered many aspects of the radiation safety record needs including inventory control. Inventory is now managed by tracking each order from purchase to disposal. A screen menu as part of the interactive program allows immediate and detailed information about the inventory at time of purchase approval and delivery. Because of this system our knowledge and control of radionuclide work on campus has increased dramatically. A description of how this system is used during ordering, delivery and disposal will be given. Details on the methods to check limits are included along with a summary of the reports made possible by the current data files

Standard criteria for disposal of liquid radioactive wastes from nuclear power plants into surface waters (river systems)

International Nuclear Information System (INIS)

Pisarev, V.V.; Tsybizov, I.S.

1976-01-01

Radioactive products discharge into natural water streams results in the necessity to regulate nuclear power plant discharges to ensure radiation safety (RS) for population using a river and surrounding river territory. To ensure RS it is necessary to set scientific-founded standards of permissible discharge level of liquid radioactive wastes (LRW) from nuclear power plant assuring observance of hygienic requirements for surface water puring. Volume of permissible LRW discharge into river systems must be set both with provision for concrete physical-geographycal conditions, specficity of utilizing the river and river valley and social-economical peculiarities of crtical population groups. The value of permissible LRW discharge into river systems is determined by three criterion groups: radiological, ecological and hydrological ones. By means of radiological group the internal and external irradiation doses for the whole body and its separate organs are set and RS of population is determined. Ecological criteria include a number of parameters (coefficients of accumulation, distribution and transition) determining quantitative ratios between radioactive element contents in water and separate links of biological chains: soil/water, fish/water, vegetables/water and others. Hydrological criteria determine the degree of waste dilution in rivers, control radioactive contamination of flood-lands areas and in common with ecological criteria determine radionuclide contents in soil and food products. A method of determining average annual values of LRW dilution in river waters is presented [ru

Integrated Management Program for Radioactive Sealed Sources in Egypt IMPRSS

International Nuclear Information System (INIS)

Hasan, A.; El-Adham, K.

2004-01-01

Sealed sources are usually in capsules made of stainless steel. They are the size of a pen or a finger and contain one of hundreds of radioactive elements (e.g., Iridium, Radium) or their isotopes. They are air-tight and very durable, contain the radioactive material but not radiation. They are used in the health sector, industry, military, and universities. Incidents occurred in Met Halfa, Egypt, 2000 (Iridium-192); Goiania, Brazil, 1987 (Cesium-137); Mexico and Southwest U.S., 1977 -1984 (Cobalt-60); Peru, 1999 (Iridium-1992); Poland 2001 (Cobalt-60). The IMPRSS Mission is based on a joined partnership between the Egyptian Atomic Energy Authority, the Egyptian Ministry of Health, the Sandia National Laboratories, the International Atomic Energy Agency and others. The IMPRSS Mission protects human health and the environment in Egypt from mismanaged sealed sources, is developed jointly with MOH and EAEA, provides capabilities for managing radioactive sealed sources in Egypt, increases public awareness, provides education and training, improves emergency response capabilities, develops a permanent disposal facility, ensures the program is self-sustaining and ensures close coordination with the IAEA. Infrastructure how to manage sealed sources is discussed. It includes awareness, tracking and inventory control, security, recovery, conditioning and storage, recycling and disposal. Emergency response, regulatory reform, education and training and its targets are provided. The government of Egypt can protect the people of Egypt and is ready for emergencies. Prevention is the first line of defence and detection is the second line of defence. Adequate Emergency Response saves lives and adequate control reduces risk of mismanaged uses or deliberate misuses of sources. A Cradle-to-Grave approach is built on existing capabilities at EAEA and MOH

The standardization methods of radioactive sources (125I, 131I, 99mTc, and 18F) for calibrating nuclear medicine equipment in Indonesia

International Nuclear Information System (INIS)

Wurdiyanto, G; Candra, H

2016-01-01

The standardization of radioactive sources ( 125 I, 131 I, 99m Tc and 18 F) to calibrate the nuclear medicine equipment had been carried out in PTKMR-BATAN. This is necessary because the radioactive sources used in the field of nuclear medicine has a very short half-life in other that to obtain a quality measurement results require special treatment. Besides that, the use of nuclear medicine techniques in Indonesia develop rapidly. All the radioactive sources were prepared by gravimetric methods. Standardization of 125 I has been carried out by photon- photon coincidence methods, while the others have been carried out by gamma spectrometry methods. The standar sources are used to calibrate a Capintec CRC-7BT radionuclide calibrator. The results shows that calibration factor for Capintec CRC-7BT dose calibrator is 1,03; 1,02; 1,06; and 1,04 for 125 I, 131 I, 99m Tc and 18 F respectively, by about 5 to 6% of the expanded uncertainties. (paper)

The standardization methods of radioactive sources (125I, 131I, 99mTc, and 18F) for calibrating nuclear medicine equipment in Indonesia

Science.gov (United States)

Wurdiyanto, G.; Candra, H.

2016-03-01

The standardization of radioactive sources (125I, 131I, 99mTc and 18F) to calibrate the nuclear medicine equipment had been carried out in PTKMR-BATAN. This is necessary because the radioactive sources used in the field of nuclear medicine has a very short half-life in other that to obtain a quality measurement results require special treatment. Besides that, the use of nuclear medicine techniques in Indonesia develop rapidly. All the radioactive sources were prepared by gravimetric methods. Standardization of 125I has been carried out by photon- photon coincidence methods, while the others have been carried out by gamma spectrometry methods. The standar sources are used to calibrate a Capintec CRC-7BT radionuclide calibrator. The results shows that calibration factor for Capintec CRC-7BT dose calibrator is 1,03; 1,02; 1,06; and 1,04 for 125I, 131I, 99mTc and 18F respectively, by about 5 to 6% of the expanded uncertainties.

Collaboration of the Dutch research program for radioactive waste disposal (OPERA) and TU Delft

International Nuclear Information System (INIS)

Bykov, D.M.; Kloosterman, J.L.

2015-01-01

Radioactive waste in the Netherlands is collected, treated and stored by COVRA (Centrale Organisatie Voor Radioactief Afval) in the interim storage facility for at least 100 a. After this period of long-term storage, geological disposal is foreseen. The policy is based on a step-wise decision process in which all decisions are taken to ensure safe disposal in a repository, but without excluding unforeseen alternative solutions that might develop in the future. OPERA is the Dutch acronym for research program into geological disposal of radioactive waste. It started in 2011 and is running for five years. The OPERA Research plan is developed by NRG in close collaboration with COVRA. Radioactive waste disposal in the Netherlands is at an early, conceptual phase. The aim of Opera is to develop a first preliminary safety case to structure the research necessary for the eventual deployment of a repository in the Netherlands. The OPERA research program aims at a close cooperation with the Belgian research program on radioactive waste disposal. The result of OPERA will be to detail a first roadmap for the long-term research on geological disposal of radioactive waste in the Netherlands, based initially on a re-evaluation of existing safety and feasibility studies conducted more than ten years ago, making use of present international and, wherever possible, national knowledge. This will be done by developing initial and conditional safety cases for generic GDFs in Zechstein rock salt and Boom Clay formations in the Netherlands. The goal in OPERA is to develop initial safety cases that are intended to mark the start of the research development process and to iterate these as knowledge grows to new developed insights. The safety case is conditional since plausible assumptions must later be confirmed in a safety case e.g. for site selection. Dutch, Belgian, German, English and French organizations participate in OPERA. These organizations can be found in the two documents with

Collaboration of the Dutch research program for radioactive waste disposal (OPERA) and TU Delft

Energy Technology Data Exchange (ETDEWEB)

Bykov, D.M.; Kloosterman, J.L. [TU Delft (Netherlands). Reactor Inst. Delft; Neeft, E.A.C.; Verhoef, E.V. [COVRA N.V., Nieuwdorp (Netherlands)

2015-07-01

Radioactive waste in the Netherlands is collected, treated and stored by COVRA (Centrale Organisatie Voor Radioactief Afval) in the interim storage facility for at least 100 a. After this period of long-term storage, geological disposal is foreseen. The policy is based on a step-wise decision process in which all decisions are taken to ensure safe disposal in a repository, but without excluding unforeseen alternative solutions that might develop in the future. OPERA is the Dutch acronym for research program into geological disposal of radioactive waste. It started in 2011 and is running for five years. The OPERA Research plan is developed by NRG in close collaboration with COVRA. Radioactive waste disposal in the Netherlands is at an early, conceptual phase. The aim of Opera is to develop a first preliminary safety case to structure the research necessary for the eventual deployment of a repository in the Netherlands. The OPERA research program aims at a close cooperation with the Belgian research program on radioactive waste disposal. The result of OPERA will be to detail a first roadmap for the long-term research on geological disposal of radioactive waste in the Netherlands, based initially on a re-evaluation of existing safety and feasibility studies conducted more than ten years ago, making use of present international and, wherever possible, national knowledge. This will be done by developing initial and conditional safety cases for generic GDFs in Zechstein rock salt and Boom Clay formations in the Netherlands. The goal in OPERA is to develop initial safety cases that are intended to mark the start of the research development process and to iterate these as knowledge grows to new developed insights. The safety case is conditional since plausible assumptions must later be confirmed in a safety case e.g. for site selection. Dutch, Belgian, German, English and French organizations participate in OPERA. These organizations can be found in the two documents with

Radioactivity and environment

Energy Technology Data Exchange (ETDEWEB)

Trivedi, R N [Fertilizer Association of India, New Delhi

1977-12-01

Power generation from radioisotopes is one of the major applications of nuclear energy for peaceful purposes and is in practice in over twenty countries including India. Other well-known applications of radioactive substances are in medicine, industry, scientific and industrial research programs, and nuclear weapons. The only serious disadvantage with the radioisotopes and their waste products is the constant release of radiation energy which contaminates the environment and endangers the life. An attempt has been made to identify the major sources of radioactivity in the environment and assess its potential impact on the environment. Recent developments in safety measures for prevention of contamination and control of radioactivity and in radioactive wastes management are also discussed.

University program in hazardous chemical and radioactive waste management

International Nuclear Information System (INIS)

Parker, F.L.

1987-01-01

The three main functions of a university program are education, training, and research. At Vanderbilt University, there is a Solid and Hazardous Waste option in the Master of Science in Engineering Program. The two main foci are treatment of wastes and environmental transport and transformation of the wastes. Courses in Hazardous Waste Engineering and Radioactive Waste Disposal present a synoptic view of the field, including legal, economic, and institutional aspects as well as the requisite technical content. The training is accomplished for some of the students through the aegis of an internship program sponsored by the US Department of Energy. In the summer between the two academic years of the program, the study works at a facility where decontamination and/or decommissioning and/or remedial actions are taking place. Progress in understanding the movement, transformation, and fate of hazardous materials in the environment is so rapid that it will not be possible to be current in the field without participating in that discovery. Therefore, their students are studying these processes and contributing to new knowledge. Some recent examples are the study of safety factors implicit in assuming a saturated zone below a hazardous waste landfill when an unsaturated zone exists, application of probabilistic risk assessment to three National Priority List sites in Tennessee, and the explanation of why certain organics precede pH, conductivity and nitrates through a clay liner at a hazardous waste disposal site

Directory of certificates of compliance for radioactive materials packages: Report of NRC approved quality assurance programs for radioactive material packages

International Nuclear Information System (INIS)

1988-12-01

This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), all Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1988. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

The regulatory actions in the management of disuse radioactive sources

International Nuclear Information System (INIS)

Truppa, W.A.; Cordoba, M.F.; Poletti, M.; Calabria, M.A.; Pirez, C.

2010-01-01

During the last years, different incidents related to the discovery of inadvertent radioactive material have been reported through the international information systems available. From the analysis of the information received it can be concluded that those situations are derived from the inadequate application of concepts such as 'safety culture' and 'risk perception' or inadequate physical safety measures towards radioactive sources by the licensee. Among the activities that the regulators perform during the use of radioactive material, the most important are the ones related to avoiding the existence of disused radioactive sources. In this regard, the Nuclear Regulatory Authority (NRA) has implemented, through its Standards, regulatory mechanisms to adequately control and dispose of radioactive material. Concerning this matter, actions were taken in Argentina with the aim of disposing or keeping the custody in an authorized long term storage of every radioactive source used to measure thickness, humidity, level, weight, etc. that remained within the facilities without use and/or a suitable program to be reutilized within a period larger than six months. The objective of the present piece of work is to present the analysis and results of the actions fulfilled between 2002 and 2009, giving details about the regulatory activities performed in relation to the disposal and withdrawal of radioactive sources and the physical safety measures taken. (authors) [es

Calibration method based on direct radioactivity measurement for radioactive gas monitoring instruments

International Nuclear Information System (INIS)

Yoshida, Makoto; Ohi, Yoshihiro; Chida, Tohru; Wu, Youyang.

1993-01-01

A calibration method for radioactive gas monitoring instruments was studied. In the method, gaseous radioactivity standards were provided on the basis of the direct radioactivity measurement by the diffusion-in long proportional counter method (DLPC method). The radioactivity concentration of the gas mixture through a monitoring instrument was determined by sampling the known volume of the gas mixture into the proportional counter used for the DLPC method. Since oxygen in the gas mixture decreased the counting efficiency in a proportional counter, the influence on calibration was experimentally estimated. It was not serious and able to be easily corrected. By the present method, the relation between radioactivity concentration and ionization current was determined for a gas-flow ionization chamber with 1.5 l effective volume. It showed good agreement with the results in other works. (author)

Radioactive air sampling methods

CERN Document Server

Maiello, Mark L

2010-01-01

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

The IAEA Standards for the Radioactive Discharge Control: Present Status and Future Development

International Nuclear Information System (INIS)

Balonov, M.; Linsley, G.; Robinson, C.; Cabianca, T.

2004-01-01

The International Atomic Energy Agency (IAEA) is the organization within the UN family with a statutory mandate to establish standards for the protection of health and environment against ionizing radiation, and to provide for the application of those standards. As part of these functions, the IAEA periodically reviews the status and continued relevance of the standards to the needs of its Member States. Recent work on the development of standards for the radioactive discharge control includes development of practical guidance for setting discharge limits, elaboration on methodology for the radiation protection of non-human species, and preparation of guidance on environmental monitoring for radiation protection purposes. Development of these safety documents is influenced by recent international and regional tendencies, based on social initiatives, to reduce radioactive discharges substantially below levels justified by radiological criteria. The IAEA has developed preliminary guidance on practical aspects of setting discharge limits, which included a review of national regulatory experience in this regard. This review suggested that societal pressures and regulatory practicalities results in discharge controls that were likely to be more restrictive that those that would be implied by formal optimization techniques. Regulatory review of authorizations includes a number of considerations, including predicted doses to members of the critical group, but the suitability of abatement forms a greater part in the decision-making process than allowed for in previous safety guidance. The IAEA has, in recent years, established a programme of work specifically addressing the development of safety standards on assessing the impact of ionizing radiation on non-human species, in co-operation with other relevant international organizations. The main issues arising will be summarised in the paper with the main focus on an exploration of the possible form of future regulatory

The regulatory system of monitoring workers in Germany for intakes of radioactivity

International Nuclear Information System (INIS)

Dalheimer, A.; Henrichs, K.

1996-01-01

In Germany, the working group 'Incorporation Monitoring' of the German-Swiss Radiation Protection Association defined a new standard for the monitoring of workers occupationally exposed to radioactive material. During the last two years this draft has been accepted by the German government in the form of three guidelines. The purpose of the approach was the installation of a consistent state-of-the-art system: defining clear criteria for the necessity of routine and special monitoring programs, giving guidelines for monitoring programs ensuring that dose assessments are as reliable as necessary with the lowest possible expenses, standardizing as far as possible the procedures of dose assessments, and guaranteeing the necessary quality standards. The scientific basis of this regulatory system are the publications 30 and 54 of lCRP. (author)

Integrating the radioactive waste management system into other management systems

International Nuclear Information System (INIS)

Silva, Ana Cristina Lourenco da; Nunes Neto, Carlos Antonio

2007-01-01

Radioactive waste management is to be included in the Integrated Management System (IMS) which pursues the continuous improvement of the company's quality, occupational safety and health, and environment protection processes. Radioactive waste management is based on the following aspects: optimization of human and material resources for execution of tasks, including the provision of a radiation protection supervisor to watch over the management of radioactive waste; improved documentation (management plan and procedures); optimization of operational levels for waste classification and release; maintenance of generation records and history through a database that facilitates traceability of information; implementation of radioactive waste segregation at source (source identification, monitoring and decontamination) activities intended to reduce the amount of radioactive waste; licensing of initial storage site for radioactive waste control and storage; employee awareness training on radioactive waste generation; identification and evaluation of emergency situations and response planning; implementation of preventive maintenance program for safety related items; development and application of new, advanced treatment methodologies or systems. These aspects are inherent in the concepts underlying quality management (establishment of administrative controls and performance indicators), environment protection (establishment of operational levels and controls for release), occupational health and safety (establishment of operational controls for exposure in emergency and routine situations and compliance with strict legal requirements and standards). It is noted that optimizing the addressed aspects of a radioactive waste management system further enhances the efficiency of the Integrated Management System for Quality, Environment, and Occupational Safety and Health. (author)

Radioactivity from Plowshare applications - Safety considerations

Energy Technology Data Exchange (ETDEWEB)

Tewes, H A [Lawrence Radiation Laboratory, University of California, Livermore, CA (United States)

1970-05-01

When the Plowshare Program was first being seriously considered some 13 years ago, a number of applications immediately suggested themselves. However, it soon became obvious that most of these applications had the drawback of producing and distributing appreciable quantities of radioactivity to the environment. Thus, the Atomic Energy Commission, together with its contractors, formulated and put into effect a program aimed at dealing with this problem, both from the standpoint of reducing the amount of radioactivity released to the environment and understanding the impact of this radioactivity on the biosphere.

Radioactivity from Plowshare applications - Safety considerations

International Nuclear Information System (INIS)

Tewes, H.A.

1970-01-01

When the Plowshare Program was first being seriously considered some 13 years ago, a number of applications immediately suggested themselves. However, it soon became obvious that most of these applications had the drawback of producing and distributing appreciable quantities of radioactivity to the environment. Thus, the Atomic Energy Commission, together with its contractors, formulated and put into effect a program aimed at dealing with this problem, both from the standpoint of reducing the amount of radioactivity released to the environment and understanding the impact of this radioactivity on the biosphere

International program: Feasibility of the evacuation of high-level radioactive wastes under the ocean depths. (Seabed Program)

International Nuclear Information System (INIS)

Barbreau, A.

1990-01-01

The Seabed feasibility program is an international scientific program of research on the feasibility of the disposal of high-level radioactive wastes into the geological formations making up the floor of the great abyssal plains of the oceans. Decided in 1977, the program is aimed at answering the three following questions: 1) are there potentially favourable sites. 2) is the disposal of wastes possible. 3) does the operation present safety guarantees. First initiated by four countries (USA, UK, Japan and France), the program sponsored by the OECD nuclear energy agency was gathering ten countries and the Commission of the European communities in 1988. The techniques of waste disposal by means of drilling in consolidated sediments and penetrators in loose sediments have been studied. The penetrator technique has been the most thoroughly studied, especially through in situ experiments in the Atlantic ocean. The various factors affecting safety have been studied and the radiological consequences of a burial operation assessed through models. It has been concluded that such an operation could be carried out technically under quite satisfying conditions [fr

Control of the surface radioactive contamination in the field of biological research

International Nuclear Information System (INIS)

Calvo, S.; Encina, A. de la; Gaspar, J.; Macias, M. T.; Sanchez, A.; Usera, F.

2012-01-01

The manipulation of unsealed sources in biomedical research involves significant risk of radioactive contamination. the aim of this study has been to analyze the radioactive contamination occurring in the field of biomedical research, assessing its magnitude, identifying the equipment that can be contaminated with higher probability and monitoring the evolution of the contaminations production taking into account the radioisotopes and the activities uses, and the radiation protection control applied. The data used for this study correspond to a very lengthy period of time and it have been collected in the radioactive facility, of the Centro Nacional de Biotecnologia (CSIC), a very large biological research centre that can be used perfectly as a reference for this area. The results obtained show a gradual and significant decrease in the incidence of the radioactive contamination. This is due to the optimization of radiation protection standards applied and the implementation or a systematic operational radiation protection program. (Author) 13 refs.

Status of environmental response efforts at radioactively contaminated sites in the united states air force installation restoration program

International Nuclear Information System (INIS)

Rowe, W.D. Jr.; McEntee, T.E. Jr.; Johnson, B.; Manning, L.

1995-01-01

The United States Air Force has identified approximately 170 radioactively contaminated sites at its domestic installations. These sites contain a variety of low level radioactive and mixed wastes and are classified as burial sites, landfills, buildings, and other disposal sites. Of these 170, approximately 70 are presently being evaluated under the Air Force Installation Restoration Program (IRP) in accordance with applicable laws and regulations. Removal and/or remedial actions have been taken at specific sites using site-specific residual radioactivity criteria. The remaining sites are either under investigation to determine the need for possible action or have been classified as response complete based on restricted or unrestricted future use. This paper describes past Air Force operations that generated radioactive waste materials; examines the current inventory of resulting radioactively contaminated sites in the Air Force IRP; reviews criteria used to evaluate sites for removal and/or remedial actions; provides summary information on actions taken at sites; and focuses on response actions and cleanup levels at two completed sites. The paper concludes with an assessment of outstanding issues relevant to the remediation of radioactively contaminated sites. (author)

Regulations for the safe transport of radioactive materials

International Nuclear Information System (INIS)

Kgogo, Obonye

2016-04-01

The report provides insight and investigates whether Transport Regulations in Botswana follow international standards for transport of radioactive material. Radioactive materials are very useful in most of our activities and are manufactured in different countries, therefore end up traversing from one country to another and being transported in national roads .The IAEA regulation for the Transport of radioactive material is used as the reference guideline in this study. The current Regulations for Transport of radioactive material in Botswana do not cover all factors which need to be considered when transporting radioactive although they refer to IAEA regulations. Basing on an inadequacy of the regulations and category of radioactive materials in the country recommendations were made concerning security, packaging and worker training's. The regulations for the Transport of radioactive material in Botswana need to be reviewed and updated so that they can relate to international standard. (au)

Teaching Radioactive Waste Management in an Undergraduate Engineering Program - 13269

Energy Technology Data Exchange (ETDEWEB)

Ikeda, Brian M. [Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada)

2013-07-01

The University of Ontario Institute of Technology is Ontario's newest university and the only one in Canada that offers an accredited Bachelor of Nuclear Engineering (Honours) degree. The nuclear engineering program consists of 48 full-semester courses, including one on radioactive waste management. This is a design course that challenges young engineers to develop a fundamental understanding of how to manage the storage and disposal of various types and forms of radioactive waste, and to recognize the social consequences of their practices and decisions. Students are tasked with developing a major project based on an environmental assessment of a simple conceptual design for a waste disposal facility. They use collaborative learning and self-directed exploration to gain the requisite knowledge of the waste management system. The project constitutes 70% of their mark, but is broken down into several small components that include, an environmental assessment comprehensive study report, a technical review, a facility design, and a public defense of their proposal. Many aspects of the project mirror industry team project situations, including the various levels of participation. The success of the students is correlated with their engagement in the project, the highest final examination scores achieved by students with the strongest effort in the project. (authors)

Teaching Radioactive Waste Management in an Undergraduate Engineering Program - 13269

International Nuclear Information System (INIS)

Ikeda, Brian M.

2013-01-01

The University of Ontario Institute of Technology is Ontario's newest university and the only one in Canada that offers an accredited Bachelor of Nuclear Engineering (Honours) degree. The nuclear engineering program consists of 48 full-semester courses, including one on radioactive waste management. This is a design course that challenges young engineers to develop a fundamental understanding of how to manage the storage and disposal of various types and forms of radioactive waste, and to recognize the social consequences of their practices and decisions. Students are tasked with developing a major project based on an environmental assessment of a simple conceptual design for a waste disposal facility. They use collaborative learning and self-directed exploration to gain the requisite knowledge of the waste management system. The project constitutes 70% of their mark, but is broken down into several small components that include, an environmental assessment comprehensive study report, a technical review, a facility design, and a public defense of their proposal. Many aspects of the project mirror industry team project situations, including the various levels of participation. The success of the students is correlated with their engagement in the project, the highest final examination scores achieved by students with the strongest effort in the project. (authors)

Review of the Commission program for standardization of nuclear power plants and recommendations to improve standardization concepts

International Nuclear Information System (INIS)

1978-02-01

This is a report of a staff study describing the need and utility of specific changes to the Commission's standardization program. The various matters considered in the study include: (1) A discussion of industry use to date of the standardization program. (2) A discussion of the experience to date with each of the standardization concepts. (3) A review of public comments on the standardization program and the staff response to each principal comment. (4) A review of the need for standardization considering the likely number of license applications to be submitted in the coming years. (5) A discussion of the reference system concept, including review of applicable experience and recommended changes to the concept. (6) A discussion of the duplicate plant concept, including review of applicable experience and recommended changes to the concept. (7) A discussion of the manufacturing license concept, including review of applicable experience and recommended changes to the concept. (8) A discussion of the replicate plant concept, including review of applicable experience and recommended changes to the concept. (9) A discussion of the effective periods for approved designs under all four standardization concepts. (10) A description of continuing staff activities related to the standardization program

Main approaches to solving the problems of radioactive waste processing and disposal

International Nuclear Information System (INIS)

Tarasov, V.M.; Syrkus, M.N.

1989-01-01

papers devoted to the problems of processing and disposal of radioactive wastes, formed during nuclear facility operation and after decommissioning are reviewed. Techniques for gaseous and liquid waste solidification, as well as solid waste processing by mechanical fragmentation and combustion are considered. Possibilities of radioactive waste disposal in cosmic space, their burial at the bed of seas ansd oceans, in geological storages are discussed. Special attention disposal. The conclusion is made that today there are no any uniform way for radiactive waste disposal and standard technical means for its realization. Solution of the problems considered should be of a complex character and it is carried out within international research programs

Low-level Radioactivity Measurements

International Nuclear Information System (INIS)

Churtgen, C.

2007-01-01

The low-level radioactivity measurements service performs measurements of alpha or beta emitters on various types of low-radioactivity samples (biological and environmental) from internal and external clients. to maintain and develop techniques concerning the measurement of low-level radioactivity of alpha and beta emitting radionuclides in environmental or biological samples; to measure these samples by means of low-background counters (liquid scintillators, proportional counters, ZnS counters and alpha-spectrometers); to support and advise the nuclear and non-nuclear industry on problems of radioactive contamination or low level radioactivity measurements; to maintain the quality assurance system according to the ISO17025 standard for which we obtained the Beltest accreditation in 1998; to assess the internal dose from occupational intakes of radionuclides for workers of the nuclear industry;

Separating defence and civilian radioactive waste programs in Nevada: can the public navigate the maze?

International Nuclear Information System (INIS)

Nielsen, R.A.

1999-01-01

Nevada is at the centre of public policy debate with regards to high and low level radioactive waste disposal. Nevada's Yucca Mountain is the only site under consideration for a US geologic repository for commercial spent nuclear fuel and defence high level waste. The Nevada Test Site (NTS) has long been a low level waste (LLW) disposal facility for the Department of Energy (DOE) defence waste and is now expected to take even more LLW as the preferred site for a regional or centralised disposal facility. Furthermore, the primary mission at NTS, defence, continues to add more contamination to the site. Combined, these facts present a public policy enigma, confused further by the intentional separation of the programs by DOE, even though all are essentially conducted at the same site. Involving the public in policy decisions for these programs is a dilemma because the public does not make the same artificial distinctions between them as DOE, DOE credibility suffers from past public involvement efforts conducted during an era of Cold War secrecy and because DOE public involvement programs are operated independently, with little or no co-operation between programs. The public does not know where it fits into the DOE decision-making process or if it impacts the policy decisions being made that affect it. This paper examines the complex maze of radioactive policy and bureaucracy in order to unveil the enigma Nevada residents face. Are they able to navigate this maze to effectively participate in government policy and decision-making? Or, will they remain confused by the government bureaucracy which deliberately makes a mess of the situation and seeks to exploit a politically weak state with large tracts of federally controlled land? lt further evaluates the effect this enigma has in producing acceptable public policy for radioactive waste disposal in the US, the role of public participation in that policy, and the reason the public is disillusioned and disengaged in the

Foodstuffs (radioactive contamination)

International Nuclear Information System (INIS)

Thompson, Donald; Taylor, Teddy; Campbell-Savours, D.N.

1987-01-01

The proceedings are given of the debate in the UK House of Commons on the maximum permitted radioactivity levels for foodstuffs, feeding stuffs and drinking water in the case of abnormal levels of radioactivity or of a nuclear accident. The motion takes note of European Community Document no. 7183/87 and urges the Community to assure a common standard of health protection by adopting a rational set of scientifically based intervention levels for foodstuffs. (UK)

China's status and strategy of radioactive waste management

International Nuclear Information System (INIS)

Bi Decai

2001-01-01

China has a forty-year history of nuclear industry and nuclear technology application. Safety management of radioactive wastes has been the great concern of related regulatory authorities. After the national policy on regional disposal for low and intermediate level radioactive waste was enacted in 1992, the management of radioactive wastes gradually focused on disposal. Currently, the strategies for radioactive waste management in China are: (a) storing high level radioactive wastes temporarily and launching the study of vitrification and deep geological disposal of high level liquid waste, treating spent fuels from PWR by reprocessing; (b) implementing regional disposal policy for low and intermediate level wastes, implementing cement solidification for low and intermediate level liquid waste before disposal, carrying out bulk casting shallow land disposal technology and hydraulic-fractured cement solidification for deep geological disposal in some special regions under specific conditions, treating low and intermediate level solid radioactive wastes by cement solidification after incineration or by compressing before final disposal; (c) stabilizing the tailing repository by reinforcing embankment, constructing flood dam and overlaying plantation; and (d) developing and formulating laws, regulations, and standards to ensure safe management of radioactive wastes. When establishing standards, other than to follow the generic principles and requirements, emphasis should be placed on the following principles: safety the first, economy, disposal of radioactive wastes as focus, and introduction of international advanced standards as possible. (author)

Radioactive waste management in Slovenia

International Nuclear Information System (INIS)

Fink, K.

1992-01-01

The problem of radioactive waste management is both scientifically and technically complex and also deeply emotional issue. In the last twenty years the first two aspects have been mostly resolved up to the point of safe implementation. In the Republic of Slovenia, certain fundamentalist approaches in politics and the use of radioactive waste problem as political marketing tool, make things even more complex. Public involvement in planning and development of radioactive waste management program must be perceived as essential for the success of the program. Education is a precursor to public comprehension and confidence which lead to adequate waste management decisions that will protect the public health, safety and environment without jeopardizing further progress and development. (author) [sl

Development of radioactive standards in epoxy matrix for the control of quality of activimeters; Desenvolvimento de padroes radioativos em matriz epoxi para controle da qualidade de ativimetros

Energy Technology Data Exchange (ETDEWEB)

Fragoso, Maria da Conceicao de Farias; Monteiro, Luciane Carollyne de Oliveira Reis; Oliveira, Marcia Liane de, E-mail: mcfragoso@cnen.gov.br [Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE), Recife, PE (Brazil)

2016-07-01

In the present study, a new approach for development of the standards for positron emitting radionuclides in epoxy matrix is presented. Different formulations were prepared using epoxy resin (bisphenol A diglycidyl ether - DGEBA) and curing agents, to immobilize the radioactive material. The efficiency curve and standard sample methods were applied for activity determination of a long-lived positron emitter ({sup 22}Na). Satisfactory results were obtained in the 3{sup rd} combination. Thus, these radioactive standards can be used to evaluate the metrological behavior of the systems used for the measurement of the radiopharmaceuticals (activimeters) in the production centers and in nuclear medicine services. (author)

Quality assurance program for determining the radioactivity in environmental samples at the Institute of Nuclear Energy Research in Taiwan

International Nuclear Information System (INIS)

Gone, J.K.; Wang, T.W.

2000-01-01

Interest in determining radioactivity in environmental samples has increased considerably in recent years after the Chernobyl accident in 1986. Environmental monitoring programs have been set up in different countries to measure the trace amount of radionuclides in the environment, and quality of the analytical results on these samples is important because the regulation and safety concerns. A good quality assurance program is essential to provide accurate information for the regulatory body and environmentalists to set proper reactions to protect the environment, and a good analytical result is also important for scientists to determine the transfer of radionuclides between environmental matrices. The Institute of Nuclear Energy Research (lNER) in Taiwan has been working on radionuclide analysis in environmental samples for years, and it's environmental media radioanalytical laboratory (EMRAL) has recently upgraded its quality assurance program for the international standard ISO/lEC guide 25 requirements. The general requirements of lSO/lEC guide 25 has been adapted by the Chinese National Laboratory Accreditation (CNLA) of Taiwan, and CNLA is also a member of International Laboratory Accreditation Cooperation (ILAC) and Asia Pacific Laboratory Accreditation Cooperation (APLAC). This paper summarizes the quality assurance program of lNER's EMRAL. It covers both management and technical sections. These sections have ensured the quality of INER's EMRAL, and they can be applied to different laboratories in the future. (author)

Quality assurance program for determining the radioactivity in environmental samples at the Institute of Nuclear Energy Research in Taiwan

Energy Technology Data Exchange (ETDEWEB)

Gone, J.K. [TRR-II Project Team, Institute of Nuclear Energy Research, Taoyuan, Taiwan (China); Wang, T.W. [Division of Health Physics, Institute of Nuclear Energy Research, Taoyuan, Taiwan (China)

2000-05-01

Interest in determining radioactivity in environmental samples has increased considerably in recent years after the Chernobyl accident in 1986. Environmental monitoring programs have been set up in different countries to measure the trace amount of radionuclides in the environment, and quality of the analytical results on these samples is important because the regulation and safety concerns. A good quality assurance program is essential to provide accurate information for the regulatory body and environmentalists to set proper reactions to protect the environment, and a good analytical result is also important for scientists to determine the transfer of radionuclides between environmental matrices. The Institute of Nuclear Energy Research (lNER) in Taiwan has been working on radionuclide analysis in environmental samples for years, and it's environmental media radioanalytical laboratory (EMRAL) has recently upgraded its quality assurance program for the international standard ISO/lEC guide 25 requirements. The general requirements of lSO/lEC guide 25 has been adapted by the Chinese National Laboratory Accreditation (CNLA) of Taiwan, and CNLA is also a member of International Laboratory Accreditation Cooperation (ILAC) and Asia Pacific Laboratory Accreditation Cooperation (APLAC). This paper summarizes the quality assurance program of lNER's EMRAL. It covers both management and technical sections. These sections have ensured the quality of INER's EMRAL, and they can be applied to different laboratories in the future. (author)

Summary of national and international fuel cycle and radioactive waste management programs, 1984

Energy Technology Data Exchange (ETDEWEB)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

1984-07-01

Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories.

Summary of national and international fuel cycle and radioactive waste management programs, 1984

International Nuclear Information System (INIS)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

1984-07-01

Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories

Safety regulation for the design approval of special form radioactive sources

International Nuclear Information System (INIS)

Cho, Woon-Kap

2009-01-01

Several kinds of special form radioactive sources for industrial, medical applications are being produced in Korea. Special form radioactive sources should meet strict safety requirements specified in the domestic safety regulations and the design of the sources should be certified by the regulatory authority, the Ministry of Education, Science and Technology (MEST). Several safety tests such as impact, percussion, heating, and leak tests are performed on the sources according to the domestic regulations and the international safety standards such as ANSI N542-1977 and ISO 2919-1999(E). As a regulatory expert body, Korea Institute of Nuclear Safety (KINS) assesses various types of application documents, such as safety analysis report, quality assurance program, and other documents evidencing fulfillment of requirements for design approval of the special form radioactive sources, submitted by a legal person who intends to produce special form radioactive sources and then reports the assessment result to MEST. A design approval certificate is issued to the applicant by MEST on the basis of a technical evaluation report presented by KINS.

Development of Standards for Textiles and Clothing Postsecondary Programs. Final Report.

Science.gov (United States)

Iowa State Univ. of Science and Technology, Ames. Dept. of Home Economics Education.

A project was conducted to validate program standards and performance standards for four postsecondary occupational areas--fashion merchandising, fashion design, apparel, and window treatment services. Returns from 117 questionnaires from postsecondary institutions in fifty states were used to develop program standards statements and to provide…

Environmental radioactivity from natural, industrial, and military sources

International Nuclear Information System (INIS)

Eisenbud, M.

1987-01-01

This document is the third edition of a book generally considered a standard in the field of radioactive materials in the environment. Topics include radiation protection standards, transport mechanisms, terrestrial and aquatic pathways, reprocessing of nuclear fuels, radioactive waste management, the fallout from nuclear explosions, nuclear accidents, and risk assessment

The IAEA and Control of Radioactive Sources

International Nuclear Information System (INIS)

Dodd, B.

2004-01-01

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

ORNL radioactive waste operations

International Nuclear Information System (INIS)

Sease, J.D.; King, E.M.; Coobs, J.H.; Row, T.H.

1982-01-01

Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards

DOE program for improvement practices for shallow burial of radioactive waste

International Nuclear Information System (INIS)

Dieckhoner, J.E.

1978-01-01

The practice of burying solid radioactive waste in relatively shallow pits or trenches at government nuclear sites dates back to the Manhattan Project. In some cases, where local conditions were considered unfavorable, intersite shipment of waste has been required. This general concept was later used at commercially-operated sites under Federal or state regulation. The purpose, scope, and results of a DOE program begun several years ago for improvements of burial ground disposal methods are reviewed. The program includes the re-evaluation of the original siting and of operating practices at existing burial grounds (including monitoring for migration of activity); the development of improved criteria for siting of new grounds that might be required as the defense site operations continue; and development of corrective measures such as diking and better draining for possible unsatisfactory conditions that might be detected. The possible applications of these findings to commercial burial grounds is discussed

Monitoring program for evaluating radionuclide emissions from incineration of low-level radioactive waste

International Nuclear Information System (INIS)

Wittmer, S.C.; Solomon, H.F.

1984-01-01

The implementation of an incineration program for low-level radioactive waste is a complex task, especially in the area of obtaining environmental permits. To provide assurance to the appropriate regulatory agencies involved with environmental permitting and others that an incineration program is properly conducted, emissions monitoring to identify radionuclides and their fate may be needed. An electronic spreadsheet software program Lotus 1-2-3 (Lotus Development Corporation) on an IBM Personal Computer has been used to perform data reduction for test results from such a monitoring program and to present them graphically to facilitate interpretation. The sampling technique includes: (1) the use of an EPA Method 5 stack sampling train modified to exclude the dry-catch filtration assembly with ethanolamine used to scrub incinerator gas at depressed temperatures and (2) a continuous composite liquid sampler for incinerator wet scrubber discharge to the sanitary sewer. Radionuclides in the samples are assayed using scintillation spectrometry

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

Science.gov (United States)

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

2012-08-01

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

Final report of the Department of Energy pilot internship program on radioactive waste at Vanderbilt University (September 1, 1993-08/31, 1994)

Energy Technology Data Exchange (ETDEWEB)

Frank Parker

1999-08-31

This final report summarizes Vanderbilt's ten year program in radioactive waste management. The report describes the interns selected for the program, the interns' course of study, and their assignments.

Development of the Discrimination Programs between the Internal and External Radioactive Contamination of Workers Using a Whole Body Counter

International Nuclear Information System (INIS)

Kong, T. Y.; Kim, H. G.; Lim, S. N.; Kim, H. J.; Jin, H. H.; Lee, S. G.; Park, S. C.

2006-01-01

A whole body counter (WBC) is used to identify and measure the radioactivity in the body of human beings in a nuclear power plant (NPP). In domestic NPPs, several whole body counters are in operation to monitor the internal radioactive contamination of workers. All workers take a whole body counting after radiation works if there is high possibility of radioactive contamination or the radioactivity is detected by portal monitoring. It is, however, found that the external contamination is occasionally estimated as the internal radioactive contamination. In this case, the worker is recommended to take showers for the decontamination of skin and take a whole body counting again. Although the detected radioactivity is reduced remarkably after several decontaminations, confirmed as the external contamination, it is determined finally as an internal contamination if the radioactivity is still detected in the body of worker. The amount of detected radioactivity can be much higher than that of the expected for this mistaken contamination since the radioisotopes attached to skin come to be close to the detectors of WBC. Finally, this makes not only the misjudgment of the external contamination as the internal contamination, but also the excessively conservative estimation of radioactive contamination. In this study, several experiments were carried out to set up the discrimination program between the internal and external radioactive contamination using the humanoid phantom and a whole body counter. After the analysis of experimental results, we found that the use of front and backside counts could be applied to the discrimination of the external contamination and the ratio of detected radioactivities between front and backside counts was more than about factor 2 for the external contamination

Identifying Strategies Programs Adopt to Meet Healthy Eating and Physical Activity Standards in Afterschool Programs.

Science.gov (United States)

Weaver, Robert G; Moore, Justin B; Turner-McGrievy, Brie; Saunders, Ruth; Beighle, Aaron; Khan, M Mahmud; Chandler, Jessica; Brazendale, Keith; Randell, Allison; Webster, Collin; Beets, Michael W

2017-08-01

The YMCA of USA has adopted Healthy Eating and Physical Activity (HEPA) Standards for its afterschool programs (ASPs). Little is known about strategies YMCA ASPs are implementing to achieve Standards and these strategies' effectiveness. (1) Identify strategies implemented in YMCA ASPs and (2) evaluate the relationship between strategy implementation and meeting Standards. HEPA was measured via accelerometer (moderate-to-vigorous-physical-activity [MVPA]) and direct observation (snacks served) in 20 ASPs. Strategies were identified and mapped onto a capacity building framework ( Strategies To Enhance Practice [STEPs]). Mixed-effects regression estimated increases in HEPA outcomes as implementation increased. Model-implied estimates were calculated for high (i.e., highest implementation score achieved), moderate (median implementation score across programs), and low (lowest implementation score achieved) implementation for both HEPA separately. Programs implemented a variety of strategies identified in STEPs. For every 1-point increase in implementation score 1.45% (95% confidence interval = 0.33% to 2.55%, p ≤ .001) more girls accumulated 30 min/day of MVPA and fruits and/or vegetables were served on 0.11 more days (95% confidence interval = 0.11-0.45, p ≤ .01). Relationships between implementation and other HEPA outcomes did not reach statistical significance. Still regression estimates indicated that desserts are served on 1.94 fewer days (i.e., 0.40 vs. 2.34) in the highest implementing program than the lowest implementing program and water is served 0.73 more days (i.e., 2.37 vs. 1.64). Adopting HEPA Standards at the national level does not lead to changes in routine practice in all programs. Practical strategies that programs could adopt to more fully comply with the HEPA Standards are identified.

Radioactivity measurements principles and practice

CERN Document Server

Mann, W B; Spernol, A

2012-01-01

The authors have addressed the basic need for internationally consistent standards and methods demanded by the new and increasing use of radioactive materials, radiopharmaceuticals and labelled compounds. Particular emphasis is given to the basic and practical problems that may be encountered in measuring radioactivity. The text provides information and recommendations in the areas of radiation protection, focusing on quality control and the precautions necessary for the preparation and handling of radioactive substances. New information is also presented on the applications of both traditiona

Rehabilitation of radioactive objects of Kirovo-Chepetsky chemical plant preliminary program of works

International Nuclear Information System (INIS)

Chesnokov, F.V.; Ivanov, O.P.; Pavlenko, V.I.; Semenov, S.G.; Stepanov, V.E.; Volkov, V.G.; Volkovich, A.G.; Zverkov, Yu.A.

2008-01-01

In 2007, the specialists of RRC Kurchatov Institute, jointly with MosNPO Radon, launched works on the radiation survey of radiation-contaminated objects and areas on the site of Kirovo-Chetetsky Chemical Plant (KCCP). This survey was launched with the object of subsequent development of the rehabilitation program and concept for buildings and storage sites left from shutdown uranium-processing facilities, as well as for sludge storage facilities and repositories of radioactive waste produced as a result of these facilities operation. Besides, radioactive contamination caused by the preceding operations involving radwaste and equipment contaminated at early stages of uranium hexafluoride (UHF) and tetrafluoride (UTF) processing technology mastering was detected in some spots at KCCP site. The radiation survey was performed in order to assess the amount of rehabilitation works, to identify the most critical objects and areas at KCCP site, and to develop the sequence of measures to be implemented in order to enhance the radiation safety of people living in the Kirov Region. (author)

SRS ES and H Standards Compliance Program Implementation Plan

International Nuclear Information System (INIS)

Hearn, W.H.

1993-01-01

On March 8, 1990, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 90-2 to the Secretary of Energy. This recommendation, based upon the DNFSB's initial review and evaluation of the content and implementation of standards relating to the design, construction, operations, and decommissioning of defense nuclear facilities of the U.S. Department of Energy (DOE), called for three actions: identification of specific standards that apply to design, construction, operation and decommissioning of DOE facilities; assessment of the adequacy of those standards for protecting public health and safety; and determination of the extent to which they have and are being implemented. The purpose of this Implementation Plan is to define the single program for all sitewide and facility 90-2 ES and H Standards Compliance efforts, which will satisfy the HQ Implementation Plan, avoid duplicate efforts, be as simple and achievable as possible, include cost-saving innovations, use a graded approach based on facility hazards and future needs of facilities, and support configuration control for facility requirements. The Defense Waste Processing Facility (DWPF) has been designated a pilot facility for the 90-2 program and has progressed with their facility program ahead of the site-level program. The DWPF, and other Government-Owned Contractor-Operated (GOCO) facilities that progress on an enhanced schedule, will serve as pilot facilities for the site-level program. The lessons learned with their requirement identifications, and their assessments of the adequacy of and their compliance with these requirements will be used to improve the efficiency of the site-level and subsequent programs

Directory of Certificates of Compliance for Radioactive-Materials Packages. Summary report of NRC approved quality assurance programs for radioactive material packages

International Nuclear Information System (INIS)

1983-01-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume I), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective December 31, 1982. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

The IAEA's role in safe radioactive waste management

International Nuclear Information System (INIS)

Flory, D.; Bruno, G.

2011-01-01

In accordance with its statute, IAEA is authorized to develop and maintain safety standards. This mission is reflected in the main programme of the IAEA on nuclear safety and security. In the field of the safety of radioactive waste management the IAEA is responsible for the delineation of a global safety regime to protect the public and the environment from harmful effects of ionizing radiation. This delineation is established on the basis of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, as well as on the development of safety standards for the management of all radioactive waste. The safety standards are the fruit of an international consensus on a high level of safety for the protection of people and environment. Safety guides are edited by IAEA, 7 volumes concern general safety requirements and 6 volumes deal with specific safety requirements (for instance for research reactors or for radioactive waste disposal facilities). Furthermore the IAEA assists Member States in the implementation of the safety standards and provides related services

Measurement of radioactivity in steel

International Nuclear Information System (INIS)

Wachtendonk, H.-J. von; Luengen, S.; Wilke, N.

1999-01-01

Even after the control of scrap deliveries, there remains a small risk that the radioactive contaminated scrap passes the detecting devices. Therefore, the chemical laboratory takes a role to measure each heat for the absence of artificial radioactive nuclides with a gamma spectrometer equipped with NaI-detector. As the measurement must be performed in sequence with the steel production process, the allowable time for the measurement is quite limited. On the other hand, there could be still some possibility that background radiation might be present as the samples may contain some natural radioactivity. The task is how to differentiate the nature of radioactivity between naturally remaining radioactivity within safe limit and artificial nuclides present in the sample at a low level even though a very small amount of radioactivity could be detected in short time in both cases. We have set the alarm limit to 0.1 Bq/g for Co-60 as indicating nuclide. This limit is set more than 4 s (s = standard deviation) from the average background radiation. Therefore, false alarms are quite improbable. Strategy: The NaI gamma spectrometer performs a gross gamma measurement but it can not differentiate the nature of the nuclides present. If the alarm limit is hurt, the sample is measured on a high resolution gamma spectrometer with Ge-detector for identification of the gamma emitting nuclides. Calibration: Even though no appropriate international standards are adapted and no commercial measuring equipment is commercially available, the desired standard should contain Co-60 in the order of 1 to 100 Bq/g. The presence of other gamma emitting nuclides is desirable. In the Workshop we will present how to surmount this difficulty. (author)

Determination of 40K radioactivity in the soil using energy dispersive X ray fluorescence spectrometer

International Nuclear Information System (INIS)

Lu Weiwei; Song Fuxiang; Zeng Liping; Lu Hongning

2012-01-01

The 40 K radioactive of' the pressed powder sample was determined by Epsilon 5 high-energy polarized energy dispersive X ray fluorescence (EDXRF) spectrometer. The correlation coefficient of the standard curve method was 0.9910, the precision was 2.98% and the relative deviation of the measurement standard samples was up to 6.40%, which showed that the precision and accuracy of the method were also good. Simultaneous measurement of seven soil samples using this method and γ-spectrometer were carried, the results of two analytical methods were compared using a paired t-test by SPSS program, which showed that there was no significant difference in the two sets of data, P>0.05. It indicated that EDXRF could be a potential simple method for analyzing 40 K radioactive in soil samples. (authors)

The deterministic computational modelling of radioactivity

International Nuclear Information System (INIS)

Damasceno, Ralf M.; Barros, Ricardo C.

2009-01-01

This paper describes a computational applicative (software) that modelling the simply radioactive decay, the stable nuclei decay, and tbe chain decay directly coupled with superior limit of thirteen radioactive decays, and a internal data bank with the decay constants of the various existent decays, facilitating considerably the use of program by people who does not have access to the program are not connected to the nuclear area; this makes access of the program to people that do not have acknowledgment of that area. The paper presents numerical results for typical problem-models

Development of an ASTM standard glass durability test, the Product Consistency Test (PCT), for high level radioactive waste glass

International Nuclear Information System (INIS)

Jantzen, C.M.; Bibler, N.E.; Beam, D.C.; Ramsey, W.G.

1994-01-01

The nation's first, and the world's largest, facility to immobilize high-level nuclear waste in durable borosilicate glass has started operation at the Savannah River Site (SRS) in Aiken, South Carolina. The product specifications on the glass wasteform produced in the Defense Waste Processing Facility (DWPF) required extensive characterization of the glass product before actual production began and for continued characterization during production. To aid in this characterization, a glass durability (leach) test was needed that was easily reproducible, could be performed remotely on highly radioactive samples, and could yield results rapidly. Several standard leach tests were examined with a variety of test configurations. Using existing tests as a starting point, the DWPF Product Consistency Test (PCT was developed in which crushed glass samples are exposed to 90 ± 2 degree C deionized water for seven days. Based on extensive testing, including a seven-laboratory round robin and confirmatory testing with radioactive samples, the PCT is very reproducible, yields reliable results rapidly, and can be performed in shielded cell facilities with radioactive samples

Proposal of a monitoring program of occupational exposure by incorporation of radioactive material for nuclear medicine services in the Caja Costarricense del Seguro Social

International Nuclear Information System (INIS)

Badilla Segura, Mirta

2013-01-01

A monitoring program of the occupational exposure by incorporation of radioactive material is proposed. Nuclear medicine services of the Caja Costarricense del Seguro Social (CCSS) are evaluated. The monitoring program is based on the provisions of the International Atomic Energy Agency and of study of nuclear medicine services of the CCSS. Radionuclides are determined for monitoring of the occupational exposure, according to the radioactive material that is worked in nuclear medicine services of the CCSS. The appropriate and alternative techniques are established for the monitoring of the occupational exposure by incorporation of radioactive material, depending on the type of radionuclide that is worked in nuclear medicine services. The worker occupationally exposed (TOE) should be subject of monitoring and how often should be realized the monitoring of the occupational exposure. The monitoring of the radiation by radioactive material must be applied to personnel working in radiopharmacies and the worker has carried out therapeutic procedures for handling of significant amounts of 13 1 I. The calculation of the committed effective dose is proposed by incorporation of radioactive material with the TOE [es

Radioactive waste management in Korea

International Nuclear Information System (INIS)

Lee, Ik Hwan

1997-01-01

In order to meet the increasing energy demand in Korea, continuous promotion of nuclear power program will be inevitable in the future. However, the use of nuclear energy eventually requires effective and reliable radioactive waste management. For the safe and economical management of radioactive waste, first of all, volume reduction is essentially required and hence the development of related technologies continuously be pursued. A site for overall radioactive waste management has to be secured in Korea. KEPCO-NETEC will improve public understanding by reinforcing PA and will maintain transparency of radioactive waste management. (author). 1 fig

The United States program for the safety assessment of geologic disposal of commercial radioactive wastes

International Nuclear Information System (INIS)

Claiborne, H.C.

1977-01-01

The safe disposal of commercial radioactive wastes in deep geologic formations is the goal of the National Waste Terminal Storage (NWTS) Program. Safety assessment begins with selection of a disposal site; that is, all geologic and hydrologic factors must indicate long-term stability of the formation and prospective isolation of wastes from circulating ground waters for hundreds of thousands of years. The long-term stability of each site under thermal loading must then be demonstrated by sophisticated rock mechanic analyses. Therefore, it can be expected that the sites that are chosen will effectively isolate the waste for a very long period of time. However, to help provide answers on the mechanisms and consequences of an unlikely breach in the integrity of the repository, a Waste Isolation Safety Assessment Program (WISAP) is studied. The overall objective of this program is an assessment of the safety associated with the long-term disposal of high-level radioactive waste in a geologic formation. This objective will be achieved by developing methods and generating data necessary to characterize the safety of generic geological waste disposal concepts, which are to be applied in the assessment of specific sites. It is expected that no one particular model will suffice. Both deterministic and probabilistic approaches will be used, and the entire spectrum of phenomena that could influence geologic isolation will be considered

Material Not Categorized As Waste (MNCAW) data report. Radioactive Waste Technical Support Program

Energy Technology Data Exchange (ETDEWEB)

Casey, C.; Heath, B.A.

1992-11-01

The Department of Energy (DOE), Headquarters, requested all DOE sites storing valuable materials to complete a questionnaire about each material that, if discarded, could be liable to regulation. The Radioactive Waste Technical Support Program entered completed questionnaires into a database and analyzed them for quantities and type of materials stored. This report discusses the data that TSP gathered. The report also discusses problems revealed by the questionnaires and future uses of the data. Appendices contain selected data about material reported.

Contribution to the study on and evaluation of radioactive waste generation in connection with the Brazilian Nuclear Program

International Nuclear Information System (INIS)

Melo, J.M.D. de.

1978-12-01

A general description is given of the causes of pollution in the nuclear industry. Emphasis was given to the radioactive pollution, especially radioactivity of fission products (FP). Physical mathematical models were established to calculate the FP activities 'in' and 'out' of the reactor and the yearly accumulated activities. To calculate FP activities 'in' reactor, all physical process of formation and destruction of nuclides were considered: nuclear fission; neutron absorption and radioactivity decay. The necessary input data were analysed and criticised. The specific activities of the discharged fuel were calculated and also their evolution outside reactor. The annual accumulation of FP activities were also calculated for the reference case: the Brazilian Nuclear Program for a 50 year horizon. The results were commented and specific discussions and comparison with other similar studies were made. (Author) [pt

Programs of recovery of radioactive wastes from the trenches and land decontamination of the radioactive waste storage center; Programas de recuperacion de los desechos radiactivos de las trincheras y de descontaminacion del predio del centro de almacenamiento de desechos radiactivos

Energy Technology Data Exchange (ETDEWEB)

Jimenez D, J.; Reyes L, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1999-06-15

In this report there are the decontamination program of the land of the Radioactive Waste Storage Center, the Program of Recovery of the radioactive waste of the trenches, the recovery of polluted bar with cobalt 60, the recovery of minerals and tailings of uranium and of earth with minerals and tailings of uranium, the recovery of worn out sealed sources and the waste recovery with the accustomed corresponding actions are presented. (Author)

Status policy and criteria for the remediation of sites with radioactive residues in China

International Nuclear Information System (INIS)

Yamin, Z.

1999-01-01

This paper introduces the status policy and criteria for remediation of sites with radioactive residues in China. We deal with the sites in difference patterns according to their circumstances. For the sites related with the decommissioning of the nuclear fuel cycle facilities, the programs for environmental restoration must be reviewed and approved by the State Environmental Protection Administration (SEPA). And the radioactive waste resulting from these facilities should be collected and eventually disposed of at the regional disposal repositories built by the country. For the sites related with use of radionuclides in medicine, research and industry, as well as the small scale extraction and processing of materials containing natural radionuclides, the provincial environmental authority is responsible for approving the restoration projects. These radioactive wastes should finally be sent to the special radioactive waste repositories built by the provincial environmental authorities. So far 21 waste repositories have been built in some provinces. More then 10 sites with radioactive residues have been restored. The standards for general public dose limit and soil residual radionuclides content have been established. (author)

Department of Energy Nuclear Energy Standards Program

International Nuclear Information System (INIS)

Silver, E.G.

1980-01-01

The policy with respect to the development and use of standards in the Department of Energy (DOE) programs concerned with maintaining and developing the nuclear option for the civilian sector (both in the form of the currently used light water reactors and for advanced concepts including the Liquid Metal Fast Breeder Reactor), is embodied in a Nuclear Standards Policy, issued in 1978, whose perspectives and philosophy are discussed

Standard Review Plan Maintenance Program implementing procedures document

International Nuclear Information System (INIS)

1996-11-01

The implementing Procedures Document (IPD) was developed by the Inspection Program Projects Branch, Office of Nuclear Reactor Regulation, with assistance from Pacific Northwest National Laboratory, for the Standard Review Plan Maintenance Program (SRP-MP). The SRP-MP was established to maintain the Standard Review Plan (SRP) on an on-going basis. The IPD provides guidance, including an overall approach and procedures, for SRP-MP tasks. The objective of the IPD is to ensure that modifications to SRP need to reflect current NRC requirements and guidance are identified and that a consistent methodology is used to develop and revise SRP sections

Office of Civilian Radioactive Waste Management: Support for university research and education

International Nuclear Information System (INIS)

Brownstein, A.B.

1990-01-01

The U.S. Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management (OCRWM) currently sponsors two programs that provide funding to universities and graduate students. The OCRWM graduate fellowship program and the OCRWM research program for historically black colleges and universities (HBCU) are designed to enhance the involvement of universities in the nation's high-level radioactive waste program. The specific goals of these programs are to (a) attract talented young scientists and engineers into OCRWM and OCRWM support contractor high-level radioactive waste management programs, (b) improve the quality of graduate education in disciplines directly related to high-level radioactive waste management, and (c) encourage university faculty to become involved in OCRWM mission-related activities

Radioactive waste management regulatory framework in Mexico

International Nuclear Information System (INIS)

Barcenas, M.; Mejia, M.

2001-01-01

The purpose of this paper is to present an overview of the current regulatory framework concerning the radioactive waste management in Mexico. It is intended to show regulatory historical antecedents, the legal responsibilities assigned to institutions involved in the radioactive waste management, the sources of radioactive waste, and the development and preparation of national standards for fulfilling the legal framework for low level radioactive waste. It is at present the most important matter to be resolved. (author)

Safety implications of standardized continuous quality improvement programs in community pharmacy.

Science.gov (United States)

Boyle, Todd A; Ho, Certina; Mackinnon, Neil J; Mahaffey, Thomas; Taylor, Jeffrey M

2013-06-01

Standardized continuous quality improvement (CQI) programs combine Web-based technologies and standardized improvement processes, tools, and expectations to enable quality-related events (QREs) occurring in individual pharmacies to be shared with pharmacies in other jurisdictions. Because standardized CQI programs are still new to community pharmacy, little is known about how they impact medication safety. This research identifies key aspects of medication safety that change as a result of implementing a standardized CQI program. Fifty-three community pharmacies in Nova Scotia, Canada, adopted the SafetyNET-Rx standardized CQI program in April 2010. The Institute for Safe Medication Practices (ISMP) Canada's Medication Safety Self-Assessment (MSSA) survey was administered to these pharmacies before and 1 year into their use of the SafetyNET-Rx program. The nonparametric Wilcoxon signed-rank test was used to explore where changes in patient safety occurred as a result of SafetyNETRx use. Significant improvements occurred with quality processes and risk management, staff competence, and education, and communication of drug orders and other information. Patient education, environmental factors, and the use of devices did not show statistically significant changes. As CQI programs are designed to share learning from QREs, it is reassuring to see that the largest improvements are related to quality processes, risk management, staff competence, and education.

Opinions of practitioners and program directors concerning accreditation standards for postdoctoral pediatric dentistry training programs.

Science.gov (United States)

Casamassimo, P S; Wilson, S

1999-01-01

This study was performed to assess opinions of program directors and practitioners about the importance and necessary numbers of experiences required by current accreditation standards for training of pediatric dentists. A 32-item questionnaire was sent to all program directors of ADA-accredited postdoctoral pediatric dentistry training programs and to a random sample of 10% of the fellow/active membership of the American Academy of Pediatric Dentistry. An overall response rate of 56% was obtained from the single mailing. Practitioners and program directors differed significantly (P dentistry: initiating and completing a research paper, biostatistics/epidemiology, and practice management. Program directors had little difficulty obtaining required experiences, and program dependence on Medicaid did not negatively affect quality of education. Practitioners and program directors agreed on the importance of most experiences and activities required by current accreditation standards.

Report to Congress on reassessment of the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

1989-11-01

In the Report of the House Committee on Appropriations (House Report No. 101-96) on the Energy and Water Development Appropriation Act, 1990 (P.L. 101-101), the Committee directed the Department of Energy (DOE) ''hor-ellipsis to submit a report within 60 days of enactment hor-ellipsis which describes in detail how the Department plans to respond to the Committee's hor-ellipsis concerns dealing with endemic schedule slips, problems in management structure, and lack of integrated contractor efforts.'' This report has been prepared in response to the above-mentioned Congressional directive. It is based on a comprehensive review that the Secretary of Energy has recently completed of the Civilian Radioactive Waste Management Program. The Secretary's review has led to the development of a three-point action plan for restructuring the program. This plan is explained in this report

Program for responsible and safe disposal of spent fuel elements and radioactive wastes (National disposal program)

International Nuclear Information System (INIS)

2015-01-01

The contribution covers the following topics: fundamentals of the disposal policy; amount of radioactive wastes and prognosis; disposal of radioactive wastes - spent fuel elements and wastes from waste processing, radioactive wastes with low heat production; legal framework of the nuclear waste disposal in Germany; public participation, cost and financing.

ARANO - a computer program for the assessment of radiological consequences of atmospheric radioactive releases

International Nuclear Information System (INIS)

Savolainen, I.; Vuori, S.

1980-09-01

A short description of the calculation possibilities, methods and of the structure of the computer code system ARANO is given, in addition to the input quide. The code can be employed in the calculation of environmental radiological consequences caused by radioactive materials released to atmosphere. Results can be individual doses for different organs at given distances from the release point, collective doses, numbers of persons exceeding given dose limits, numbers of casualties, areas polluted by deposited activity and losses of investments or production due to radioactive contamination. Both a case with a single release and atmospheric dispersion situation and a group of radioactive release and dispersions with discrete probability distributions can be considered. If the radioactive releases or the dispersion conditions are described by probability distributions, the program assesses the magnitudes of the specified effects in all combinations of the release and dispersion situations and then calculates the expectation values and the cumulative probability distributions of the effects. The vertical mixing in the atmosphere is described with a Ksub(Z)-model. In the lateral direction the plume is assumed to be Gaussian, and the release duration can be taken into account in the σsub(y)-values. External gamma dose from the release plume is calculated on the basis of a data file which has been created by 3-dimensional integration. Dose due to inhalation and due to gamma radiation from the contaminated ground are calculated by using appropriate dose conversion factors, which are collected into two mutually alternative block data subprograms. (author)

Model Regulations for the Use of Radiation Sources and for the Management of the Associated Radioactive Waste. Supplement to IAEA Safety Standards Series No. GS-G-1.5

International Nuclear Information System (INIS)

2015-01-01

IAEA Safety Standards Series No. GSR Part 1, Governmental, Legal and Regulatory Framework for Safety, requires that governments establish laws and statutes to make provisions for an effective governmental, legal and regulatory framework for safety. The framework for safety includes the establishment of a regulatory body. The regulatory body has the authority and responsibility for promulgating regulations, and for preparing their implementation. This publication provides advice on an appropriate set of regulations covering all aspects of the use of radiation sources and the safe management of the associated radioactive waste. The regulations provide the framework for the regulatory requirements and conditions to be incorporated into individual authorizations for the use of radiation sources in industry, medical facilities, research and education and agriculture. The regulations also establish criteria to be used for assessing compliance. This publication allows States to appraise the adequacy of their existing regulations and regulatory guides, and can be used as a reference for those States developing regulations for the first time. The regulations set out in this publication will need to be adapted to take account of local conditions, technical resources and the scale of facilities and activities in the State. The set of regulations in this publication is based on the requirements established in the IAEA safety standards series, in particular in IAEA Safety Standards Series No. GSR Part 3 (Interim), Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, in IAEA Safety Standards Series No. GSR Part 5, Predisposal Management of Radioactive Waste, and in IAEA Safety Standards Series No. SSR-5, Disposal of Radioactive Waste. They are also derived from the Code of Conduct of the Safety and Security of Radiation Sources and the Guidance on the Import and Export of Radioactive Sources. This publication allows States to appraise the

Model Regulations for the Use of Radiation Sources and for the Management of the Associated Radioactive Waste. Supplement to IAEA Safety Standards Series No. GS-G-1.5

International Nuclear Information System (INIS)

2013-12-01

IAEA Safety Standards Series No. GSR Part 1, Governmental, Legal and Regulatory Framework for Safety, requires that governments establish laws and statutes to make provisions for an effective governmental, legal and regulatory framework for safety. The framework for safety includes the establishment of a regulatory body. The regulatory body has the authority and responsibility for promulgating regulations, and for preparing their implementation. This publication provides advice on an appropriate set of regulations covering all aspects of the use of radiation sources and the safe management of the associated radioactive waste. The regulations provide the framework for the regulatory requirements and conditions to be incorporated into individual authorizations for the use of radiation sources in industry, medical facilities, research and education and agriculture. The regulations also establish criteria to be used for assessing compliance. This publication allows States to appraise the adequacy of their existing regulations and regulatory guides, and can be used as a reference for those States developing regulations for the first time. The regulations set out in this publication will need to be adapted to take account of local conditions, technical resources and the scale of facilities and activities in the State. The set of regulations in this publication is based on the requirements established in the IAEA safety standards series, in particular in IAEA Safety Standards Series No. GSR Part 3 (Interim), Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, in IAEA Safety Standards Series No. GSR Part 5, Predisposal Management of Radioactive Waste, and in IAEA Safety Standards Series No. SSR-5, Disposal of Radioactive Waste. They are also derived from the Code of Conduct of the Safety and Security of Radiation Sources and the Guidance on the Import and Export of Radioactive Sources. This publication allows States to appraise the

USL/DBMS NASA/PC R and D project C programming standards

Science.gov (United States)

Dominick, Wayne D. (Editor); Moreau, Dennis R.

1984-01-01

A set of programming standards intended to promote reliability, readability, and portability of C programs written for PC research and development projects is established. These standards must be adhered to except where reasons for deviation are clearly identified and approved by the PC team. Any approved deviation from these standards must also be clearly documented in the pertinent source code.

Approval of radioactive consumer goods

International Nuclear Information System (INIS)

Paynter, R.A.

1992-01-01

The 1980 Euratom Directive obliges the UK to draw up a system of prior authorization for the use of radioactive substances in a range of consumer products, and the Government intends to make regulations to fulfil the requirements of the Directive. These regulations will empower NRPB to approve such products prior to their supply to the public. In this brief article, the NRPB reviews the criteria against which to consider any proposed use of radioactive substances, considers radiological production standards for products and discusses the questions of the labelling of radioactive consumer goods. (UK)

Avoiding dual regulation of the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

Vlahakis, J.G.; Palabrica, R.J.

1994-01-01

The Office of Civilian Radioactive Waste Management (RW) has successfully negotiated the issuance of a Department of Energy (DOE) Headquarters Order that provides for exemption of RW from certain DOE directives. This exemption assures precedence of Nuclear Regulatory Commission (NRC) requirements in radiation protection, nuclear safety (including quality assurance), and safeguards and security of nuclear materials. This Order is necessary to avoid the unwarranted cost and potential confusion resulting from dual regulation of RW facilities and activities by DOE and NRC. Development of this Order involved a systematic review of applicable DOE directives and NRC requirements to identify potential overlaps and duplication when applied to the RW program. Following this review and extensive negotiations with appropriate DOE organizations responsible for directives development, this Order was issued as HQ 1321.1 on December 22, 1993

Management of radioactive wastes in China

International Nuclear Information System (INIS)

Pan Ziqiang

1994-01-01

The policy and principles on management of radioactive wastes are stipulated. Cement solidification and bituminization unit has come into trial run. Solid radioactive waste is stored in tentative storage vault built in each of nuclear facilities. Seventeen storages associated with applications of nuclear technology and radioisotopes have been built for provinces. Disposal of low and intermediate level radioactive wastes pursues the policy of 'regional disposal'. Four repositories have been planned to be built in northwest, southwest, south and east China respectively. A program for treatment and disposal of high level radioactive waste has been made

Regulatory requirements on management of radioactive material safe transport in China

International Nuclear Information System (INIS)

Chu, C.

2016-01-01

Since 1980s, the IAEA Regulation for safe transport of radioactive material was introduced into China; the regulatory system of China began with international standards, and walked towards the institutionalized. In 2003 the National People’s Congress (NPC) promulgated “the Act on the Prevention of Radioactive Pollution of the People's Republic of China”. In 2009 “Regulation for the Safe Transport of Radioactive Material” (Referred to “Regulation”) was promulgated by the State Council. Subsequently, the National Nuclear Safety Administration (NNSA) began to formulate executive detailed department rules, regulations guidelines and standards. The present system of acts, regulations and standards on management of safe transport of radioactive material in China and future planning were introduced in this paper. Meanwhile, the paper described the specific administration requirements of the Regulation on classification management of radioactive materials, license management of transport packaging including design, manufacture and use, licensing management of transport activities and the provisions of illegal behaviors arising in safe transport of radioactive material. (author)

Russian Containers for Transportation of Solid Radioactive Waste

International Nuclear Information System (INIS)

Petrushenko, V. G.; Baal, E. P.; Tsvetkov, D. Y.; Korb, V. R.; Nikitin, V. S.; Mikheev, A. A.; Griffith, A.; Schwab, P.; Nazarian, A.

2002-01-01

The Russian Shipyard ''Zvyozdochka'' has designed a new container for transportation and storage of solid radioactive wastes. The PST1A-6 container is cylindrical shaped and it can hold seven standard 200-liter (55-gallon) drums. The steel wall thickness is 6 mm, which is much greater than standard U.S. containers. These containers are fully certified to the Russian GOST requirements, which are basically identical to U.S. and IAEA standards for Type A containers. They can be transported by truck, rail, barge, ship, or aircraft and they can be stacked in 6 layers in storage facilities. The first user of the PST1A-6 containers is the Northern Fleet of the Russian Navy, under a program sponsored jointly by the U.S. DoD and DOE. This paper will describe the container design and show how the first 400 containers were fabricated and certified

The program RADLST [Radiation Listing

International Nuclear Information System (INIS)

Burrows, T.W.

1988-01-01

The program RADLST (Radiation Listing) is designed to calculate the nuclear and atomic radiations associated with the radioactive decay of nuclei. It uses as its primary input nuclear decay data in the Evaluated Nuclear Structure Data File (ENSDF) format. The code is written in FORTRAN 77 and, with a few exceptions, is consistent with the ANSI standard. 65 refs

Low-level radioactive waste program of the US Geological Survey - in transition

International Nuclear Information System (INIS)

Fischer, J.N.

1983-01-01

In 1983, the US Geological Survey will publish final reports of geohydrologic investigations at five commercial low-level, radioactive-waste burial sites in the United States. These reports mark the end of the first phase of the US Geological Survey program to improve the understanding of earth-science principles related to the effective disposal of low-level wastes. The second phase, which was initiated in 1981, is being developed to address geohydrologic issues identified as needing greater attention based upon results of the first-phase site studies. Specific program elements include unsaturated-zone hydrology, geochemistry, clay mineralogy, surface geophysical techniques, and model development and testing. The information and expertise developed from these and previous studies will allow the US Geological Survey to provide sound technical assistance to State low-level waste compacts, the Department of Energy, the Nuclear Regulatory Commission, and the Environmental Protection Agency. 11 references

Design of benign matrix drums for the non-destructive assay performance demonstration program for the National TRU Program

International Nuclear Information System (INIS)

Becker, G.K.

1996-09-01

Regulatory compliance programs associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program) require the collection of waste characterization data of known quality to support repository performance assessment, permitting, and associated activities. Blind audit samples, referred to as PDP (performance demonstration program) samples, are devices used in the NDA PDP program to acquire waste NDA system performance data per defined measurement routines. As defined under the current NDA PDP Program Plan, a PDP sample consists of a DOT 17C 55-gallon PDP matrix drum configured with insertable radioactive standards, working reference materials (WRMs). The particular manner in which the matrix drum and PDP standard(s) are combined is a function of the waste NDA system performance test objectives of a given cycle. The scope of this document is confined to the design of the PDP drum radioactive standard internal support structure, the matrix type and the as installed configuration. The term benign is used to designate a matrix possessing properties which are nominally non-interfering to waste NDA measurement techniques. Measurement interference sources are technique specific but include attributes such as: high matrix density, heterogeneous matrix distributions, matrix compositions containing high moderator/high Z element concentrations, etc. To the extent practicable the matrix drum design should not unduly bias one NDA modality over another due to the manner in which the matrix drum configuration manifests itself to the measurement system. To this end the PDP matrix drum configuration and composition detailed below is driven primarily by the intent to minimize the incorporation of matrix attributes known to interfere with fundamental waste NDA modalities, i.e. neutron and gamma based techniques

Radioactive-site-remediation technologies seminar. Speaker slide copies

International Nuclear Information System (INIS)

1992-06-01

The contents of this report include the following: approaches to sampling radioactive heterogeneous waste; soil characterization methodology for determining application of soil washing; vorce (volume reduction/chemical extraction) program; treatment of radioactive compounds in water; polymer solidification of low-level radioactive, hazardous, and mixed waste; in situ vitrification of soils contaminated with radioactive and mixed wastes; decontamination of contaminated buildings; incineration of radioactive waste; in situ stabilization/solidification with cement-based grouts; environmental restoration and waste management; removal of contaminants from soils by electrokinetics; and treatment, compaction, and disposal of residual radioactive waste

Implementation of ISO 28218 quality system in the laboratory of body radioactivity counter CIEMAT

International Nuclear Information System (INIS)

Navarro Amaro, J. F.; Perez Lopez, B.; Lopez Ponte, M. A.; Perez Jimenez, C.

2011-01-01

The laboratory of body radioactivity counter has implemented IS0 28218 standard Performance Criteria for Radio bioassay in all measured in vivo techniques of internal contamination in the human organism in monitoring programs defined by the Personal Dosimetry Service Internal CIEMAT. The application of this rule in the laboratory's quality system is essential to meet the technical requirements of the standard IS0/IEC 17025 with the purpose of obtaining ENAC accreditation as a testing laboratory and calibration within the framework of the accreditation of Service CIEMAT Radiation Dosimetry. (Author)

The basics in transportation of low-level radioactive waste

International Nuclear Information System (INIS)

Allred, W.E.

1998-06-01

This bulletin gives a basic understanding about issues and safety standards that are built into the transportation system for radioactive material and waste in the US. An excellent safety record has been established for the transport of commercial low-level radioactive waste, or for that matter, all radioactive materials. This excellent safety record is primarily because of people adhering to strict regulations governing the transportation of radioactive materials. This bulletin discusses the regulatory framework as well as the regulations that set the standards for packaging, hazard communications (communicating the potential hazard to workers and the public), training, inspections, routing, and emergency response. The excellent safety record is discussed in the last section of the bulletin

Environmental radioactivity in Canada - 1982

International Nuclear Information System (INIS)

Tracey, B.L.

1984-01-01

The radiological surveillance program of the Department of National Health and Welfare is conducted for the purpose of determining levels of environmental radioactivity in Canada and assessing the resulting population exposures. Special investigations were carried out during 1982 on metabolism of natural radionuclides and on the accumulation of radon in energy-efficient homes. The pre-operational phase of the monitoring program at the Point Lepreau Nuclear Generating Station was completed. Dose commitments have been estimated for the ongoing natural radioactivity, fallout and reactor studies. All measurements made during the year are below the limits recommended by the International Commission on Radiological Protection

Doses from radioactive methane

International Nuclear Information System (INIS)

Phipps, A.W.; Kendall, G.M.; Fell, T.P.; Harrison, J.D.

1990-01-01

A possible radiation hazard arises from exposure to methane labelled with either a 3 H or a 14 C nuclide. This radioactive methane could be released from a variety of sources, e.g. land burial sites containing radioactive waste. Standard assumptions adopted for vapours would not apply to an inert alkane like methane. This paper discusses mechanisms by which radioactive methane would irradiate tissues and provides estimates of doses. Data on skin thickness and metabolism of methane are discussed with reference to these mechanisms. It is found that doses are dominated by dose from the small fraction of methane which is inhaled and metabolised. This component of dose has been calculated under rather conservative assumptions. (author)

Low-level Radioactivity Measurements

International Nuclear Information System (INIS)

Hurtgen, C.

2002-01-01

The objectives of the research performed in the area of low-level radioactivity measurements are (1) to maintain and develop techniques for the measurement of low-level environmental and biological samples, (2) to measure these samples by means of low-background counters (liquid scintillators, proportional counters, ZnS counters, alpha spectrometry), (3) to support and advise the nuclear and non-nuclear industry on problems of radioactive contamination and low-level radioactivity measurements; (4) to maintain and improve the quality assurance system according to the ISO17025 standard; and (5) to assess the internal dose from occupational intakes of radionuclides of workers of the nuclear industry. Progress and achievements in these areas in 2001 are reported

Low-level Radioactivity Measurements

International Nuclear Information System (INIS)

Hurtgen, C.

2001-01-01

The objectives of the research performed in the area of low-level radioactivity measurements are (1) to maintain and develop techniques for the measurement of low-level environmental and biological samples, (2) to measure these samples by means of low-background counters (liquid scintillators, proportional counters, ZnS counters, alpha spectrometry), (3) to support and advice the nuclear and non-nuclear industry in matters concerning radioactive contamination and/or low-level radioactivity measurements; (4) to maintain the quality assurance system according to the EN45001/ISO17025 standard; and (5) to assess the internal dose from occupational intakes of radionuclides of workers of the nuclear industry. Progress and achievements in these areas in 2000 are reported

Radioactive waste management: a utility view

International Nuclear Information System (INIS)

Draper, E.L.

1982-01-01

The management of radioactive waste continues to be a matter of public concern and discussion. There is broad agreement among members of the technical community that the various types of waste radioactive species can be managed without jeopardizing public health and safety. Despite this consensus, one of the major reasons cited by opponents of commercial nuclear power for their opposition is the lack of a fully deployed waste management program. Such a program has been suggested but implementation is not yet complete. It is essential that a program be undertaken so as to dispel the impression that past inaction on waste disposal represents an inability to deal safely with wastes

Management of Radioactive Wastes in Developing Countries

International Nuclear Information System (INIS)

Abdel Ghani, A.H.

1999-01-01

The management of radioactive wastes is one area of increasing interest especially in developing countries having more and more activities in the application of radioisotopes in medicine, research and industry. For a better understanding of radioactive waste management in developing countries this work will discuss the following items:Classification of countries with respect to waste management programs. Principal Radionuclides used in medicine, biological research and others and the range of radioactivity commonly used. Estimation of radioactive waste volumes and activities. Management of liquid wastes Collection. Treatment. Management of small volumes of organic liquid waste. Collection Treatment. Packaging and storage of radioactive wastes

MANAGEMENT OF RADIOACTIVE WASTES IN CHINA

Institute of Scientific and Technical Information of China (English)

潘自强

1994-01-01

The policy and principles on management of radioactive wastes are stipulated.Cement solidification and bituminization unit has come into trial run.Solid radioactive waste is stored in tentative storage vault built in each of nuclear facilities.Seventeen storages associated with applications of nuclear technology and radioisotopes have been built for provinces.Disposal of low and intermediate level radioactive wastes pursues the policy of “regional disposal”.Four repositories have been planned to be built in northwest.southwest,south and east China respectively.A program for treatment and disposal of high level radioactive waste has been made.

The IAEA's high level radioactive waste management programme

International Nuclear Information System (INIS)

Saire, D.E.

1994-01-01

This paper presents the different activities that are performed under the International Atomic Energy Agency's (IAEA) high level radioactive waste management programme. The Agency's programme is composed of five main activities (information exchange, international safety standards, R ampersand D activities, advisory services and special projects) which are described in the paper. Special emphasis is placed on the RADioactive WAste Safety Standards (RADWASS) programme which was implemented in 1991 to document international consensus that exists on the safe management of radioactive waste. The paper also raises the question about the need for regional repositories to serve certain countries that do not have the resources or infrastructure to construct a national repository

Management Aspects of Implementing the New Effluent Air Monitoring Standard

International Nuclear Information System (INIS)

Glissmeyer, John A.; Davis, William E.

2000-01-01

The revision to ANSI/HPS N13.1,'Sampling and Monitoring Releases of Airborne Radioactive substances From the Stacks and Ducts of Nuclear Facilities,' went into effect in January 1999 - replacing the 1969 version of the standard. There are several significant changes from the old version of the standard. The revised standard provides a new paradigm where representative air samples can be collected by extracting the sample from a single point in air streams where the contaminants are well mixed. The revised standard provides specific performance criteria and requirements for the various air sampling processes - program structure, sample extraction, transport, collection, effluent and sample flow measurement, and quality assurance. A graded approach to sampling is recommended with more stringent requirements for stacks with a greater potential to emit. These significant changes in the standard will impact the air monitoring programs at some sites and facilities. The impacts on the air monitor design, operation, maintenance, and quality control processes are discussed.

Classification of Radioactive Waste. General Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-11-15

This publication is a revision of an earlier Safety Guide of the same title issued in 1994. It recommends revised waste management strategies that reflect changes in practices and approaches since then. It sets out a classification system for the management of waste prior to disposal and for disposal, driven by long term safety considerations. It includes a number of schemes for classifying radioactive waste that can be used to assist with planning overall national approaches to radioactive waste management and to assist with operational management at facilities. Contents: 1. Introduction; 2. The radioactive waste classification scheme; Appendix: The classification of radioactive waste; Annex I: Evolution of IAEA standards on radioactive waste classification; Annex II: Methods of classification; Annex III: Origin and types of radioactive waste.

Classification of Radioactive Waste. General Safety Guide

International Nuclear Information System (INIS)

2009-01-01

This publication is a revision of an earlier Safety Guide of the same title issued in 1994. It recommends revised waste management strategies that reflect changes in practices and approaches since then. It sets out a classification system for the management of waste prior to disposal and for disposal, driven by long term safety considerations. It includes a number of schemes for classifying radioactive waste that can be used to assist with planning overall national approaches to radioactive waste management and to assist with operational management at facilities. Contents: 1. Introduction; 2. The radioactive waste classification scheme; Appendix: The classification of radioactive waste; Annex I: Evolution of IAEA standards on radioactive waste classification; Annex II: Methods of classification; Annex III: Origin and types of radioactive waste

The Radioactive Ion Beams in Brazil (RIBRAS) facility. Description, program, main results, future plans

Science.gov (United States)

Lépine-Szily, A.; Lichtenthäler, R.; Guimarães, V.

2014-08-01

RIBRAS (Radioactive Ion Beams in Brazil) is a facility installed at the Institute of Physics of the University of São Paulo (IFUSP), Brazil. The RIBRAS system consists of two superconducting solenoids and uses the "in-flight method" to produce radioactive ion beams using the primary beam provided by the 8UD Pelletron Tandem of IFUSP. The ion beams produced so far by RIBRAS are 6He, 8Li, 7Be, 10Be, 8B, 12B with intensities that can vary from 104 to 106 pps. Initially the experimental program covered the study of elastic and inelastic scattering with the objective to study the interaction potential and the reaction mechanisms between weakly bound (RIB) and halo (6He and 8B projectiles on light, medium and heavy mass targets. With highly purified beams, the study of resonant elastic scattering and resonant transfer reactions, using inverse kinematics and thick targets, has also been included in our experimental program. Also, transfer reactions of astrophysical interest and fusion reactions induced by halo nuclei are part of the near-future research program. Our recent results on elastic scattering, alpha-particle production and total reaction cross sections, as well as the resonant elastic and transfer reactions, are presented. Our plans for the near future are related to the installation of a new beam line and a cave for gamma-ray detection. We intend to place in operation a large area neutron detector available in our laboratory. The long-range plans could be the move of the RIBRAS system to the more energetic beam line of the LINAC post-accelerator (10MeV/nucleon primary beams) still in construction in our laboratory.

Presence of radioactivity in a sewage system: a proposal for radioactivity control

International Nuclear Information System (INIS)

Serradell, Vicente; Ballesteros, Luisa; Ortiz, Josefina

2008-01-01

Most hospitals use radioisotopes in diagnostics and to a lesser extent in therapy. The liquid residues thus generated are usually subjected to treatment before being discharged into the sewage system. Nevertheless, a certain amount of these residues escape from the treatment system and are poured directly into the sewer. In addition, other radioactive products used for research and industrial purposes may also be disposed of in the same way. The waste waters in many sewage systems can therefore be expected to be radiologically contaminated and the need for at least a basic control system in such situations seems obvious. When designing a procedure to measure radioactivity, certain conditions should be borne in mind: 1) The control program has to be simple and inexpensive; 2) Samples must be taken from the appropriate places; 3) Short life radionuclides will probably be present in significant amounts, so that specific recipes should be prepared; 4) Iodine is also frequently present. Special precautions should be taken to keep it in solution. In recent years, the Environmental Radioactivity Laboratory of the Universidad Politecnica de Valencia (Spain) has carried out a series of tests on the Valencia city sewage system and sewage treatment plant in order to design a permanent program to control radioactive contamination of the city's sewage system. This paper presents a proposal which we believe can provide the answer to this problem. (author)

Bases for safety of shipping radioactive materials

International Nuclear Information System (INIS)

Frejman, Eh.S.; Shchupanovskij, V.D.; Kaloshin, V.M.

1986-01-01

Classification is presented and design of packaging containers for radioactive substance shipment is described. Standard documents and the main activities related to the shipment radiation safety provision are considered. Practical recommendations on environment and personnel protection during radioactive cargo shipment by all types of vehicles are presented

NPP radioactive waste processing and solidification

International Nuclear Information System (INIS)

Nikiforov, A.S.; Polyakov, A.S.; Zakharova, K.P.

1983-01-01

The problems of proce-sing NPP intermediate level- and low-level liquid radioactive wastes (LRW) are considered. Various methods are compared of LWR solidification on the base of bituminization, cement grouting and inclusion into synthetic resins. It is concluded that the considered methods ensure radioactive radionuclides effluents into open hydronetwork at the level below the sanitary, standards

10 CFR 72.144 - Quality assurance program.

Science.gov (United States)

2010-01-01

... quality history and degree of standardization of the item. (d) The licensee, applicant for a license... 10 Energy 2 2010-01-01 2010-01-01 false Quality assurance program. 72.144 Section 72.144 Energy... NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE Quality...

Where is New York State relative to cleanup standards for soils contaminated with radioactive materials

International Nuclear Information System (INIS)

Merges, P.J.

1995-01-01

In September 1993, New York State adopted a cleanup guideline for radioactively contaminated sites being remediated for unrestricted release. This paper reviews this cleanup guideline and discusses its implementation by Bureau of Radiation staff. A cleanup guideline (1) has been adopted by the State of New York which applies to residual radiological contamination on sites undergoing remediation for unrestricted use. The guideline is flexible and allows for alternative site cleanup approaches. The application of this guidance by radiation control program staff is discussed herein. There may be a need to revisit properties that were felt to be open-quotes cleanclose quotes previously - but fail to meet the new guidance

Standard guide for radioactive pathway methodology for release of sites following decommissioning

International Nuclear Information System (INIS)

Anon.

1989-01-01

The purpose of this guide is to provide guidance in determining site-specific conversion factors for translating between dose limits and residual radioactive contamination levels on equipment structures, and land areas. This guide is to serve as a guide to acceptable methodology for translating the yet to be determined dose limits into allowable levels of residual radioactive materials that can be left at a site following decommissioning

DOE standard: The Department of Energy Laboratory Accreditation Program administration

International Nuclear Information System (INIS)

1998-12-01

This technical standard describes the US Department of Energy Laboratory Accreditation Program (DOELAP), organizational responsibilities, and the accreditation process. DOELAP evaluates and accredits personnel dosimetry and radiobioassay programs used for worker monitoring and protection at DOE and DOE contractor sites and facilities as required in Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection. The purpose of this technical standard is to establish procedures for administering DOELAP and acquiring accreditation

Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Washington

International Nuclear Information System (INIS)

2003-01-01

This ''Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement'' (HSW EIS) covers three primary aspects of waste management at Hanford--waste treatment, storage, and disposal. It also addresses four kinds of solid waste--low-level waste (LLW), mixed (radioactive and chemically hazardous) low-level waste (MLLW), transuranic (TRU) waste, and immobilized low-activity waste (ILAW). It fundamentally asks the question: how should we manage the waste we have now and will have in the future? This EIS analyzes the impacts of the LLW, MLLW, TRU waste, and ILAW we currently have in storage, will generate, or expect to receive at Hanford. The HSW EIS is intended to help us determine what specific facilities we will continue to use, modify, or construct to treat, store, and dispose of these wastes (Figure S.1). Because radioactive and chemically hazardous waste management is a complex, technical, and difficult subject, we have made every effort to minimize the use of acronyms (making an exception for our four waste types listed above), use more commonly understood words, and provide the ''big picture'' in this summary. An acronym list, glossary of terms, and conversions for units of measure are provided in a readers guide in Volume 1 of this EIS

10 CFR 20.1005 - Units of radioactivity.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Units of radioactivity. 20.1005 Section 20.1005 Energy NUCLEAR REGULATORY COMMISSION STANDARDS FOR PROTECTION AGAINST RADIATION General Provisions § 20.1005 Units of radioactivity. For the purposes of this part, activity is expressed in the special unit of...

Strategic program for deep geological disposal of high level radioactive waste in China

International Nuclear Information System (INIS)

Wang Ju

2004-01-01

A strategic program for deep geological disposal of high level radioactive waste in China is proposed in this paper. A '3-step technical strategy': site selection and site characterization-site specific underground research laboratory-final repository, is proposed for the development of China's high level radioactive waste repository. The activities related with site selection and site characterization for the repository can be combined with those for the underground research laboratory. The goal of the strategy is to build China's repository around 2040, while the activities can be divided into 4 phases: 1) site selection and site characterization; 2) site confirmation and construction of underground research laboratory, 3) in-situ experiment and disposal demonstration, and 4) construction of repository. The targets and tasks for each phase are proposed. The logistic relationship among the activities is discussed. It is pointed out that the site selection and site characterization provide the basis for the program, the fundamental study and underground research laboratory study are the key support, the performance assessment plays a guiding role, while the construction of a qualified repository is the final goal. The site selection can be divided into 3 stages: comparison among pre-selected areas, comparison among pre-selected sites and confirmation of the final site. According to this strategy, the final site for China's underground research laboratory and repository will be confirmed in 2015, where the construction of an underground laboratory will be started. In 2025 the underground laboratory will have been constructed, while in around 2040, the construction of a final repository is to be completed

Italian Antarctic Research Program: environmental radioactivity survey around the Italian base (1987-1991) Terra Nova Bay - Ross Sea region

Energy Technology Data Exchange (ETDEWEB)

Tubertini, O.; Bettoli, M.G.; Cantelli, L. [Bologna Univ. (Italy)] [and others

1995-12-31

Investigations have been carried out by the Italian Antartic Research Program to determine the natural and artificial radioactivity levels of both the marine and terrestrial environments. Also, natural and anthropogenic fluxes of aerosol particles onto the Antartic surface have been examined. (Author).

Italian Antarctic Research Program: environmental radioactivity survey around the Italian base (1987-1991) Terra Nova Bay - Ross Sea region

International Nuclear Information System (INIS)

Tubertini, O.; Bettoli, M.G.; Cantelli, L.

1995-01-01

Investigations have been carried out by the Italian Antartic Research Program to determine the natural and artificial radioactivity levels of both the marine and terrestrial environments. Also, natural and anthropogenic fluxes of aerosol particles onto the Antartic surface have been examined. (Author)

Directory of Certificates of Compliance for Radioactive Materials Packages. Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages. Volume 3. Revision 5

International Nuclear Information System (INIS)

1985-10-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume I), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1985. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory. Shipments of radioactive material utilizing these packages must be in accordance with the provisions of 49 CFR Section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with a Nuclear Regulatory Commission approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR Section 71.12 does not authorize the receipt, possession, use or transfer of byproduct, source or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, or 70

Siting the high level radioactive waste repository in the United States

International Nuclear Information System (INIS)

Tourtellotte, J.

1992-01-01

For more than twenty-five years after the National Academy of Science issued its 1957 report recommending a Mined Geologic Disposal System (''MGDS'') for high level radioactive waste, no substantial progress was made in selecting and siting a repository. The United States Congress attempted to give substantive and procedural direction to the program in the Nuclear Waste Policy Act of 1982. Seeing that very little had been accomplished some five years later, Congress gave further direction and tentatively selected a single site, Yucca Mountain in Nevada, in the Nuclear Waste Policy Act Amendments of 1987. Selection of the Yucca Mountain site created a political conflict between federal and state authorities. Until recently, that conflict stalled the site characterization and evaluation program. Standards development under a polycentric regulatory regime has also been slow and has created a number of technical, legal and policy controversies. The Environmental Protection Agency (EPA), charged with setting radiation protection rules, may be developing regulatory standards which are technically unachievable and, therefore, legally unprovable in a licensing proceeding. The Nuclear Regulatory Commission (NRC), having the responsibility for licensing and setting performance objectives, may be taking an overly conservative approach. This approach could seriously impact the cost and may preclude the ability to reach an affirmative finding on license issuance. The Department of Energy (DOE) has responsibility for siting, construction and operation of the repository. In so doing, DOE must apply both EPA and NRC standards. To the extent that EPA and NRC standards are untimely, poorly defined, unrealistic, inconsistent, and technically or legally unsound, DOE may be forestalled from fulfilling its responsibilities. The US must rethink its approach to siting the high level radioactive waste repository and take realistic, timely action to preserve the nuclear option. (Author)

A method for developing standard patient education program

DEFF Research Database (Denmark)

Lura, Carolina Bryne; Hauch, Sophie Misser Pallesgaard; Gøeg, Kirstine Rosenbeck

2018-01-01

for developing standard digital patient education programs for patients in self-administration of blood samples drawn from CVC. The Design Science Research Paradigm was used to develop a digital patient education program, called PAVIOSY, to increase patient safety during execution of the blood sample collection...... of the educational patient system, health professionals must be engaged early in the development of content and design phase....

Radioactivity analysis of food and accuracy control

International Nuclear Information System (INIS)

Ota, Tomoko

2013-01-01

From the fact that radioactive substances have been detected from the foods such as agricultural and livestock products and marine products due to the accident of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company, the Ministry of Health, Labour and Welfare stipulated new standards geared to general foods on radioactive cesium by replacing the interim standards up to now. Various institutions began to measure radioactivity on the basis of this instruction, but as a new challenge, a problem of the reliability of the data occurred. Therefore, accuracy control to indicate the proof that the quality of the data can be retained at an appropriate level judging from an objective manner is important. In order to consecutively implement quality management activities, it is necessary for each inspection agency to build an accuracy control system. This paper introduces support service, as a new attempt, for establishing the accuracy control system. This service is offered jointly by three organizations, such as TUV Rheinland Japan Ltd., Japan Frozen Foods Inspection Corporation, and Japan Chemical Analysis Center. This service consists of the training of radioactivity measurement practitioners, proficiency test for radioactive substance measurement, and personal authentication. (O.A.)

Assessment of the Japanese Energy Efficiency Standards Program

Directory of Open Access Journals (Sweden)

Jun Arakawa

2015-03-01

Full Text Available Japanese energy efficiency standards program for appliances is a unique program which sets and revises mandatory standards based on the products of the highest energy efficiency on the markets. This study assessed the cost-effectiveness of the standard settings for air conditioner as a major residential appliance or typical example in the program. Based on analyses of empirical data, the net costs and effects from 1999 to 2040 were estimated. When applying a discount rate of 3%, the cost of abating CO2 emissions realized through the considered standards was estimated to be -13700 JPY/t-CO2. The sensitivity analysis, however, showed the cost turns into positive at a discount rate of 26% or higher. The authors also revealed that the standards’ “excellent” cost-effectiveness largely depends on that of the 1st standard setting, and the CO2 abatement cost through the 2nd standard was estimated to be as high as 26800 JPY/t-CO2. The results imply that the government is required to be careful about the possible economic burden imposed when considering introducing new, additional standards.

Radioactive waste management in perspective

International Nuclear Information System (INIS)

1996-01-01

This report drafted by the Nuclear Energy Agency (NEA) deals with the basic principles and the main stages of radioactive waste management. The review more precisely focuses on what relates to environment protection, safety assessment, financing, social issues, public concerns and international co-operation. An annex finally summarises the radioactive waste management programs that are implemented in 15 of the NEA countries. (TEC). figs

CRUSH1: a simplified computer program for impact analysis of radioactive material transport casks

Energy Technology Data Exchange (ETDEWEB)

Ikushima, Takeshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1996-07-01

In drop impact analyses for radioactive transport casks, it has become possible to perform them in detail by using interaction evaluation, computer programs, such as DYNA2D, DYNA3D, PISCES and HONDO. However, the considerable cost and computer time are necessitated to perform analyses by these programs. To meet the above requirements, a simplified computer program CRUSH1 has been developed. The CRUSH1 is a static calculation computer program capable of evaluating the maximum acceleration of cask bodies and the maximum deformation of shock absorbers using an Uniaxial Displacement Method (UDM). The CRUSH1 is a revised version of the CRUSH. Main revisions of the computer program are as follows; (1) not only main frame computer but also work stations (OS UNIX) and personal computer (OS Windows 3.1 or Windows NT) are available for use of the CRUSH1 and (2) input data set are revised. In the paper, brief illustration of calculation method using UDM is presented. The second section presents comparisons between UDM and the detailed method. The third section provides a use`s guide for CRUSH1. (author)

CRUSH1: a simplified computer program for impact analysis of radioactive material transport casks

International Nuclear Information System (INIS)

Ikushima, Takeshi

1996-07-01

In drop impact analyses for radioactive transport casks, it has become possible to perform them in detail by using interaction evaluation, computer programs, such as DYNA2D, DYNA3D, PISCES and HONDO. However, the considerable cost and computer time are necessitated to perform analyses by these programs. To meet the above requirements, a simplified computer program CRUSH1 has been developed. The CRUSH1 is a static calculation computer program capable of evaluating the maximum acceleration of cask bodies and the maximum deformation of shock absorbers using an Uniaxial Displacement Method (UDM). The CRUSH1 is a revised version of the CRUSH. Main revisions of the computer program are as follows; (1) not only main frame computer but also work stations (OS UNIX) and personal computer (OS Windows 3.1 or Windows NT) are available for use of the CRUSH1 and (2) input data set are revised. In the paper, brief illustration of calculation method using UDM is presented. The second section presents comparisons between UDM and the detailed method. The third section provides a use's guide for CRUSH1. (author)

United States high-level radioactive waste management program: Current status and plans

International Nuclear Information System (INIS)

Williams, J.

1992-01-01

The inventory of spent fuel in storage at reactor sites in the United States is approximately 20,000 metric tons heavy metal (MTHM). It is increasing at a rate of 1700 to 2100 MTHM per year. According to current projections, by the time the last license for the current generation of nuclear reactors expires, there will be an estimated total of 84,000 MTHm. No commercial reprocessing capacity exists or is planned in the US. Therefore, the continued storage of spent fuel is required. The majority of spent fuel remains in the spent fuel pools of the utilities that generated it. Three utilities are presently supplementing pool capacity with on-site dry storage technologies, and four others are planning dry storage. Commercial utilities are responsible for managing their spent fuel until the Federal waste management system, now under development, accepts spent fuel for storage and disposal. Federal legislation charges the Office of Civilian Radioactive Waste Management (OCRWM) within the US Department of Energy (DOE) with responsibility for developing a system to permanently dispose of spent fuel and high level radioactive waste in a manner that protects the health and safety of the public and the quality of the environment. We are developing a waste management system consisting for three components: a mined geologic repository, with a projected start date of 2010; a monitored retrievable storage facility (MRS), scheduled to begin waste acceptance in 1998; and a transportation system to support MRS and repository operations. This paper discusses the background and framework for the program, as well as the current status and plans for management of spent nuclear fuel at commercial utilities; the OCRWM's development of a permanent geologic repository, an MRS, and a transportation system; the OCRWM's safety approach; the OCRWM's program management initiatives; and the OCRWM's external relations activities

Automatized system of radioactive material analysis

International Nuclear Information System (INIS)

Pchelkin, V.A.; Sviderskij, M.F.; Litvinov, V.A.; Lavrikov, S.A.

1979-01-01

An automatized system has been developed for the identification of substance, element and isotope content of radioactive materials on the basis of data obtained for studying physical-chemical properties of substances (with the help of atomic-absorption spectrometers, infrared spectrometer, mass-spectrometer, derivatograph etc.). The system is based on the following principles: independent operation of each device; a possibility of increasing the number of physical instruments and devices; modular properties of engineering and computer means; modular properties and standardization of mathematical equipment, high reliability of the system; continuity of programming languages; a possibility of controlling the devices with the help of high-level language, typification of the system; simple and easy service; low cost. Block-diagram of the system is given

Performance assessment overview for subseabed disposal of high level radioactive waste

International Nuclear Information System (INIS)

Klett, R.D.

1997-06-01

The Subseabed Disposal Project (SDP) was part of an international program that investigated the feasibility of high-level radioactive waste disposal in the deep ocean sediments. This report briefly describes the seven-step iterative performance assessment procedures used in this study and presents representative results of the last iteration. The results of the performance are compared to interim standards developed for the SDP, to other conceptual repositories, and to related metrics. The attributes, limitations, uncertainties, and remaining tasks in the SDP feasibility phase are discussed

24 CFR 200.948 - Building product standards and certification program for carpet cushion.

Science.gov (United States)

2010-04-01

... Minimum Property Standards § 200.948 Building product standards and certification program for carpet... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Building product standards and certification program for carpet cushion. 200.948 Section 200.948 Housing and Urban Development Regulations...

The radioactive waste management videoconference training series for an international audience

International Nuclear Information System (INIS)

Callan, C.; Hylko, J.M.

1996-01-01

A proven cost-effective method for delivering new educational opportunities to employees in different locations simultaneously is by using the live videoconference format. Also, the videotapes produced from this format allows employees to participate who are not routinely available for traditional classroom training. However, the primary challenge is to design a distance learning series that meets the requirements of a diverse audience. The National Environmental Technology Network (NETN), a program associated with the College of Engineering at the University of New Mexico, has a proven track record in developing and producing effective videoconference and distance learning programs for industry, government, national laboratories, and universities. Specifically, The Radioactive Waste Management Videoconference Training Series is comprised of eight individual programs: (1) Introduction to Radioactive Waste Management, (2) Interactions Between Radiation and Matter; (3) Decommissioning and Decontamination; (4) Transportation; (5) Low-Level Radioactive Waste; (6) High-Level Radioactive Waste; (7) Transuranic Waste; and (8) New and Other Technologies for Radioactive Waste Management. Each program consists of a tiered approach featuring an introduction, case studies, legal and regulatory issues, radioactive waste characteristics, disposal Options, and transfer of technology. The participants receive a packet containing a full outline of the course, including charts and illustrations used by the presenters. At the conclusion of each program, the interactive question/answer period allows viewers to ask pertinent questions and to participate as a group

Setting the standard: The IAEA safety standards set the global reference

International Nuclear Information System (INIS)

Williams, L.

2003-01-01

For the IAEA, setting and promoting standards for nuclear radiation, waste, and transport safety have been priorities from the start, rooted in the Agency's 1957 Statute. Today, a corpus of international standards are in place that national regulators and industries in many countries are applying, and more are being encouraged and assisted to follow them. Considerable work is done to keep safety standards updated and authoritative. They cover five main areas: the safety of nuclear facilities; radiation protection and safety of radiation sources; safe management of radioactive waste; safe transport of radioactive material; and thematic safety areas, such as emergency preparedness or legal infrastructures. Overall, the safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment. All IAEA Member States can nominate experts for the Agency standards committees and provide comments on draft standards. Through this ongoing cycle of review and feedback, the standards are refined, updated, and extended where needed

Boiling water reactor liquid radioactive waste processing system

International Nuclear Information System (INIS)

Anon.

1977-01-01

The standard sets forth minimum design, construction and performance requirements with due consideration for operation of the liquid radioactive waste processing system for boiling water reactor plants for routine operation including design basis fuel leakage and design basis occurrences. For the purpose of this standard, the liquid radioactive waste processing system begins at the interfaces with the reactor coolant pressure boundary, at the interface valve(s) in lines from other systems and at those sumps and floor drains provided for liquid waste with the potential of containing radioactive material. The system terminates at the point of controlled discharge to the environment, at the point of interface with the waste solidification system and at the point of recycle back to storage for reuse. The standard does not include the reactor coolant clean-up system, fuel pool clean-up system, sanitary waste system, any nonaqueous liquid system or controlled area storm drains

Review of standards and guidelines pertinent to DOE's remedial action programs

International Nuclear Information System (INIS)

Soldat, J.K.; Denham, D.H.

1984-10-01

A number of radiological standards, guidelines, and dose criteria have been promulgated that may be relevant to the Department of Energy's (DOE) Remedial Action programs. Some of these will be applied to remedial actions undertaken by DOE to ensure that health and safety aspects will be adequately addressed. Pacific Northwest Laboratory staff are reviewing and evaluating existing and proposed environmental radiological standards and criteria for their applicability. National and international environmental standards and criteria, and studies conducted by other DOE contractors are being evaluated. The aim of the review is to identify gaps in these standards and guidelines and to recommend further development as necessary. This paper provides a summary of the standards and guidelines evaluated for applicability to DOE's Remedial Action programs. 33 references, 5 tables

41 CFR 102-194.5 - What is the Standard and Optional Forms Management Program?

Science.gov (United States)

2010-07-01

... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false What is the Standard and Optional Forms Management Program? 102-194.5 Section 102-194.5 Public Contracts and Property Management... PROGRAMS 194-STANDARD AND OPTIONAL FORMS MANAGEMENT PROGRAM § 102-194.5 What is the Standard and Optional...

Annual radioactive waste tank inspection program: 1995

International Nuclear Information System (INIS)

McNatt, F.G. Sr.

1996-01-01

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1995 to evaluate these vessels and evaluations based on data accrued by inspections performed since the tanks were constructed are the subject of this report

Annual radioactive waste tank inspection program - 1992

International Nuclear Information System (INIS)

McNatt, F.G.

1992-01-01

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1992 to evaluate these vessels and evaluations based on data accrued by inspections made since the tanks were constructed are the subject of this report

Annual radioactive waste tank inspection program - 1991

International Nuclear Information System (INIS)

McNatt, F.G.

1992-01-01

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1991 to evaluate these vessels and evaluations based on data accrued by inspections made since the tanks were constructed are the subject of this report

The new German regulatory system of monitoring workers for intakes of radioactivity with special reference to thorium

International Nuclear Information System (INIS)

Henrichs, K.

1995-01-01

In Germany, the Association for Radiation Protection (member of IRPA) defined a new standard for the monitoring of workers occupationally exposed to radioactive material. During the last two years this draft has been accepted by the German government in the form of three directives. The purpose of our approach was the installation of a system defining clear criteria for the necessity of regular and special monitoring programs, giving directives for monitoring programs ensuring that dose assessments are as reliable as necessary with the lowest possible expenses, standardizing as far as possible the procedures of dose assessments, and guaranteeing the necessary quality standards. The most important features of these regulations will be discussed in this contribution and their application will be exemplified for the specially difficult monitoring of thorium intakes. (author). 2 figs., 2 tabs

Uranium Mill Tailings Remedial Action Program. Annual status report

International Nuclear Information System (INIS)

1982-12-01

Progress made during FY 1982, present status, and plans for FY 1983 are described for the following programs: radiological surveys and inclusion of vicinity properties; establishment of cooperative agreements; promulgation of standards for remedial action; acquisition of lands and materials; reprocessing of residual radioactive materials; National Environmental Policy Act (NEPA) documentation; program planning; technology development; remedial action; public participation; other federal agency activities; state and Indian tribe activities; and status of designated sites. Program funding is given

The Radioactive Ion Beams in Brazil (RIBRAS) facility. Description, program, main results, future plans

Energy Technology Data Exchange (ETDEWEB)

Lepine-Szily, A.; Lichtenthaeler, R.; Guimaraes, V. [Instituto de Fisica, Universidade de Sao Paulo (Brazil)

2014-08-15

RIBRAS (Radioactive Ion Beams in Brazil) is a facility installed at the Institute of Physics of the University of Sao Paulo (IFUSP), Brazil. The RIBRAS system consists of two superconducting solenoids and uses the ''in-flight method'' to produce radioactive ion beams using the primary beam provided by the 8UD Pelletron Tandem of IFUSP. The ion beams produced so far by RIBRAS are {sup 6}He, {sup 8}Li, {sup 7}Be, {sup 10}Be, {sup 8}B, {sup 12}B with intensities that can vary from 10{sup 4} to 10{sup 6} pps. Initially the experimental program covered the study of elastic and inelastic scattering with the objective to study the interaction potential and the reaction mechanisms between weakly bound (RIB) and halo ({sup 6}He and {sup 8}B) projectiles on light, medium and heavy mass targets. With highly purified beams, the study of resonant elastic scattering and resonant transfer reactions, using inverse kinematics and thick targets, has also been included in our experimental program. Also, transfer reactions of astrophysical interest and fusion reactions induced by halo nuclei are part of the near-future research program. Our recent results on elastic scattering, alpha-particle production and total reaction cross sections, as well as the resonant elastic and transfer reactions, are presented. Our plans for the near future are related to the installation of a new beam line and a cave for gamma-ray detection. We intend to place in operation a large area neutron detector available in our laboratory. The long-range plans could be the move of the RIBRAS system to the more energetic beam line of the LINAC post-accelerator (10MeV/nucleon primary beams) still in construction in our laboratory. (orig.)

A reference standard-based quality assurance program for radiology.

Science.gov (United States)

Liu, Patrick T; Johnson, C Daniel; Miranda, Rafael; Patel, Maitray D; Phillips, Carrie J

2010-01-01

The authors have developed a comprehensive radiology quality assurance (QA) program that evaluates radiology interpretations and procedures by comparing them with reference standards. Performance metrics are calculated and then compared with benchmarks or goals on the basis of published multicenter data and meta-analyses. Additional workload for physicians is kept to a minimum by having trained allied health staff members perform the comparisons of radiology reports with the reference standards. The performance metrics tracked by the QA program include the accuracy of CT colonography for detecting polyps, the false-negative rate for mammographic detection of breast cancer, the accuracy of CT angiography detection of coronary artery stenosis, the accuracy of meniscal tear detection on MRI, the accuracy of carotid artery stenosis detection on MR angiography, the accuracy of parathyroid adenoma detection by parathyroid scintigraphy, the success rate for obtaining cortical tissue on ultrasound-guided core biopsies of pelvic renal transplants, and the technical success rate for peripheral arterial angioplasty procedures. In contrast with peer-review programs, this reference standard-based QA program minimizes the possibilities of reviewer bias and erroneous second reviewer interpretations. The more objective assessment of performance afforded by the QA program will provide data that can easily be used for education and management conferences, research projects, and multicenter evaluations. Additionally, such performance data could be used by radiology departments to demonstrate their value over nonradiology competitors to referring clinicians, hospitals, patients, and third-party payers. Copyright 2010 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Establishment and utilization of radiological protection programs for the transport of radioactive material

International Nuclear Information System (INIS)

Lopez V, J.; Capadona, N.

2006-01-01

The present work has by objective to indicate rules for the establishment and the use of the Radiological Protection Programs (PPR) that are of application to the transport of radioactive materials according to that required by the Transport Regulation of the International Atomic Energy Agency (IAEA). The PPR are established and applied in systematic form for remittent, transport and addressees, to consider the measures of radiological protection and its appropriately control during the transport stages of radioactive material. In particular, in the work it is analyzed the PPR applied to the operative stage, in the one that can be considered as one of the more important documents to use since it summarizes the evaluations and the necessary controls of radiological protection. Also it is analyzed the importance that this document gets ready on the base that it converges in the the analyses, evaluations and data that have been kept in mind during the previous stages of design of bundles and production of packings, the types and quantities of involved bundles, as well as of considering the quantities of expeditions and its frequencies, the ways of transport, etc. It is included a brief description of the parts that the PPR conforms on the base of that suggested in the advanced draft of the TS-G-1.5 Guide 'Radiation Protection Programmes for Transport of Radioactive Material', of October, 2005, of the IAEA: objectives. necessity, scope, basic elements of a PPR in function of the occupational dose. assignment of functions and responsibilities for the establishment of a PPR, evaluation and dose optimization, surface contamination, segregation and other protection measures, responses in emergencies. training and administration systems for baled and transport of radioactive material. Next an example of PPR for the transport of bundles of the A Type by lorry with content of radiopharmaceuticals that are the bundles more used worldwide in the expeditions of radioactive

Operational radioactive waste management plan for the Nevada Test Site

International Nuclear Information System (INIS)

1980-11-01

The Operational Radioactive Waste Management Plan for the Nevada Test Site establishes procedures and methods for the safe shipping, receiving, processing, disposal, and storage of radioactive waste. Included are NTS radioactive waste disposition program guidelines, procedures for radioactive waste management, a description of storage and disposal areas and facilities, and a glossary of specifications and requirements

Institutional storage and disposal of radioactive materials

International Nuclear Information System (INIS)

St Germain, J.

1986-01-01

Storage and disposal of radioactive materials from nuclear medicine operations must be considered in the overall program design. The storage of materials from daily operation, materials in transit, and long-term storage represent sources of exposure. The design of storage facilities must include consideration of available space, choice of material, occupancy of surrounding areas, and amount of radioactivity anticipated. Neglect of any of these factors will lead to exposure problems. The ultimate product of any manipulation of radioactive material will be some form of radioactive waste. This waste may be discharged into the environment or placed within a storage area for packaging and transfer to a broker for ultimate disposal. Personnel must be keenly aware of packaging regulations of the burial site as well as applicable federal and local codes. Fire codes should be reviewed if there is to be storage of flammable materials in any area. Radiation protection personnel should be aware of community attitudes when considering the design of the waste program

Implementation of the program law from June 28, 2006 on the sustainable management of radioactive materials and wastes

International Nuclear Information System (INIS)

2009-07-01

This presentation, given by the national agency of radioactive waste management (ANDRA) at the meeting of July 1, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), describes the two projects of the ANDRA in the framework of the program law of June 28, 2006 about the sustainable management of radioactive materials and wastes. The first project is a reversible deep geologic waste disposal facility for high level/long living wastes. The second project is a low depth waste storage facility for low level/long living wastes. For each project, the site selection, the type of waste and its conditioning, and the concept and specifications of the facility are presented. (J.S.)

The review of radioactive waste management in the world

International Nuclear Information System (INIS)

Jalilzadeh, R.; Mirzahosseini, A.; Rahnomaei, N. A.

2008-01-01

Radioactive waste is generally classified on the basis of how much radiation and the type of radiation it emits as well as the length of time over which it will continue to emit radiation. Many activities dealing with radioactive materials produce nuclear wastes, including civilian nuclear power programs (nuclear Power plant operations and nuclear fuel-cycle activities), defense nuclear programs (nuclear weapons production, naval nuclear reactor programs, and related R and D), and industrial and institutional activities (scientific research, medical operations, and other industrial uses of Radioisotopic sources or Radio chemicals). To minimize the potential adverse health and environment impacts to people and other systems including of animals, plant and etc, during the entire lifetime of the radionuclides involved, nuclear waste must be carefully and properly managed. The scope of nuclear - waste management encompasses generation, processing (treatment and packaging), storage, transport, and disposal. in this research the effect of radioactive waste on environment and also disposal methods and radioactive waste management in countries is surveyed

Fifteen years of radioactive waste management at Ontario Hydro

International Nuclear Information System (INIS)

Carter, T.J.; Rao, P.K.M.

1985-01-01

Ontario Hydro is a large Canadian utility producing 84% (7394 MWe) of the Nuclear Electricity generated in Canada. The low- and intermediate-level radioactive wastes generated by the Ontario Hydro program are currently being managed at the Bruce Nuclear Power Development with various volume reduction, packaging and interim storage systems. Ontario Hydro also owns and operates a radioactive waste transportation system. Studies are in progress for final disposal of these wastes in a suitable geology in Ontario. Since its inception in 1971, Ontario Hydro's radioactive waste management program has evolved into providing a full fledged radioactive waste management capability to the utility's two nuclear generation centres at Pickering and Bruce, and later in the decade, to Darlington. This paper summarizes the various developments in this program; highlights the major facilities both in-service and planned to be built; reviews the experiences gained over fifteen years of in-house waste management; and discusses the proposed reorientation towards ultimate disposal of these wastes. 2 refs., 8 figs., 1 tab

Current status and prospect on the radioactive waste management program in the Republic of Korea. Focusing on recent development

International Nuclear Information System (INIS)

Park, Hyun-Soo; Chang, In-Soon

1996-01-01

Since its first commercial operation at Kori near the city of Pusan in 1978, nuclear energy has become one of the prime resources for the electricity. However, proper treatment of its byproducts, radioactive wastes, has been the national concern. Despite vigorous effort by the Korean Government and NEMAC(Nuclear Environment Management Center), the series of attempts for the site selection to build the national radioactive waste complex has been ruined. After the failure at Guleop Island, the Government recently amended its policy so that the major tasks on the management program of radioactive wastes shall be transferred to KEPCO(Korea Electric Power Corporation), sole national electric utility, while the current authority, KAERI(Korea Atomic Energy Research Institute)/NEMAC is limited to focus on the research and development in the safe management of spent fuels. Detailed plan to support the Government redirection is under discussion among concerned institutes. (author)

Meeting the regulatory information needs of users of radioactive materials

International Nuclear Information System (INIS)

MacDurmon, G.W.

1996-01-01

The use of radioactive materials is one of the most regulated areas of research. Researchers face ever increasing regulatory requirements and issues involving the disposal of radioactive material, while meeting the demands of higher productivity. Radiation safety programs must maximize regulatory compliance, minimize barriers, provide services and solutions, and effectively communicate with users of radioactive materials. This talk will discuss methods by which a radiation safety program can meet the needs of both the research staff and regulatory compliance staff

Meeting the regulatory information needs of users of radioactive materials

Energy Technology Data Exchange (ETDEWEB)

MacDurmon, G.W. [American Cyanamid Company, Princeton, NJ (United States)

1996-10-01

The use of radioactive materials is one of the most regulated areas of research. Researchers face ever increasing regulatory requirements and issues involving the disposal of radioactive material, while meeting the demands of higher productivity. Radiation safety programs must maximize regulatory compliance, minimize barriers, provide services and solutions, and effectively communicate with users of radioactive materials. This talk will discuss methods by which a radiation safety program can meet the needs of both the research staff and regulatory compliance staff.

Development of methodology for the characterization of radioactive sealed sources

International Nuclear Information System (INIS)

Ferreira, Robson de Jesus

2010-01-01

Sealed radioactive sources are widely used in many applications of nuclear technology in industry, medicine, research and others. The International Atomic Energy Agency (IAEA) estimates tens of millions sources in the world. In Brazil, the number is about 500 thousand sources, if the Americium-241 sources present in radioactive lightning rods and smoke detectors are included in the inventory. At the end of the useful life, most sources become disused, constitute a radioactive waste, and are then termed spent sealed radioactive sources (SSRS). In Brazil, this waste is collected by the research institutes of the Nuclear Commission of Nuclear Energy and kept under centralized storage, awaiting definition of the final disposal route. The Waste Management Laboratory (WML) at the Nuclear and Energy Research Institute is the main storage center, having received until July 2010 about 14.000 disused sources, not including the tens of thousands of lightning rod and smoke detector sources. A program is underway in the WML to replacing the original shielding by a standard disposal package and to determining the radioisotope content and activity of each one. The identification of the radionuclides and the measurement of activities will be carried out with a well type ionization chamber. This work aims to develop a methodology for measuring or to determine the activity SSRS stored in the WML accordance with its geometry and determine their uncertainties. (author)

Management of radioactive wastes of iodine therapy

International Nuclear Information System (INIS)

Silva, Andre R.M.; Santos, Helena C.

2015-01-01

The main objective of waste radioactive management is to ensure the protection of man and the preservation of the environment. The regulation that established the basis for the good radioactive waste management was elaborated by the Comissao Nacional de Energia Nuclear (CNEN), in 1985. It is the CNEN-NE-6:05: 'Management radioactive waste in radioactive facilities', which although it an important standard related to radioactive waste management and help largely in the design of a management system in radioactive facilities of radioisotope users, covers the topics in a general way and does not consider individuals aspects of the different plants, as is the case of nuclear medicine units. The main objective of this study is to show the segregation and safe packaging, avoiding unnecessary exposure of professionals involved and public individuals in general

Evaluation model applied to TRANSPETRO's Marine Terminals Standardization Program

Energy Technology Data Exchange (ETDEWEB)

Almeida, Maria Fatima Ludovico de; Mueller, Gabriela [Pontificia Universidade Catolica do Rio de Janeiro (PUC-Rio), Rio de Janeiro, RJ (Brazil). Instituto Tecnologico; Garcia, Luciano Maldonado [TRANSPETRO - PETROBRAS Transporte S.A., Rio de Janeiro, RJ (Brazil)

2009-07-01

This paper describes an innovative evaluation model applied to TRANSPETRO's 'Marine Terminals Standardization Program' based on updating approaches of programs evaluation and organizational learning. Since the program was launched in 2004, the need for having an evaluation model able to evaluate its implementation progress, to measure the degree of standards compliance and its potential economic, social and environmental impacts has become evident. Within a vision of safe and environmentally responsible operations of marine terminals, this evaluation model was jointly designed by TRANSPETRO and PUC-Rio to promote continuous improvement and learning in operational practices and in the standardization process itself. TRANSPETRO believes that standardization supports its services and management innovation capability by creating objective and internationally recognized parameters, targets and metrology for its business activities. The conceptual model and application guidelines for this important tool are presented in this paper, as well as the next steps towards its implementation. (author)

Determination of the probability for radioactive materials on properties in Monticello, Utah

International Nuclear Information System (INIS)

Wilson, M.J.; Crutcher, J.W.

1991-02-01

In 1978, under the authority of the Atomic Energy Act, the US Department of Energy (DOE) established the Surplus Facilities Management Program (SFMP) to manage the maintenance and surveillance of numerous DOE-owned, radioactively contaminated facilities that have been declared surplus and to conduct a program leading to the ultimate disposition of those facilities. The primary responsibility of SFMP is to protect public health and the environment from potentially harmful radioactive contamination contained within or derived from DOE-owned facilities. Management of SFMP is directed by the DOE Office of Environmental Restoration and Waste Management, Washington, DC. Prior to mill site remediation, Monticello properties surrounding the site and designated privately owned are being assessed for inclusion in the SFMP. Oak Ridge National Laboratory (ORNL) was directed by DOE in July 1988 to assess the radiological condition of privately owned properties in Monticello that have been identified as possibly containing Monticello mill-related materials. Properties containing Monticello mill-related materials and with associated radiation levels that exceed US Environmental Protection Agency (EPA) and DOE standards are eligible for cleanup under SFMP. The objective of this study was to determine the probability that a property which contained Monticello mill-related residual radioactive material in excess of the guidelines would not be assessed under the current protocol. 3 refs., 3 figs., 2 tabs

77 FR 59712 - Energy Conservation Program: Energy Conservation Standards for Dishwashers

Science.gov (United States)

2012-10-01

... amended energy conservation standards, DOE conducted a market survey using all available public... Energy Conservation Program: Energy Conservation Standards for Dishwashers AGENCY: Office of Energy... establish amended energy conservation standards for dishwashers in the Federal Register on May 30, 2012. DOE...

Law of radioactive minerals

International Nuclear Information System (INIS)

1980-01-01

Legal device done in order to standardize and promote the exploration and explotation of radioactive minerals by peruvian and foreign investors. This device include the whole process, since the prospection until the development, after previous auction given by IPEN

Data Processing and Programming Applied to an Environmental Radioactivity Laboratory; Desarrollo Informatico Aplicado a un Laboratorio de Radiactividad Ambiental

Energy Technology Data Exchange (ETDEWEB)

Trinidad, J.A.; Gasco, C.; Palacios, M.A.

2009-07-01

This report is the original research work presented for the attainment of the author master degree and its main objective has been the resolution -by means of friendly programming- of some of the observed problems in the environmental radioactivity laboratory belonging to the Department of Radiological Surveillance and Environmental Radioactivity from CIEMAT. The software has been developed in Visual Basic for applications in Excel files and it solves by macro orders three of the detected problems: a) calculation of characteristic limits for the measurements of the beta total and beta rest activity concentrations according to standards MARLAP, ISO and UNE and the comparison of the three results b) Pb-210 and Po-210 decontamination factor determination in the ultra-low level Am-241 analysis in air samples by alpha spectrometry and c) comparison of two analytical techniques for measuring Pb-210 in air ( direct-by gamma spectrometry- and indirect -by radiochemical separation and alpha spectrometry). The organization processes of the different excel files implied in the subroutines, calculations and required formulae are explained graphically for its comprehension. The advantage of using this kind of programmes is based on their versatility and the ease for obtaining data that lately are required by tables that can be modified as time goes by and the laboratory gets more data with the special applications for describing a method (Pb-210 decontamination factors for americium analysis in air) or comparing temporal series of Pb-210 data analysed by different methods (Pb-210 in air). (Author)

Strategy on radioactive waste management in Lithuania

International Nuclear Information System (INIS)

Poskas, P.; Adomaitis, J.E.

2003-01-01

In Lithuania about 70-80% of all electricity is generated at a single power station, Ignalian NPP which has two non-upgradable RBMK-1500 type reactors. The unit 1 will be closed by 2005. The decision on unit 2 should be made in Lithuanian Parliament very soon taking into consideration substantial long-term financial assistance from the EU, G7 and other states as well as international institutions. The Government approved the Strategy on Radioactive Waste Management in 2002. Objectives of this strategy are to develop the radioactive waste management infrastructure based on modern technologies and provide for the set of practical actions that shall bring management of radioactive waste in Lithuania in compliance with radioactive waste management principles of IAEA and with good practices in force in EU Member States. Ignalina NPP is undertaking a program of decommissioning support projects, financed by grants from the International Ignalina Decommissioning Support Fund, administered by the European Bank for Reconstruction and Development. This program comprises also the implementation of investment projects in a number of pre-decommissioning facilities including the management of radioactive waste and spent nuclear fuel. (orig.)

Radioactive material (RAM) accident/incident data analysis program

International Nuclear Information System (INIS)

Emerson, E.L.; McClure, J.D.

1985-03-01

This report describes the development of the Radioactive Material Transportation Accident/Incident Data Base (RAM-AIDB), which contains information on the occurrences of transportation accidents and incidents, for radioactive materials (RAM) that are involved in the process of transportation, loading and unloading operation, or temporary storage. These transportation operations are in support of the nuclear fuel cycle for electrical energy generation. This study analyzes in some detail basic accident/incident statistical data, RAM packaging accident response data, and the health effects associated with RAM transport accidents/incidents. This report presents a summary of US RAM transport accident/incident experience for the period 1971 through December 1981. In addition, a sample annual summary of accident/incident experience is presented for the calendar year 1981

Annual radioactive waste tank inspection program - 1999

International Nuclear Information System (INIS)

Moore, C.J.

2000-01-01

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1999 to evaluate these vessels and auxiliary appurtenances along with evaluations based on data accrued by inspections performed since the tanks were constructed are the subject of this report

Monitoring of radioactivity in drinking water

International Nuclear Information System (INIS)

Legarda, F.; Herranz, M.; Letessier, P.

2008-01-01

Radioactivity is a physical phenomenon whose presence in water is monitored due to its potential capability to induce deleterious effects on human health. In this article the effects that can be caused by radioactivity as well as the way in which regulations establish how to perform a monitorization of water that enables us to ascertain that the radiological quality of water is in agreement with the accepted standard of quality of life are analyzed. Finally the means available to know the content of radioactivity in water together with some clues on how to remove it from water are described. (Author) 5 refs

Economics of low-level radioactive waste disposal

International Nuclear Information System (INIS)

Schafer, J.; Jennrich, E.

1983-01-01

Regardless of who develops new low-level radioactive waste disposal sites or when, economics will play a role. To assist in this area the Department of Energy's Low-Level Radioactive Waste Management Program has developed a computer program, LLWECON, and data base for projecting disposal site costs. This program and its non-site specific data base can currently be used to compare the costs associated with various disposal site development, financing, and operating scenarios. As site specific costs and requirements are refined LLWECON will be able to calculate exact life cycle costs for each facility. While designed around shallow land burial, as practiced today, LLWECON is flexible and the input parameters discrete enough to be applicable to other disposal options. What the program can do is illustrated

Impact of standards and certification on environmental impairment liability insurance programs

International Nuclear Information System (INIS)

Gulledge, W.P.

1993-01-01

Environmental impairment liability (EIL) insurance is available for petroleum storage tank and other environmental exposures. Recent standards and performance criteria for leak detection for underground storage tanks (USTs) and other technical standards for USTs have been both a benefit and an interference to risk-based underwriting of storage tank EIL insurance programs. Insurance underwriters and state financial responsibility program administrators are confronted with confusing information to manage these environmental risks. Standards and certification are also key issues for site assessment programs. Recent activities from ASTM and the Institute for Environmental Auditing (IEA) have addressed the need to increase the professional stature of site assessments and environmental management. Reaction and acceptance of these efforts by the users have been mixed. Ultimately, these efforts will greatly impact insurance coverage for environmental risks

Packaging and transportation of radioactive materials: summary program

International Nuclear Information System (INIS)

1978-01-01

This document contains summaries or abstracts of reports presented at the Symposium on Packaging and Transportation of Radioactive Materials. Separate indexing has been performed on individual items presented at this conference

Government/Industry Partnership on the Security of Radioactive Sources

International Nuclear Information System (INIS)

Cefus, Greg; Colhoun, Stefan C.; Freier, Keith D.; Wright, Kyle A.; Herdes, Gregory A.

2006-01-01

In the past, industry radiation protection programs were built almost exclusively around radiation safety and the minimization of radiation dose exposure to employees. Over the last decade, and especially the last few years, the emphasis has shifted to include the physical security and enhanced control of radioactive materials. The threat of nuclear and radiological terrorism is a genuine international security concern. In May 2004, the U.S. Department of Energy/U.S. National Nuclear Security Administration unveiled the Global Threat Reduction Initiative (GTRI) to respond to a growing international concern for the proper control and security of radioactive and nuclear materials. An integral part of the GTRI, the International Radiological Threat Reduction (IRTR) Program, was established in February 2002, originally as a Task Force. The IRTR Program is foremost a government-to-government cooperative program with the mission to reduce the risk posed by vulnerable radioactive materials that could be used in a Radioactive Dispersal Device (RDD). However, governments alone cannot prevent the misuse and illicit trafficking of radioactive sources. By expanding the role of private industry as a partner, existing government regulatory infrastructures can be enhanced by formulating and adopting industry self-regulation and self-policing measures. There is international concern regarding the security and control of the vast number of well-logging sources used during oil exploration operations. The prevalence of these sources, coupled with their portability, is a legitimate security concern. The energy exploration industry has well established safety and security protocols and the IRTR Program seeks to build on this foundation. However, the IRTR Program does not have sufficient resources to address the issue without industry assistance, so it is looking to the oil and gas industry to help identify alternative means for accomplishing our mutual objectives. This paper describes

Final disposal of radioactive waste

Directory of Open Access Journals (Sweden)

Freiesleben H.

2013-06-01

Full Text Available In this paper the origin and properties of radioactive waste as well as its classification scheme (low-level waste – LLW, intermediate-level waste – ILW, high-level waste – HLW are presented. The various options for conditioning of waste of different levels of radioactivity are reviewed. The composition, radiotoxicity and reprocessing of spent fuel and their effect on storage and options for final disposal are discussed. The current situation of final waste disposal in a selected number of countries is mentioned. Also, the role of the International Atomic Energy Agency with regard to the development and monitoring of international safety standards for both spent nuclear fuel and radioactive waste management is described.

NRC Task Force report on review of the federal/state program for regulation of commercial low-level radioactive waste burial grounds

International Nuclear Information System (INIS)

1977-01-01

The underlying issue explored in this report is that of Federal vs State regulation of commercial radioactive waste burial grounds. The need for research and development, a comprehensive set of standards and criteria, a national plan for low-level waste management, and perpetual care funding are closely related to the central issue and are also discussed. Five of the six commercial burial grounds are regulated by Agreement States; the sixth is regulated solely by the NRC (NRC also regulates Special Nuclear Material at the sites). The sites are operated commercially. The operators contribute to the perpetual care funds for the sites at varying rates. The States have commitments for the perpetual care of the decommissioned sites except for one site, located on Federally owned land. Three conclusions are reached. Federal control over the disposal of low-level waste should be increased by requiring joint Federal/State site approval, NRC licensing, Federal ownership of the land, and a Federally administered perpetual care program. The NRC should accelerate the development of its regulatory program for the disposal of low-level waste. The undisciplined proliferation of low-level burial sites must be avoided. NRC should evaluate alternative disposal methods, conduct necessary studies, and develop a comprehensive low-level waste regulatory program (i.e., accomplish the above recommendations) prior to the licensing of new disposal sites

LLNL radioactive waste management plan as per DOE Order 5820.2

International Nuclear Information System (INIS)

1984-01-01

The following aspects of LLNL's radioactive waste management plan are discussed: program administration; description of waste generating processes; radioactive waste collection, treatment, and disposal; sanitary waste management; site 300 operations; schedules and major milestones for waste management activities; and environmental monitoring programs (sampling and analysis)

Appraisal for France of the safety of the transport of radioactive material. Provision for the application of the IAEA safety standards

International Nuclear Information System (INIS)

2004-01-01

The IAEA has the specific statutory function within the United Nations system of establishing standards of safety for the protection of health against exposure to ionizing radiation. As part of this mandate, the IAEA has issued Regulations for the Safe Transport of Radioactive Material, and has also established the Transport Safety Appraisal Service (TranSAS) to carry out, at the request of States, appraisals of the implementation of these regulations. The IAEA carried out such an appraisal in France from 27 March to 8 April 2004. The appraisal addressed all relevant transport activities in France, both national and international, for all modes of transport, with special emphasis on the maritime transport and air transport of radioactive material. This report summarizes the findings of the 13 independent experts who participated in the appraisal

Procedures for the Safe Transport of Radioactive Material

Energy Technology Data Exchange (ETDEWEB)

Kim, Jang Lyul; Chung, K. K.; Lee, J. I.; Chang, S. Y.; Lee, T. Y

2007-11-15

This technical report describes the procedure and work responsibility along with the regulation and standard necessary for the safe transport of radioactive or contaminated materials. This report, therefore, can be effectively used to secure the public safety as well as to prevent the disastrous event which might be resulted from the transport process of radioactive materials by establishing a procedure and method on the safe packing, handling and transport of radioactive materials.

Radioactive waste management services. Safety and technical advisory services available from the IAEA

International Nuclear Information System (INIS)

2000-09-01

This brochure provides updated information about the services and assistance the International Atomic Energy Agency (IAEA) is able to render, upon request by Member States, in the area of radioactive waste management. The ultimate objective is to ensure that all wastes are managed safely and in a way which protects both individual and the environment, now and in the future. The IAEA is the sole global international organization with the statutory authority to establish safety standards for the protection of health against exposure to ionizing radiation. These include safety standards for radioactive waste management. A comprehensive set of such standards is being established, and continuously updated, under the Agency's aegis, which lay out the requirements for the safe management of all types of radioactive waste. The Agency has a further statutory obligation ro provide for the application of these standards at the request of States. The safety of radioactive waste management is not attainable through safety standards alone but requires special technology. An additional function of the IAEA is thus to foster the transfer of technology among States, including the specific technology needed to ensure safe radioactive waste management

Packaging and transportation of radioactive materials: summary program

Energy Technology Data Exchange (ETDEWEB)

None

1978-01-01

This document contains summaries or abstracts of reports presented at the Symposium on Packaging and Transportation of Radioactive Materials. Separate indexing has been performed on individual items presented at this conference. (DC)

A directory of computer programs for assessment of radioactive waste disposal in geological formations. Volume 2

International Nuclear Information System (INIS)

Ashton, J.; Broyd, T.W.; Jones, M.A.; Knowles, N.C.; Liew, S.K.; Mawbey, C.S.; Read, D.; Smith, S.L.

1993-01-01

This directory describes computer programs suitable for the assessment of radioactive waste disposal facilities in geological formations. The programs, which are mainly applicable to the post-closure analysis of the repository, address combinations of the following topics: nuclide inventory, corrosion, leaching, geochemistry, geomechanics, heat transfer, groundwater flow, radionuclide migration, biosphere modelling, safety assessment and site evolution. A total of 320 programs are identified, of which 84 are reviewed in detail, 192 in summary and 44 in tabular fashion. Originally published in 1983, the directory was updated in 1985 with the addition of new programs and the revision of some of the existing program reviews. This directory has been completely rewritten in 1991 with the addition of more new programs and a full revision of all the existing program reviews, some of which have been deleted as they are no longer in general use. Although the directory is specific to the post-closure assessment of a repository site, some of the programs described can also be used in other areas of repository (e.g. repository design). This directory is composed of two volumes, the present volume is the second

A directory of computer programs for assessment of radioactive waste disposal in geological formations. Volume 1

International Nuclear Information System (INIS)

Ashton, J.; Broyd, T.W.; Jones, M.A.; Knowles, N.C.; Liew, S.K.; Mawbey, C.S.; Read, D.; Smith, S.L.

1993-01-01

This directory describes computer programs suitable for the assessment of radioactive waste disposal facilities in geological formations. The programs, which are mainly applicable to the post-closure analysis of the repository, address combinations of the following topics: nuclide inventory, corrosion, leaching, geochemistry, geomechanics, heat transfer, groundwater flow, radionuclide migration, biosphere modelling, safety assessment and site evolution. A total of 320 programs are identified of which 84 are reviewed in detail, 192 in summary and 44 in tabular fashion. Originally published in 1983, the directory was updated in 1985 with the addition of new programs and the revision of some of the existing program reviews. This directory has been completely rewritten in 1991 with the addition of more new programs and a full revision of all the existing program reviews, some of which have been deleted as they are no longer in general use. Although the directory is specific to the post-closure assessment of a repository site, some of the programs described can also be used in other areas of repository (e.g. repository design). This directory is composed of two volumes, the present volume is the first

Operational procedure standard for occurrences involving radioactive materials

International Nuclear Information System (INIS)

Piekarz, Leonardo; Rezende, Talita C.; Pinheiro, Christiano J.G.

2017-01-01

This study has as objective to analyze more deeply the actions of response to emergencies involving radioactive materials, in the intent to establish a pattern to the actions performed by the military fire fighters of the Military Fire Brigade of Minas Gerais. To met these goals, it has been attempted to analyze the procedures utilized and recommended, nowadays, for the military fire fighters of CBMMG, and through directed studies, to suggest new actions possible to be executed in the local of the emergency in a way that will not expose the garrison to doses of ionizing radiation that may prejudice them. It is a study of bibliographic, exploratory, and also descriptive nature, realized through a qualitative approach. The techniques used for the research were the analysis of institutional documents, norms and other literature produced by renamed entities in the radiologic and biosafety areas. It was then concluded that CBMMG, through simple actions of response, can provide higher quality and safety in the operations involving radiologic accidents, standing out that the implemented actions nowadays are very beneath the capacity of the corporation, due to the lack of knowledge of the matter by the fire fighters. It was proposed, then, that new actions be implemented and instituted as operational procedures to be used on those emergencies, with the objective of provide a higher safety and professionalism in the attendance to emergencies involving radioactive materials. (author)

Operational procedure standard for occurrences involving radioactive materials

Energy Technology Data Exchange (ETDEWEB)

Piekarz, Leonardo, E-mail: leonardopbm@yahoo.com.br [Academia de Bombeiros Militar de Minas Gerais, Belo Horizonte, MG (Brazil); Rezende, Talita C.; Pinheiro, Christiano J.G., E-mail: talitacolombi@yahoo.com, E-mail: christrieste@yahoo.it [Universidade Federal do Espirito Santo (CCA/UFES), Alegre, ES (Brazil). Programa de Pós-Graduação em Engenharia Química

2017-07-01

This study has as objective to analyze more deeply the actions of response to emergencies involving radioactive materials, in the intent to establish a pattern to the actions performed by the military fire fighters of the Military Fire Brigade of Minas Gerais. To met these goals, it has been attempted to analyze the procedures utilized and recommended, nowadays, for the military fire fighters of CBMMG, and through directed studies, to suggest new actions possible to be executed in the local of the emergency in a way that will not expose the garrison to doses of ionizing radiation that may prejudice them. It is a study of bibliographic, exploratory, and also descriptive nature, realized through a qualitative approach. The techniques used for the research were the analysis of institutional documents, norms and other literature produced by renamed entities in the radiologic and biosafety areas. It was then concluded that CBMMG, through simple actions of response, can provide higher quality and safety in the operations involving radiologic accidents, standing out that the implemented actions nowadays are very beneath the capacity of the corporation, due to the lack of knowledge of the matter by the fire fighters. It was proposed, then, that new actions be implemented and instituted as operational procedures to be used on those emergencies, with the objective of provide a higher safety and professionalism in the attendance to emergencies involving radioactive materials. (author)

Establishing community trust at radioactively contaminated sites

International Nuclear Information System (INIS)

Simpson, E.

1999-01-01

Establishing community trust is an essential element in the successful remediation of a radioactively contaminated site. The US Environmental Protection Agency (EPA), Region 2 has been involved in the clean up of numerous radioactively contaminated Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), Resource Conservation Recovery Act (RCRA), and Formerly Utilized Site Remedial Action Program (FUSRAP) sites in New Jersey and New York. Each site presented a unique challenge which centered around establishing and, often, re-establishing the trust of the surrounding community. Thanks to the United States government's history regarding the use of radioactive materials, people question whether governmental regulators could possibly have the public's best interests in mind when it comes to addressing radioactively contaminated sites. It has been our experience that EPA can use its position as guardian of the environment to help establish public confidence in remedial actions. The EPA can even use its position to lend credibility to remedial activities in situations where it is not directly responsible for the clean-up. Some ways that we have found to instill community confidence are: establishing radioanalytical cross-check programs using EPA's National Air and Radiation Environmental Laboratory to provide analytical quality assurance; and establishing an environmental radiation monitoring program for the contaminated site and surrounding community. (author)

40 CFR 131.8 - Requirements for Indian Tribes to administer a water quality standards program.

Science.gov (United States)

2010-07-01

... administer a water quality standards program. 131.8 Section 131.8 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS WATER QUALITY STANDARDS General Provisions § 131.8 Requirements for Indian Tribes to administer a water quality standards program. (a) The Regional Administrator, as...

75 FR 18850 - National Protection and Programs Directorate; Chemical Facility Anti-Terrorism Standards...

Science.gov (United States)

2010-04-13

... Directorate; Chemical Facility Anti-Terrorism Standards Personnel Surety Program AGENCY: National Protection...-terrorism Vulnerability Information (CVI), Sensitive Security Information (SSI), or Protected Critical... . SUPPLEMENTARY INFORMATION: Program Description The Chemical Facility Anti-Terrorism Standards (CFATS), 6 CFR...

International Regulations for Transport of Radioactive Materials, History and Security

International Nuclear Information System (INIS)

EL-Shinawy, R.M.K.

2013-01-01

International Regulations for the transport of radioactive materials have been published by International Atomic Energy Agency (IAEA) since 1961. These Regulations have been widely adopted into national Regulations. Also adopted into different modal Regulations such as International Air Transport Association (IATA) and International Martime Organization (IMO). These Regulations provide standards for insuring a high level of safety of general public, transport workers, property and environment against radiation, contamination, criticality hazard and thermal effects associated with the transport of radioactive wastes and materials. Several reviews conducted in consultation with Member States (MS) and concerned international organizations, resulted in comprehensive revisions till now. Radioactive materials are generally transported by specialized transport companies and experts. Shippers and carriers have designed their transport operations to comply with these international Regulations. About 20 million consignments of radioactive materials take place around the world each year. These materials were used in different fields such as medicine, industry, agriculture, research, consumer product and electric power generation. After September 11,2001, the IAEA and MS have worked together to develop a new guidance document concerning the security in the transport of radioactive materials. IAEA have initiated activities to assist MS in addressing the need for transport security in a comprehensive manner. The security guidance and measures were mentioned and discussed. The transport security becomes more developed and integrated into national Regulations of many countries beside the safety Regulations. IAEA and other International organizations are working with MS to implement transport security programs such as guidance, training, security assessments and upgrade assistance in these fields.

78 FR 73589 - Energy Conservation Program: Energy Conservation Standards for Commercial and Industrial Electric...

Science.gov (United States)

2013-12-06

... Conservation Program: Energy Conservation Standards for Commercial and Industrial Electric Motors; Proposed... Conservation Program: Energy Conservation Standards for Commercial and Industrial Electric Motors AGENCY... proposes energy conservation standards for a number of different groups of electric motors that DOE has not...

A directory of computer programs for assessment of radioactive waste disposal in geological formations

International Nuclear Information System (INIS)

Broyd, T.W.; Dean, R.B.; Hobbs, G.D.; Knowles, N.C.; Putney, J.M.; Wrigley, J.

1984-01-01

This Directory describes computer programs suitable for the assessment of radioactive waste disposal facilities in geological formations. The programs, which are mainly applicable to the post closure analysis of the repository, address combinations of the following topics: nuclide inventory, corrosion, leaching, geochemistry, stress analysis, heat transfer, groundwater flow and radionuclide transport. Biosphere modelling, surface water flow and risk analysis are not covered. A total of 248 programs are identified, of which 50 are reviewed in detail, 134 in summary and 64 in tabular fashion. The directory has been compiled using a combination of literature searches, telephone and postal correspondence and meetings with recognised experts in the respective areas of work covered. It differs from previous reviews of computer programs for similar topics areas in two main respects. Firstly, the method of obtaining information has resulted in program descriptions of considerable breadth and detail. Secondly, the Directory has concentrated wherever possible on European codes, whereas most previous work of this nature has looked solely at programs developed in North America. The reviews are presented in good faith, but it has not been possible to run any of the programs on a computer, and so truly objective comparisons may not be made. Finally, although the Directory is specific to the post-closure assessment of a repository site, some of the programs described could also be used in other areas of repository analysis (eg repository design)

Establishing a national system for radioactive waste management. A publication within the RADWASS programme

International Nuclear Information System (INIS)

1995-09-01

This Safety Standard is intended to cover the requirements for establishing a national system for safe management of radioactive wastes especially, for solid, liquid and airborne radioactive waste resulting from the nuclear fuel cycle. The main text of the Safety Standard is organized as follows: (a) Section 2 sets out the main objective for radioactive waste management and the principle on which radioactive waste management policy and strategies should be based; (b) Section 3 presents the basic components of a national framework for radioactive waste management; (c) Section 4 outlines the responsibilities of the Member State, the regulatory body and the waste generators and operators of radioactive waste management facilities; and (d) Section 5 describes important features of radioactive waste management

Trace radioactive measurement in foodstuffs using high purity germanium detector

International Nuclear Information System (INIS)

Morco, Ryan P.; Racho, Joseph Michael D.; Castaneda, Soledad S.; Almoneda, Rosalina V.; Pabroa, Preciosa Corazon B.; Sucgang, Raymond J.

2010-01-01

Trace radioactivity in food has been seriously considered sources of potential harm after the accidental radioactive releases in the last decades which led to contamination of the food chain. Countermeasures are being used to reduce the radiological health risk to the population and to ensure that public safety and international commitments are met. Investigation of radioactive traces in foods was carried out by gamma-ray spectrometry. The radionuclides being measured were fission products 1 37Cs and 1 34Cs and naturally occurring 4 0Κ. Gamma-ray measurements were performed using a hybrid gamma-ray counting system with coaxial p-type Tennelec High Purity Germanium (HPGe) detector with relative efficiency of 18.4%. Channels were calibrated to energies using a standard check source with 1 37Cs and 6 0Co present. Self-shielding within samples was taken into account by comparing directly with reference standards of similar matrix and geometry. Efficiencies of radionuclides of interests were accounted in calculating the activity concentrations in the samples. Efficiency calibration curve was generated using an in-house validated program called FINDPEAK, a least-square method that fits a polynomial up to sixth-order of equation. Lower Limits of Detection (LLD) obtained for both 1 37Cs and 1 34Cs ranges from 1-6 Bq/Kg depending on the sample matrix. In the last five years, there have been no foodstuffs analyzed exceeded the local and international regulatory limit of 1000Bq/Kg for the summed activities of 1 37Cs and 1 34Cs. (author)

75 FR 37733 - Regulation of Fuels and Fuel Additives: Modifications to Renewable Fuel Standard Program

Science.gov (United States)

2010-06-30

... Regulation of Fuels and Fuel Additives: Modifications to Renewable Fuel Standard Program AGENCY... direct final rule to amend the Renewable Fuel Standard program requirements on May 10, 2010. Because EPA... Fuel Standard program requirements, published on May 10, 2010. We stated in that direct final rule that...